NUREG/CR-5490, Vol. 1, 'Regulatory Instrument Review ...
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NUREG/CR-5490 PNL-7190 Vol. 1 Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components ( Prepared by Bs V. Werry Pacific Northwest Laboratory Operated by Battelle Memorial Institute Prepared for U.S. Nuclear Regulatory Commission
Transcript of NUREG/CR-5490, Vol. 1, 'Regulatory Instrument Review ...
NUREG/CR-5490PNL-7190Vol. 1
Regulatory Instrument Review:Management of Aging of LWRMajor Safety-Related Components
(
Prepared by Bs V. Werry
Pacific Northwest LaboratoryOperated byBattelle Memorial Institute
Prepared forU.S. Nuclear Regulatory Commission
/
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NUREG/CR-5490PNL-7190Vol. 1R9, RV
Regulatory Instrument Review:Management of Aging of LWRMajor Safety-Related Components
Manuscript Completed: May 1990Date Published: October 1990
Prepared byE. V. Werry
Pacific Northwest LaboratoryRichland, WA 99352
Prepared forDivision of EngineeringOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555NRC FIN B2865
ABSTRACT
This report comprises Volume 1 of a review of U.S. nuclear plant regula-tory instruments to determine the amount and kind of information they containon managing the aging of safety-related components in U.S. nuclear powerplants. The review was conducted for the U.S. Nuclear Regulatory Commission(NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear PlantAging Research (NPAR) Program. Eight selected regulatory instruments, e.g.,NRC Regulatory Guides and the Code of Federal Regulations, were reviewed forsafety-related information on five selected components: reactor pressurevessels, steam generators, primary piping, pressurizers, and emergency dieselgenerators. Volume 2 will be concluded in FY 1991 and will also coverselected major safety-related components, e.g., pumps, valves and cables.The focus of the review was on 26 NPAR-defined safety-related aging issues,including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of thereview is that safety-related regulatory instruments do provide Implicitguidance for aging management, but include little explicit guidance. Themajor recommendation is that the instruments be revised or augmented toexplicitly address the management of aging.
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CONTENTS
ABSTRACT . . . . . .. . . . . . . . . . . . . . . . .
PREFACE . . . . . . . . . . . . . . . . . . . . . . . . . ..
ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . .
ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . .
SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . .
1.0 INTRODUCTION/PURPOSE. . . . . . . . . . . .
2.0 SELECTION OF INSTRUMENTS, COMPONENTS AND ISSUES, ANDMETHODOLOGY . . . . . . . . . . . . . . . .
2.1 REGULATORY INSTRUMENTS REVIEWED. . . . . . . .
2.2 MAJOR COMPONENTS . . . . . . . . . . ........
2.3 AGING ISSUES ....................
2.4 REVIEW CRITERIA. . . . . . . . . . . . . . . . . . .
2.5 REVIEW METHODOLOGY . . . . . . . . . . . . . . . . .
2.6 REVIEW EXAMPLES. . . . . . . . . . . . . . . . . . .
3.0 DISCUSSION. . . . . . . . . . . . . . . . . . . . . . . .
3.1 REGULATORY INSTRUMENTS AND AGING MANAGEMENT. . . . .
3.2 REGULATORY INSTRUMENTS AND THE AGING ISSUES . . . .
3.2.1 Code of Federal Regulations . . . . . . . . .
3.2.2 Technical Specifications. . . . . . . . . . .
3.2.3 Standard Review Plans . . . . . . . . . . . .
3.2.4 Regulatory Guides . . . . . . . . . . . . . .
3.2.5 ASME Boiler and Pressure Vessel . . . . . . .
3.2.6 Generic Safety Issues . . . . . . . . . . . .
. . ..
. . ..
. . ..
. . . .
* . . .
. . . .
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xi
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1.1
2.1
2.1
2.3
2.4
2.6
2.7
2.8
3.1
3.1
3.1
3.1
3.3
3.4
3.4
3.5
3.6
3.7
. . .
. . ..
. . ..
. . ..
. . ..
. . . .
. . . .
3.2.7 Institute of Electrical and Electronic EngineersStandards . . . . . . . . . . . . . . . . . . . . . g
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3.2.8 American Nuclear Society Standards. . . . . . . . . .
3.2.9 General Correlation of Implied Aging. . . . . . . . .
4.0 CONCLUSIONS AND RECOMMENDATIONS ................
4.1 CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . .
3.8
3.8
4.1
4.1
4.2 RECOMMENDATIONS. . . . . . . . . . . . . . . . . . . . .
5.0 SUGGESTED FUTURE REGULATORY INSTRUMENT REVIEW ACTIVITIES. . .
5.1 CONTINUATION OF THE GUIDE TO REGULATORY INSTRUMENTS. . .
5.2 COMPUTER DATA BASE FOR THE REGULATORY INSTRUMENT REVIEW.
6.0 OBSERVATIONS OUTSIDE THE SCOPE OF THE REVIEW. . . . . . . . .
7.0 REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . .
APPENDIX I - GLOSSARY OF AGING ISSUES . . . . . . . . . . . . . .
APPENDIX II - REGULATORY INSTRUMENT REVIEW FORREACTOR PRESSURE VESSEL. . . . . . . . . . . . . . .
APPENDIX III - REGULATORY INSTRUMENT REVIEW FORSTEAM GENERATOR . . . . . . . . . . . . . . . . . .
APPENDIX IV - REGULATORY INSTRUMENT REVIEW FORPRIMARY PIPING . . . . . . . . . . . . . . . . . . .
APPENDIX V - REGULATORY INSTRUMENT REVIEW FORPRESSURIZER (INTERNALS AND SUPPORT PIPING). . . . . .
APPENDIX VI - REGULATORY INSTRUMENT REVIEW FOREMERGENCY DIESEL GENERATOR . . . . . . . . . . . . .
::
. .
4.1
5.1
5.1
5.1
6.1
7.1
1.1
1I.1
. . 111.1
,. . IV.1
, .. V.1
. . VI.1
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PREFACE
This report was developed to provide a preliminary assessment regardingthe extent of those regulatory instruments that contain information pertinentto managing aging. Assessments of the applicable regulatory instrumentsregarding aging management is complex and subject to differences in interpre-tation. Therefore, the perspectives in this report should be consideredpreliminary. These perspectives are not established needs or views and donot reflect regulatory positions or requirements.
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ACKNOWLEDGMENTS
The author of this report acknowledges the support and technical guid-
ance provided by J. P. Vora and C. Z. Serpan, Jr., of the Nuclear Regulatory
Commission (NRC) during the course of the regulatory instrument review task
under the Nuclear Plant Aging Program. A special thanks goes to V. N. Shah
of the Idaho National Engineering Laboratory for his contribution to the
review by providing the "Understanding and managing aging tables and figures
for the RPVs and reactor piping systems." The author also wishes to thank
the following Pacific Northwest Laboratory staff for their contributions to
this report: A. B. Johnson, Jr., for Project Management support and tech-
nical guidance; and to E. F. Love, P. M. Daling, B. W. Smith, S. H. Bush,
W. N. McElroy, J. W. Jaeckle, S. R. Doctor, J. C. Spanner, K. R.
Hoopingarner, R. J. Kurtz, R. H. Ferris and W. B. Scott for their expertise,
review of the instruments, and input to the review of the regulatory instru-
ments. A special thanks to J. W. Nageley for his timely editing effort for
the review and report.
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ACRONYMS
A&E Architect Engineer
ACI American Concrete Institute
ANL Argonne National Laboratory
ANS American Nuclear Society
ANSI American National Standards Institute, Inc.
ASME American Society of Mechanical Engineers
ASTM American Society of Testing and Materials
BPVC Boiler and Pressure Vessel Code
BTP Branch Technical Position
BWR Boiling Water Reactor
CCS component, systems or structure
CFR Code of Federal Regulations
DMS diminishing manufacturing source
EDG emergency diesel generator
EMTB Material Engineering Branch
EPRI Electric Power Research Institute
FSAR Final Safety Analysis Report
GDC General Design Criteria
GSI Generic Safety Issues
HAZ heat affected zone
HPI high pressure injection
IEEE Institute of Electrical and Electronic Engineers
IGSCC intergranular stress corrosion cracking
ISI inservice inspection
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LE life extension
NDE nondestructive examination
NDT nondestructive testing
NFC National Fire Code
NPAR Nuclear Plant Aging Research
NPP nuclear power plant
NRC Nuclear Regulatory Commission
NSSS nuclear steam supply system
NUMARC Nuclear Management and Resources Council
NUPLEX Nuclear Plant Life Extension
NUREG Nuclear Regulatory Commission Report
PLEX Plant Life Extension
PNL Pacific Northwest Laboratory
P/T pressure/temperature
PTS pressurized thermal shock
PVRC Pressure Vessel Research Committee
PWR pressurized water reactor
QA quality assurance
RCC reactor core cooling
RCPB reactor coolant pressure boundary
RCS reactor coolant system
RG NRC Regulatory Guides
RHR residual heat removal
RPV reactor pressure vessel
RT(NDT) reference nil-ductility temperature
SAR Safety Analysis Report
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SCC stress corrosion cracking
SG steam generator
SRP Standard Review Plan
SSE safe shutdown earthquake
SWG Special Working Group
TDI Transamerican DeLaval Inc.
TS Technical Specification
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This report comprises Volume 1 of a review of U.S. nuclear plant regula-tory instruments to determine the extent that they contain information per-tinent to managing aging of safety-related components in nuclear powerplants. The instrument review was conducted for the U.S. Nuclear RegulatoryCommission (NRC) under the NRC Nuclear Plant Aging Research (NPAR) program.
As used in this report, an "instrument' is a procedure or document as inan instrument of government, e.g., the Code of Federal Regulations. Theterms regulatory instruments or instruments are used throughout this reportand in this context are not to be confused with an instrument of measurement,e.g., a pressure gauge or flow meter. Eight regulatory instruments wereselected for the review:
* Code of Federal Regulations (CFR)
* Technical Specifications (TS)
* Standard Review Plan (SRP)
* NRC Regulatory Guides (RG)
* American Society of Mechanical Engineers (ASME) Boiler and PressureVessel Code (BPVC), Sections III and XI
* Generic Safety Issues (GSI)
* American Nuclear Society (ANS) Standards
* Institute of Electrical and Electronics Engineers, Inc. (IEEE)Standards.
Historically, all these regulatory instruments have been used for the design,construction, start-up and operation of Nuclear Power Plants. In this, theirprimary purpose has been to protect the health and safety of the generalpublic. The intent of this review was to determine the degree of emphasis onthe management of aging found in the instruments now in use. No attempt wasmade to take into account that approximately 50% of the Nuclear Power Plantsnow operating were licensed before 1975. Therefore, not all of the plantswere licensed under the same set or edition of instruments noted above. Thereview of the applicable instruments was based on the technical issuesrelated to aging. The descriptions included are the author's and do notrepresent NRC considerations for license renewal.
The components on which the review focused were five light water reactormajor safety-related components: reactor pressure vessels, steam generators,primary piping (reactor coolant piping), pressurizer vessel, and emergencydiesel generators. (Cables, containment and basemat and selected pumps and
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valves will be investigated in FYs 1990 & 1991 and will be published asVolume 2.) The components were selected from the NPAR program documentNUREG-1144, Nuclear Plant Aging Research Program Plan, that has identified alist of components of current interest and concern relative to the managementof aging. The components are high priority, safety-related components thathave been, in varying degrees, subject to aging problems.
The focus of the review was on 26 NPAR-defined aging issues, includinggeneric issues, e.g., examination, inspection and maintenance, embrittlement,corrosion, erosion, and thermal cycles; and component specific issues, e.g.,steam generator tube specific - intergranular attack, fretting and denting,and emergency diesel generator specific - harsh and frequent testing.
Each regulatory instrument was evaluated for each aging issue chosen foreach component, e.g., for the RPV and the aging issue of corrosion, eachinstrument was evaluated for aging features that provide implied or explicitdirection in the management of corrosion. The results of the review arecontained in tables in appendixes for each of the major components.
The principal conclusion is that aging management does exist in thesafety-related regulatory instruments; however, the information is largelyimplied. The emphasis of the instruments appears to be on initial design,construction, qualification and start-up and actions to address aging prob-lems that develop after the problem is found. Finally, it was also concludedthat revisions should be made in the instruments to explicitly address aging.
The major recommendation is that the existing body of regulatoryinstruments should directly address aging and the management of aging. Thedifficulties, however, with any revisions are acknowledged, and it isrecommended that a project plan for the revision process be evaluated anddefined. The planning should include evaluations of ongoing NRC agingresearch and industry aging-related research, e.g., Electric Power ResearchInstitute and individual utilities, and the development of a realistic timeframe for implementation of the revisions.
It is also suggested that all regulatory instrument review informationbe installed in a computer data-based system for broader use by the NRC andothers.
A number of observations outside the scope of the review were developedduring the analysis of the review by PNL staff. The principal observationsare 1) evaluation of component replacement methods as an aging managementprocedure should be addressed in the regulatory instruments for augmentationof safety and cost effectiveness; 2) aging management could be enhanced byimprovement of NDE methods and inspection tools; 3) the ASME BPVC, as themajor contributor to design and construction and aging management, provides avaluable contribution to the NPP industry; however, improvements in the Codeare needed to address component material deterioration, design that encour-ages and allows for repair, replacement, and improved inservice inspection,and improvements in the time cycle for revising the Code (ASME is currently
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addressing hard to backfit design problems in Section III and the problems oflong time cycles in Section XI); and 4) a safe and well-maintained plant,i.e., a plant with excellent maintenance methods and procedures, is likely tobe a plant that is successfully managing the aging of its components andsystems.
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1.0 INTRODUCTION/PURPOSE
This report comprises Volume 1 of a review of U.S. nuclear plant regula-tory instruments to determine the extent that they contain information per-tinent to managing the aging of safety-related components in nuclear powerplants (NPPs). The review was conducted for the U.S. Nuclear RegulatoryCommission (NRC), Office of Nuclear Regulatory Research, by the PacificNorthwest LaboratorykaJ under the NRC Nuclear Plant Aging Research (NPAR)Program (NRC 1987a). In conducting the review, the focus was on safety-related aging as it relates to selected safety-related components in NuclearPower Plants (NPPs). NPAR has defined aging as "the cumulative degradationthat occurs with the passage of time in a component, system of structure."Therefore, the essential elements of the review on which this report is basedmay be presented as follows:
REGULATORY INSTRUMENTS
SAFETY-RELATED NPP COMPONENTS - & SAFETY-RELATED AGING ISSUES
As used in this report, an "instrument" is a procedure or document as inan instrument of government, e.g., the Code of Federal Regulations. The termsregulatory instruments or instruments are used throughout this report and inthis context are not to be confused with an instrument of measurement, e.g., apressure gauge or flow meter. The regulatory instruments reviewed for safety-related information are listed in Section 2.2. Each is described in the bodyof this report. Historically, these safety-related regulatory instrumentshave been used as the basis for the design, construction, start-up, equipmentqualification, and operation of NPPs. Their primary purpose has been toprotect the health and safety of the general public. This review was under-taken to determine the degree of emphasis, if any, regarding the inclusion ofexplicit requirements for the management of aging found in the instruments nowin use. No attempt was made to take into account that approximately 50% ofthe NPPs now operating were licensed before 1975. Therefore, not all theplants were licensed under the same set or edition of instruments noted inSection 2.1. The review of the applicable instruments was based on thetechnical issues related to aging. The descriptions included are the author'sand do not represent NRC considerations for license renewal.
The components on which the review focused are the reactor pressurevessels; steam generators; primary piping (reactor coolant piping); pres-surizer vessel, with special emphasis on pressurizer spray and surge lines and
(a) Operated for the U.S. Department of Energy by Battelle MemorialInstitute.
1.1
internals; and the emergency diesel generators. (Underway or planned arereviews for cables, containment and basemat and selected pumps and valves;this work will be published as Volume 2 in FY 1991).
To determine whether the selected instruments contain significant agingsafety-related information related to the five safety-related components, thereview concentrated on NPAR defined safety-related aging issues. A completelist of the 26 identified aging issues is found in Section 2.3. These agingissues include examination, inspection and maintenance, embrittlement,corrosion, erosion, and thermal cycles; and component--specific issues, e.g.,steam generator tube specific--denting, fretting and crevice intergranularattack, and emergency diesel generator spesific--harsh and frequent testing.Each aging issue is defined in Appendix I. aJ
The results of the review on which this report is based are containedin tables in Appendixes II a through VI entitled "Regulatory InstrumentReviews": Appendix II for Reactor Pressure Vessels; Appendix III for SteamGenerators; Appendix IV for Primary Piping (Reactor Coolant Piping); Appen-dix V for Pressurizer Internals; and Appendix VI for Emergency DieselGenerators.
Section 2.0, "Selection of Instruments, Components and Issues, andMethodology," describes the regulatory instruments, the selection of com-ponents, the rationale for the aging issues, the instrument review criteria,and the review methodology. Also included in Section 2.0 are two typicalexamples of how to use the tabular data in Appendixes II through VI.
Section 3.0, "Discussion," provides background information on the regula-tory instruments versus aging management and the aging issues. Specificexamples of aging management guidance, either direct or indirect, are providedfor each instrument.
The "Conclusions and Recommendations," "Suggested Future RegulatoryInstrument Review Activities," and "Observations Outside the Scope of theReview" are found, respectively, in Sections 4.0, 5.0 and 6.0 of this report.
(a) The regulatory instruments, e.g., Code of Federal Regulations andAmerican Society of Mechanical Engineers Code, frequently make use of theAppendix A, B, etc., within their text; therefore, the appendixesattached to this report will be designated in Roman numerals to distin-guish them from those found in the instruments.
1.2
2.0 SELECTION OF INSTRUMENTS. COMPONENTS AND ISSUES. AND METHODOLOGY
This section describes regulatory instruments, the selection of themajor components, the rationale for selection of the aging issues, and thedevelopment of the review criteria and methodology. Examples of how to usethe review information contained in appendixes are included.
2.1 REGULATORY INSTRUMENTS REVIEWED
The following regulatory instruments were reviewed for this report.While not necessarily all inclusive, they are the most important and applic-able to the pressure boundary aspects of the current components. IEEEStandards were added to the list to account for the electrical aspects of theemergency diesel generators and pressurizer. IEEE Standards were notconsidered in the reviews of RPV, steam generator (SG), or the primarypiping. PNL staff with experience in the aging issues and familiarity withthe applicable regulatory instrument performed the reviews and interpretedthe instrument text.
* Standard Review Plan (SRP)
* Code of Federal Regulations (CFR)
* NRC Regulatory Guides (RG)
* American Society of Mechanical Engineers (ASME) Boiler and PressureVessel Code (BPVC), Sections III and XI
* Generic Safety Issues (GSI)
* Technical Specifications (TS)
* Institute of Electrical and Electronics Engineers, Inc. (IEEE) Standards
* American Nuclear Society (ANS) Standards.
Each instrument is described below.
* Standard Review Plan. The SRP is published by the NRC and providesguidance for the review of Preliminary Safety Analysis Reports (SAR)and the Final Safety Analysis Reports (FSAR) for plant design and oper-ations. The SRP contains 18 chapters and covers all facets of NPPoperations, including plant descriptions, design and construction,safety features, instrumentation, electrical power, radiation protec-tion, waste management, quality assurance, and human factors engineer-ing. The SRP also presents specific Branch Technical Positions (BTPs)that are developed and published by branches within the NRC, e.g., BTPISCB 19 by the Information Security Branch found in SRP Chapter 7,Instrumentation and Controls.
2.1
* Code of Federal Regulations. These regulations codify general andpermanent rules published in the U.S. Federal Register by the Executivedepartments and agencies of the U.S. Federal Government. With referenceto this report, these codes establish the rules for design, constructionlicensing and operation of commercial NPPs. For the NRC, a federalagency, the most significant CFR relating to commercial reactors isTitle 10, Chapter 1, Part 50, Domestic Licensing of Production andUtilization Facilities. Part 50 includes important appendixes, such asthe General Design Criteria requirements, specific material requirementsfor reactor vessels, emergency planning, and quality assurance criteriafor NPPs.
* Regulatory Guides. These guides are published by the NRC in 10 broaddivisions, including Division 1, Power Reactors. The guides are avail-able to the public and NPP licensees. They provide general guidance toapplicants and describe methods acceptable to the NRC staff, to imple-ment specific parts of the Commission's regulations and, to delineateevaluation techniques used by NRC staff for specific problems and postu-lated accidents. The RGs often explain and detail acceptable methodsfor the rules found in the CFRs.
* American Society of Mechanical Engineers. Boiler and Pressure VesselCode. Sections III and XI. The ASME Code establishes the rules ofsafety governing design, construction, operation and testing of NPPcomponents and systems. Section III covers a broad range of componentsand systems including, pressure vessels, piping, pumps, valves, supportsand core internals. Section XI provides rules for inservice inspectionof components and systems. Section XI constitutes the requirements ofexaminations, testing and inspection to maintain an NPP in a safe andexpeditions manner. Section XI is applicable when the requirements ofthe Construction Code, e.g., Section III, have been satisfied. The ASMECode Editions, Addenda and Code Cases used by the owners of NPPs aresubject to acceptance by the NRC. The ASME codes are frequently refer-enced in the CFRs. The ASME Maintenance and Operation (O&M) committeesprovide an important function through the testing of pumps, valves andsnubbers.
* Generic Safety Issues. GSIs are published by NRC to identify safetyissues generic to NPPs. The GSIs can cover a wide variety of subjects;however, for the purposes of this review, the GSIs used are those thatare predominately concerned with material degradation and operationsthat cause degradation of plant components. When a solution to thegeneric issue is found, the usual result is an NRC Generic Letter or anNRC NUREG report that provides an industry wide dissemination of thesolution.
* Technical Specifications. Technical Specifications are NPP mandatoryoperational specifications that provide instructions for limiting con-ditions and surveillance requirements for plant operations. Licenseapplications for authority to operate an NPP are required to supplyTechnical Specifications as enumerated in 10 CFR 50, Section 50.36.
2.2
* Institute of Electrical and Electronic Engineers Standards. The IEEEStandards present criteria and requirements for electrical systems thatare specifically related to providing protection to the health andsafety of the public. The standards included in this review are princi-pally those prepared by the IEEE Nuclear Power Engineering Committee.The IEEE Standards, through the Equipment Qualification (EQ) standardsdefine "qualified life" and provide guidance for requalification orreplacement of components when their qualified life is reached. TheIEEE standards are not mandatory and use of the standards is whollyvoluntary. Use of the standards, as acceptable practice, are subject tothe approval of the regulatory agency, i.e., the NRC. Specific IEEEstandards are frequently called out and/or qualified in the RegulatoryPosition Section of the RGs as acceptable to NRC staff.
* American Nuclear Society Standards. The ANS standards are agreementsamong designers, engineers, governmental regulatory agencies, manufac-turers, and nuclear scientists. The standards are developed to providecurrent practices on various subjects that affect NPPs. Among the sub-jects are criteria for earthquake Instrumentation, various safetyguides, selection and training of personnel, QA, security for NPPs, andauxiliary feedwater system for PWRs. The ANS standards are frequentlypublished as American National Standards with the approval of theAmerican National Standards Institute (ANSI). ANS standards are guidesfor prospective use and are not mandatory; the designers are notrestricted to the ANS standards and may propose alternate criteria toprovide adequate safety.
These instruments are listed in column 2 of the component reviews AppendixesII through VI.
2.2 MAJOR COMPONENTS
The following components were chosen for the current review. They wereselected from the major LWR plant elements of current interest in the NPARprogram, as found in Table 5.3 of the NPAR program document NUREG-1144,Nuclear Plant Aging Research Program Plan. These selected components arerecognized by the NRC as safety-related components that historically, invarying degrees, are subject to aging problems. Finally, the selectedcomponents provide a good mix for the review by covering the three majordesign disciplines, i.e., structural, mechanical and electrical. Thecomponents are listed in Column 1 of Appendix II through VI.
* reactor pressure vessel
* steam generator
* primary piping (reactor coolant piping)
2.3
* pressurizer
* emergency diesel generator.
2.3 AGING ISSUES
Listed below is a list of the component aging issues used in theinstrument review.
* corrosion
* corrosion/erosion
* crack initiation and flaw propagation
* creep/swelling
* element burnout(s)
* erosion
* examination, inspection and maintenance and repair
* excessive/harsh testing
* fatigue
* fracture toughness
* intergranular stress corrosion cracking
* irradiation embrittlement
* low-flux long-time irradiation of vessel internals and supports
a seismic failure/damage
* specific environmental factors, e.g., moisture, oxidation, chemicals,oils, and dust.
* stress corrosion
* stud failure
* thermal cycles
* thermal embrittlement
* thermally induced bending
2.4
* thermally induced mechanical wear
* transient thermal loads
* tube specific - denting, fretting and crevice corrosion
* vibration
* wear
* weldments - specific to dissimilar metals of safe ends.
For illustrative purposes, some of the aging issues of the instrumentreview are shown below.
For the reactor pressure vessel (RPV),
* IRRADIATION EMBRITTLEMENT - degradation of the structural integrity ofvessel materials due to the consequences of long-term exposure to highradiation levels that induce changes in the vessel's materialproperties.
* FATIGUE - degradation associated with cyclic loading, transient cycles,and thermal and pressure cycles.
For the steam generator (SG),
* CORROSION - degradation associated with the deterioration of materialsurfaces, chiefly, through chemical actions. The chemical reaction isinfluenced by environment of the material or component.
* TUBE SPECIFIC (DENTING, FRETTING AND CREVICE CORROSION) - aging issuesassociated with the generator tubes include denting caused by thecrevice corrosion of the tube support plate and tube sheet material;fretting is caused by the wear action between the tubes, tube supportsand antivibration bars; crevice corrosion due to localized stagnantsolutions in lap Joints, holes, welding surfaces, etc.
All specific aging issues were derived from the general guidance foundin NUREG-1144, Rev. I., Section 2.1 (NRC 1987a). Typical degradationmechanisms are neutron embrittlement, fatigue, erosion, corrosion, oxidation,thermal embrittlement, and chemical reactions. Aging is also induced bystressors, e.g., service wear, testing, improper installation, and applica-tion and maintenance.
Each aging issue was considered, and those believed by PNL staff to bespecific to the components were chosen for the review. The aging issues foreach component were then grouped into principal categories that define themechanics or phenomena of the aging processes for the component. For atypical example see Appendix III, page 11I.9, item (50), Dynamic effects,that includes vibration, thermal cycles and erosion.
2.5
Aging issues are not necessarily specific or all inclusive for eachcomponent nor do they manifest themselves in the same way for each component.For example, neutron embrittlement is not typical to all components. Radia-tion is unique to the RPV and is not generally regarded as a problem in theother review components. On the other hand, the RPV as a pressure retainingcomponent has many safety-related degradation problems that are common to allvessels and piping systems.
The aging issues for each component are found in column 3 of the reviewAppendixes II through VI.
2.4 REVIEW CRITERIA
The review criteria chosen to examine the regulatory instruments answerthree questions: 1) Do the instruments address aging? 2) If so, in whatform is the aging addressed? For example is aging management implied orexplicit and is the guidance or direction adequate or incomplete for theaging issue? 3) What are the current initiatives that would change theinstruments to address aging and life extension?
The review criteria as they appear in the component review sections arenoted below with a brief definition:
1. Aging Features:
2. Life ExtensionFeatures:
3. CurrentInitiatives:
4. Aging Needs:
5. Life ExtensionNeeds:
What parts of the instrument, if any, identify themanagement of component aging. Are aging issuesaddressed by the instrument? Is the informationimplied or explicitly expressed?
Does the instrument address life extension orcomponent replacement needs?
Is work currently underway to update or changethe instrument to include aging features or lifeextension features? What, if any, is the statusof special working groups, of technical committees,or of on-going research that could lead to therevision of the instruments to include thesefeatures?
What changes or revisions generally are needed inthe instrument to address aging issues?
Does the instrument require further investigation/research of the aging issue to accommodate lifeextension? How could the instrument be used ormodified to meet life extension needs?
The review criteria are listed in columns 4 through 8 on each page ofthe component review sections, Appendixes II through VI.
2.6
2.5 REVIEW METHODOLOGY
Each regulatory instrument was examined for data for each designatedmajor component's aging issues. Thus the regulatory instrument review for acomponent with five aging issues required five reviews for each instrument.The review relative to the components was carried out in the generic sense;that is, no distinction was made for the different configurations or manu-facturers of SGs or for RPVs, or for PWRs versus BWRs. However, the reviewdoes account for the regulatory documents that specifically address a designconfiguration or type of reactor. The general approach was to review theinstrument for reference to the aging issues or for a specific reference tothe major components by name or system.
Typically, minimal specific component or aging issues references, byname, are found in the regulatory instruments. The principal reference is tosystems, such as the reactor coolant system or reactor containment. However,there are some exceptions; Appendix G, in 10 CFR 50, is specific for fracturetoughness requirements and Appendix H is specific for surveillance require-ments to monitor changes in fracture toughness. If the instrument revealedany relationship or potential relationship to the aging issue, furtheranalysis was conducted to determine the explicit and/or implied relationship.The related information, if found, was analyzed by using the review criteriaof Section 2.4. Applicable results of the five review criteria analysis wereentered in columns 4 through 8 for each of the aging issues designated foreach component (see Appendix II through VI). Special attention was given tothe current initiatives criteria, and a number of on-going actions were notedthroughout the review. Criteria 1, Aging Feature, is the key criteria ofthis review and provides the bulk of the information found in the regulatoryinstruments and indeed provides the emphasis to examine the instrument inmore detail. The larger instruments, e.g., the SRP and ASME code, wereinvestigated by subsections, chapters, etc., and those sections that werecompletely unrelated to the aging issues were ignored for detailed analysis.The smaller instruments, e.g, RGs and IEEE standards, were investigated as awhole. Many of the instruments were eliminated by title or subject orobjectively determined not to be related to the aging issue(s).
2.6 REVIEW EXAMPLES
Two examples from the PNL regulatory instrument review are shown below.Example I examines the NRC RGs for the issue of EXAMINATION, INSPECTION ANDMAINTENANCE AND REPAIR as they apply to the RPVs. Example 2 examines theGSIs for the issue of IRRADIATION EMBRITTLEMENT as applied to the RPVs. Eachexample begins with a question, followed by an answer.
ExamDle 1
Do the RGs refer to the aging issue of EXAMINATION, INSPECTION ANDMAINTENANCE AND REPAIR with respect to RPVs?
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* On page 11.5 of Appendix II, five entries are shown for the RGs items(15) through (19). For example, item (15), RG 1.150, indicates thatthis RG does have an Aging Feature (Column 4), "UT of RPV welds,"discusses evaluation of prior UT examinations for determination of crackgrowth rates, and Life Extension Features (Column 5), "Inservice inspec-tion (ISI)," discusses continued structural integrity of reactor throughreliable flaw detection vessels. No Current Initiatives (Column 6) werefound; the entry refers to Note 1, page II.3 which indicates a need forfurther study. Aging Needs and Life Extension Needs (Columns 7 and 8)were shown to be suggestions for improved flaw detection and assessment.The comments (Column 9) note that cracks may propagate from claddinginto the steel (shell) in the RPV and raises the question that 100% UTmay be required for BWR to assess under cladding cracks.
Example 2
Do the GSIs refer to the aging issue of FRACTURE TOUGHNESS with respectto RPVs?
As shown on page II.10 of Appendix It, three entries, items (56) through(58), were made for the GSI relative to the noted issue. The firstentry, Item (56), indicates that GSI A-li (Column 3) does have an AgingFeature (Column 4). Column 4 notes that "As plants accumulate more andmore service time, neutron irradiation reduces the material fracturetoughness and initial margins of safety." The GSI does not discussLife Extension Features (Column 5) and it has no Current Initiatives(Column 6). For the Aging Needs (Column 7) and Life Extension Needs(Column 8), an entry is made indicating that further analysis is neededto resolve these review criteria. The comment (Column 9) indicates thepriority for this issue has been resolved with the issuance ofNUREG-0744 (NRC 1982).
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3.0 DISCUSSION
Although the review data on regulatory instruments developed in thisstudy, as presented in the Appendixes II through VI for each component,appear to be comprehensive, the reader is cautioned that the magnitude of theliterature, research time, and funding levels did not permit an exhaustivestudy of all the text, references and background documentation on eachinstrument. The review is, however, a good overview of the degree to whichaging guidance is found in the regulatory instruments. The following sec-tions provide discussion and insights as to the effectiveness of the safetyregulations to provide guidance for the management of aging.
3.1 REGULATORY INSTRUMENTS AND AGING MANAGEMENT
The PNL review revealed that, in effect, the regulatory instruments docontain information that does relate either directly or indirectly to currentsafety-related concerns and aging management. A strong corollary existsbetween safety and aging management, i.e., it is implied that a safe plant ismore likely to be well maintained and more effectively monitored for problemsand degradation. Yet, generally speaking, the instrument review does notreveal explicit requirements for aging and life extension needs or features.The majority of related information, i.e., the aging features of the instru-ments, is interpreted by PNL staff to be implied guidance. The implied guid-ance or, in some cases mandatory guidance, i.e., the technical specifications(TSs), have been useful in the management of aging. Simply stated, thesafety-oriented regulatory instruments used for NPP have indirectly managedaging through safety-oriented design and safe operations.
3.2 REGULATORY INSTRUMENTS AND THE AGING ISSUES
This section presents the key objective of the review, which is con-tained in the question, "Do the regulatory instruments address aging issues?"In this section, a general assessment statement is provided for each instru-ment relative to the aging issues.
Each issue is listed in Section 2.3 and defined in the glossary ofAppendix I. Examples of specific features in each regulatory instrument thataddress aging issues are included with a typical degree of depth on how theinstrument addresses an issue. (In this section, the instruments arediscussed in the order that they appear in the review data, Appendix IIthrough VI.)
3.2.1 Code of Federal Regulations
The CFRs are the principal base for all the regulations that mandate thedesign, construction, inspection and operation of the components chosen inthis review. Appendix A, General Design Criteria for Nuclear Power Plants(GDC), 10 CFR 50, provides the largest measure of implied aging management.
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The GDC of Appendix A coupled with Section 50.55a, Codes and Standards,provides the broad base design and inspection requirements.
The CFRs tend to be generic in description because they often addressbroad plant categories such as the reactor coolant pressure boundary. Inthis review, four of the components considered are within the reactor coolantpressure boundary. Consequently, the Criterion needs given in 10 CFR 50,Appendix A, implies aging management even though the component is notmentioned in specific description. In general, the review components, withthe exception of the RPV, as referenced in 10 CFR 50, Appendix G and H, arenot discussed in the CFRs. Aging and life extension are not explicitly citedin the text. NPAR aging, as defined in the introduction, does not appear.The implied aging features as found in the review, are based principally onthe assumption that a reactor designed, constructed, tested and operatedwithin the rules of 10 CFR 50 will provide the licensee a facility that canbe managed for aging. Aging does appear in 10 CFR Part 50, §50.49, "Environ-mental qualification of electric equipment important to safety for nuclearpower plants," (e), (5). This aging is in reference to equipment qualifiedby test and preconditioned by natural or accelerated aging. Also, in 10 CFR,Part 50, Section 50.109, Backfitting, c, (8), states that "the potentialimpact of difference in facility type, design or age on the relevancy andpracticality of the proposed backfit," will be considered when addressingbackfit requirements. Yet in these examples, the "aging" and "age" are notused in the same context as NPAR defined aging.
The following are typical examples of the more specific requirements ofCFRs; while not using the terms aging and life extension, these examples maybe regarded as aging management guidance:
10 CFR 50, Appendix A, General Design Criteria for Nuclear Power Plants,Criterion 51, states that "The reactor containment boundary shall bedesigned with sufficient margin to assure that under operating, mainten-ance, testing, and postulated accident conditions (1) its ferriticmaterials behave in a nonbrittle manner and (2) the probability ofrapidly propagating fracture is minimized. The design shall reflectconsideration of service temperatures and other conditions of thecontainment boundary material during operation, maintenance, testing,and postulated accident conditions, and the uncertainties in determining(1) material properties, (2) residual, steady state, and transientstresses, and (3) size of flaws." Aging and life extension are notspecifically used in the above quote; however, the criterion doesaddress a number of aging issues identified in this review including,irradiation and thermal embrittlement, fracture toughness, fatigue,thermal cycles, crack formation and growth, testing and maintenance andseismic failure/damage. The criterion terminology of "under operating,maintenance, testing, and postulated accident conditions" encompassesall plant operating phases and strongly advocates a design that assuresmaterial reliability throughout the plant's operating period.
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* Appendix A, Criterion 2, address the aging issue of seismic failure/damage. The criterion states that "structures, systems and componentsimportant to safety shall be designed to withstand the effects ofnatural phenomena such as earthquakes, tornadoes, hurricanes, floods,tsunami, and seiches without loss of capability to perform their safetyfunctions." The design is subject to the most severe (historically)known natural occurrence, to the combinations of normal conditions andaccident conditions and natural phenomena and, to the importance of thesafety function performed.
3.2.2 Technical Specifications
The TSs are mandatory requirements that provide the safety limits, thelimiting safety systems settings, the limiting conditions for operations andthe surveillance requirements for NPPs. TSs should not be confused with orcalled "guides" because they provide specific mandatory rules for operationof a particular plant. They are required for NPP operations by the rules ofthe CFRs and are enforced for the life of the plant. TSs may provide agingmanagement through enforcement of limits that are set at acceptable levels orprocedures which will control, reduce, mitigate, detect or preclude agingdegradation. The TSs, for example, require that safety-related equipment bein acceptable operable condition or, if not repaired within a specific timeframe, the plant will be shut down. TSs also require records to be main-tained for operating cycles, e.g., cyclic loading/P/T cycles. These recordscan provide documentation for material life or life extension documentation.The TSs reference the ASME code, Section XI, for inservice inspection.
The following are examples of specific TS applications that containimplied aging management.
* Technical specifications require inspection for "wall penetrations" orother modes of SG tube wall thinning. This requirement addresses theaging issue of erosion. The present inspection technique is eddycurrent for a fraction of the SG tubes on a 12-to-24 month basis.
* Thermal pressure cycles are recorded during thermal/pressure reactorcoolant heat-up or cool-down on the primary side only. These cycles areuseful for aging management by providing records for evaluation of thereactor coolant system P/T and PTS history.
* TSs require primary reactor coolant system (RCS) chemistry control andthe retention of water analyses and associated records. This informa-tion is useful in determining the water chemistry history of RCS and isuseful in the management of aging and life extension.
* The TSs require inspection of component and equipment mechanicalrestraints, snubbers, on a periodic basis. Failure of visual orfunctional tests require maintenance or replacement.
3.3
3.2.3 Standard Review Plan
The SRP by definition (see Section 2.1) provides a plan "for the reviewof safety analysis reports (SARs) for nuclear power plants." The SRP con-sists of eighteen chapters, ranging from site description of the plant anddesign of structures and components to human factors engineering. The prin-cipal concern of the SRP is safety, e.g., does the SRP review of the FSARindicate that a plant can be started and operated safely and, if a failureoccurs, can the plant be shut down in a safe manner? The SRP, typically,wants to know whether the plant design/procedures comply with applicableCFRs, such as 10 CFR 50.55a, inservice inspection. Many of the implied agingfeatures in the SRP occur because of references to the ASME Code, 10 CFR 50,General Design Criteria and other standards.
Specific examples of aging related guidance in the SRP are as follows:
* SRP 5.2.3, Reactor Coolant Pressure Boundary Materials, discusses thereview of suitable materials and review of procedures for manufacturingand welding. The SRP has implied aging management by determiningwhether the plant design has used the right materials, i.e., correctmaterials will or should stand up to the plant operation andenvironment.
* SRP 3.9.2 has an aging feature for the dynamic effects of vibrationsthrough the review of the structural and functional integrity of thepiping systems under vibratory loads.
3.2.4 Regulatorv Guides
The RGs are principally issued to describe methods acceptable to NRCstaff and to provide guidance to applicants in the use of the 10 CFR 50regulations, especially as applied to the GDC. The "Introduction" of a RGwill frequently refer to the importance of safety and safety systems;"aging," on-the-other-hand, is not part of the text. Yet some of the RGs dodiscuss the aging issues. Information on corrosion, vibration, progressivetube deterioration, and secondary water chemistry maintenance, e.g., may befound in the "Discussions section of RG 1.83; however, the purpose of RG 1.83is for guidance in the performance of inservice inspections (ISI) for steamgenerators. Some individual RGs may be specific to a single component orpart of a component, and these individual RGs tend to support the directmanagement of aging, even though the intent of an RG is to promote safety.
Examples of aging management guidance in RGs are shown below:
Degradation of steam generator tubes has been identified as a problembecause of mechanical damage or progressive deterioration caused byinadequate design, manufacturing errors, or chemical imbalance. Tubeproblems are caused by a number of mechanisms including, IGSCC, IGA,pitting, denting, fatigue, wastage and erosion/corrosion. Managementof the tube degradation is assisted by RG 1.121, "Bases for PluggingDegraded PWR Steam Generator Tubes." The guide describes methods
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acceptable to the NRC staff for establishing limiting safe conditionsof SG tube degradation. Conditions beyond the limiting safe conditionsshould result in removal from service by plugging (welding each end) ofthe tubes.
Regulatory Guide 1.85 allows the use of approved ASME "Code Cases," thusproviding a mechanism to use current repair and replacement techniqueswithin the Jurisdiction of the code. These alternate methods within thejurisdiction of the code may provide improvements in repairs and mate-rials that could enhance aging management and life extension.
3.2.5 ASME Boiler and Pressure Vessel
The ASME Boiler and Pressure Vessel Code, especially Section III andSection XI, are used for the design and construction of NPPs. Section XI,inservice inspection remains in effect throughout the life of a plant andprovides inspection criteria, intervals, and acceptable methods. Sections ofthe ASME code are mandated in 10 CFR 50, Section §50.55a, Codes and Stan-dards, which specifically notes that "Structures, systems, and components ofboiling water and pressurized water-cooled nuclear power plants must meet therequirements of the ASME Boiler and Pressure Vessel Code." Manufacturers anddesigners are expected to use sound engineering practice and Judgment withinthe rules of the Code. The expressed purpose of the Code is to provideprotection of life and property and a margin for deterioration in service fora reasonably long, safe period of usefulness. The review, however, revealsthat material deterioration is not fully addressed and needs attention. TheASME Code does, in general, address "life of plant" issues and, in somecases, it is very specific, e.g., corrosion allowances for vessel and pipethickness. The Code also provides for use of current technology for repairs/replacement and materials by the use of approved Code Cases. The Code is aliving document which is currently revised and published every three years,e.g., the latest was published July 1, 1989. Addenda are issued in Decemberof the years between major publications. Code interpretations are usuallyprovided twice a year as an update service to the various sections.
The following are examples of the Code that are related to aging-management issues:
* A strong implied aging features exist in Section III, Class I, piping.If corrosion or erosion is expected, the piping thickness, shall beincreased over the design thickness to be consistent with the specifieddesign life.
* The ASME Code recognizes that problems exist and, consequently, the codeis under continuous revision to effect improvements and changes. Forexample, a Section XI, Special Working Group (SWG), has implementedrevisions to IWA 2400 which will delete the current 40-year operatinglimit of nuclear plants. A SWG has been set up to consider the develop-ment of a new Section XI, Article IWX-8000, called Requalification ofFatigue Life. A Section III, SWG is also reviewing fatigue curves todetermine revisions to accommodate operation beyond the 40 years. A new
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Subsection IWT for Section XI is now under consideration by ASME; thesubsection addresses the aging-related issue of erosion-corrosion.
3.2.6 Generic Safety Issues
Generic Safety Issues, as their name implies, are concerned with safetyissues common to all NPPs or to types of LWRs, PWRs or BWRs. The GSIs do notexplicitly reference aging management. The GSIs are, however, concerned withmany of the aging issues, and the reader will note that, in the reviews,Appendix II through VI, the aging issues for each component are frequentlythe subject of a GSI, including cracking and degradation of bolts, mitigationof steam generator rupture/degradation, SCC, fracture toughness, corrosion ofinterior metal surfaces, control of overfilling transients, pressurizedthermal shock, and neutron irradiation of RPY welds. Thus the GSIs identifymany aging issues as problems, and this identification process does assist inthe management of aging. When a solution to the problem is determined,management of the problem, i.e., the aging issue, is addressed by the NRCusually through Generic Letters, NUREGs and the SRP/BTP.
Examples of applicable aging issue subjects found in GSIs are listedbelow.
* GSI A-1l notes that as plants accumulate increasing service time thatneutron irradiation reduces the fracture toughness and the initialmargins of safety. This issue was thought to have been resolved byNUREG-0744 (NRC-1982); however, a need to monitor and analyze trends ofnil-ductility temperature exists; that is, what are the impacts ofextended life on brittleness? A related GSI is USI A-49. This issue isconcerned with irradiation of reactor vessel weld and plate materialsand the reduction of fracture toughness in these materials.
* GSI 29 addresses cracking and degradation of bolts and studs from stresscorrosion, fatigue, and boric acid corrosion.
* GSI A-15 addresses the aging issue of corrosion activated by neutronflux. Operation of LWRs result in slow corrosion of interior metalsurfaces of the primary coolant system.
* GSI A-12 addressed the problems of lamellar tearing and low fracturetoughness in SG and reactor pump supports. This problem was alsoaddressed in NUREG-0577 (NRC-1979), Potential for Gas Fracture Toughnessand Lamellar Tearina on PWR Steam Generator and Reactor Coolant PumpSupports.
GSI A-3 and A-4 reported the SG tubing degradation due to wastage andSCC in Westinghouse SG (A-3) and Combustion Engineering SG (A-4).
3.2.7 Institute of Electrical and Electronic Engineers Standards
Many of the IEEE standards provide qualification/acceptance criteria;thus they tend to dictate an aging management perspective through
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qualification testing. The IEEE standards cover a multiplicity of subjectsrelated to electrical and electronic systems. Numerous IEEE standards arededicated specifically to the nuclear industry's Class IE equipment, and itis these specific standards that this review investigated. The IEEE stan-dards are frequently referenced in the regulatory instruments, such as theSRP. The regulatory basis for the use of the IEEE standards is found in theCFRs and the RGs. The NRC RGs frequently, in the 'Regulatory Position* sec-tion, list the IEEE standards that are acceptable (with exceptions) to theNRC staff for satisfying the Commission's regulatory requirements. Thestandards are generally not acceptable in whole and the "Regulatory Position"will state the exceptions or other requirements. The majority of IEEE stan-dards are jointly approved by the ANSI and may be designated as ANSI/IEEE andpublished as an American National Standard.
The following are some specific examples of the explicit and impliedaging management found in the IEEE standards:
* The IEEE standards require that an assessment of the effects of agingmust be addressed when considering the ability of equipment to performsafety functions. Types of aging that must be addressed include vibra-tion, wear, and natural and environmental conditions. Standard 323recognizes the need for aging management and defines the steps toaddress aging. This standard defines aging and explicitly address thesubject. IEEE 323 defines aging as "the effect of operational, environ-mental, and system conditions on equipment during a period of time upto, but not including design basis events, or the process of simulatingthese events."
* IEEE standards recommend establishment of procedural practices to obtainthe qualifying (test) data. The data is required to qualify that theequipment will meet its performance requirements following one safeshutdown earthquake (SSE). Included are tests for vibrational aging,seismic aging and normal operating loads. IEEE 323 defines qualifica-tion as "the generation and maintenance of evidence to ensure that theequipment will operate on demand to meet the system performancerequirements."
* IEEE 934 standard addresses an aging perspective by providing criteriafor the use of replacement parts for both construction and operations.The standard requires acceptance testing of parts for wear, fatigue,defects and insulation breakdown prior to release to service. Failureof parts provides aging management by addressing the aging issues, e.g.,wear and fatigue and insulation breakdown.
3.2.8 American Nuclear Society Standards
The ANS prepares and publishes standards for the design and operation ofNPPs. The standards are usually published as Joint American National Stan-dards Institute (ANSI) and ANS standards. The ANSI/ANS standards tend to bemore safety specific than are the other instruments included in this review.The ANS standards do not, however, explicitly mention aging or aging
3.7
management. They were included in the review because they do address anumber of the aging issues for various components.
Some examples of the ANS standards that can be related to implied agingare as follows:
* ANS-3.2 provides requirements and recommendations for administrativecontrol, including written procedures for activities associated with NPPoperation to help ensure that operations are carried out without unduerisk to health and safety of the public. Among the activities are agingactivities of inspection, testing and maintenance and repair.
* ANS-58.11 provides design criteria for achieving and maintaining coldshutdown conditions from a hot standby or post accident condition. Thisstandard is explicit to safety; however, aging management of pressureand temperature cycles are addressed and adverse conditions are modu-lated by the suggested design criteria that confront nuclear safetyissues of reactivity control, RCS integrity, P/T control, heat removal,and inventory control.
3.2.9 General Correlation of Implied Aging
While the above examples for all of the regulatory instruments andindeed the instrument review itself tend to correlate with the "implied"aging scenario, most of the instruments were developed to emphasize plantdesign and construction, plant pre-operational stages, and SARs. The instru-ments include concepts related to pertinent aging issues, but they were notwritten to solve aging problems or manage those issues. However, it is alsotrue that some of the instruments apply throughout the life of the plant.The SARs are effective for the life of the plant and receive annual updates.Codes and standards, such as IEEE standards, that are noted in the SARs orother correspondence/agreements become a life-of-plant commitment. The Codeof Federal Regulations apply throughout the life of the plant. The TSs applythroughout the length of the license and the ASME B&PV Code, Section XI,applies as long as the plant operates. In addition, the NRC RegulatoryGuides apply and may become part of the license commitment if the utilitycommits to the guidance of the RG. GSI resolutions can be implementedthroughout the life of the NPPs and become part of the licensing base.
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4.0 CONCLUSIONS AND RECOMMENDATIONS
The following conclusions and recommendations were derived from the workcompleted to date on the five components selected for the first part,Volume 1, of the regulatory instrument review.
4.1 CONCLUSIONS
The following are the central conclusions derived from the review:
* The instruments included in this review, with minor exceptions, do notexplicitly use aging or life extension terminology. The instruments, bydefinition, are dedicated to safety and have the ultimate purpose toestablish and maintain safe operation of NPPs. Yet aging managementdoes exist in them because safety-related design, construction andoperation are consistent with the principles needed to provide agingmanagement and life extension. This is to say, the technology associ-ated with providing safety is congruous with technology required formanagement of aging.
* The emphasis in the regulatory instruments is on design, construction,equipment qualification and on the final safety review that will providea safe plant at start-up. Specific actions to address aging and agingmanagement, on the other hand, are generally initiated after a plant isplaced in service.
* Revisions should be made to the instruments that explicitly addressaging, see 4.2, Recommendations. Revisions will be difficult toachieve. Revisions of an instrument by instrument basis is the mostpractical approach at this time.
4.2 RECOMMENDATIONS
The following are the primary recommendations identified as a result ofthe review:
The content of the regulatory instruments need to be changed toexplicitly address the consequences of component, systems or structures(CSS) aging rates. Aging (degradation) rates are often not explicitlyaddressed in the body of the instruments and a key principal in themanagement of aging is understanding the rate of degradation over time.Emphasis on CSS aging rates, in the body of regulatory instruments, willserve five purposes: 1) establish an explicit need in NPP functionaldesign criteria; 2) accelerate the improvement in trending and themethods of obtaining trending data; 3) accelerate the upgrading ofapplicable codes and standards; 4) accelerate the improvement in NDEtools and methods; and 5) improve CSS design and improve the designmargins or the factors of safety needed.
4.1
* Project planning for revisions to the instruments will be a key featurein the success of any revision strategy and should address, as aminimum, the following questions:
1. Should the individual instruments be changed or should a newcomprehensive regulatory guide be prepared to address the agingmanagement issue?
2. What is the status of current industrial aging-related activities,such as EPRI research efforts, Nuclear Management and ResourceCouncil (NUMARC) and Nuclear Plant Life Extension Committee(NUPLEX) reports, industry sponsored working group guidelines,documents and standards? (All sound solutions to aging problemsshould be included in the revision process.)
3. What is the status of existing national society codes and standardsrelative to aging initiatives? This status check should includecodes and/or standards of societies such as ASME, ANS, ANSI,National Fire Code (NFC), American Society of Testing and Materials(ASTM), American Concrete Institute (ACI), IEEE, and PLEX. (ASMEhas been given the overall PLEX responsibility for all standardsgroups.)
4. What is a realistic time frame for implementation of the revisions?
4.2
5.0 SUGGESTED FUTURE REGULATORY INSTRUMENT REVIEW ACTIVITIES
The following are activities that should be considered for future workassociated with this review task.
5.1 CONTINUATION OF THE GUIDE TO REGULATORY INSTRUMENTS
During the course of this instrument review, a Technical EvaluationReport containing the results of the review on LWR reactor pressure vesselswas published: PNL-6848, Guide to Regulatorv Instruments for LWR ReactorPressure Vessels: Aging and License Renewal Considerations. The resultscontained in PNL-6848 are included in this report as Appendix II. It issuggested that the results of all the reviews, Appendix III, IV, and V andthe reviews of FY 1990, be added to PNL-6848.
5.2 COMPUTER DATA BASE FOR THE REGULATORY INSTRUMENT REVIEW
It is suggested that the basic data from the Regulatory InstrumentReview, Appendixes II through VI, be installed on a computer data-base systemto make the information available for broader use. Information collected onother components should be added to the data base as it becomes available.
5.1
6.0 OBSERVATIONS OUTSIDE THE SCOPE OF THE REVIEW
The following are observations and recommendations that arose out of thereview results that are not directly related to the objectives of the instru-ment review. They are based on the analysis of the instruments used to con-duct the review, mainly on a close review of the comments included in thetables in Appendixes II through VI. For final validation, these observationsshould be subject to further study.
COMPONENT REPLACEMENT
In general the regulatory instruments reviewed do not address componentreplacement as an aging management tool. Many components have designfeatures for replacement and have been replaced well within the 40-yearlicense period. Components such as, pumps, valves, motors, electrical andinstrument controls fall within this category and are routinely replaced.Some components, notably the SG and primary piping, were never intended to bereplaced; yet, a number of these replacements have been made within the40-year license period. Some replacement direction is provided throughcomponents under TS surveillance and replacements will be made if repairscannot be successfully performed. Also, electrical qualified (EQ) componentswithin containment will be replaced according to their lifetime qualificationtesting. Thus, the scenario is that replacements are taking place because ofdesign and necessity and within the Jurisdiction of regulations/codes. Theemphasis of the body of instruments, however, does not address replacement asa management tool. It is concluded that the instruments revisions shouldemphasize replacement methods by encouraging design for routine replacementand by encouraging improvement in CSS life assessment methods, includingimproved material degradation trends and component life predictions.
A factor in replacement methods is Diminishing Manufacturing Sources(DMS) or the increased unavailability of parts and components from manu-facturers. DMS results in an increased vertical unsupportability of agingcomponents and subsystems. DMS also results in an increase in maintenancecosts. The NRC has identified DMS problems (NRC 1986) within the nuclearindustry. These problems have resulted in down time and the necessity tooperate in a degraded mode because of unavailable replacement parts. DMS hasbeen identified by the Department of Defense (DOD) as a serious and prevalentproblem. The DOD has, however, taken aggressive action to counteract the DMSphenomenon, e.g., using performance specifications rather than plant speci-fications, using improved long range forecasting and using improved procure-ment techniques. It is suggested that improved component NPP replacementmethods should recognize the DMS problem and actively pursue solutionssimilar to the DOD strategy.
IMPROVED ISI METHODS AND TOOLS
The regulatory instrument review revealed that the management of agingcould be enhanced with improved ISI tools, e.g., Appendix II, page I1.13,item (83) of this review for the reactor pressure vessels, with reference to
6.1
RG 1.150, states that improved flaw detection for the distribution of micro-flaws is needed. Also Appendix III, page III.13, item 92, addresses theaging issue, embrittlement, for the steam generator, with reference to10 CFR 50, Appendix A, Criterion 51. Criterion 51 stipulates that the con-tainment pressure boundary be designed for operating, testing and postulatedaccidents such that the ferritic materials behave in a non brittle manner.The Aging Needs, Column 7 for item 92 states that 'Methods to measureembrittlement properties" are needed. The Life Extension Needs Column 8states that "Improved NDE techniques to determine embrittlement properties"are needed. Therefore, for item 92, the review recognizes the need forimproved NDE to provide in-situ embrittlement evaluation to verify that thecontainment material is behaving in a non brittle manner as stipulated inCriterion 51. Based on the results of the review, research is needed toimprove traditional NDE and dsvjlop new NDE techniques for management ofaging in the following areas: a
1. Effective means to determine fracture toughness and strength, and mate-rial embrittlement, including embrittlement induced by irradiation,hydrogen, and thermal changes. For example, embrittlement appears as aproblem in nine out of eleven priority rankings (NRC 1987b) for PWR com-ponents shown in the priority rankings of NPAR degradation mechanisms.
2. Assessment of magnetic methods for material properties measurements todetect aging degradation of NPP steel materials should be encouraged andcontinued. Magnetic methods (Jiles 1988) may provide the techniques andhave advantages over other NDE for in-situ evaluations especially asapplied to the prediction of fatigue or creep damage.
3. Assessment of the use of acoustic emission (AE) for evaluating thecontinued serviceability of materials should be encouraged. AE is aunique tool that should have capabilities in environmental hardening,toughness, fatigue, and yield strength (Spanner 1979; Spanner 1985; DalRe 1986).
4. Additional improvements are needed for the evaluation of stress corro-sion cracking and intergranular attack on the outside diameter andinside diameter of steam generator tubes. Current technology has prob-lems in this area; in most cases, cracks in the U bends or tube sheetarea cannot be detected until they are through-wall. NDE technologyimprovements are also needed in vessel evaluation. Current methodscannot, with proven accuracy, detect shallow flaws of most interest invessel fracture evaluations.
5. Studies are needed to determine NDE time intervals for inspection andthe amount (coverage) of inspection needed to manage the aging process.(ASME Risk-Based and Reliability studies should provide a probabiliticbasis for optimizing the level of NDE, as well as the intervals.)
(a) This observation supports the need for the current work in NDE toimprove existing techniques and develop new ones.
6.2
WATER CHEMISTRY CONTROL
Water chemistry control is an important aging factor in the operation ofLWRs, including steam generator tube corrosion in PWRs. Although consider-able work on this factor has been conducted, especially in the 1970s, moreresearch may be required before existing guidelines and/or instruments can berevised. As noted in the review, Appendix I1I, page 111.17, item 125,control of primary side water chemistry is technically controlled by the TSs.The comments of item 125 (Column 9) note that secondary side water chemistryis administratively controlled and not controlled by the TSs. The commentsindicate that improvements should be made in the management of the SG'ssecondary water side chemistry.
EMPHASIS ON THE ASME CODE
The ASME BPVC Code is a principal instrument used in the design and con-struction of LWRs and it provides significant guidance and insight into themanagement of aging. The code is a living document with ongoing revisions,and many of the aging issues noted in this review are currently beingaddressed by ASME code committees and special working groups, e.g., thecurrent PVRC Section III/XI committee, is addressing code limitationsincluding PLEX. However, special emphasis needs to be placed in thefollowing areas:
1. Code revisions are needed that more vigorously address material and/orcomponent deterioration as functional criteria of the design.
2. The Code's emphasis on plant design requirements that allow for componentISI, repairs and replacements should continue. Improvements in the codethat prescribe alternate or better design methods for ISI, repairs andreplacements should be encouraged.
3. It has been estimated that a change in the Code takes about eight to tenyears to fully implement. When appropriate, shorter time intervals areneeded for implementing changes in the Code. The time cycle for specificitems that did not appear in earlier codes needs to be shortened. (In someinstances the time cycle has been shorten; it can be done. For example anew subsection for Section XI, [WT on erosion and corrosion, was approved byASME's Main Committee within a three year time frame and in two years afterASME's Council on Codes and Standards gave the go-ahead. An additionalproblem, however, exists after the ASME involvement and that is theimplementation through 10 CFR 50, 50.55a Codes and Standards. Thus, achange in code can also be coupled with the implementation delays. ASMECode Case(s) procedures and the RGs that identify acceptable cases certainlyhelp the overall picture, but they are not the total answer.)
6.3
7.0 REFERENCES
U.S. Nuclear Regulatory Commission (NRC). 1987a. Nuclear Plant AgingResearch (NPAR) Program Plan. NUREG-1144, Rev. 1., Washington, D.C.
U.S. Nuclear Regulatory Commission (NRC). 1987b. Residual Life Assessmentof Major Light Water Reactor Components--Overview. NUREG/CR-4731, Vol. 1EGG-2469, eds., V. N. Shah and P. E. MacDonald, Idaho National EngineeringLaboratory, Idaho Falls, Idaho.
U.S. Nuclear Regulatory Commission (NRC). 1982. Resolution of the Reactor(Task A-li) Vessel Materials Toughness Safety Issues. NUREG-00744,Washington, D.C.
U.S. Nuclear Regulatory Commission (NRC). 1979. Potential for Low FractureToughness and Lamellar Tearing on PWR Steam Generator and Reactor CoolantPump Supports. NUREG-0577, Washington, D.C.
Jiles, D. C. 1988. Review of Magnetic Methods for Nondestructive Evaluation.Center for Nondestructive Evaluation, Iowa State University, Ames, Iowa.
U.S. Nuclear Regulatory Commission (NRC). 1986. Status of Maintenance inthe U.S. Nuclear Power Industry - 1985. NUREG-1212, Vol. 2, Washington, D.C.
Spanner, J. C., Sr. 1979. Acoustic Emission - Some Examples of IncreasingIndustrial Maturity. American Society for Testing and Materials,Philadelphia, Pennsylvania.
Spanner, J. C., Sr. 1985. Acoustic Emission. Pressure Vessel and PipingTechnologv 1985 - A Decade of Progress. American Society of MechanicalEngineers, New York, New York.
Dal Re, V. January-March 1986. Fracture Toughness Measurement of a NiCrMoSteel by Acoustic Emission. Journal of Acoustic Emission, Vol. 5, No. 1,pp. 39-44. Acoustic Emission Group, University of California at Los Angeles,Los Angeles, California.
7.1
APPENDIX I
GLOSSARY AGING ISSUES
APPENDIX I
GLOSSARY OF AGING ISSUES
corrosion - Corrosion is an aging issue that applies to all components invarying degrees and is manifested in different ways. Corrosion in the broadsense is the deterioration of material surfaces, chiefly, through electro-chemical reactions and is influenced by the environment of the material orcomponent, e.g., high humidity. A familiar example is the rusting of iron.Corrosion is also linked to other aging issues by causing an acceleration ofthe degradation, e.g., stress corrosion cracking, irradiated assistedcorrosion cracking, corrosion fatigue, and corrosion/erosion.
corrosion/erosion - Corrosion/erosion occurs when the eroding fluid (liquidor gas) or particulate matter is in the presence of or contains corrosioncausing products, i.e., the corrosion reaction is accelerated by the relativemovement of the corrosive fluid and the metal surface. This mechanisminvolves the effects of mechanical wear or abrasion. Characteristics ofcorrosion/erosion are the appearance of grooves, gullies, waves, round holesand valleys on the surface of the component. An example of corrosion/erosionis tube wall thinning caused by impingement of water droplets containingsuspended solids.
crack formation and flaw growth - Material crack formation and fatigue growthof flaws are indicators of material degradation and possible failure bythrough-wall cracks. A crack is a discontinuity at a particular location ina material as a result of localized excessive elastic/plastic deformation. Acrack will propagate as long as the tensile stress acting on the componentsupplies sufficient energy to sustain a new crack surface (this aging issueis related fatigue and SCC, i.e, without a driver a crack will not grow).Present methods of flaw and crack detection are not 100% effective andimprovements are needed for evaluation of crack initiation and growth. Theissue also encompasses human factors of NDE staff, e.g., training.
creep/swelling - Creep is defined as the progressive deformation of amaterial at constant stress. Creep failure (fracture) or stress ruptureexhibits the influence of relative high temperatures on long-time load-bearing characteristics. The creep temperature is often expressed as ahomologous temperature, i.e., the ratio of the operating temperature T to theabsolute melting temperature Tm (K). Creep of load carrying componentsbecomes of importance at a homologous temperature greater than a ratio of0.50. Load carrying components operating in the temperature range of 5380Cto 8700C (10000F to 16000F) are susceptible to creep. Generally, creep isnot a major problem in LWRs because of their temperature operating levels.These levels at around 550¶F are below the creep range for ASME Codematerials specified in ASME BPVC, Section III. This aging mechanism, how-ever, is of interest to the NPAR program because of its impact on electricalcomponents/systems. An increase in the dimensions of components (e.g., fuelelements, and fuel cladding) swelling is caused by the accumulation of
I.1
fission product atoms in the structural lattice of components. The fissionproducts occupy a larger volume than the original material which causedswelling.
element burnout(s) - Element burnouts and repair and replacement of heatersare identified as an aging issue for the pressurizer vessels.
erosion - Erosion is a broad aging issue that is principally associated withfluid flow in components. High velocity water impingement can erode thewalls of pipe and fittings. By definition pure erosion is the mechanical orwear action of a fluid and/or particulate matter on the surface of componentparts. Erosion is usually accelerated by the presence of solid particles inflowing fluid. The possible consequences of typical erosion is the thinningof a pipe wall to failure.
examination, inspection and maintenance and repair - These activities may beconsidered aging issues because the management of aging is affected by theseactivities and in some cases aging is accelerated by poor examination, harshinspection, and improper maintenance and repair. Also conditions may existthat do not permit adequate performance of the activities.
excessive/harsh testing - Testing programs and procedures that require exces-sive testing can lead to accelerated aging, e.g., harsh testing programsassociated with the emergency diesel generators have been identified ascontributors to aging.
fatigue - Fatigue in reactor operations is broadly defined as structuralweakness and loss of resiliency in materials resulting from stressors, e.g.,vibrations and thermally-induced fatigue cracks. Fatigue is defined as thephenomenon leading to fracture under repeated or fluctuating stresses havinga maximum value less than the tensile strength of the material. Stressinduced by stratified flow is an example of thermal fatigue. As the nameimplies, in stratified flows the cool water flows on the bottom of the pipewhile steam flows on the top. These conditions can cause temperaturedifferences that can lead to thermal cycling and fatigue of piping systems,e.g., pressurizer spray line and vessel nozzles.
fracture toughness - Fracture toughness is a material property that relatesto the ability to resist fracture. Fracture toughness is related to theunique stress intensity level that causes failure in a component (is alsocalled the critical stress intensity level). Its measure is the stressintensity factor, which incorporates both geometrical terms (the crack lengthappears explicitly, while the crack tip radius is assumed to be very sharp)and the stress level. It is an embrittlement aging issue specific to NPPsbecause ferritic materials suffer from decrease in fracture toughness as aresult of irradiation. The CFRs specifically provide limits for the RPVmaterial tests, i.e., initial Charpy tests of material shall be 75 ft-lb(102J) and throughout the life of the vessel shall not be less than 50 ft-lb(68J). Additionally, the material RTNDT is limited by the PTS screeningrule.
1.2
intergranular stress corrosion cracking (IGSCC) - IGSCC is a preferentialcorrosion at the grain boundaries of a susceptible metal or alloy in thepresence of a chemically aggressive environment, e.g., hot oxygenated water,and a tensile stress. IGSCC has occurred in austenitic SS in oxidizingenvironments such as BWRs. It also has occurred in SG tubes, safe ends, andtype 304 SS piping. The principal concern is that SCC can cause ruptures,leakages, and plant shutdowns.
irradiation embrittlement - Irradiation embrittlement is defined as adecrease in fracture toughness due to long-term exposure to nuclear radia-tion. High neutron fluence levels can cause embrittlement in the RPVbeltline region as well as other reactor internals and core supports. Areduction in tensile ductility is also caused by the neutron exposure.
low-flux long-time irradiation of vessel, vessel internals and supports -This aging issue is principally identified for the RPVs and vessel supports.Long-term flux reduces toughness and initial margins of safety in RPVs.
seismic failure/damage - Aging issues associated with earthquake damage wereconsidered. Although not a classic aging issue, NPPs are required to evalu-ate seismic conditions and the consequences of natural phenomena and thedamage that may result from these events. Aging could weaken a component sothat it would not be able to withstand a seismic event.
specific environmental factors, e.g., moisture, oxidation, chemicals, oils,and dust - Environmental factors can induce aging in many NPP components.For this review the factors of moisture, chemicals, oils, dust, etc., areprimarily of concern in the operation, testing, and performance of the EDGs.Because these factors can induce aging, physical location, surroundings,housekeeping and maintenance are important to EDGs. All these factors orelements can accelerate many of the aging mechanisms associated with theoperation of diesel engines and their support equipment.
stress corrosion cracking (SCC) - SCC is degradation associated crackingaccelerated by the combined effect of constant tensile stress, corrosionenvironments and susceptible microstructures. The stress may be residual inthe material, as from cold working or heat treatment, or it may be externallyapplied. The observed crack may be transgranular or intergranular, dependingon the nature of material and the environment. This term is a broader agingterm than IGSCC and has been linked to bolting degradation in many cases as aprincipal aging problem, e.g., leaking steam through gaskets can react withthe bolting lubricants and cause SCC.
stud failure - This aging issue is a factor in degradation of closures,flanges, manways, etc., through the cracking of bolts and studs from stresscorrosion, fatigue, and corrosion.
thermal cycles - Aging issues are aligned with temperature cycles. Thermalcycling induces stress through thermal gradients/temperature changes.Thermal cycling induces thermal stress, low-cycle thermal fatigue, and highcycle fatigue (water temperature fluctuations). Low-cycle fatigue is defined
1.3
as fatigue caused by high stresses and low numbers of cycles. Significantplastic strains occur during each cycle. Cycle lives are less than 104 to100. High-cycle fatigue is defined as fatigue caused by low stresses andhigh numbers of cycles. Strain cycles are in the elastic range. Cycle livesare greater than 10 to 100.
thermal aging embrittlement - Thermal embrittlement is defined as a reductionin the ductility of a susceptible material due to a chemical changeinfluenced by high temperature for long times. Thermal embrittlement of caststainless steel components (pump housing, valve bodies, piping and fittings,etc.) is possible over periods of many years, resulting in increased criticalflaw sizes. Thermal aging can significantly reduce fracture toughness andductility of LWR reactor components materials. The rate of thermalembrittlement generally increases with increase in temperatures; however,specific material compositions of various steels are factors in thermalembrittlement.
thermally induced bending - This aging issue is principally (for this review)associated with the pressurizer caused by high-and low-cycle thermal loads atthe water-steam interface in the vessel wall. (Thermally induced bendingstresses can be a factor at other locations).
thermally induced mechanical wear - This aging issue is principally (for thisreview) associated with the heater failure in pressurizers caused by wearingand thinning of the heater due to rubbing action with supports because ofthermal growth.
transient thermal and pressure loads - Transient or short thermal loads havebeen identified (for this review) as the transients effecting the pressurizerduring heatups, cooldowns, testing, and abnormal events. For example,transients can occur in a few seconds and cause temperature changes of 55 C(1006F) in the surge-line nozzle.
tube specific - denting, fretting and crevices - These aging issues are SGtube specific. Denting results from crevice corrosion of the tube supportplate and tubesheet materials; corrosion of carbon steel support plate andtubesheet squeezes the tube outside diameter and can result in decrease ofthermal efficiency and cracking in the tube. Crevices provide areas forlocalized corrosion due to stagnant solutions in lap joints, holes, weldingsurfaces etc. Fretting in SGs results principally from wear action betweenthe tube and tube supports and antivibration bars.
vibration - Vibration is a broad aging issue that can cause degradation inmany of the components. Vibration by definition is any physical processwhich produces cyclic variations or motion. It is an aging issue to theextent that the vibration may cause failure or damage to a component.Excessive vibration can damage components by wear and promote materialmechanical fatigue and pipe weld fatigue cracking. Vibration is a dynamicaction and is associated in this review primarily with piping systems and theEDG. Dynamic loads are caused by response of the component to an oscillatinginput, e.g., flowing water or a rotating equipment.
I.4
wear - Wear usually results from the relative motion between two surfaces.Wear is the removal of discrete particles of material from a solid surface bythe relative motion between that surface and one or more contacting surfaces.Wear is accelerated by hard and abrasive particles or action of fluids(erosion), vibration, or corrosive environments. The common result of wearis the reduction of thickness or damage to the mating surfaces. Wear is of aconcern in rotating machinery, e.g., in pumps and EDGs and the otherequipment/parts, e.g., valves stems and seats, and other mechanism subject tomotion and vibration.
weldments - specific to dissimilar metals of safe ends - Weldments are formedby the welding together an assembly of pieces such as pipe to nozzles. Safe-end weldments have specific problems due to dissimilar metals. Among theseare low-cycle thermal and mechanical fatigue, and IGSCC in the heat affectedzone (HAZ) in the base metal.
I.5
APPENDIX II
REGULATORY INSTRUMENT REVIEW FOR REACTOR PRESSURE VESSEL
Understanding and managingaging of PWR reactor pressurevessels
Temrperaturo iF0 200-4O -200
l l l l
Mateas Vessel Low alloyabon .t SASS3S-1SA50W2 &SD3028
Cladding 1rType 30 55 nd 309 SS,Wuldments Submerged we (grnular Itux -linde
M0 91 124 nd 1092
miller wirel narrow gap submergedmr. shielded metal arc, andelectrostag
Closu studs SA-S40 Or. 924 Clas S
Neutron flux an fluenee, temperaUr, recorcoolant, cyclic the rma and mechanical loadpreloeds, and borie aeid leakage
cg200I
Ur 41
Upper shelfUnirradidetd (ductile Iailure)
Ductile to biittletransition temperature
Lower shelf(brittle failure) i sladiated
a0
16
u _ _ _ . _ _. u
-300 -1 0 iSO 300StressorsVWdEnvironment
Temperature (C)
Effect of Irradiation on the Charpy impact energy for a nuclearpressure vessel steel.
Typical PWR vessel showing Important degredation sites.
UNDERSTANDING AGING MANAGING AGING(Materials, Stressors, & Environment Interactions)
Sites I Aging Concerns Inservice Inspections, Surveillance, and Monitoring I Mitigation
eit Iine region irredlation embrttflament
* Chemical composition ofWesse materials (Cu. Ni, P)
* Drop In upper shelf onerg (USE)
* Shift In relerenc nil-ductifltytrons llntempenrtue (FT )
Environmentai fatigu
i-41-4q
NRC Requirements
Survelilance program to heessirradiation damae, Le., shift In RTOTand drop In USE (I0 CPR 50 AM H.Rag. Guide 1.99 Rev. 2)
Pressurized thermal shock PS) screeicrtierb (10 CFR 10.631tFTS rule, RQ 1.154Dameg evaluation (10 CFR 50 App. 0)Pressure -Temperature (M) limIts duringhestup, cooldown, crIticality, and Inservceleakage and hydrostaic pressure test toprevent nonductile fracture (lbch. Specrequimment, 10 CFR SO AMF 0)
P-T limits are also applied to non-ilbitline egion j
Low temperature overpressurizatlon (LTOP)prtection setpoint (Tech. Spec. requirement
VolumetrI examination of at we lddurn sech Inspection interval (10 CPR 50.59,iW&250M Rag. Gude 1.150, Rev. 1)
Flaw evaluation (tO CVR 5D55a, JOO.3000)
Lakage and hydrostatic pressure tests(10 CM 50.5sa, IWA-WSOC)
RecommendationsInclude fracture toughness end tensiletest specimen In surveillance program
Develop use of reconstituted andminiture semens
Deveop techniques for In situdetermination of mechanical propetltb
Peorm acceteeked irradiaton testsof reconstituted specimens
Revise Rbtg. Cuod 1.". Rev. 2 to accountfor phosphonrs with kow copper
Use state-of-the-art ultrason inspectiontechnies for piprod melhlHtyo deecdetection, otzing, and characterization
Automated mplitude-based sye msTip diffraction techniquesLg-diaetr focused tranaducer
Uae fatie crack growth curves(ASME SC Xl, Appeix A)
Develop acoustic amieslo monitoring to'detet crack growth (Nonmnar"appewdix Is being developed forASME Sction XI)
Neutron flux reduction
Inservice annealing(ASTM E 509-86)Determine efhets ofannealig andovembi Itlement rate
Oullefiinlet nonlies Evionmenm t tat gus Volumetric examination of sit nonzle-to-vessel Use on-line fatiue monitoringwels and nozzle inside radu sections (monitorIng of pipe wait ltmperatures
Irradiation embittlement during each Inspection Interval 1WS-2500) nd coolant fows, temperatures. andFunction of nozzle eevation prs )Potential impact Of Volumetrc and surface examination of sit Evatuate Irradiation .mbritfltem nt
kRag. Guide 1.119, Rev. 2) dIssimilar metal weids during each inspection damageIntervralPIWB-2S00)
Instrumentaion nonbles Ernvlrnmentit ltigu Visual examinalon of external weldCRDM housing nozzles surface of 25% ot nonles during
system hydrostatic test IW-2500)
Environmental fatigus Volumetric and surtace examinailon of itClosure studs -prnied cycles during heed replacement studs and threads in flange stud holes
itorc id corrosion if leakage occurs) during each inpect on interval (iW-2500)rev. S
Understanding and managingaging of BWR pressure vessels
1aterials
StresorsandlEnvronient
Vessel - Low silcy carbon steelSA.638.t. SA.3020
Cladding Type 3068 S or 5.SS.Nozzle SA-508-2Sole Ends wpe 304 SS, Type 316 E5.
Inconel S8-166, Inconel 5-16Z7SA-5061-
Thermal Sleeve.- Type 304 SSClosure Studs SA-U40 Gr. 822 or 023Weldenis . SA"193 Or. it
Opereatlnal transients, neutron flux and fluence.temperature, and isct coolant
tI amer
Typical SWN pressure vessel Cross aection of fedwster nozzle with cracking locatIon
6-1
UNDERSTANDING AGING MANAGING AGING(Materials, Stressors, and Environmental Interaotions)
Sites Aging Concerns Inservice Inspection, Surveillance, and Monitoring MitigationFeedwater nozzle* and HIg.cycl thermal 'Ugw caused NRC Requirements Rscommendmtcon Modify design,ssle end welds by leedwaler leikage Use on-line fatigue monitoring procedures, and
Environmental fatigue Volumetric examination ofall1 nozzle-to-vessel (moniring of pipe wal tuempertures u r mov edwaterwelds and nozzle inside radus sections during coolan flows, temperatures, and pressures nozzle cladding toeach InspectIon Interval (IWO-2500) Develop criteria or assessing high-cycle prevent batigue
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~~ f tig ue d a m ag e crac ktn gVolumetric and surface examination of all faiudmg cckn
Recirculation Inletoulet 1GSCC crack InItIated In HAZ may propagate dissimilar metal welds during sach inspection Develop on-line corrosion monitoring Implement hydrogennozzlee and dbissmilbr Into be metal interval (IWi32600) Evaluste long-term stlects ol hydrogen rwduce IGSCCmetal w eld Environmental t'ue water chemistry damage
Weods IGsCC crack Initiated In HAZ may propagate Visual examination of all accessible Interior Develop robotics system for remote-Control rod drive Into bae metal by corrosion andhor attachment welds during each Inspection Inspection probe positioning and
stub tubes environmental fatigue Interval (PWO-260) scanning-Interior attachments
eitirne Region Irradiation embrittlement Surveillance program to assess shift In br Revise Rg. Guide 1itS, Rev. 2 to Insrvwce annalingChemical composition of vessel meterials and drop In USE (10 CFR li App. H, account or phosphorous when copper (ASTM E t609)(Cu, Ni P) Reg. Gukde 199, Rev. 2) content le low
-Drop In upper shelf energy (USE) Detemnine effects ofShift In reference niI-ductility-transiton- D ie 5vluatUon (10 CFR 50 App. G) Use Itntso-the Inpaction nneling andtempera tre (Ro) PrssrrT lmit during Improved reliability of rembrittlement ratsPressre-teperatre (PT) liits dring defect detection, sizing,anAWe ae me susceptible than be heatup, cooldown. criticallty. and Inservice characterization mplement neutron
meta leakage and hydrostatic pressure tests to lux reductionFlux is lower then that In PWR vessel prevent nonductile fracture (Tech. spec. Develop robotics system for remote pgrem
requlrment, 10 CFR 50 App. M) Inspection probe positioning andEnvironmental fatigue [P-T limits are also applied to non- batllne canning
region] Include fracture toughness nd btensle
Volumetric examination of all se11 welds during tedt*pecim In urvillanc pmgr meach Inspection Interval (10 CFR sSUe, Develop use of reconstituted andIWS-2500. Reg. Guide 1,150, Rev. 1) miniature specimens and accelerated
Flow evsksetion (10 CFR 60.55a, IWB-3000) Irradiation of recondtitued specimen
Use fatigue crack growth curves (ASMELeakage and hydrostatic pressure tests (10 CFR Section Xi, Appendix A)5O55a, IWA 4000, IWO-5000)
Develop acoustIc emission monitoring todetec crack growth (nonmandatoryappendix Is being developed by ASMESection XI)
Closure Studs Fatigue, tting Volumetric and surface examination of al studsand threads In flange stud holes during eachInspectIon Interval tIWO-2500)
External attachment Lowcyce th rmnat and mechanical fatigue Volumetric or surface examination (IWI-2500)welds such as skirtsupports
MV. 4 ml*
REGULATORY INSTRUMENT REVIEW FOR REACTOR PRESSURE VESSEL
(1)EXAMINATION, IiiSPEC-TION fAND StIML.-LAN"U (115)
REG. INSTRUIENTDDLUMN 3
10 CFR 50 Appe.A Criterion 32
AGING fEATURES
The RPv should be de-signed to permit in-spections.
LIFE EXTENSIONFEATURESCOLmUM S
NM
CURREtlT INITIATIVESCCLLUNI 6
AFPropriate meguresare being definedfor plunts whereinspections aredifficult.
AGIG NtEEDSCOUItI 7
t/A. Design donn tehaws over time.
(2) 10 CFR 50, All Inspection proerApx. C (111) as per the ASHE eode.
(3) 10 CfO S0 Surveillance mVorInservIco axaineationor fracture toud-nese
NM Evayulte effects of agean the material proper-tien used in the cal-culations (see epbrit-tlment Issue).
Appm. C (V-5.
C.
10 CFN 50,AP.N H
Alternate criteria in-wiving ISI per ASESection Xl
LIFE ExTENSION NEEDSCO~teqe 8
RPVs need to be consid-ered for aeceptabilityif crItical ares afrenot eityy inepected.
Inspections My need touse different proceduresaimed at detectingeging/degradetion fortife evalustion includ-
ing irradiation andfatIgue failure mdes.
Are r_ operating limitsad Ine etion frequn-cies need for lifeexteneion? Inspectioncriteria for irradiationand fatigue failuremdes myb ned
Asument of the with-drewet scheckte andrsaier of saotes my beed. Copsutes my
need to be reinserted orpre-irrediated caeutesmy roed to be inserted.Anesteling effects neediwestioation.
The unr eiability ofdcetectlor iolng ft abecause of cladingeffects should be ad-dressed. Ntam factoreffects of lDE staffshould also beaddressed.
Assesx t of acceter-ated Irrediation ef-fects.
ceExTSCOLtM 9
The pressure boissary should be designed to permitinspections and qropzria meterlal surveillanceprogrum for the RsV p, e ging related criteria myred to be written and referenced by this criterion.Currently the plants are required to apply criterion32 or mee a best effort to inspeet the RPV.
Should reflect life xtsensIon decislons ad agingresearch. Evidence for aging of RPV hardare in-cludes erosive degradetion of thimble tubes. A needaxists for a new ben tine esxainetion.
10 CFR SO Appm C (IV) requirnts at be satisfiedprior to life axtension. squirmnts for operationis 10 CFx S0 Appx. C (IV) is not satisfied: Beitlineftls exmined as per ASME Section XI. Work Isneeded to include life extension decisions ard agingresearch. Inspection examptione will neod to bereconsidered for life extension.
no _ternat lturveillence progree Is required forSPt for thith It cen be deinstrated the peakneutron flusnt.,7t the ead of the design life witlrot exced 10 nlem (E >1 May). The capeuleprogre should be as per ASTN E-IOS. Capsule otca-tiona ad wlthdrmeet schedutes are reguired. Madifl-cations to ASTl E-I1S for cpule withdr-wal *chofor ne fuel management progrm are in progress.Similar designed ad operated reactors my useIntegrated ourvailtareo progr.
Current ftlt detection system are not 100% effec-tive. Detection syst should be ibproved.Accessibility to SWR PRvs is a problem; remotesctnnrs are ne dd.
Extand ticense If sufficient margins exist.
.-
CA)
(O) Copeule survey proFem. xron to exist. Assessment of the with-drool schedute andruber of sampLes my beneded. Alternate test-ing methods (i.e. mini-saples) should becoamiddred.
(S) Tech Spec 4.0.5 O S erences ANNE SectionXl .
FetIr. Adeences In ailabletDE technology arenedd to detect sohattwfloes of t interestin vessel fractureevaluations.
(6) Tech Spec4.4.9.1.2
Capsule Suvey Program urveitlenea ofWV tranienttemperatures
Testing ampte freqiuncy. Alternate testingmethods lie. mini-samles) should beconsidered.
General NotesII. A I" ldicete furthed Ntudy/Iieetl tlla to es _bd.2. For the Nis, xrXsotwet mum the enle safety leae is roolved, not necessarily the egirs lsen.3. For miseng Of aberevletirm, ecrornE and Initlilaio, used throghoAt, o ecronym on peg xi, Xill and xNiM of the report.
-- Reactor Pressure VesseL
Cta tlNt ISStE BEG. INSTALMENT AGING FEATAES(XLttt I CtctdUM SP 3 3..u.. 4
(7) EIS tctd) SttP 3.9.2.1.4 tlOttE
LIFE EENSIWIFEATURES
US
aLRyT INITIATIVEStCOLUM 6
NOME
AGING NEEDSM UItA t 7
5A
LIFE EXTEtSICtt MEEStCOL:W~tt
Should the SAP edtresslife ectension?
(a)
(9)
SAP Inservice Inepectian code USNE5.2.1.2.11.2 C"s ard EG mW icabi l-
ity.
SWP 5.2.4.11.4 In service inspection USMEIntervals.
mm
mm
Need to verity that the USEreference code casescover an adeqate tiespn for reactor opra-tin.
COMENTSCU1LS~a 9
Testing during pre-poeratioa and stanhup testprroar ThIts aection diee not aply aft r the startof plant operatiorn.
Acceptable code cases for insarvice irnpectiin arefound in Bag. ulde 1.147. Cods cans t at be re-vieSd every three years.
Eequired in ections ant be performd en reactorcoolant preasre beuddry components durin each10-year Interval of service as per ASE Section XIIWfA-2000. option.. impose inspection plan A.
(10)
(12)
SEP 5.3.1.1.3 aorslsstructive exmin- UOSEtinr CWE)
SRP 5.3.1.1.6 surveillaice det, coltec- USEtion over vessnl life-tim.
SEP 5.3.1.11.6 NateriaL Surveillance. WE
SxP 5.3.1.111.6 Flume calculation or USWsurvel lance.
US
USE
US
See note 1.
US"
t-t
Dotes inpection freqeer-cy need to be IncreasedIn the test ten vorinterval? More exten-sive euaXinations my beneeded.
Asseamnt of the with-dral adiaedlh aidnuter of smples my hended. Atternate teat-ing methods (i.e., mini-s.ptes) should beconsidered.
Asessment of the with-dreaat schedule mndnuber of smplee my beneeded. Alternate teat-ing mathade (i.e. mtni-suptes) should becontidered.
Assessment of the with-draIt schedule andruber of s*ptes my bendd. Alternate teetlng method (I.e. WMli-sIptes h bould beconrlidred.
fppropriate reutlatoryinotruents xat beecdifled for aging.Alternate testing _th-od i~e tt i ni-saptes),should be considered.tEvime of cIrOaerenrtial wslde ad theeffects of streiing eraalso needed.
Should the SaP adresstifE extension?
Should the SEP atresetIfe extension?
Should the SP ddresslife extenalon?
Should the SRP addesLife extension?
Should the SiP addresslife extelson?
Special tethods for tIE other than those in ASHEshould be reviewed.
iPV asuveilelnce mat be performed to monitorchaines in fracture toushneos properties.
No interail surveillence program Is required it 7itis rown thet the flumee silt be less than 10nloe, tE * I Nev). If this is not Not, a surveil-late proarn is needed as per ASTM EiMS. Irra-diation _ge is a tess severe prdble for kIsnthen for PURs.
End-of-life fluencet mt be Less than the asximas ort erveillaice ac beas per ASTT EtIE.
The SIP provide a sa ary oF the requirements forfracture toughtess, pressure, taperature, adsuirtace reuirments s stated In ASlE codesVd 10 Cfl 50
Bow life extensiondocunent that reflectstim pester than fortyyears?
(13)
(14) SEP 53S3 ETP Frecture toushiesse5-2A preeur, toeperature.
ad a t c rewUire-mnts.
WM
-- Reector Pressure Vessel
IUPONIENT
(13)
(16)
(1?)
BII$ (contd)
(18)
(19)
(203
(21)
tEC. INSTRIIENT AGING FEATIEnCOLtlh 5 aimO 4
RC 1.150 VJT of WV wtids.
R0 1.154 In situ teat for fstiue.
RC 1.4 Trace .lnt efftcts onlectrolag welAd: reIid-
uL lsteeats not camsidered.
NO 1.65 ,Dtju for crOck, tc. inStuds.
RC 1.2 In situ test for fatlgus.
A5 Sc Xi idontifies the rules end10-2200 rmquiremnts f or Inrpec-
t 2310 I tiln responsibiiilles.Iu-2400 accessibility, e ira-
timo methods, pirOffitqual ifications frequencyand records. Hinim..bais for slt require--nts.
CSI 29 Cracking end dsqradstionof bolts end *tuis fromstress corrosion,fatigue, boric acidcorrosion nd erosioncorrosion.
LIFE EXTmIiilExAiJRES
COLLMte 5
Inervice lntpec-tirn ISl)
iOE
OAREs? IIIITIATIWS
1St
lmll
eSOE
ROSE
Sec Xl under revieufor life extensionopplicability
601MGt 56CS
Setter flew detectionsyste are d fordistributed micro-felws.
ieeds resulatory post-tin developwant.
Asees Effects of rssid-utt *lnnts.
Revise 1C 1.65
N.eds regulatory posi-tion de It .
Atlaeote testing oee*-ode (i.e. minf-asoptes)should be camridered.
osen the inapetionfrequemcy or fractionImpacted need to beincre-ed for exttededlife? Do records n.dto be Miinteined andanalyzed for trerds ofreplaced studs ardbolts?
Further wnilysis needed.
LItE SXTElgiS I~i31aSLiV EU10II NED
Ihmn factors of "Eshould be evxlusted,i.e.. flaw incorrectlysized should be evelded.
seeds regulatory Poi-tion developoant.
Needs regulatory posi-tion developnt.
Revise to 1.65
seeds reiulatory p051-lion dlqnt.
N/A
Further anelysis n d.
Further nawlyse nnd.
CIL" 9
lOE of woids for crock initiation and Growth. kewdetection eystin would cotatitute a Mjor itfefort. Is 100l UT required for ONs, to ane
urdr clading cracks? Creach my pisto fromcladding into steel in the "V.
Applies to pre-totrtup vibration tests. The VA doesnot coenider fluane effects.
Applies to pre-startup Vibration tests. The NG doesnot conelder flouece effects.
The doc ont slow for the Mnitoring of studs for_ e with tiem.
Applies to pre-startup vibration tet$. The to doenot ctaulder ftuwt effects.
Applies to the prie retainint c an only.The only life uteneion application is the detaen,fabrie tion, instellation xnd in ltion of replace-MOnt c wuntS. Specific raquiremit are Found InAxE Set Xi 110-25W0.
Bolting deogrdation or failure In nuclear pewaplants
Priority - HIltProposed Imnpedng i10T of bolts eaa outage.xteding on outage 1.5 da.
This Isaw is treed than stutds nd bolts forthe AV.
LUwalyzed Y tihewet stress during netural cetion cooldown. Priority -- ID"i
Additionol low toopersture overpressure protectionfor Lafa* Priority -- "1IN1
Stre corroeion crafting of pressure bounryferritic steals in selected environnit
Priority -- LOWC ltsseifled as Licensing Ilesa
'-4'-a
(7,
(22) DO179
OSI 94
astIII
Axilt terature gradi- mEwnts that could cmetheel stress in thefleow *re or In theStuds. Cycling over thelife of the plant myredxo fetiga _rgin.
eIar overpreesur. of the iNeKS, In coobinatlon withthe existaence of flows,could result in a bCrttt1failure of the RPY.
Stress corrosion cracking mE
NaOE
(2M) further wNalysis needed. Further Analysis neded
(24) ROME Further analysis nd. Further analysis n d.
-- Reactor Pressure Vesel
VOMOULkNT ISSUE-922I- COL
(25) ElS (contd)
(26)
(27)
REG. INSTRUMENT
GSI A-11
AMI& FEATaRESCOLUi.N 4
As plants accum (ateIncreasing ervice time,neutron irradiationredjces the eaterialfracture tamhess anrdinital irgine of safe-ty.
LIFE EXTEASIONFCAIIIAES titREAit IiIITIATIOIS
CDLM
A=IAG tiEEDSCaLmed 7
monitor md analyzetrends of Nilt-Ductititytemperature
LIFE EXEISMIOK NEEDS
Further analysis needed.
COINIiE9TSM~oI- a
GSI A-26 ToIughess at low teera- NOEture
USt A-R9 iucron irradiation of NONEthe reactor pressurevessel weld nd platemterfals decrage thefracture toughness of theeateriats.
Further mialysis needed. Further Analysis needed.
Reactor vee materials toughness. Priority -- RESOLVED with issunce of IIMEG-07U
And Geric Letter A2-66See A-49 for a related discASion.
Ractor Preasure Vessel
Reactor Pressure Vessel Transient. Priority -- RESOLVED with pbli cation of
W1EAs-0224 and WP 5.2* urous reported presre transients In Pwesshare TS pressure ard terature limits wereexceeded. iMaority at solid water condition ofstartup or shutdon arid reLatively tow reactortemperature. Less toughness at low teeereture,therefore aore susceptible to brittle fracture.
Preesurited Thermat Shock (PIS)* uesolution for aging sill be affected by licensee
actions that include anrealing and fuet mense-sent practices to reduce flue at reactor pressurevessel.
Load, load combinations, stress limits* Priority-- NIGa* see iaEG-28o0 Skpl
Priasry syatm vibratiare. Priority -- RESOLVED
Monitor And neltyxetrade of Ail-Suctilitytoperature.
Further mnelysis needed.
Further analysis isned to daternine whatimpact life extensionwilt have on thebrittleness of RPVmaterials.
Further Anelysis needed.F-i
P-4 (28) CSI 1-6 Through watt cracks and OiEfatigue crack growth
UWE
(291 GSI C-l2 Structural damge byvibrations of sufficientmagnitude, Fretting dumto deficient design andmaterial selection foranti-vibration bars.Fatigue faiiure, particu-terty at nozzles wharestresses are highest.
Further analysis needed. Further Analysis needed.
RPV IRRADIAIIONi EI6iT-(30) TLEIiET , FRACTURE
TOUIGNESS (IEFT)
(31)
(32)
1D CPR 50.5
54 Syste aerd comonentdesigns shall eet ASKErequiremnts.
10 CFR 50.60 Acceptable criteria forfracture prevention.
tO CFR 50.61 fracture toughness re-qiirssents to protectagainst PTS
Reference documents needto reflect aging.
NONE
See note 1.
Sef erence decrmnts needto reflect aging.
lopedt of aging onIncreased risk for PIS-related event occurrenceneded to be addressed.
Related documents needto be reviswed for lifeextension.
Amw document section mybe needed to addresslife extension.
P19 needs to be betteruiderstood for the pltntconditions that wouldexist after life estan-amie.
ASxE reluirmeents at be mat throughout the operat-ing life. ASiE Section Xl it currently urder reviewfor Li aplicability.
Raferences 10 CFR 50 Appx. arnd A.
Provides fracture toughness requirments for protec-tion against pressurized thereal shock. Celculationof
5 1DaI for the RPV nrd the overtay clad irredia-
tion r . Renireent may need to be charged toreflect potential new failure modes caused by ir-radiation _ge. A need "xita for the improvementof smaningfut fltw population data aid for identify-Ing the influence this data has on probabilisticfracture Aanlysis.
-- Seactor Pressure Vessel
COPENiT ISSUECOtLNM I CoLllt
(33) LEFT (contd)
(34)
(35)
RES. INSTRLMENTCaLUse 3
TO CFR SO0Apsx. A Cri-terion 31.
AGIN FEATREScanL 4
Design Margin apifIce-tions.
LIFE EXTENSIOiMFEATLRESCaLUn S
NE
aggRENT hIITIAl1VES
HURE
AGING NEEDSCoatL 7
Are margins quantifieda a function of tepeewe or are they bsadonly on initial design?
Erhanced IDE of vesselmy be needed.
Inapection scope myneed to be tereased.
10 CFR 50, Fracture touaass re-px. G quCiraents for ferritic
steets referenced to ASIESection III codes.
10 CFR 50, Fracture toughness re-Appx. C (1ii) quirmesnts as per the
ASHE codas. Altl Irepc-tien progr_ es per theASME coed.
NM1 INE
WK HUE
LIFE EXTEeSIU SEEDS
Evaluation of APIESection Xl AWNp. A forargin fior exturded
duty, ctrsarison torefurbien activitiessuch as usetirg.
Effact of ursewti onfracture toughess andcrack tip geatries(aice- _ge adifica-tion by diftfsionaleachani_ during eneating).
Inspection my need touce different proceturesaimed at detectingegir/deeradetion forlife extension includingirradiation and fatiguefai Lure ads.
Need to determine af-facts of anne ting.
Are new operatiq Limitsad Inspection frequrncies needed for lifeextension? Inmpectioncriteria for Irradiationad fatigut failuremodes my he needd
Ansesmamt of the with-drenk schedule admur of sptles ay be
d. Amneling ef-fects need investige-tion.
The pressure boundary should he designed with suffi-ctiet margin to prevent brittle fracture and rapidpropagation of fractures, The design reflects water-ial propertiesa effects of Irradietion, the size offlu, and the stresses that ar experienced. Thissection doee not pply efter the start of plaitoperations.
Should reflect life extenscon decision and agingresearch. uss the fluts of ASME Section Xl.Appandix A.
Should reflect ELfe extension decisions and agingresearch. Evideae for aging of RAf hardiare in-ctudes erosive dweration of thidute tuies.
COEtSCaLnM 9
(36)
_-
1-4
tO CFR 50 Fracture tougmess re-Apes. C (IV) quirannts.
tO CFR So, Inservice examinationAppx. C (V) (B) requirenits.
NE HUNE Review of frequancy ofassessments of RPV Klocation on tquprseeliad upperehelf tossiess
reduct ion.
Evaluate effects of ageon the materials proper-ties used In the catcu-Eations.
(37) xolE HURE
Includes Chxrpr upper ef energy restrictions, andteaperature Iimitatioas for operations and tests.AsWus the fl1t of ASE Section Xl, AppfdiX A.Reuirm ts may need to he chonged to reflectpotential new faiture wodes caned by irradiationdags, fatigpa, erosion, aet.
10 CFR 5S Alpx 0 (IV) requirments mat be satisfiedprior to life extension. Aequiremants for operationif 10 CFI 50 Appx. C (IV) Is not satisfied: letttine
nlms examined as per ASXE Section XI; evidence offracture toughness from tests; existence of wfsf-cient safety margins. lork is needed to include lifeextermion decision and aging research. Inspectionexsmptions sill nred to he reconsidered for lifeextension.
No msterial surveillance prop-m is required forHIPVs for dhdch It ctn be duetrated the peekneutron flutsnst* te and of the design Life wiltnet exceed 10' r_ (E * I Xev). The capeuleprogra should he ma per ASTT E-t85. Capsule toca-tios and withdrewal dhuedules are required. lodifi-catitrs to ASIM E-185 for capsule withtdral ach_for new fult _asamaut progra are in progress.Similar designed and operated reactors my useintegrated surveillance progr_.
Trend deta to project when flux raductions areneeded.
(38) IO CFI 50,Appe. N
Capsule srvey progr'°. N' Assessmnt of the with-drueet schedule adiusber of saples my beneeded. Alternate test-Ing amh' (i.e. mini-sples) should beconsidered.
(39) Tesh Spec P/T Curve Adjustments Acmal Ing, re-3/4.4.9 placement
HUE Extand radiation sig Reed to determine thecurve to higher fluer effects of etanling.ces.
-- Reactor Pressure Vessel
LIFE EXTENSIONCOIENT INSLE REt. INSTRUMENT AGliN FEATURES FEATlRES F RRENT INITIAIVES
(40) IEFT (cantd) lat Spec Capsule Survey Progrs Fuel Managent NONE4.4.9.1.2
(41) SRP 5.3.1.1.1 Material irradiationresistaice.
mm
(42) SOP 5.3.1.1.3 Nrdestructive examine- NlOEtirn.
SUP 5.3.1.1.5 Fracture toughnrss catcu- INOEltion.
(43)
tE
MAE
NiONE
NaNE
AGleC NEEDS
Testing sapte frequen-cy. Alternate testing_thods (i.e., ainilRalpte) shouLd becormidered.
Need to assess if designdata bases are suffi-cintty coepltet withrespect to fLuenc.
Alternate testing methdoa (i.e., sini-samptes)
should be csrldered.
Many of the vessels withlow uwper-shetf weldprtblt are ring forgedvessels. Present crmpr-tetionat methods arebased an axis-syetric(2-0) aalysis. Theeffects of streasirg arethought to be poatn-dtialy sisnificant andthis my reqire a 3-Danalysis esdot withappropriate streamingsiulatian. Calciua-tionaL _ethoda arestendard regardless ofmateriaL.
Record keepins.
Assessment of the with-drwat schedule adnuaer of smptes my bened. Alternate test-Ina methods (i.e. mini-samples) should becormidered.
Assessnt of the with-drawel schule andcudr of samples my beneeded. Alternate test-inS methods (i.e. mini-samples) should beconsidered.
LIFE EXTENSIOl NEEDS
Acceletatad Irr. f-fact.
Should the SRP addr-sstife extension?
Should the SRP addrsslife extesion?
Minor revision of exist-irg document is ndto reflect the _seaseof material propertydegradetians. A dateae reference for aged,
anneeled materials isneded, or the expectedresuLt should best rdizel.
Should the SRP ddressLife extension?
Should the SRP addresslife extension?
Should the SAP addresslife exteriin?
Estend License if sufficient margins exist.
Deasl with the Initial design choice of materiaLs.Adeqpacy for ure of saterisls is to be assessed anthe basis of mecricat and physicsl properties,effects of irradiation, corrosion resistaice, andfaolitability. This section does not apply after thestart of plant operetions.
Spatial mathods for WDE other then those in AWtEshould tb reviled.
Fracture toughness tests mat be performed on ltlferritic tests sptiin. Fracture toughness ischaracterized by a reference temperature.
RPV surveillance mit be performed to lonitortheses in fracture toughness properties.
No meteriel su-veilasce progres is reqired if 7itis xqlos that the flunce witLt he lee then 10iv s' It 1kw - If this is not mt. a wsailt-tare prosras is nedd as per ASTh E165.
End-of-tife fltuae mat be les then the mxis orsuveillance mat be as per ASTil El8S.
COaTSCOLELe 9
i-4I-4
;O
(44) SRP 5.3.1.1.6 Data collection overvessel lifetima.
UP 5.3.1.11.6 Materalt Surveillatce.(45) ioE
(46) SRP 5.3.1.111.6 Fiuence calculation or iNOEsurv litane.
* Reactor Presse Vessel
(4?)
ISSUECMtW 2
REG. INSTRUEINTCAtUl 3
SRP BTP-YTEB5-2 A
AMIS PFEATIREStOtliti 4
Fracture toughnesspresse. tmeratze*mnd surveilttace require-Wants.
LIFE EXTEESIo"FEATUREScl2M S
mg
CIRRET INITIATIVESCDLUM 6
NON/E
(48) lEFT (centd) EC l1)15 In situ test for fatigue. NE NCIIE
AGING WEEDSC.tged 7
Appropriate regulatoryinstruients mast bemodified for aging.Alternate testing moth-ode 1e. mini-saptes)ohould be conidared.
Needs regulatory poei-tion develtt.
Need to account forphosphoroues with lowCopper.
Appropriete developmentof ny new starderde.
(49) EC 1.99 Rev. 2 Ftuanee/chesitry factors NtWfor troteitien teepera-ture shift.
(50) RK 1 XXX (New Identifies the physica-RC - not rum, dosimetry requiraesntsbared yet) for PW ftuence catcuta-
timen. E cesdationsare based en eurrentIndeutry practice adstate-of -the art dosime-try methods.
ASlE Sae III MT shift
Licensee RTpTAn tyles
ider review forgenerat applica-bitity.
LIFE EXTESIOII NEEDS
Should the SRP ddresslife aetenImn?
Needs regutatory poso-tion development.
Irradiation series toftunes appropriate forlife extension. Revisionto K foer Bit P/Tctaves.
Assessnt of needo forany new standards.
N/A
5/A
U/A
COMENTasCDLUMI 9
Suemary of the requiremnts for fracture toughness,pressure, teoperature, and seeveiItwnce reeiraentses etated In ASE aid I0 CFR 50.
Applies to pre-startep vibration tests, The RE doesnot consider fluence effects.
Conservative predictim of NOT shift a a functionof fluwnce md alloy centent. May conrtitute apenalty for VA P/t cur-v rastriction n RPVS. ThereIs a revision of ASTT E-900 in progress. Ther isalso a yet unnsdered RK for physics dosimetry.Irradiatimn effacts mnd fracture toughness inform-tion for bese metal welds mid clads to high tuercesneeds to be evaluated.
This is a new regulatory guide. Tha mthods aidassurptions presented In this guide wilt provide enacceptable approach for determining pressure vesseldage (t1 Nev) fltuences for irput to the RTPTSprescriptin given in 10 CFR 50.61.
The code is baed en fossil fuel experience and doesnot Include fLuernce-ceusd problt_. This sectiondoes not apply after the start of plant operations.
This appendix is non-maidetory. Conteins procaderesfor obtaining attoowbte loadings for ferritic pres-sure retaining interials. Methods for calculatingcritical stress intensity factors, allowable pre-
xurns, ard Rhell ard hend service lisits are given.monles, flanges and shetl regions are considered.Service limits and hydrostatic test temperaturelimits ar given. Equiremnts mey need to bechanged to reflect potential new failure mcased by irradiation doge EOT mergins arebeing re-evaluated for xFV hydrotest.
This appondix Is nn-mnetory. It centains pro-cadres for sccpting fleos that *xced ItlB-3500stmards. Includes rules mid equatims for fracturetoughness determination, fatigue crack growth rateanalysis, ad cacutation of irradiation effects enI for the WV. It also Includes crack growthre curves. eqirments my ned to be chqnged to
reftect potential new failure modes caused by ir-radiation _a .
I-41-4
1,0(51)
B -2160YB-2331RB-3124
ASME Sac IllAppx. G-2000
(52)
(53)
Protection against nc-dictite vesset failure.
Ns, except for Section uider review l/Aoriginal design for tife extensionconsiderations, applicability.
IM Section under review U/Afor life extesImonapplicability
Ke Section widr review N/Afor life extensionapplicability, Thereis a yet urnaneredEQ for physicsdosimetry thet wiltreate to this*action
ASXE SaC XI Analysis methods forAppx A. fracture toughness ard
irradiation effects.
-- Eeactor Pressure Vessel
LIFE EXTIJSIOSCOMPNIENT ISSE AEC. INSTRUMENIT ACING FEATUES FUATUES CIRENT INITIATIVESCOf L I COULE 2 cc ILL3 COaLU 4 cILUL 5 ODLM 6
(54) IEFT (contd) AVE Sec XI Fracture toughness crite- NONE SectIon undor reviewApps. C ri. See comments. for tlfe extensien
sapliceablity.
ACING NEEDS
A need *Aists to ce-Aldar ny special re-quireints for fltw incircumferential welds.
LIFE EXTENSIS0 NEEDSCOLNA
W/A
(55)
(56)
(sr)
CSI 94 maJor overpresoure of the llCS, If cosbinod withcrItical size crack,could result In e brittlefailure of the reactorvessel.
CSt A-Il As pLtnts accusaote more NWMerd more service Liam,neutron irradiationradxceo the aternadfracture toughness ardInItial eurgins ofsafety.
CSI A-26 Toughness ot low twper.- NOsEture
UISI A-49 Neutron irradiation of IONEthe reactor presourevessel weld and plateseterials decreses.fracture touwhnes ofmaterials
CSI 1-6 Through well crecke mad NONEfatigue crack growth
NOiE
NOE
NONE
NONE
Further enelysis needed. Further analysls needed.
Further analyosi needed. Further arilysis needed.
Further analysls needed. Further aralysis nmaded
Further anelysis needed. Further xnayefs needed.
Further mielysos needed. Further analysis needed.
caTS
This appendix is non- _tory. Fracture toughiesscriteria for protection agaeint feilure. For ex-e. e, AT asrgins re beinq re-evelueted for SPVhydrotest. Pr*cedres for obtaining alloweble Load-ings for forritic pressure retaining moteriels.Calculation of stress internsity factors. Allowablepressure aq~etions that cmn elso be used for noz-zles, flanges And ohelt regien. Service limits andhydrostatic test taperature raquiremnts spetifled.Solting reqirtments to prevant feilure.
Additionat tow teerature overpressure protectionfor WAS5- Priority -- MIEN
Reactor vessel esteniels toushness* Priority -- RiSOLVED with osatICe of Mii-C0744
and Caener Letter U-66See A-49 for a reletated discussion.
Reactor Pressure Vessel Traneient. Priority -- RESOLVED with pelication of
UREGC-O224 and SRP 5.2N umnerous reported pressure trenmients In PMMihere TS pressure aid teepersture limits wereexceeded. iejority et olid mater condition ofstarstp or shutdown and relatively low renctortapereture. Less toughness at low toagerstur,therefore sre suaceptible to brittle fracture.
Pressurized There.l ShockFor life exteneion analysis for resolution of CSIshould address licenses Actions stah as annealingand fuel mtngement.
Loods, toed co btnattons, stress limite. Priority -- NICG* See MSEG-210 SupI
xeanelysis recedd to determine IF cycle limitscan be extd. thermal barrier reseerch needed.
tSP guidee initlal design. This section dxes notApply after plant startup.
Acceptable code csee for Inservice inspection erefound in Sg. Guide 1.147.
-4-4
C4 (5M)
(59)
SP`Y
(61)
FATIGC Tech Spec Cytlic loadings. P/T4.4.9.1.2 records.
SAP 3.9.1 Transient Inac edfatgue. Perform fatigueanalysis In design stage.
SRP Inservice inspection code5.2.1.2.11.2 cawe And SC applicabil-
ity.
Analysso, thermbarriers.
mOmI
NONE Actuel loading antysis. Evaluete cycle limits.
alOE 5/A Should the SOP addresLife extension?
(6?)xrJIE Adequate tcle for the NMIE
Le of code cases.. Codecases expire or srereviowed every threeyears.
-- Reactor Pressure Vesoe*
LIFE ESTENSIONoMtSET ISSUE tES. INSYTRiEST AGISG FEAWUkES FEArtRES
COLUMN 1 C= 2 COLUMN 3 CriOHN 4 COLMNl
(63) KG 1.2 In situ test for fatis. mm1
CuLRRet INITIATIVESNOLUMN 6
OfNE
ROE
AGINlG IIEEDS~ifXll 7teed regulatory pool-
tion development.
ieede revision; noanforctmnt capebilIty.
(64) SC 1.48 Prediction of cycles.
(65) Fatigue tcontd) ASKE Sec IlI Thm t and pesotre r exscept fori2 3000 cyycle. Cesign ard anaty- original design.101-3222.4 Big.
Section uner review N/Afor lIfe extenseinapplicability.
LIFE EtSUrK b HEEDS
Needs regulatory post-tlion dewtopment.
Doctsantation of thesctuel service history
N/A
Further analysis needed.
Further analysis ndd.
Ctrn 0TSM-tz 9
(66)
(67)
GSI 29
GSI 79
GSI 94
Cracking and degradetionof bolts *nd studs fromstress corrosion,fatigue, ad boric acidcorrosion.
Axica teperalture gradiants that could camethterat stress in thefling ares or In thestul. Cycling over thelife of the plant myreduo fetigte magin orusace factor
Major overpressure of thetCS. If cobirmd withcritical size crack,could result in a brittletfalure of the reactorvessel.
WME WOIE Doen the Inpetionfrequency or fractionInspected need to beIncreesed for extAdedlife.
Further analysis nede.
t-'-_4
1.-s
(68)
OE
tOE
itC
NO
fpplien to pre-starto vibration tets. The SC doesnot consider fluence effcts.
Design los we not the _ As ctutal. Need toaccotait A, NS C, D, teds throu Iut lif*.
Plants no spersting need to start castIng middoctnting the cyclic history of each plant socoeprlsons cn be Made to asemed design cyclesfollowing the design code. This section does notapply after the start of plant operetiaie.
Bolting degradation or falttew in raicter poeer
plantsPriority HIGH
. Proposed inspecting ID0 of bolts each outage,xteldineg an outsee 1.5 days.
Unatalyzed reactor vesslt thermat stress duringnettre tconvection sooldon. Priority -- tEDtll
Reactor Pressure Vessel Trawient. Priority -- NESLVED with putbication of
tUREC-t0224 aid SRP 5.2Starous reported presslee traleinta In Pusthere TS pressure and tempereture limits wereexceeded. Majority at solid water condition ofstartup or asutdam and relatively otw reactorteeperature. Less teteseos at tol teratureetherefore more susceptibe to brittle fracture.
Preseurised Thermal Shock
Loads, load cabinations, stress limits* Priority .- NIGH. See 056-28"0 StP
Primary systes vibrations. Priority -- RtESLVED
(70)
(71)
(72)
US) A-49 Neutron Irradiation ofthe reactor prsssurevessel Held and plateMaterials decresss thefracture tourghnes of thematerials.
GSI 8-6 Throth mtal cracks andfatigue crack growth
GSI C-12 Structural dags byvibrations of sufficient
asgnittud. Fretting dugto deficient design midmoteriat selaction foranti-vibration bars.Fatigue fallture perticularly at the nozzle thorestresses are highest.
Aurther melysie de. Further analysis needed.
Further antysis needed. Further analysis need.
further analysis nded. further mrulysis neXd
Further anatysis neebde. Further lysis needd.NE
h iector Prassure Vessel
COMPONENTCOLUMN I
RW),73)
LIfE EXTENSIONISSUE RE. INSTRU1IEXT AGING FEA1URES FEATURES CURRENT INITIATIVES
COLUhH 2 COLUN S COLPN 4 COLAIN S COLUMX 6
LW FLUX, LONG TIXEIRRADIATION OFVESSEL AIID EXTERNALSUPPORTS
AfIlG HEEDStOUlsa 7
Tlme-taperature effectsnot uiderstood.
LIFE EXTENSIO NEEWS
unklunn at this time.
COME N TSCOLUNN 9
There are ACRS letters Identifying the issue. TheNIC is beginning to research the issue. there isevidence of larger RT shifts In NiU PRVs thenpreviously espected. is not yet knoin wether towflux conditions re significant contribjutins to theshifts.
(74)
175)
(Not used)
GSi A-11 As plants acciumlat owe JK)Eand mor service tIme,neutron Irradiationredcwes the materialfracture toughness andinitial margins ofsafety.
tSI A-26 Toushns at low tempers- CEturt
NOXE Further analysIs neded. Further analysIs needed.
(76) Further Analysis needed.
t-I-I
PO. (77) CSI A-49 Neutron irradatIon of NONEthe reactor pressurevessel weld and plstssaterlals decreases thefracture toughness of thematerlals.
Tech Spec 4 0.5 References ASNE Section Repalr.Xi.
NE Further analysis needad. Further analysis neaded.
Re ctor wast materials toughness* Priority -- RESOLVED with Issuance of HRJEE-0744
nd Generic Letter tt2-66* See A-49 for a related discussion.
P5V transIentsPriority -- RESOLVED with pblilcetion of NRaES-0224 and SRP 5.2Numerous reported pressure transients In PWRsshere TS pressure and tesperature limits sereexceeded. Majority at slid water cordition ofstartup or shutdosn end relativaly low reactortesperature. Less toughness at tow teoperaturesotherefore ore susceptible to brittle fracture.
Pressurized Thereat Shock
Current ftlw detection system are not 100S effec-tive. Dtection sysot my need to be Ilproved.
Bolt torque data may be collected mnd stress cycleanalysIs performed to justify life estermlon.
Environrentat conditlons nust be controlled aurlngfabrication of auutenittc stainless steets to reducethe possibility of senaitizatlon and aicrofissuring.This section doss not eppty after the start of plantoperations.
RW CRACK INITIATION,178) STUD FAILaE, FLAW
PRCPA5AhIWO (CISF)
NONE Ruin factors of NOEshould be evaluated;missed ttl_ or Incor-rectly sized should beavoided. Inspectioncriteria for nrw, ir-rediation lnduced fall-ure mds that my occurmay be needed.
Docueitation for dataeualysis needed in lieuof a replaceaent policy.
Shoutd the SRP ddresslife extenslon?
(79) Tech Spec3/4.4. 10
SPP 4.5.2.Ill. 4
Refererces ASE SectionXi .
Envi rouwital control
Dats retentlon.Replacent.
NE
NONE Ftuane effects notfully decumnted.
N/A; Eieted to fabrica-tion
(A0) NE
-- Reactor Pressure Vessel
COMPONENT ISSUE RE. INSTRAIENTCOALM I cOLR 2 AOLLW 3
(t1) CISF (contd) SRP5.2.1.2. 11.2
LIFE EXTENSIOlAGIND FEATLUES FEATURES
CLUs. 4 aCtiL S
Inservice inspection code Ecse and RN appticabil-ity.
CRRENT INITIATIVESCOLUIN 6
IOIE
AGINC NEEDSCaLsa 7
Need to verify that thereference code casescover an adequate timespan for reactor opera-tion.
LIFE EXTEHSIOWI NEEDS OJUENTSLa^tet o COtgi 9
mi HRC accepted code cases for ISI are found inED 1.14?
(82)
(83)
(BK)
(c5)
SRP 5.3.1.1.3 Nondestructive exmins- NMOEtions
AC 1.150 UT of RPV aide. . Monitoring Better flaw detectionsyst ar need d fordistributed micro-,flotw
RC 1.65 SE/UT for crack, etc. instuds.
ASIE Sac III Acceptable fla, andIIH50DO bercheerking Irdtctitone
coverd
ASIE Sec XI Acceptable flea adItlA-33DD benchirking IndicationsItlA-34W covered.
ISI
AdeouteLy coversacceptable ftsad betinrkirgindications.
Inspection andannitorine.
"tWE Aevis RN 1.65
Sectio under review A/Afor life extensionapplicability.
Section urder review N/Afor life exteneionapplicability.
Should the SRP addresslife extension?
IDE human factors meth-ods need evaltution forclssed ftls or Incor-rectty sized flats.Inspection criteria fornew failure modes my beneeded.
Aevise AC 1.65
N/A
N/A
Further analysis needed.
Further analysie needed.
t-s
CA3
(86)
(87) CSI 29
(88) CSI 79
Cracking and degradation NOEof bolts and stucd froEstress corrosion,fatigue, boric acidcorrosion and rosioncorrosion.
Axial teeperature gradi- NOMEents that could canetherml stress in theflange area or in thestuds. Cycling over thelife of the plant myredtie fatigue mrgin orwaage factor
major ov rpreSUre of the NONEACS, If combined withcritical size crack.could result in a brittlefailure of the reactorvessel.
Stress corroesion cracking NMl
AWE
AWNE
Does the inepectionfrequency or fractioninspected need to beincreased for ctendedlife?
Further analysis needed.
Special mthods for SOE other than those in ASIEshould be reviewed.
SDE of aleds for crack initiation ad growth.
ISI of studs for dage with tim. Updating ofRC 1.65 is recomended.
Ftsw detected and benchmarked in Section Itt, andxonitored and repaired by Section XI rules. Thissection does not apply after the start of plantcperat Ions.
Research or code work needed on the safety and riskieprovesent of imspaction mthods and tim periodcihen the original design period is exceeded. Accept-able methods of establishing such guidelines andpractices are needed.
koting degradation or failure In nuctear poaterplants
Priority - HIGHProposed inspecting 10X of bolts each outage,cxterding an outage 1.5 days.
inanatyzed reactor vessel thermt stress duringnaturat convection cootdoen* Priority -- NEDIiM
Additional low temperature overpracstre protectionfor ti~e* Priority *- HAIH
Stresa corrosion cracking of pressure boundaryferritic *te ts in selected environeents. Priority -. LW
C Lssified as Licensing Issue
(89) CS1 94 Further analysis needed. Further enalysis needed.
Further analysi neded. urther analysis ned.(90) GSI III
-- Reactor Pressure Vessel
CCOWENT ISSUE RECG. IUSTEiUET MISh FEATURESCotW I 1A L Z COup 3 COaLIs 4
(91) CISF (contd) CSI S-6 Through iall cracks mndfatigue crack grost
(92) CSI CU12 Structural dae byvibrations of sufficientmagnitude. Fretting dosto deficient design andmaterial selection forsntl-vibration bars.Fatillgu fiture particu-larty at the nozzle dhirestresses are highest.
LIFE EXtlESIOwifATORES CUxREI lllIAlIltS AGING SEEU LIFP EXTENSION SEEDS CrOENTS
COUM S CN . . 6 COttsl l 7 CLtoM a COLUs 9
leON NW Further analysis ned. Further analysis ned. Loede laod combinatior, $tsesx limits* Priority - RIGII* see 1,11110-2800 QquI'-
- NNE Further analysis nedsd. Further anaLysis nd d. Primary aystem vibrations* Priority -- RESOVED
RPV(93)
(94)
(95)
CORROSIOt
Tech Spec Cheistry control3/4.4.7
SRP 4.5.2.1.2 NIOE
SVA
NW
mm
aNE
P-iP-4
4-i
(96) SRP 4.5.2.11.4 fitE NM
(97) Sx.°
5.2.1.2.i4.2
SFP 5.2.4.11.4
Inservice inspection code NWcase sad RC ayplicability
In service Inspction NtInterva ls
ae
flit
l/A
Update/oxtify the ap-propriate regulatoryInetruoents.
Determine the aeqacyof the three year timtInterval for code caseae related to ISI.Don inspection intervalperiod need to be de-cressed in the Lest tenyear Interval?
seed ssesmnt ofchdges in the proper-ties aI the corrogiveenvironment as a turction of tim_/fluence.
'N/A
(95)
lI/A
sew life extensiondocuxsnt needed beyond40 years
Should the WSP addressLife extension?
sE
Sow life extensiondecuxent that reflectetim greater than fortyye rs?
New life extensionguidonce neded bayed40 wars.
New life extensionguidence ned bayend40 yars.
ie. life estensiondocutent ned
This may be minor Issue In RPvs. There Is no evi-denc of internal prbem. Leaks frm external
ources hev caused corroding on the externat ar-face.
Adequte prograt exist for aCs chaistry control.
Pracese controls are needed during mswfacture andcentructlon In order to lessen the likelihood ofSC. This section does not pply after the start ofplant operations.
Acceptance criteria for uestenitic stainLess steelsreferenced to SG 1.44 nd 1.31.
S6RC accepted code cas are found in o 1.147.
5e0.ired itnspction an the SPY pressure botxdaryaring each 10 year interval of service Is per SecXI lIA-A20o. Question Ia. .ehould Int4ection Progrn* he used?
Adeqacy for Lao of materials is to he assessed onthe basis of mechanical and physical properties.effects oi irradiation corrosion resistace, oldfsbrictility. This section doe not aeloy after thestart of plant operatins.
The effects of special febricotion processes onstres corrosion characteristics snt he evsluated.This section dos not apply after the start of plantoperations.
Special methods for Iet other than those in ASIshould he reviwed.
(99)
(100)
(101)
SRP 5.31.1 1 1 aterlul corrosion rosle NOetance.
SRP 5.3.1.1.2 fliE flNE
SRP 5.3.1.1.3 oroaestritive e demina- htotlone
ae
ae
NO"
- Reactor Pressire Vessel
CO04OENT ISSUE afa. iastTW AGING FEATLI*SCOLLWI I M 2 CORIN CaWLW 4
(102) CORMIONi (contd) SeP 5.3.1.1.7 iME
LIFE EXTENSION
NWE
CURRETe INITIATIVES
NWi
"15 No WED
NIA
LiPt "1TENSION W1EDSCOLia A
Now life extensionuidance e beyond
40 yews.
(103)
(1K)
StP 5.3.1.111.2 OaWE X-uE V/A New life extensionldence needed boVad
40 years.
Now l Ife ektauonsodonce n dId bond
40 yers.
SeP S.3..t111i4 NW P/A
-TIUiItU 9
A deelgn valtutien of the aetilos propertlie ofthe reector vaeee footne is pe fori d to mwnrere st to lCC. This section Oem not apply att rthe Strt of plant oper tian.
Special mosf acturln5 processes wro reviwad foreffects on atnro corrosion cracking. This sectiondoes not apply dfter the twrt of plant speratiorm.
Special processes ued on forritic rd mutnitlestainless $twl( mat be vet fled to conform tosWpoprI ate controls to avoid contdinnt Ion ndsomititation that can Increase the poseibility ofgCC. This section does not apply aft r the start ofplant operations.
Intdd to cover dsigm. cnautruction nd accept-wnc* testing of th pressts retainirs emrnts.The ace should be rtainaed. It does not a&des,aging or life extenion. This section dose not applyat r tte St art of plant operations.
Appties to the prwesue retaining coonents only.The only tif extension sPpication Is the design,fr~Ication, Inatottatlt en inspection of replace-_ent cwpIuuts. The scope of Inapectiens my nr dto he broaded to covar a*ew that serl not Previ-ousty considered. Alt high stoas. wre yed to beconsidered. lSould be expaded to cover vismatexalknution of the m1 exttrior for cotrosion.
(105)
(106)
t-aL"
ASK Sec III Corresion attowentes am-A2160 provided.
NB-3121
ASKE Sec Xi Identifies the rules WdIvA-220D rewiremsnsu for Inspac-ilA-2300 tion respaubilities.IW4A-2400 accessibility examsne-
tian Mthd petlgo.lqaltification freqincynd records. iqinilmbhsis for all requrie-onts.
C51 29 Cracking amd degradationof bolts ard studs fromstres corrosion.fatigue, boric acidc err nd ssioncorrosion.
, E section uarr revise NiAfor tlif extensionappliembitity.
Section Xti undr N/Arevie for *pplic.-bIttity
5/A
N/A
(¶07)
(¶05)
(109)
mm lIlE Os the inspectionfraimoy or fractioninspected need to beIncraased for extandeMste.
Further siulysis _seded. letting daersdstion or failure in ructeer pflrplantsPriority - 5IXNProposd irSPactins 10 of bolts sach outa,4Xtcndtino n outage 1.5 days.
Stres corrosion catckin Of pressure boundaryforritic steels In salectad nvironsents. Priority - LO* Classified as Licenming Issue
Primry str vibratiti* Priority -- 5sIvE
CSI III Street corrosion trackin MaE NeON Further rnalis wadd. further analysis nd.
esl C-l2 Structural damage byvibratinoa of sufficientmagnitude. Fretting 14Ato deficient dssign nd"eteria selection forntl-vfbration bhrs.
Fatiaa failtures partic-utlrty at the nozzlewhere stresss are highest.
Further mulysis I .
e- rctor Pressure Vessel
APPENDIX III
REGULATORY INSTRUMENT REVIEW FOR STEAM GENERATOR
Understanding and managing agingof PWR steam generator tubes
Materials
SteamGeneratorTypes
StiresornandEnvironment
Tubes Incone 6O0 or 090Tube Sheot SA 508 clad with NCr-F alloy
(equivalent to se Is8)Tube Supports SA 285 Or. C Frritic SS 1TVpe 405
or 406Sleeves Incoml 625 or nickel bonded on outside
surface of Inconef 600 or 6890Plugs Inconel 600Recirculating Westinghouse, Combustion EngineeringOnce-Through babcock & Wilcox
Reaidual Stres, primary coolant c1emistry (primarilyhydrogen concentratlon), secondary coolenl chemistry(chloride, oxygen. copper, uIfates), phocphete chemistry,resin leage from condensate poliher, bracish water,temperature, fnow-Inuce vibratlons, flow-volocitise. Ndoperating transIents
Onca-Through steam generatorwith Indicated prblenm areas
-4
Understanding Aging(Materials, Stressors, and Managing Aging
Environmental Interactions)Types Sites Aging Concerns Inservice Inspection, Surveillance, and Monitoring Mitigation
Recirculating U-bends, roil trensitlon, and PWSCC (Pure water SCC) NRC Requivements Recommendations Prevent transient conditione In secondaryinside dented reaions Tubes with low mill-annealing water chemistry, install titters betweenSurface _ temperature are Noe Volumetric examination of hot Follow S1eam Generaor condensate polishera end team
Tube plugs susceptble b sifde, U-bend poltion, and Owners Groups' guidelines tor generators. Use ultrallhratUon of makeup(optionally) cold leg sde of continuous monitoring and water and remedy condenser leakage a
Recirculating Hot-leg tubes In tube-to- IGSCC, IGA tubes In recirculating steam control of secondary wat quruleky a po5sibleOutside tubeshet crevice region generators (IWI-2500) chemistry Use shotpeening and rotopeening toSurface introduce compressive residual stresses
Volumetric examination of the Reduce uncerttintie In on tube Inner urface In the roil*nrtre length of tubing In Inspection results and transition region, aN anneel U-bends to
Cold leg a~~de in sludge pile ~ once-through steam quantity flew growth rates reduce PWSCCCold log *Id* In *bdg pile or Ptbg generators (IW-2500)where caele containing copper Monitor fild performance of Apply nicefl platng on the Inner surfacedeposIts Is found Frequency of Inspection and vnrtou sleeve designs of the tubes to prevent PWSCC crack
number of tubes to be Initiation nd propagationInspected (minimum of 3% of Perform Inservice inspectionTubes ind tube ouppt regons oentingtlltu e of tube plugs Use tube rolling to eliminate tube he et
Tubes In tube support ntglon* Denting all tutc*) are dittermhed crevices and use crevice flushing,by Toeh. Specs. (Reg. Guide 1.83) crevice alkalinity neutraliatlon, alkaline
impurity control, acid chlorideStandards for allowable flws elIminatIon, hot soaks, sludge lncing,
Inadequltely supported tube High-cycle fatigue in recirculating steam pressure pulst, water slap, chemicalIt denied neaw the top generators (standards or cleaning, and borie acid additionssupport plate once-through steam to control IGAJIGSCCsupport plate ~~~~~~~~generators are being prepered)
QW9-3521) ElIminate copper pickup by use oftitanium or ateinles ste condenser
Contact points between tube Fretting Flow aeptance crterha tubes, and replace the copper-bearingand ant ivtbrstlon ber determined by Tech Specs. 5liop' In the foedwater train to reduce
(IWo-3630) pitting and dentingUse all-voletile treatment water
hehmitry, sludge lncing, chemicalTubes above tube t Wasteg Critefi5 fo doemining Cleaning, hot aoak, hot blowdown and
necessity o plugging flushing, wnd *elmination of hideouto graded tubes chemical concentration to control
(Peg. G uide t1i2t) wa tg eOnce-Through Tubes Erosion-corrosionOutside Unscheduled Inservice Use chemistry control to preventSurbsce Fall Impaction of each steam concentration of Impurities leeding to
generator Is required when ~~~~~~~~fatIgue crack Initiation In once-throughprimary to secondary tube semgnrtr
Tubes In upper tubosheet Environmental leaks exceed the limits Use lane-flow blocker In once-throughregion tatigue delind In Tech. Spes. steam generators to mltigete
erwironmental fatigue
rev. 4 *7UM
STEAMGEIIERAIOR(1)
ISSUECOLUNe
STRESS:VESSEL PROBLEMSINTERGRANIKAISTRESS CORROSIONCEACKTC G- IGSCCMELMENETSFATTIGUI%MTI NG
jIBE PROBLEMS*IGSCC/SCC
*FATIO.EF RETTIING
*CREVICES TUBE SHEET
REGULATORY INSTRUMENT REVIEW FOR STEAM GENERATORS
LIFE EXTENSICOREG. INSTRUMENT AGIG FEATIURES FEATURES COtRERT E IXIATIAvES AGING NEEDS LIFE EXTENSION XEEDS
MUNN 3 COLUMN 4 COLUMN S 4h 6 COLUMN 7 COILMl a
Cf's10 CFR 50 Records. Records indicate Mone. Material Evaluation- Time intervals andAppendis A mintscice amount of coverage may records adequacy.
problew. need review to assureadeq.acy of Inspection.
R S Cod EMTScot~wa 9
Eefereeices ASXE Code ISI Requirearenco.
(2) Appendix B ruality AosurAr1a.
TIS3/4.4.5
P"';.)
(3) TSa requires Inspect-tion for wit penetra-tions (via any mode ofwIt thiing).
More.
xont.
Proper GA witlassure that Ode-qiate nd accuratemintonatce recordsare recored andproper proceduresare followd.
Mone, not ddressed.
oore, not addressed.
Mona, not addressed.
MoRe not addressed.
MOa. Erbritttament FatigueStress.
Xone. Iproved inspectionrfor fretting/denting/ICSCC are needed.
loproved methods ofdetection for sizingcracks and ICA need tobe reviewe/researched.
Depends on the ade-quacy of section xl,IS'.
M/A-Section, TSs.3/4.4.0.5.
Depends on theadequacy of SectionXl, ISI requirernnts/reports vs. licenserneawt n eeds.
References AShE code for ISI requirerents.
Current inspection techrique is eddy currentteoting of a fraction of tube huedie every12-24 calendar months. No requirement con-cerning the SG shall or secondary side of thetube bundIe. Root-cuse, analysis require-ments for tubs aIt thinning are notexplicitly delineated. Reporting require-ments would have to be expanded.
This I5 requires ASMEE Section Xl ISIt InspectionsIWA - TSS 3/4.4.0.5.
10 expand the scope of the required inopec-tions the Section Xl requiremtnts would haveto be changed or additional requirementswould have to be added to TS 4.4.10 to specifythe types/frequency of inspections Ad testsrequired. (The ISo currently cover the SG tubetest frequency; Section Xl doesnrt ddress thefrequency.) See Section Xi analysis.
Does not address rapid SG teoperature transientscaused by feedwatereaergency, feedwster transients,or rapid depressurizatlons of the secondary side.however. tnstnces of transients or rapid depres-surizatfon would be reportable incidents.
14)
(s)
5/4.4.10
314.4.0.5ASNE, SectionXi ISI, Inspec-tions arerequired.)
Mono.
mne.
Mn.
N/A
Depends on theadequacy of SectionXl. tSI rsuireentareports vs. agingneeds.
(6) 3/4.4.9.1.1 Thersal/pnressure cyclesare recorded during RCSheatuop or cooatdaim(priomry side only).
Cycles are recorded.might be useful Inevalueting theretl/pressna- cyclehistory/savarity.
General Motes:1. A rp Indlcates further study/investigatfon ia needed.2. For the GSM, -resolv.r meam the generic safety issue is resolved, not necessariLy the aging isue.3. For moaning of abbreviations. acroartsr and initiativ, used througbout, se ecronam on pge xi, xli, d Xgifl of the report.
-. Stem Generator
CPNT IhSUCOLUPO t CIL
STRESS (contd)(7)
LIFE EXTENSIONREG. INSTRUMENT AGING FEATURES FEATLRES CURRETg INITIATIVES AGING NEEDS LIP!1 EXTEWSIN NEEDS
COLUN 3COLUMN 4 * jOUM. CLPW COLMN COUM aWE1TS
McCaIl 9
Tis(Alt) Section Xi VA rn
operating plantcriteria Is deWAL-opirn several rno(n am tory)appendices toaddress raturn toservice situationswhen ccraonant TShae been exceeded.
5a3.9.1(O) General Posip Cri-
teria (DC): desIgnwith aufficient esrgin.Also iDC 1 2.14;10 CFR 100 Appendix A
d 10 Ccm S0.AppWojlx S.
Norm (except forinitial margins).
Nons. Evaluate transient used In the design adfatigue analysis.
(9) 3.9.3 Material Integrity. References ASIECode.
gon.
(10) 5.2.3 Review suitability ofesterials chosen, Per-form tests (fractetoehess). Review pro-cedures of manuacturingAnd welding. WE perSection III. R8-20W.
Mrne. lone.
I-iI-4bp-u
(A)
Covers all reactor crooant pressure bounry.
ASME Sec XI reqjrnts my not be adaqetfor deterioration. A naw Apperdix IV updetesET And my assist In these requiremnts.
Doesnt ddres specific gtr Issues; Section11, Class I copnent design criteria mst befollowed for pressure beuatry.
(11) 5.2.4 General.
(12)
(13)
(14)
(15)
5.2.1.1 Ant met 10 CT!50.55 (t.e., metASI req irmnts forprese" banlraea).
5.4.2.1 Oserall IntegrityRafae nces ASE.
5.4.2.2 ReferencsRegulatory Guide 1.83.
Maw.
Ibne.
Mon.
None.
Mon.
Yes.
on.
Man.
None. In Rewrite. Specific inforeatlonnmde to be camil ledwith referece to a 16.
Eliminete unintentional.d'Id 40-years con-
straint In lRC Roo andCodes rnd Staedrds.
Mew Guides needed to establish a deteriorationoverview of cronant.
MUEG-0313 ppiles to contairnmet boundary piping,not to #t tuces.1.83
NRPLEX Code" Stan-dorde Work. Identifyobvious charges--fatigue Iltfr 0313.
-- Stem tonerator
(16)
ISSLE REG. IMSTBRUEST
$TIES$ Ccontd) Rrs (Contd)
LIFE EXTENSIONAGalx FEATURMES CaRRENt INITIATIVES AGIYC IEEDS LIft EXTENSIOX MEEMS
COLMIG 4 CLLM 5 C WU* 6 ELl 7 COLIAM BCOMMENTSCQLL 0
No expticit refer nceto agiq: provides anxRC acceptable List ofapproved ASW codecases for Section Ill.
(17)
(1S)
1.121 Defines stress limitsfor filaed tube.s
1.147 No explicit refermeto aging; provides anYRC acceptable list ofapproved ASK codecases for Section XI.
The BC mist, life NC revisions weextension by pro- made to include orviding acceptance exclude appropriatemethod of approved Code Cae.(ASME) mterialsacceptable to cur-rent pproved CodsCa".
slon.. C 1.121, Rev. 1,being developed fromStem GeneratorIntegrity Progra_.
The Mt *seiste life RC revisions re Madeextmision by provid- to incltue or *xcludefng acceptance mth- apropriete Code Cases.od of approved(ASxE) Inepectionnethds uswing currentCode Cases .
M/A N/A
None. AME code Margins should be Maintained.
ASME Code Cass wre not andatory. Code Caenprovide a mechatiss to use elterrate methodswithin jurisdiction of tha code. The case
re usutlly sopersaded (annulled) by revisionsto the code, i.e., the case becina port ofthe code. in other Instancese the case my bereverned or dropped As n applicable mthod.
K/A ASHE Code Case oe not indetory. Code Casesprovide a aechwniss to us. alternete methodswithin jurisdiction of the code. The ceoe usually seperseded (Anutlled) by revisionsto the code, i.e.. the case bcome pert ofthe code. in other Instaes, the cae my bereversed or drspped as on aWpicable method.
AgSection Ill(I9)
I_-
e-4
Requstification of A now ppendix iscoonents. under consideration
which sy be usedto regulate copo-nents which havee*cedod the rulesfor cyclic operationin Section III,
1-3Z2224. A TaskGroup he been formedto address the Isms.This also aptlies toSection XI.
fatigue curve Section Yl SC onrevisiols. Operating Plant Cri-
teria is reviewingfatigue curves inSection ILL todetermine If they canbe revised to accoo-sedate operationbeyond 40 years.
Beqemlificatlonrule. for components.
laproved Ersi-of-Lifeprojections, 40 yearsnd beyond.
From Attacment Ill of the Meeting Agenda forAME55MVCS (Bord lotor Code. nd Stardarde)Steering Cmmittee on PLEY (p. 8); Codes ndstansirde auch as SPV Section Vil for pres-sure vessels, 31.1 Cods for Poser Piping, nd116 Valve Stasderda fall within the Jurisdic-tian of the AiiE ioard on Pressure TecinologyCodes end Sta erds (SPTCS). Both NMCS ENdWATCS report to the ASWE CoGUcCil on Codes endStandards. Consideration of Section Vil ndI31.1 sllt be undr PLEY since they wsreextenslvely u ed In the corntrixtion ofnuclear poser plants prior to the publics-tion of AxE WV Cods. Section III.
Studies wre ueder my to sess the mgnituesof the effects of actual envireroentat con-ditions. Code curvee we beaed on smothspeclems In air at room temarature. whermMateriels in se-vice have such rouhersurfaces Ntd Mr exposed to Iflosing ceont
at operating teeratures. The actualsurf ace re oe prone to crack Initiation.Studies Ned resrch to asses maqtntude ofeffect of environmental factors could reaultin need for now Reg. Guide, Reg. InstrumentsNaedwr Code revisiacs.
(20) FatiNIe.
-- Stem Generator
CMWOMT 2ISE PEG. INSTOIPIEI?
STRESS (contd) AME (cofltd)(21) subsection
aNCof
AS9E Cock provideerequirents fordesign, *.g.. P _,eagetemperature uvdechnirt tood, toeeeu*e the strengthut Integrity of thepressure bmirvioy.
LIFE EXTENSIUNFEATUtES
own eopticit. yetprovides Buidncernd oets forth
rules for ropeir*Wd replacmntsof eod comoents.
CUR*RET INiTIATIVES AGING 0NEE LIFE EXTESIO2 l NEEDS iOXENTSCO~LL" 6 Cott" 7 - calus a COLL" 9
Iept fed in the desifn Cuidln A neede to for Ctes I £eUSt5. AM Ce requitedetipn criteria (Ce cover the limits of special consideration for weteriel sohjectcoments). ceomoent deterioration, to thimning by corrosion, erosion. chanicat
0resion, or othmr Iwfrmwentat effects end"ta have proisiw wad for the effectsurtniq the desitn or specified life bye
sutlabte increase In or sedition to thsthicknees of the base ntael over that detr-mined by the design.
Rules cover design wW constructitn roqire-Rnts but do not cover deteriorathen.
(22) Section Xi Conditifo Asosewent.
Is hav been etceeded.(23)
Messi ification Consideration of Conition Asesentof system *nd develptt of erAwe Informstiordvta.ceepononts. Article 6IW 8n,
Reqtification forFatigue Life.-
VA6 on perst IngPtlnt Criteriadeveloping rseatnow normanodtory
ndices toareo return toservie situations
=n cUmonent TShav been exced
Acceptonce 0mwe. kmn.Stanrds.
Acceptutce 0mw. paw.Stederde.
Acceptane Nam. oow.Stonderds.
Acceoptae 0omw. 0mw.
Reqalificstienof systm wd
Wir iemiration ofoperating license.
n-4e-4
VI4
(24)
(25)
(26)
(27)
(26)
(29)
(30)
600-3510
60B-3512
IW0-3516
M0-3519
6113-3520
6515-2500
000-3521
Acceptasce Sttrlrde.
Acceptonce ittederds.
Acceptuise Stuvbrde.
Acceptonce Standards.
Acceptonc. Stasherde.
r.de of pluwed orrepltced tubes.
Standrds.AcceptenceStandrds.
Nomw.
Code evaluetion limitsfor attasbte tndice-timw of deteriora-tion suhold bedetawined.
Iseum now RequletoryGuide 1.53.
Ale4le Indicationfor U-bit flee is now405 through-well.iroth rate euggeetsthits i toe hiDh.
Present rutle limit peer but do not specifythe udr of defective tbuts that a steingenerator can contein before reptacement isreqoired.
3n inspection is not edeqte and full tlngths needed (ttube ehent to tuoe shect). Currant
rutsn eqire secIuntiel 151 if ftlo(s) aredetected. i.e. If ewething Is feasd suPesize in incre
Number of btus plugwed in a stem generatorcould Influence license rrnsit.
Xom.
Regulatory Guide 1.83.
N0m.
Yee.
Shmber of plugged orrepteced totee.
t- Stem enrstor
Crit" ISaUE
STRESS (contd)(31)
RES. IMSTALWAJT
ASHE (contd)1113-24 13,IWB-2430,
LIFE E TENiSIONAGIllsFTU*ES FEAltiS
Cam 4 OSICURRENT INITIATIVES MillS llIAS
CIiL" 7LIFE EXES~esION NEEDS
CtOLUMN aCOMENTSrMwei 9
NOW. bnoe. Yes.
(32) lu -3630 Rewrite of Regula-tory Guide 1.83.
Detection ad sizingof SCC and ICA.
Should have Increased examination programafter detection of flee 3-1/2 years betweeneaminatior s ono permitted.
States that evaluation of cracks or IGA, etc.,shatt bt performd by analysis acceptabte toregulatory authority.
Appendix IV rewrite In process.
This section of ASE (Section X) may betransferred to Saction V. Section XI will bereplaced with a perforeance demntration ondqualification guideltin. This Is in theprocess of being written now but could taketwo ywrs.
(33) Appwdix IV gone.
(34)
(35)
(36)
C6181e Failures of partially
degraded stem gen-rator tdees.
29 Cracking _d degradetionof bolts ad studs fromstress corrosion,fatigue, boric acidcorrosion, nd erosion/corrosion.
35 Loose obJecte insec'ondary piping couldbecom missiles duringstem generator blowrnand rupture one or oretutbes
66 mitigate or reducestem generator tubedegradations _ndruptures.
67 3
III Stress corrosion crack-ing in stem geurator.
gone.
None.
gone.
Nore.
None.
lore.
tore. Does the irepectionfrequency or fractionInspected nred to hoincreased for exterdedlife?
gore. Determine ,Aetherpriority of the issuechanae for longerplent life.
Mone.
"OM. ?
Nawe. lin0s. Stem-line Ereak with Consequential Sll LOCAo lplmented with Ti] action pln Item I.C.1
of ilSEG-0737.* Sgplemnted by kRC Generic Letter O. 02-33.
olting Degradation or Failure In Sucie rPower Plents* Priority - RIAl* Proposed Inspecting 10X of bolts each
outage, extending en outage 1.5 days.
Degredation of Internal Apturtenances in LlRS* Related to 0-60
Priority - Low.
Stem Generator Reqjirements* Priority - NIcN.
Stem Garerator Staff Actions* Priority - LOW.
Stress corrosion cracking of pressure bwdaryferritic steels in selcted envirornmts.
(37)
(38)
(39)
-- Stem Generator
COL(L
e4)
ism REG. INTUttMENT
STRESS (contd) Wes (contd)A-3
5.4
AGI=N FEATrESceLIU 4
stem generator tutxIntegrity degroded dueto waste and stresscorrosion cracking.
Stem Generator tu.eIntegrity degraded deto autage end strescorrosion cracking.
WlFE EXTExsIleFEATUtE5 aCIRENT INITIATIVES AGING NEEDS LIiF FEVSSEI1 ilSEDCoLtm S tDLU 6 COwLM 7 ie- COUM COWUN 9
(41)
on.
None.
Nn.
.one.
Note.
None.
sestinnoase Stem generator Tuie Integrity* See E ii-03n.* Degradation decreased by conversion fromihosphats to on *tl-votltive water treat-sme. Denting siceb toem to primary sidestres corrosion continues to be a probte.
C stem Generator Tube Integrityo s 0MG-D371.Degradation decresed by cwesrsion free
thosbhte to on stl-volatile water treat-mmn. Denting which tlee to prisery-sidsstres corrosion continues to be a probt_.
EM Stem GCnrstor Tube IntegrityI se NUREG-03fl.
Fracture Toues_ of Stem Generator endReactor Coolant Ftup mports* Solution meed availabte in October 19583
w.ith publicetion of IES-0577.* pegls. to now construction mn S,
Section 5.3.4 is aised.
Primary coolont systan decontaninetion andstm Eeuxretor dhmicat cleening.
(42) A-$
(43)
_-J
(44)
A-12 Leaster teering and tlwfracture touvr^ese ofstee gnrator undreactor iop supportwaterians.
A- 5 Operation of La resultsIn stow corrosion ofinterior astsl surfacesof the privery coolentoyotee. Those areactivated by neutronfltux mn circulatedtihroeh reactor midplate-out.
LIJA-47 Define geieric criteriafor ptent specificreviews for steegenerator overfilltraisients In Prs andreactor overfill* InAs.
5-60 Presence of loose objectIn prienry coolent sys-tee can be Indicativeof degred reactorsafety systee resultingfro fait lure or eken-Ing cosponent.
km.
Moro.
kiem.
km.
(45) Safety tqltications of Control SystemI Need to dess rupture of instrumentonsing lines.
(46) None. xm. Ferfort trend eaelysison toose pert e nttor-mng data.
Loome Part Monitoring SyStnPriority - REOseLE.
- Stee Generator
COMONENiT ISS.ECOLL I CLLM
STRESS (cmntd)(47)
REG. INeSTRUMENT AGIN FEATURESCOLUVOI 3 ~ Caiie 4
AMS3.2 aM".
(48) 5.37
(49) 5.3.10
?--IiI
(50) DYNAMIC EffECTS* VIluATlIO* TRERIAL CYCLES* EROSION
(51)
(52)
(53)
(54)
CiTe10 CFO 50,Appendix A
Appendix B
TS63/4.4.5
3/4.4.104.0.5
AsE Code ClassMaintenancecowittee
3/4.4.9.1.1xCS heat-up/coot -damw
Nione.
Records.
tut Ity Assurance.
TS resuires eddycureent testing oftubes that couldIndicate tues session(shell not addressed).
wic .
Thermt Cycles arerecorded during UShaat-up and coot-down.
LIFE EXTEXStIOxFRAIIARES
X vim of plantprocedwes/recordscoutd give inesihtinto deterioration.
Revile of plantprocodures/recordscould give inisihtInto deterioratien.
Review of pltntprocedures/recordscould give ire iaihtInto d terioratlon.
Yes.
Yes.
None* Mtaddres ed
Moes. notaddressed.
Mores notaddresed.
CUiRREsT IXITIATIVf S
Mores.
Maw.
MGM.e
t1"
to Ia 7 C airn a
M a w . If w.
Ma.
Maw.
Moteriat Evlust ion.
tStrittes nt fs tl.wStress.
tlm.
Nol.
Ifw. Inspect ysenderyside of tuIes forvibration (fretting)*ed shell erosion).
Interval betweenesa nmed to bervied.
iMethods of detectingend sizing cracksnd 1i. need to be
revwleed.
leports froms Inrspectione could be uwadto evaluste tues ero-sin coenditions.theefh root-ceanatysis _y belocking.
D ar on adequay ofSection XS IS1 require-muits aind other
requirenarts alreadyin plice.
CtlTSCOUSIN 9
Otifty A isuenco docuintation andlor racordsare requird to ohe NWd eveuate deteriora-tion of a crnt
References ASE Code for 11.
Referencees ASJE Code for ISI.
Eddy cuiraent testing fired watt thinning btunot ncessrily the m of thinning etlessthe utility included this in Its correspond-Ing report of the Inspection to the MRC.Oily a fract Ion of the total evter of tuberwr rae lred to be inspected during en outage.
TS 4.4.10 defers to T.5 4.0.5 which specifiesthat the ASN. Section XT, rquiremente wrppicable. Se Sactlon Xi analysis.
Does not eddeess rapid SO toeraturetrmnisnnts caied kty feehater/sirgncyfeedwater tremiients (e.g. transientsassociated with fooestor/mrsency feedweterSC over-fooding or rapid loses at fesdaterpraheeting).
i". M/A
ionts. The theriNt cyctes arerecorded and retained.Perhaps useful inevatueting cyclehistory/agwelty.
- Stem Generator
00100MENT himMLL I U
DIMOIC EFFECTS(55) (Contd)
REG. ImSTRlUEet ACING IOTtEfsCQLUtiN 3 mumt 4
3.9.2 Review of the criteria.
LIFE5 EXIENS IONFEAIIAES CURENeT INITIATIVES AGING EMC LIFE EXTlENSION NEEDS COW""S
COUINe 9
test Im poedrs ndaneaic Iaty it.
Ilaterie Integrity.I5O 3.9.3
Of?) 5.2.4 General.
Norm.
Yef. ASK.
Nove.
Mona.
mu.
NoIe. Cplete aI relablecote bees.
Norm, tye.
SAe structust hA iunctionet integrityider vibratory loeding.
Cmpete mD reliabledate be".
A91E SWe Yl XruireMta My not be adequatefor deterioration.
Dosm t ad m specific Isemma; Section IIInot be followed.
(5M)
(59)
(40)
(44)
(62)
3.2.1.1 lemt meet 10 CtF 50.55e(i.e.. Mt ASE Sectionfi1 reqiirants forpressure bmclodries).
5.4.2.1 Overetl Inteerity,Refernces ASE.
5.4.2.2 l1fernerfewluatory Guide 1.83.
1.121 beft ms diaicA Loadingconsideratiorns over Imgtube fail ture.
1.147? No explicit referenceto agin; providee anRC acceptable list OfDoved AWE codt
cae for Section It.
1.85 No explicit refenc*to ainC; provides onIlC acceptable list ofapproved AIE codacase for Section 1I1.
None. Nons.
11".
norc. In *eweit*. Too. aew Guldes nerd to establish a deteriorationoverview of component.
Limited. NG 1.121 limited tothe integrity.
Consideration of other Lam term failurstructural deoration. resistance of SG vessel.i.e., vessels.
I/A ttA
.-4
0-4
(63)
The RG assists life to revislln are madeextenion by provid- Inctude or ecsludeIn acceptimcs Math- appropriate Cead for epproved Cae.(AVE) inqpctionMethods Ling cur-rgnt Code Cas.
The MG asallts life NG revisLau We meextension by provid- Include or ecludeing aceptance mth- appropriate Code Cases.ad for approved(AfE) _ateriesacceptable to cur-rent approved CodeCases.
A9E Code Cae ae not _xtory. Code Casesprovide a medimnime to was alternate methodswithin jurildiction of the code. The case.are usually spuerseded Cmvstled) ty revislonsto the code, I.e.. the ca e pert ofthe code. In otler instcea. the case ay bereverd or d *ope an m Wicable method.
AWSE Cod Cas ae not etory. Code Casesprovide a Mechanism to uie alternate methodewithin Jurisdiction of the code. The caseswe umually superseded (tmettld) by revislonto th code, I.e., the caee part ofthe code. In other instancee, the c-s may bereversed or r ane nappicable method.
N/A I/A
(64)ANSection 111lSubsectiontienNCNp
AS91 Code provide.rPeramts fordesisn. e.g., presmue.temperature misechanical lade, toaseure the strength
W integrity of thepressure bmtary.
Iona esplicit yet,provides Guidane
rid sets forthrules for r"peirand ropteamentsod code ompnents.
Imptled in the deeign Guidance Is naeda todestin criteria (ee cover the limits ofcomnts). c mot deteriora-
ttion
foer Class I comewts, AME Code reqiresspecial consideration for materisi subjectto thinning by corrosion, erosion. mechaticaldraion or other onviraramntsl effects ai
l htve provisions _d for the effectsdoting the design or specified life by auitable increase in or *elton to the
thickness of the bes Metal over that deter-Mined by the design.
Iules cover design int conatruction reqire.nets but de not cover deterioration.
Steam Generator
Lift EXTENSIONOMlE t ISSUE REG. INISTRALKENT AGIlI FEATWRES FEATLIEES
fOLWI CSLLI 2 COLUMI 3 CQ 4tM A COL S
DYNAMIC EFFECTS ASM (contd)(65) (contd) Section Xl Corrosion ad Erosion.
CUARElt IEITIATiVES ACIRC MEM LIFE EXTENSION hEEDSCOLUIIII 6 COLUMIN 7 COLWM a
A nre VA on pipewIa-thinnin hasbeen estaltiahed ndWilL review thislasut with EPI.tain at" of conernat this time is theeffects of trosioevcorroion on pipin innon-suclear applica-tions MSIUASHE*3tC-1901K HM forWotrminire the Ro-
sininR Strength ofCorrod d Pirxttne S
Rewrite at Regulatory yes. 1su now RegutateryGuide 1-81t Guide 1.o3.
None tbne Evatu ti0n nd guld tFor allowable Indlesltors wd doterloratten limits houtd bedetere d ed.
memArs
Th SectIon XI Sutbgroup on MestructlveExamination is currently developing a
CaW ad n dattory ppandix onUltresonic Detection d i._7eastjfnt ofEreoimvrCrrosihn.
Amsi/ASW 3-31.6 may have limited appicationto nistl r fecilities.
13 inspection Is not adequate ad full lengthis needed (tUbt Sheot to tuoe sheet). Currentrules require, spatiat ISl, If flats) aredetected. I. * if ethinw is ioud* siplesize Ia increased. (The tut# "ptirg 1s *etby the Ts, not by Section tli)
Preset rules limit power but do not apecifythe ner of defective tubs that a stemgenerator ean contain before ropLaeonit Isecssry.
(66)
(67)
Iw7-2500 moa.
IWS-3510 Acceptance Stadards.
F-4
i.-I
CD (68)
(69)
(70)
(71)
(72)
IWt-3512
Itd-3516
IIL-3519
I11-3520
IW5-3521
Acceptance Statdards.
Accaptance Standards.
Acceptance Statdards.
Acceptance Staidards.
tader of ptumed orrepleced tutee.
None.
AcceptanceStanderds.
AcceptanceStandards.
AcceptawaStardards.
ArAptSAStaidards.
AcceptanceStandards.
Number of pluggedor replaced tues.
None.
Ma.
Iwb.
None.
tbne.
0.
-ar.
Mar.
Allowable indication mst of tues ptuged In a steam generatorfor U-herd flaw Is could Influence license renewal.40Y throth-wett;growth rate etafeststhis is too high.This my not be con-servative oeoth, h.e.,all indication of aflew should requirepltus.
-- Stem Senerator
MUMtM1 COSIN
DUNMIC EFFECTS(73) fcaned)
NEG. INESIMMENT
ASHE Ccmtd)11II-2413,
2430
LIFE EXTENISIONAGING MATIMES FEATMES Ot*UM~T INITIATIVES AGING NEEDS LIFE EXTENSION NEEDS
COaLUM 1. CLM *W****MN 6~J ** WOLMS 7 COLLPI aCENTSMIAMI 0
Morm. None. YTo.
(74) 1IMI-36" *Ma.
xon.
Regulatory Gild. 1.83 Yes. detectimn ndsizing of ScC nrd li.
Shoutd tae Increased examination proeramefte f eactien of f1lat 3-1J2 years betewenexaminations Is now possible.
States that evaluation of cracks or ICA, etc.,shalt be perfoowed by aIlysis acceptable toregiuatory ateorityi
Appendix IV rewrite In procee4.(751) p is IV M".
This section of ASe (Salion Xl) my betrosf erred to Mactimn V. Sectin xl will bereplaced with a perforae - trotlon ndquslificatin Guideline. This is In theprocese of beIng written now but could taketwo were.
(76)
(77)
18
35
i"
I-4
I.- (78) 60
Looe* cbjects Insecondsry pipiog couldc I missiles djring
stem Generator bteosdsnxnd rupture e or moretubxe. Prsencs oftoor objects I pliss aSystm has ifa led.
Lemiltr teeringrepresents a resutionIn toad a joint coutdhandle, particularlyuner aersency condi-time sch as seismicconditions.
mitigate or redeosstem generator tL*w'degraistions ardruptures.
More.
Nn.
NOn.
Na'.
M".
11n.
Nn.
Stem-tine break with conepanntifa emtl iOCA.
Degrodation of Interact APPUrtmesc in LiRs* Priority - LOW.
Lamttl Tlering of temctor tystem Structuralsupports
Is a subtask unider A-12.
(79,) eS N". Stem Generator NeqjirantsFeur Item Priority . NItC.
(80) 67 7
ilare.
Nam.
Mo.
Nam.
N'.
5te Generator Staff Actia's! Priority . LW.
esatinshouae Stem generator Tabs Integrity* Sam 9fte-03711.
(S1) A-3
stem Generator
(8LU
(ez)
IS"E
DYNAMIC EFfECTSIcrt4d
LIFE EXIENSIONREC. lNlSTUMEl A61C0 FEATEUES FEATRS CLAEMM INITIATIVES AGIG EEMS LIFE EXTENSION NEEDS
COUSINl 3 _ tcaL" 4 a6 S9 tC ielI I C7.OLLM agill"es
COLUH 9
GISs icontO)A-4 tam. hon.
(AS) A-5 *obe Cracs of urakimorigin propagated Inthe circumferantialdirection by fltwindjced vibratiot.Erosion cavitationPheomen.
A-12 Lassiter tering end Ia.-fracture tluJrOM ofste gesurator eNdreactor pW eu4 portMaterials.
(84)
(SB)
Mon.
Xar.
one.
11r.
11r.
Sa".
OE Stem _ erator T1he Integrity* sIo . -0371.
iS& Stem Gernrator lube Integrity* SIUIEC 5-0371.
Fracture Toghness of Ste Gawerator endRetator Cooltnt Pk S'pports
Solution mod available in October t93twith publication of 5*50-0577.In tUe cte of Xortb Anna Iicensee agreedto raise terature above 22-F beforepreauarizing above 1100 PSi.
Safety Iplaicatione of Control System.
Loos Part Solitotring SystmPriority - ESOVEDO
USIA-47 Contribution of controlSyst' faitures result-Ing In overfillingtraratents wd pros-surized tlhert shock.
More.
Xcr.(56)1-.1'.-4
1-60 Presence of too"object in priMarycoolant systn can beindicative of degradedreactor uftah systinresuLting froms foledor weakened cponent.
A3S3.2IS?) ilne.
ISO) 5.37
Review of ptantprocedares/recordscould give Itlashtinto deterioration.
erives of pltntprocedures/recordscould give insightInto deterioretion.
Seview of plantprocaures/recordscould give Insightinto deterioratfon.
Sa.
Sa".
ir.
Ease. 0l4elity AS urnce detoUentetion end/or recordser rewired to shw and evaluate deteriors-tion of a cmponnt.
Saw.
cm9) 5.3.10 Xron. Xone. h r .
-- Stem Generator
COaiPNT IUW AEG. IISIcMtNT AGIN FEATIAESU I coLlt 2 COLUMN 3 COuLUM 4
SIItRAL INTEGRITY es(90) * PSACIW TOMfEI 10 CfE so, Rom d
* ElITTtENT appsodix AtIEUNAL
* SEISMIC (DAMAGE)FASaIRES
(9i) _ x A Design be for pro-Criterion 2 tection dof ewipent
from natural VI - -inclurin4 cn tsIoportUnt to safety.
(92) Criterion 51 Woaw expticit/tiputatese aector
Preesur Boundary tobe designed to includecornideretions (su-ficiint _frginx/fctorof safety) for pressureontatinmt under oper-
sting, testing, nWpoetuieted eccidentConditions suci thatthe prem" bourdoryferritic _tonralsbehave in * eewrittle_ner.
(93) Appedix a 'Q'ality Assurane.
TSe(94) 314.4.5 U/A
(95) 3/4.4.10 mI.
(96) 3/4.4.7.9 Require periodictesting of snu eesa1ciated with theSG And piping.
LIFE EXTPIOX1
Yes.
Eoe explicit; pro-vides direction tou t eeblnet historicalphenonans for thedesign. I.e.. thisconretive designbe".
Wont explicit; Im-plied by the dIgnif the ferritic*torilt contimreto show ni-brittteprCetiee.
yes.
on, notaddresesd.
ewne. rotoddresed.
bone, notddressed.
CUF EtT INITIATIVS AGING WESOWN 6 COL~UMN 7
Wore. Materiel Eveluation.
eone. oruric and specificdesigns) mat meetCurrent nd bInatural pdin.
Wbnx. mthods to assesirittled prop rtes.
LIPS SXTERSI9 WEDS
Intervels between *fre aees AK for 1i1.ex need to bereviewed.
Design mat meet current Wegulation should be upted to refl ctdesign criteria for the life extuwion options mid the optionpteoe. to ssaluste nuctear f*cilities for
plant aging.
lined lNDE techniques Wegulation criteria needs updsting toto determine Orittlt- fehtune Life exteneiin applicatien.ment prprties.
I-..Wine.
Won.
o n .
W e.
Embrittlemnt IFtipes Provide adits/records of References ASE Code for I1I resqirents.
Stress, methods of detectionand sizing cracksNd IGA.
WA 7 TtS ruires periodic eddy current testing ofSG 11-tame.
S/A 7 This TS rquires ISI ASK. Section Is. If SectionXI is et sfowato, and the TSs re to be expended.this my be whore the revisions should occur.
This TS Is limited with reference to the seismicisum i.e., seienic monitoring of the sits Isrequired. Wo other refernces oe ends. In addi-tion, periodic tenting of the SG sr*bers doenot occur. The utilities are unble to do so.
.- Stem Generator
ComisMT
(9?)
(98)
LIFE EXTESlIOiNIs". REG. iSTIUiMLIET AGIG FEATWIS FEATURESCMlILL 2 O MINIMd 4 LAISTRMLCIAi. INTEGRITY Ts (all)(COMOd)
CtlOENT INITIATIvES ASlhC NEEDS LIFE EXTfESION 0 EEDSC.ttl A CoLtue 7 C ais 8
Workinr Sroue onOperating Plant COfteris, proposdaddition to Article11W-3S0 of SectionXi. Would containrules and forlutnsfor perforilng analuation of a c-m
pon nt's fitness forcontinued servicewhen either TSa orelemnts of Its con-strurtiaendeieniil-tatione had beenecded
TTNMIS9
3.9.3 -d3.9.3A pnix A
(99) 5.2.3
I-.40-4
(SO0) 5.2.4
Materilt IntearityReference to ASHESection III nrd GDC1,2,4.14,15.
Reriew suitability ofmaterials chosen. Per-fore tests (fracturetougess). Review pro-cedures of amufacturungand welding. iDE test-ng es per Sectiton I,
Me-2500.
Reeqire II Progremof WeU (CDC32) toeases structural endleak-tight integrity.
Must met 10 CFA 5O.55S(i.e., meet ASlE Sec-tion III rquirmnntsfor pressu boundaries).
Overall IntWrityMeet CDC 1,14,15,31 midIS CFO so, Appuitix A.Nave sufficiunt designmergin. eview nltec-tlon rd fabricatien ofmeterlals. lust metASK code.
Rehren Agg.Nm (except fororiginat designeag lre).
km.
Nn.
Mom.
hom.
More. Covers alt reactor coolent pressure beouaery.
MoM. Y". Loeding crminationm. syste operatingtrawients, and stress limits.
Based on rquirits of 10 CFR 5055a anddetailed in ASEK Section Xi.
(101) 5.2.1.Nn.
Nm.
mone.
(102) 54.2.1
Doesn't ddress specific essun; Section 111mat to folttred.
To Met the CDC 1, the acceptable meteoiatsre specified in Section III, pndix 1I
Section 11, Ports AtC. Nat also meat RS1.5. To meet CC 1i14, mnd 31, the fracturetoughness mast met 10 CFR S0, Appendis G.ndl section I1 15-2300 and ASE, Appendix C6-2800. for weldingse ASlE CodeSatform III and TS.
(103) 5.4.2.2 Reference, RegulatoryGuide 1.3.
brm. Rewrite in process. Ves. Now quide needed to establish a deteriorationoverview of cronent.
-- StBe Generator
ODNhEUT SN REG. INST5IIET
ST"TUmL NEGIT M(104) (contd) 1.121
AGIeC NATURES
efins mthod forcalculating minimaacceptable tdb wallthickness.
LiFt ITtElIOiaPEATIMS aEQEOT INITIATiIVE AGING REM1CORNL COLUN Mg 7
LIFE MlTEHr WEDS
Long-ter failurer lstane of K vessel.
(MhDN 9
Limited. E0 1.121 limited to Consideration of otiertuie Integrity. strtural degradetion,
L.e., ve...ls.
(105)
(106)
1.14? XD explicit refereto aging; provides anUR acceptable list ofapproved A91E codecaes for Section XI.
1. ilSN0 eplicit refererpeto aInc. provides nX1C scceptabe list ofaoved ASKE codCos" for Section 11.
The t esisto life KG revisions We med.exteiwion by proid- Include or eactuds!nq acceptance moth- appropriate Code Came.ad for 91rovsd(ASE) Inectionmthodi using au-rent Coce Cos".
Tha £0 feafst. life KO revIalona wr.eateision by provid- to incude or aetudeins atteptac meth- aMpropriate Code C_.me.ed for aved(ASE) moteriaISacetab to aur-rca approved CodeCase.
s/A i*/A APE Code Cae ae rat dltory. Cods Casesprovide a machorls_ to use alternate methodswithin Juriediction of the code. The ra"re us..tty st erd (annuillad by revisionsto thi cod. i.e.. thi cam bacs part ofthe code. In other Instanmes the case my bereversed or droped a n u appicobte method.
ASIE Cods Cme we net dstory. Code Casesproiade *a mechenfo to use alternate methodswithin Jlurisdictln of the code. The casewe uwsutly s eparsd (wurwted) by reviwsoto the cods, I.e. the ca eco s s part ofthe codes In other inetmnces, the came my hereversed or drepd as n m tlicable method.
*/A M/A
(107) Sactian III,leimection
PCeF
ASE Cod* provideroiirownts fordesign. e.g., press'et"rature ndmechanical foods. toamoeur the strengthand Integrity of thepregsue br.
lonei expticit; yetprovides gudnrce wedaid sets forth rutesfor repalrs Ndrepacmntst of codecrionunts.
Imptied In the desioncriteria (soe coints).
Cuidast Is neededto cover tie limdtsef rI ntdeteriortion.
*-I_-I1.
Ln
For Clas& I ceonts, ASE Code reuiresepecial consideration for meterial scbiectto thining by corrosion, erasion. _echaicalabrasion or other snvironmental effects ndshall how preoisions mde for the effectsdurang the deign or specified life by asuitable incrse In or adfifon to thethickness of the baes metal over that deter-mined by the design.
sules cover design and censtruction reqiro-mints but de nt cover deterioration.
Present guides limit pwer .but do not specifythe rer of defective tutes that a steamgenrator can contain before replacesont isrequird.
(105) nWE-3510 Accaptuste StuKWiderd. Aceptant.stnrdsrds.
Sons. tOM. Evetuetitn mnd guidefor altlewle Irdice-tiens and deteriora-tion limits should bed*etorined.
(109)
(110)
IW.1-3512 Acceptu'cm Standards.
ii-3516 Accaptaice Itsasierde.
ACceptasIStandards.
AcceptanceStanclrds.
bna.
5w.Xa.
-- Stem Generator
aOWCAMEN la Et. INstRUmEArODUM I OU UI
SbTMXTUaAL INEGRITYb ASE (contd)(Ill) (covit) lwa-3519
(112) lIW1-3520
(113) lwo-200
(114) IW.-3521
AMIO MEATIAES
Accaptunce ttaerwdee..
AcceptMnca Stanidards.
None.
Numer of plugged!or replaced td.@..
LIFE EXTENSIONlFUATURES
AcceptencaStandrds.
AcceptenceStandards.
bimber of plgeat~ replaced tubes.
SR£A1I IITIAlIVES
Non.
ion.
begulatory uide 1.83.
bmw.
LIFE XTE0SIG NEEDS
1MWu new Regulatorybulde 113.
Allowabit irdicatlOnfor U-bnd flaw is 'aw40: throu-*walt.Growth rat. aeetsthis to too high.
iOlOaTSCOLL" 9
b,.r of tiieg pluag In a stem generatorcould lnfluo* r lceie rrw{al.
(115) l*-2413,a4go
in. oen. Yc$.
(116) Regulatory buode 1.U3. Tm detection ndalzing of SM and lil.
(117) Article IV bore. more.
6-t0-4
Should hae Increaaed eamiation progrewmiter detection of f*a1s 3-1/2 years betweenexinatimw Is now poaaible.
States that evaluation of cracks or tCA. *tc.,shalt be perforid by enalysis acceptable toregulatory authority.
Regulatory Authority hk been rewritten enda In final stow.
This aection of A"hE (Section tS) _y betrawfefrrd to Sectiwn V. Section XI will bereptated with a performice demuatratiun andqalification guideline. this is in theprocaaa of being written now but could taetwo yews.
uat I ty Asurance documentat fon and/or recordsare re irad to omw and .valuate deteriora-timn Of a Comonent.
An3.2(Ila)
(119) 5.37
AMn.
bAre.
bMG.
beview of plantprocero es/recordscould give inetihtinto deterioration.
Review of plantproc duroe/recordcould give innightInto deterioration.
bevies of plantproce dwrearecordscould give insightinto deterioration.
in.
bone.
Aone.
Nm.
born.
None.
Xle.
bale.
M.(120) 5.3.10
-- Stem Caierator
LIFE EXTENSIONCOMPOENT ISSU MGB. 155151J51T AGING FEATWRES FEATURES CURRENT INITIATIMI AGING NEEDS
10505115N CIFIS(121) INTERS CIMSZISI 10 CFU 50 10, Records. Yes. None. Noterial Evaluation.
* lIMULITIES Appendix A*INTEUGAMULARATTACK CIBA)*IRRAIATION ENl-FANO0 EFFECTS
(INRFASS0 SAaO-LYTIC DGI5PCOI-13ON OF WAlES ANDCONmESER INLEAK-AGE INFLUENCESWATER CHE"ISSTR)
LIFE EXrENEIIU NEEDSM5tU" a
a nENrSMINOt 9
Intervalt betwtn ais Anfeiices ASK for ISI r irenvts.needs to be reviewed.
(122) Appeoiis 8 Dual ity Assuance.. Y . Non. Embrtttlweu FettlwsStremU.
nthd of detectionand sizing for cracksard ICA ned to berevi5sd.
T'o3/4.4.5(123) Edly crwrent testinw
could detect wet thin-ning dus to cdhinstryproblem.
-
NoWe. notaddresed.
Nop. notaddeesed.
Nope.
mone.
Ems.
Inmpction r porntcould be e Id totook at *t estertetsfor dhmfstry-apecificIearns.
N/A
t/A
(124) 3/4.4.10 Yqaires AhE,4.05 Section xi, rWqire-
Monte for M.
Inspction rortseight be usful forraiwet criteriareview If reqirmatsfor reports were madssor Specif ic.
Depends on iwhtluerreports/records ofASE, Section XI. areadequate to be useful.
Primery sIds chmistrymrtysis records weretained. perhapsuseful In evlusting s4history with regardto chemtstry of fluid(RCS).
(125) 3/4.4.4.?7 Reauree priory coolant Nwn. not(CI5) demistry control. as d
This TS reqfires maky crurrnt testing of SG U-tubes.IA effects ma U-tube wett thickness could bedetected tthou the crae Is not necessarilyInferred. Reportine requirements would have to be
This TS reoaires the requirnts of IS 3/4.4.0.5CASINE, Section XI. ISI) be potlied to SG.
GENERAL CORROION NOTE: Technital Specifics-tiona do not ad*," secondary (steam plantside) ciemistry control at alt. This isware dhemicel attack of U-tds wuld seenthe mat likely. Therefors, especially forold 525, sacmdery chemistry end its bearingmn U-tuhs Integrity wcutd be of greetisportance. (Secandary aide cheeistry isdinistratively controlled bit rat by
TSt)Limits placed on Ct, F. ad dissolvedoeypen. Are thli, adeqte?
Steaed stateP . met. r Limit Trarslerit Limit
(dissoLvtd 02)* 4.10 PP v °° Pon(C1 ) 4.1s an o1.50 po(F ) <0.15 pi 150 pan
*I/A If C3 to. is <250-F.
*- Stev GeCerator
rUat
(126)
(12?)
(128)
[ism 850. IKSTMJEMICOLM2 CDLM
COMICIN (contd) Sof3.9.3
A51G PII-S71iWO FEFRCLtity. 4
MatCerial Integrity.
LIFE EXTENSIOIFEATUhER O.355 IN.IIATIVtS AGIN5 CRESS LIFE EXTENSIONt NEEDS CCIEXTS
COt'LUM 9
(129)
(ItO)
S.2.3 Corroslon.
S.2.4 General.
5.2.1.1 "Mt met 10 CP1 90.55S(i.e., mt ASK Sec-titn III rquirerentUfor preaire bonarl ies).
5.2.4.1 ihat mat CDC 1. 1415nrd 31 of 10-CFt5S05
As fdix A. The desitnmat have Sufficientowein. Rewuires reviewselection Oid fabricationof Moterials. Fractureprevention Oriteria matbe satisfied.
STP WTI 5 3 Maintain wet r choeistry. Guidea todesign to pere-ntsludgp butid-up.
5.4.2.2 Reference Guide 1.83.
10.4.8 Stm generetor blow-doen system reviebdesign bael.. CDC 14:secondary waterchemsitry.
References ASIE.
None.
Cans.
Neam.
ione.
xore.
None.
oNea.
Ye..
50,0.
More.
Yes. Covers eonetruttion nty.
ASHE Sae XI requfiroentU -y not be Keloquefor deterioration.
7 Doesn t dres specific Isss; Section IIImsat b followed.
7 To meet the iOC 1, the acceptae materielsare speciflad In section 1II, Appendix I,Section 11 Parts A.R C. Must ates metRegulatory Guide 1.85. For welding seeSectiens III and ItX. To met corroslon-resistance. s Section IX, Part OW. Articles1, I. 111 and IV, Referenc. DP MES S-3uatert Chemistry for Stem Generaters).
e1e.
(131) Maintaining -gonewater citmistry.
Actually _tione slone-term reliableoperatiorn." Referonce Regulatory Guide 1.37.
(132) Cone. Rewrite In precess. Yes.
i-_
X74
e.w Guide, need to establish a deteriorationoverviiw of coeponont.
Review only initial design of the syte-m.(133) None. inn.
to1.121(134)
(135)ASiHtSection 111Subection
itsCNCUP
Degrsdation growthallowance Included Inminimum tub walldetermination.
ASK Cede providesrocivirmonts fordesisn, e.g.. preesure,tapeeatue andmedcanical ltods. toasur the stronethand integrity ef thepres ure btoudary.
Limited. Revisleon of ES 1IZI t Rtter definition ofpar atialy sdrsases degradatIon growthdegradation growth rate. needed forallowances fer tunes. specific defecta.
Setter mdets of dgra-edation growth needsd toprotect remining tubeIntegrity.
Guidance Is needed tocorer the limits ofcomfont deteriora-tion.
Xone-qepllict; yetprovide. guidm reand sets forthrule. for repair*mnd reptacgemnte of
code comonents.
Implied In the designdesitn criteria (seecobnts).
Available data froe accelerated laboratorytests. May rot be useful for predicting SGperformance.
For Class I components. AM Code reojirespecial coneideration for materiel subjectto thiming by corroslon, erosion, *echonicalabrasion or other nvironmntal effects andshall hwe provisions made for the effetsduring the design or specified life by aswitable increae In or eddition to thethickness of the bose meat over that deter-mined by the deeisn.
Rules cover desigt mnd construction retre-snntu but do rot coer deterioration.
-- Stem nerator
COPONENT
(136)CEORRlI tcontd)
RE. IMSIMIMEIITODLIq 3
ASME (cntd)Section XiI1-310
A31GI: FMATtffS
Acceptance Stmndrds.
LIFE EXTENSIONFEltWIFStOtUINI 5
AcceptanceStanrds.
CURENTe INITIATIVES AGING 55505COLUMN 6 CO~~LUMN I
lions. NonMa.
LIFE E8EI5 NlEEDS
Evalurtion Ad Guidefor atowbie indics-tiens n.d deteriors-tin limits should bedetermined.
.,ml;
Present pAides liet pear but do nlt spacitythe Rabi of defective tubes that a stemGenerator can contain before reptecnt isrequired.
(13?)
(136)
(139)
(140)
(141)
IUB-3512
155-3516
155-3519
IWB-3520
255-2500
Acceptance Standards.
Acceptance Stav'arde.
Acceptaaca Staiderde.
Acceptance Staudards.
Maw.
AcceptanceStavrds.
AcceptanceStabrds.
AcceptanceStandards.
Acceptan5Standrds.
st*.tMo.
11".
11".
Nor,.
Ma.
11w.
ion.
Nore. MOM.
Regutatory Guide Yes. Guide 1.83.1.83.
lsar now OwaatoryGuide 153.
(142) I51-3521 Nuber of tubaesptuagod.
, of tubplumged.
Xon.
Alloweble Indicationfor U-batd fla is mm408 thru malt, Growthrate aUgests this istoo hish.
(143)'-4
&-4
P-.LC)
(144)
(145)
155-2413,2430
tU -3630
Appedix IV
"am. yet.
3% inspection It not edequatc and full ltngthis ed (tub shoot to tube sheet). Cifrentrule reuire sequential 11. If ftlWs) aredetected. i.e.. If s rnthing is found, sapleaIoe Is Increaaed.
Aont of tubes ptugged in aster generator couldInfLumica titers renewal.
Should ham Incroased exalination progrsafter detection of tta: 3-V/2 years bet~enexamination Is mm poebe.
States that evalnation of cracks or ICA, etc..shalt be performed by aalysis acceptabte toregutatory sucrorlation.Appdlx IV rewite In process.
This section of ARE (section XI) my betransferred to Section V. Section XI wiltcontain perforoa demntration endqunlificstiwi rules. This could tek twoYears.
Naw. Rseutatory Guide1.83.
Oetection nd aizingof SCC md ICA.
Mane.
-- Stem Generator
COLFUT|
( 146)
(147)
(148)
CORROSION (esntd)
REG. INSTRIL&IVET
tas
35
66
AMI"SFEATWRES
MI"tigate or- reckicitem gwlsrgtor tatedegradations andrupture @.
(149)
(150)
(151)
(152)
6-4
1-4
"3)(153)
(154)
67 7
III Stress corrosion crack-ins in stem generator.
A-3 Stem Generator tubeintegrity degraded 0Jeto watageadt stresscorroeion cracking.
6-4 stem Generator tuieintegrity dgraded duoto wastage end stresscorrosion cracking.
A-5 I
A-12 Laseltar teering andlow fracture t(sedneseof Stem Generator andreactor pW LWprtmteriats.
A-15 Cperation of LiRresults in slow corro-sion of interior motelsurfaces of the pri-_ry coolant systm.then activated byneutron flux mn circu-lating throup thereactor and ptate-out.once plated, they c'av'tCe rved by plantester chdeistry systee.
LIFE EXTENSIOIFEATUESiCOULS 5
Noni.
i".
gn.
Sol.
on.
None.
For.
CaRENT INITIATIVES AGilC NiEEOS LIfE EXTENSIO NEECJSmOLILial 6 COLUNe 7 CASUVA a
mons. 7 I
More. 7 7
Non. 77
oils. 7 7
oils. 7
7 ? 7
7 7 7
None. Assess the afficiencyof wster chesistrysyotee to met axtendedplant life.
TDIWAISCOLU*I 9
Stem-line break with cornsequetial _Sal1 LOCA.
egradat ion of Intarel Apisrtoa cs in LiNe^ Priority - LOW.
Stem Generator aqairmentsFour Item Priority - MON.
Stem Generator Staff Actlwne* Priority - LOW5.
Stress Corrosien Cracking of PressureBoundary Ferritic Stoels in SelectedEnvi ronents.
Westinghouse Stem Generator Tkae IntWrity* See REG-0371.* Degradation decreed by conversion frr
Aaoepate to an all-voiative ester treat-_ent. Denting which ilede to prisary sidestreso corrosion ctntinues to be a probtes.
CE Stem Generator Tite InteritySee MJNS-0371.Gagredation decreased by coniargion frosphosphate to en ati-volative wster treat-_ent. Denting hich lea to primary sidrstress corrosion centinues to be a probim.
SWU Stem Generator Tube Integrity*ee WMG`0371.
Fracture Torgtneee of Stem Generator andReactor Cooltnt Pulp S ortg* Solution d available in October 1983
with pubtlicatirn of UMEG-0577.
Priesry coolant systes deconteeinetirn andstem generaor chamicl cleaning.
(155)
-- Stem Salsrator
(156)
Is"M REG. ldIlflTRUCoLum 2 QDLUM 3
CiweORtSI (contd) OSIs (cmtd)1-60
AMIW FEATURESCOLLINN
Preeen.e of tooeobject in ptItarycoolnt syst can beindicative of deridedractor safety syst_reteLting from failureor weiakning conit.
LIFE ExNE IONPEAIi OMRRElET IWITIATIVES AGIN0 NEEDS LIFE EXTENION NEiDS
SI . CLL.UW 6 CoLa I 7 CaM aWeIETSCOUiPei 9
one. km. Lome Part Monitoring tetaPriority - RESOLVED.
3.2(157)
O") 5.37
lone.
orm.
new.
Reise of ptintproceires/recordecould Gin IrightInto detleroratim.
Revis of plantprororue/recordscould gin insightInto deterioration.
levis of pintprocedkree/ecrcould give insgihtinto detarioratimn.
km. kn.
tm. iM.
hne. Outity Aseraice decmntatlon ndor racerSrequired to dhmw aid miuti deterioration of econm'mt.
Nmw.
Nt.(159) 5.3.10 km. km.
SUlVEILLAKE(160) * TESTIN
INSPECTIO* ItAINTERAMCE A
REPAIR* MW! LEANING& REPAIR
* RDEf* INFMTIUJDATA
i tE9UI~~101111VEIITSFREQUENCYDATA CLLCTI
- DATA EVALUATION
KEEPIN
10 CFR 50 Survelllance Progra PNw progratic ProgrtIc cr1- Overal l guidnce/critea- statdard taeH- type staiderd planning for aurveil-that coud, by Ref., being considerd by twnc prgrm.beoes a part oF NUPLEX for ntire10 CPR 50 If It nuietar pLtnt und *tare eatabLiahed comoents of concern.
by a etanderdestr at reqneat
of MPLEX.
This atanderd would*erve as a guide to anucleer utiLity inbee their demi-plant-specifie programpint It would provideoverall guld nce forates generator Iase.
Suggested that this Prertic-ritCrterlrstanderd bts a p enrt stanad and thatother deuohtsr staderd may be nseded tospecify Ineptimn techniques, the svaluationaid identification of aging mchanim, theestabtleFlnt of special or erhanced mints-
- pr m, mnd the developwt midieptentation of recordeeping and tradingpragreg. Guidane couid *stt be providedseparately for evelueting the effcts of pinttrewin events on _coponent Or Syatee life.This standard is expected to be 0eed bynucleer utilitlee to eetabtiah a plan foraaseeang the feasibility of a pi nt lifeextension proram nd for developing indImplemnting auch a proge dere practical.It would aoist utility perannew in identifyIng actiws required to preserve a pi nt lifeaxteion option aid for identifying needfor quclpnt testing. Inpection, monitoringand s nt. It wiii provide a frnmeerkfor qddrasaing future regulatory requirNemta- they sight f fect the extenion of plantlife mid to eoart particular pint operatingand mintenmece practice -e an Integrat partof pruient pi nt ng nt.
(prepared by J. Christle for KIWIECodei mnd Stnd rdd Su bcsittee.)
-- tem nerator
(162)
ismf REG. INSTRUMENTCOUN2 CXM
SURVILLANCE (contd) CiSc (contd)
TSe3.4.4.5
AGINC FiATURES
Could lead to URC rulecharges.
LIFE EXTENSIONFEATURES
eq.Wires eddy eurrent one, nottesting of sa U-tubes. addressed.
CiURENT INITIATIVESCtLUM 6
iUPLEX Codes WnStendsrds Identifica-tidon Nu r PWR.0 Onstem Gienrator (44coents). UPLEXI to be prepared.
1o.
None..
.on.
A.
Non.
Non.
AGING NEDS LIFE EXTENSION MEEDSCOLUt 7 CxiU1 iia
N/A
CtlOMTSiOLUIIII 9
escriptioni Develop UT teCInlqje And ISIprogrm for detection nd sizing of ftsr Instem generators.
TS reiles eddy ceurrnt testing of GA U-tubes.ICA effects on U-tbe weatt thicknsse crld bedetected thoigh the came is not netesoorilyInferred. Rieorting rooluiremnts would hve tobe expsnod.
This TS r-res the reqir-ints oi TS 3/4R.4.0.S(ASKE Section XI, ISI) to be applied to the StemGonerator.
(163)
(164)
(165)
(166)
(167)P-i;la
3/4.4.10 ReWires ANE Non. not3/4.0.5 Section XI, treetment addressed.
for SO with regard tomintenerre if CodeCloss 1, 2, or 3.
3.9.3 Noterist Integrity. Reference AlCodes.
5.2.3 Corrosion end Stress. eons.
5.2R4 Generat. eone.
5.2.1.1 Mwst Met 10 CFR 30.55. NSo.(i.e., met ASME Sec-tion III reqiireontsfor pressure bonderies).
5.4.2.1 Overall Integrity Nonr.Referenee ASME Codes.
5.4.2.2 Stem Generator Tube ISIIn-service Inspection(GDC-32) Referenceto G i.il3 sod TO foresach SSS ragptlier(E-ola0103, 0212.0152).
6.6 In-service Inspection None.of Clas 2 & 3 caenents(G seconrdry ide.)
10.3.6 10E n d clearing (Stem None.Geierotor shelt side)cith referentc toRN 1.37 for cleaning.Alto 10 CFR 50 50.55.,end Appendix A.
P4E
Yes.
Yes.
None.
Covers construction onty.
ASiE Soe XI requirmant, my not be odequetefor deterloration.
Doen't adr-es specific issues; Section IIIant be fotlajed.
W/A
(168)
(169)
(170)
(171)
Non.
Inepection Progrm to detect geing ies iteffective? onn't prnt aging.
Progrm bmad on 10 CFR 50.55 aSnd detailedin Section XI.
Concernd with Class 2 6 3 cpnents, thereforeonly shell Ide of i;C. einly ref erences otherdocur ts to fotlow.
"Nne.
-- Stem Generetol
COOMENT IlS" REG. INSRIEISENT
S*WVILLANVE (contd) SRet (cxntd)(52) 17.2
AGING EAn*ESM~as 4
Imlemet GA pi agreM.
Eddy-Curreflt of Tubes.
LIFE EXTENSIONFEATURES CURRENT INIITIATIVES ACING NEEDStOLUII 5 tttUOI 6 tOtUPIR 7
LIFE EXTENSIOA NEEDSCt"Ui S
CuNENTSMutil 0
None.
geonitorfra.
SEP doe not provide an in-depth descriptionof GA reqiremnt and doest address agingper N.
(173) 1 .83 Rev. 1 PC 1.3* eVW. 2, Better equilnt ndbeinr developed methods for defecttroe St_ Generator detection, characterit-Integrity Progrm. tim, md elttiin reeded.
(174)
(OMl,
1.NS5 No explicit referenceto aging; allows useof ASKE proved adIlC coX ct *pplI-cebte to Section Il.
1.147 No espicit referano.to olien; atows ussof ASHE aeproved adUEC code tee app l -calbl to Section Xi.
Me RC Implies life NC revieslo sreextenslon by provid- md to Inotuee orIrn ecceptonce meth- exclude appirpritead forepproved code Cam_.(ASK) _tenrtseccepteble to eurrent Cdoe Cas.
The NC inplies life NC revsieu weextanelon by preovid- _dr to Include orIng acceptonce meth- exclude eppropriateod for approved Cde Coxe.(APES Inspectioneathod uing aua-rent Cede Coxe.
onitoring. ASK Section XISpeclt lorkng roup
develepirq prtfor-wce deometrstirnreqwirmnlm for ETinrpections.
N/A
N/A
Netter detection adsizing of defectseded eelaty for
Creeak.
Nore eccurate Inform-tion nreded on defecttype ad size to pre-dict remining tubeIntegrity.
N/A
W/A
Rev.2 of NC 1.83 dees not ddres performeaedrustratlon issues.
APE Code xes are rat _ndetory. Code Cam"provide a mech*nim to use alternete methodswithin Juraldiction of the code. The caseswe usually stpereded (annulled) by revlelonsto the code, I.e. the cne bI pert ofthe code. In other Inrtres. the cae y bereverted or dred as n applicable method.
ASUE Code Cases we not Mdatory. Code Casesprovide a _ nI Ism to uae Atternute methodswithin Jurlediction of the code. The caseswe usuatly spersaded anriutled) by revisimnrto the code, i.*.. the cAse becones pert ofthe code. In other Instances, the case my bereversed or tropped As An appl Icabl, method.
)_4
C.e
(176) 1.158 ualification forIn petlion personnel.
Need methodology forqutifying ET inFpec-tors.
(177)ASMSection Ill,Susection
WEof
Requiremnts-futt-strength nd pressuraIntegrity.
Nonr. Non. l/A xaw guide to coverlimit of deteriorationis rd.
jules cowr coutruction roqirmlrnts but donot cover deterioration.
(175) Section XI lieterit mnd co nretcondition assessnnt.
jet. Info.hDate Mm Nnmndietorybeset e they apply IdhI on Recordto roiesc for xe ping bha passedlicee extersiorn/ the SWC-PEX.rnermms.
tef. Info/databases to sepportexteens/lronewets.
As materials ad caunnts age,the pradictive capabilities for p"yi-at and inchnicalt property changes
mint Improve. Since during a plmnt'aeervice tife An incrersing amunt ofInforeetloredeta will be aRlable fromisaveittaneo progres, batter pro-ctee to eavluate ad ue. this Infor-intioxVdats mat ba developed.
(179) Suillanct. New baseline A n0M teok groupexamination on Beeline Eaxt-reqhimnet. netion hls been
estebliehed.
Evatuate * awbeline examine tlonfor license extensionreotjnts.
-- Stem Gerrator
COMPOINET IS5m AG. INSITM bD AGING FUATt"SCOLUPIN I CbLex 2 COLUM 3 COLLOW 4
ilAEILLAUCE (contd) ASK (cantO)(iSO) Section XI Altows for Inopoctiol
beytrd 40 yers.
(l6t) monitoring mnd Testing.
(182) t nitoring and Testing.
(1813) Inforoet ion md Oatefor trend cuaveprojection.
(14) Fatige faitures.
LIFE EXtasalNFEAIUES CURENT INtTIATIVES
aienas to Insec- SW bau tepc-tin PlRn A mid santed rsvisions to0 ihich arm ur- Iht.24300 whichrutty bted a *a Witt det the40-year operating 40-year limit cur-tite based n fews rentty csntained Inintersl, the ts Section XI. Also,of uidtch * 40. reviauing need ter
ore freqentinveptiora.
Infloratio0tVe Oavstowt of Tomfor trand cuwves. *ai techiqes to
datect age-relateddeadstien ndfetlIon beinoconridered.
InfotmtiVn/Dts Cnsideiring hydro-for trund curves. static testing
trends kitrchange. or, neededfrr aging effects.
Records- SW Is consideringIformatirVOsts. develont of
mstory ap xdiafor racoroeaping.
Anticipate nid Fails. monitoringevoid fttigus tachnolosy developedfailwre. mid dmtratad.
Sevrt faciitie,ae proceeding.
eon. RSeuiatory Guide1.83.
830 5EEDS ULIPS EXTENSION WEW"INSI 7 Catlm a
Uttmied swrteitnie aveiIttnmc heyondboyid 40 years. 40 yers.
=eleet
the frequeny of inspection should depmnd anthe degrdadetion soheniss end the canditionof the copent.
Into tion nid Dats.
Information mnd Oats.
Inforattion d Cotofor trend cuavew.
Sxperlmc NWd tootdetA for hiuh-cyleeffects.
too.
Nmnitoting/tesing
honitarife~testinstec ntru .
Xecords- this Appndiio uouid provide theInformtiondOts. utility mear etil guldmnce as to the
type of rcords which su be beneficialIn a otins a ticann satenrien
4eepAatary scoop ) Faileso mliketly from cycles consideredtense of alternate in design. Dsaign approach Is coneervative.approach to design Coopont features InStueid to preclulebasis fatigue faitlure. Coonents hava hidh
toltrarm. to flews.
b) Patlgue cracking hao ocurred drisgoperations:
vibration; rapid thert cycling;Pri-A1istiMO f lamo ther coiditla not - -mdered in desiag.
tIssu ns isWtstory U inspection Is not edowate tid full tenthGuide 1.83. is needed (tubs sheet to Ute shoet). Current
rules rewire socportiat Ul3. If fl Os) adetected. i.e.. if sNothing is fouAd. r plesite Is Increased.
15 M) t1tt-2500 .ons.
- Stem Gioator
(186)
(187)
(188)
(189)
(190)
(191)
Is" iEC. Ih5TRhENTOL~t 2 tntu i 3
SUW iLtAtE (contd) ASM (eertd)IWB-3510
I53-3512
ItS-3516
I1IM-3519
Ist-3520
IUO-3521
X.LR 4
Acceptone Standrd.
Acceptace Standd.
Accepturce Standard.
Acceptance Stdit.
Acceptance Standed.
rn.
LIFS EXtENtSIOFEATURS
AcceptanceStandrd.
AcceptanceStanbrd.
AcceptanceStandard.
AcceptenceStaderd.
AcceptanceSt-ord.
es.
tl"RET INilTIATIVES ACINGi RlEMetiLUiii A GU 7
kn. kM.
LIiE F S mEn
Eltuation iG tGidefor ltelt.e indite-tie aid deteriora-tion limits shouldbe deterined.
Oest?,mtUPIn 9
11".
km.
Rem.
Rm".
km.
km.
M.
m.
Aiiotbte Indicationfor Uiband Fto is an405 through-wet(.Growth re shome thisIs too high.
nt of ttbe pted in a stem sr torcould vive VAdwI. for liens rentes.
(192)
s-I
a.r
flW-2413,2430
Iti-3630(193)
(194)
(195)
(196)
Appudix IV
18
29
Rone.
k m .
He.
Visut exeairetion tsthe peary mthod todetect degradation byacid corrosion orerosionfcorrosion.
Regulatory Ghide1.83.
km. Yes.
M.
Should have increeaed emination progrieft r detection of ftlea 3-1i/ years beteenexasinetione Is ew posible.
ten detection and Stein thst evatwation of cracks or ISA, etc.,sizing of St snd ICA. Salt be perforeed by anlysii acceptable to
regulatory authority.
Appendix IV rewite In puosss.
This section of AS (Section XI) oy betrateferred to Sectfon V. Section Xi will bereplaced with a perforane _Atration andqtleification uideine. This Is in theprons of bei written now but could taketwo year.
Stem-tine beak with consequntat Small A.
km Roating Dieredetion or Fature in nultear plants* Prioritty * Rit.
k0.
k m .
k m .
k" .
I
Reed NM for teatingbolts aid studck Rowthe i npectionfrequency or fractionInspected need to beIncrepase for ntetd-life?
-Stm Cnerster
COLLM I t iCOLUt41 2
PAVEILLANCE (contd)(197)
AEG. INiSTRUMSENT
GMl (contd)35
(190) 66
A9G F=ATIMESCQLIW 4i
Loos Part anitoriniprograr.
itiste ,or raedcst generator tutedegra-ltion ndruoure.
Wtemant TnbeInspections.
?
(199)
(20')
(201)
(202)
(203)
(204)
(205)
67
A-3
A-4
_-
A-S Nra.
A-12 Laster tearing ewdlow-rttcre toulmof sttm*u gierator andreactor pW siWortmateriats.
A-IS Cperation of LkRresultt in stIae corro-sion of interior matalejrfaces of the primarycoolant sy*tV. 'hi sar activated by neutrenftun udtn circulatinsthrowlih the reactor endplate out. Radiationlevels incrase In thepriasry systtm. thuscosplicating routineinspection animainteance.
USIA-47 Define generic criterifor plant specificrevies for stemgenerator overfilltransients In Pws wnWreactor overfitts inbms.
FEATURES
None.
Ra".
None.
Mons.
CURRENT INITIATIVES AGING NEWS LIFE1 EXTENSION WASCOLUMN 6 K.CfLwO ? COLWWA a
a"n. I 7
None. 7 7
Nione. 7 7
lione. I7
Mone. 7
Arnie. 7 ?
a cn . 7 ?
aawe. Assess ispect of In-creases In radiationtevels on Inmpactionand minteaioe.
eTSCOLLONI 9
Degradation of Internil Apjrtenances in LItb* PriorITY - LOW.
Stem Generator RequirenutsFoeu Item Priority - HtGM.
Stem Generator Staff Actions* Priority - LW.
Wesetinghousje Stem Generator Tuts IntegrityoSee NUREG-0371l.
CE Rosin Generator Tube Integrityo s awJft-037i.
iY Stem Generator Tube Integrity* See *siG-0371.
Fracture T rousa of Stem Generator midReactor Coolant Pump S, ports* Solution mode available in October 1913aitl piblication of UEcG-0577.
Primary Cooltnt System Decontamination andSteam Generator Cilmicel Cleaning.
Safety Implications of Control System.None. ?
-- Stem Generator
WUENT ISSUE
tZIRWILLAMCE (contd)(206)
(20?)
LIFE EXTENiSIONKG. IiSTLMmT AiGIN FEATURES FEATIAXS CaRNTw INITIATIVES AXING KMU LIFE EXIENiSIWN NEEDS
COLUM 3 CLUMN 4 OU CM M COLL 7 causi S
GSls (contd)1-60 Prwoceof Loose MNam. oa". Perform trwd1 analysis
COMMENtSOeUI 9
object In primary cooiant system can beindicative of degradedreactor safety systmsresulting from fatlureor weakening cronent.
erae.
on loa, part monitor-Irv data.
Loose Pert Moitoring SystmaPriority - RESOLVED.
Ms3.2
(208) 5.37 erone.
Nione.
Review of plantprocedures/recordcould give InsightInto deterioration.
Revier of ptantprocedures/recordscould give insightInto deterioration.
Review of plantprocedures/recordscould give ireightInto deterioration.
None. mons. eone. ruatity Assurnce decawntation end/or recordsare required to shor end evaluate deteriora-tion of a coonmat.
None.
aere.
Nen.
110e.
eerie.
gone.(209) 5.3.10
i-4
;a-
- Steam Gonerator
APPENDIX IV
REGULATORY INSTRUMENT REVIEW FOR PRIMARY PIPING
Understanding and managingaging of PWR RCS piping and nozzlesMaterials Main coolant pipe - Centrilugally cost SS-Gr. CFBA and
CF8M (W), Tlype 30415 and 316S5(ea W plants). SA-516 Or. 70 (CE).SA-106 Gt C (11W)
Fittings Statically Cast SS Or. CF8A andCF8M QO; SA-S1 Or. 70. Type 309LSS (CE. BiW); ,Type 3051 SS (85W)
Cladding 1T" 305L SS (CE. B&W)Type 304L SS (89W elbows)
Surge and Spray lines Type 315 SS, Cast SS -Or. CF8M(surge line in some CE plants)
Charging, satety Injection,- Type 316 SSand residuat heat removaltines
Nozzles on main coolant * SA 105 Or. 2 (CE), Type 304N SS 01)pipeSote ends Type 316 SS. Inconel 5-166 (CE, B&W)Thermal sleeves Inconed 56&16
Stressors & Operationdi transients, temperaiume, flowInduced vibratlons, stratifiedEnvironment lions, thermal striping, valve kge, and thermal Shockb
, wall)
Cold leg A- Cros
Reactor vessel
Typical RCS piping for W 4-loop plant
s-over ISeContinuous roilecd 'Spot welds (4)bead on sleeve
Typical nozzle-thermal leeve assembly for a W plant
s-
UNDERSTANDING AGING MANAGING AGING(Materials, Stressors, & Environment Interactions) MANAGING _AGING
Sites Aging Concerns Inservice Inspections, Surveillance, and Monitoring Mitigation
Nozzles and thermal sleeves Low- and high-cycle NRC requirements Recommendations Maintain full flow In spraythermal and mechanical fatigue Perform more frequent examinations line and operate It continuously
Charging VolumetdC and surface examination of nozzle welds and horIzontal to prevent stratified flow
Safety Injection of 25% of butt welds, Including the piping welds having significant and thermal shock conditionsfollowing welds during each Inspection fatigue damage Redesign surge and splay line
Surge Interval (10 CFR 50.55a, IWB-2500): Determine fatigue damage by on-line piping by replacing shortSpray - All terminal ends In each pipe monitoring of pipe wall temperatures horizontal sections with sloped
connected to vessels and coolant flows, temperatures, and sections to prevent stratified_________________________ to ~~~~~~~ pressures In nozzles and horizontal flow conditions
Terminal end dissimilar Low- and high-cycle thermal All dissimilar metal portions of piping subject tometal welds and mechanical fatigue welds operational transients, Including Redesign piping to eliminate(between carbon steel stratified flows and thermal sleeves deleterious effects of valvecomponents and stainless All welds having leakagesteel piping) cumulative usage factor Perform nondestructive examinations
equal to or greater than 0.4 and loose parts monitoring to Minimize valve leakageSurge and spray lines Low- and higth-cycle assess status of thermal sleeves Maintain smaller temperature
thermal and mechanical fatigue All welds having primary plus Develop use of acoustic emission differences betweenCharging, safety Inlection, and secondary stress Intensity range method to detect crack growth In the pressurizer and hot legresidual heat removal lines equal to or greater than 2.4 Sm base metal and welds coolants during heat upto first Isolation valve Some welds are required to be Develop techniques to monitor actual and cool down
Isamecwelds auren requhIrsedction bedegree of thermal embrittlement in castInspected during each inspectlon stainless steel piping: Maintain smaller temperature
Cost stainless steel Thermal embrittlement interval Analytical modelling of Inservice differences between thepiping dgdtonpressurizer and spray line
Hot leg Coolant temperature Flaw evaluation Metallurgical evaluation tocoolntFerrite content and (10 CFR 50.55a, IWB-3000) characterize microstructure
Cross-over leg spacing Lekg n hdottc rsueNOE to establish correlationCro shoder leg - Chemical composiion Leakage and hydrostatic pressure between ultrasonic attenuation
Cold leg - Chemical compositiona tests (10 CFFR 50.55s, IWA-5000) and fracture toughnessMonitor valve leakage In safety Injection
Fittings Cycle counting of specified and residual heat removal linesdesign transients
Surge line (Tech. Spec. requirement) Develop UT to detect flaws In caststainless steel piping
rev. 4 stat
REGULATORY INSTRUMENTS REVIEW FOR PRIMARY PIPING
UIFE EXTENS1IOMr.. lIlNSTALET AlxG FEAIUES FEATtUES csuahr ItITIATIVES AGiCx IMDS LIFt EXTESUi OIEEOS
COLUMN 3 caOLUM 4 j S COLUM 6 COLUMN 7 caWL a
PlIPNG(1)
'taB
* IACKEIW.SC
a. FERAITIS DIS.SIMILARM ETALSOF SAFE E 58
* FATIGUEa. LOWi CYCL.E
FAIGUEb. TIONAL At -
MECHANICAL.(SEE FIST? COROTrOF COLUMs 9)
I~aSI
cTm10 CUR S0 MkpIex codes and
Standerds work.Idmntify obvousChag" macil vaSIC In NJIAG-0tIS.
Itimtinate applicalotoulintentimnl embedde40-year conmtraints InRegulatory Inatnowtcodas end etendorda.
Fatilue is generic te *1 t s of ptant, ndcames and "tent differ from plant to plant. ItIs also recognized that now unwique e h prvblusde exist blt~. Pks nWd Ts.
Forty-year onstrinta do not apply to sit &sinefactors; i.e.. fat Ig is a cyctlc pI R idcould bame cemalve after 5 or 10 ywr ofeperation
(2)ISO3/4.0.5 &A/.4.10
Mx. xmn . a whetherSection Xi ISI reqire-misareports aedmiute vs. ialt ntsda
owe attention.
monX ( commat). Cycles re recorded.Nidit be _eful Inevaluatins thermalprusaur cycle history.
- an wetherSmctin Xi tit reiare-mns/raporte weadeqtae vs. t w neIN" Attntion.
Effective _ethbdt tosonitor fatius cyclesfor magnitd andeffect over ths cra-ponrant service lift.
This TS reqaires AsS Section Xi raclee-ntscoecernin ISI nd MAintenrnce for AMC pipingIUW T.S. 3S4 4.0.5).
(3)
(4)
"_
314.4.9.1.1 Primary side thensel/pressure cycles rerecordai during xUeat-up nd rcol-
deown.
TS* All
SME3.9.1 Meeting CTC IS: design
with sufficient _nrgin.Also. ceC 12.14;10 CIF S0. Appmidix I(QC): 10 CFA 100,Appendix A.
Nn. cycles Name-eilted with start-Ws and shutisw ta" recordad nWcountted
Section Xi A an 0W*rating Plant Criteriais deveilping us non-_ tory appendixesto addrer return toservice sittatisdh.n TS hew beenexrceeed.
EPxl-spxonred fatlia awitortnr ZFatigum-Pro could ilpact the credibility of 1Scycle coont data. Fatieu-Pro Is reported tobe a seusr of the severity of the cycles duringoperation. LO.. my oporating Cycles ae lesseverv then xseaed dwing the design.
(S) WmOn (except forinitial sargins).
xa. 7 Evelute tramients ued in the design andfatlie altysis.
(6) 52.1.1 mat met 10 CtF se.ss.(I.e., met AM51Section III reaire-xln for preseursbowdaI as).
M m . Ma. None. I iont specifically dram eny am i1sweASJI Section fit, mat be followed.
G-nral Motes:1. A .1. Indictaes further stuidy/frwetigation is needed.2. for the Oils, *rootl0 eme the gtenic stfety isu Is ragolvad, not necessarily the agint is'ua.3. for amnino of brevietlirn. ecry, nd Initiati, wsd throclhuxt, es scrall on pass xi, xil n d xwii of the report.
-- Primary Piping
COMPONENT ISSUE REG. 15STOLM15T
STRESS (contd) IRse (cofltd)(?) 5.2.3
AGING FEATOUESCalm.z 4
Review suitebility ofMaterlals diosoen. pr-for tests (fracturetouimess). Review pro-codeMs, of .ssfecturwelding. S ectlon III10-2500, -2550, snt1- 2570.
LIFE EXTENSIONPCATUWES CURRENT iINTIATIVES AGING HEOS LIFE EXTE5SiIN NEEDS
jals CO!LUMN 6 COLUMN 7 CoatgE a
111"s. ? I
catas 9
Covers Ott IeXctar Coolant Pressur kunderyiiteffels
(a) 1.147 Xo asplicit referanceto *gino; provides anIRC ecsptlet list of
toved ASU codecases for Section XI.
(9) 1.85 No eplicit r tfereicsto eins; provides anWRC acceptabte list ofwprovd ASK codc
cases for Section Ill.
AWSection Ill(10)
CA3
me IG op(fees (Ife, Pf revslns aeeextension by provid- NNW to include orIng actptam Moth- exclud epprotriateod for spproved Codo Cases.(AWE) inspection_ttod using cur-
rent Cods Cse.
The PG implies life PG revisio n weextension by provid- ae to include orIng acceptance seth- xaclude MpM iostsad for approved Code cases.(SE) Code CaseMaterias nd test-Ing accepotble to55C staff.
Retqtificeiton A naw appendix Isof Cents. undser considerstion
,hich Mey be edto rsqslifty ce-pMnlots which hav
xceeded the rutesfor cyclic qor-lion In Section111, 111-322.4. Atask group hasbean forsed toejies the issu..Ths elso appliesto Section XI.
fatigue auive Section XI, V onrevisions. Operatinf Plant Cri-
terin Is reviewingfatilus curves InSection ill todeteneine if theycan be revised toeNMdete ewr-tion bynd 40years.
A/A
N/A
Evaluste ns apndix.
A/A
II/A
Seqiulficetion Rutolfor cosponnts.
ASE Code Cases ae nt *tory. Code Casprovide a _odhanis to uwe siteto sthdwithin jurisdiction of the code. The casaes usaly superseded (mntalled) by revisloto the cod, i.e.. the cas bece_ pert of thecode, in other instances, the cas Mey bereversed or dr Id a n MO Icaete Method.
ASK Code Cass se not Itory. Code Casprovide a pechenie to we eteinso. methodswithin Jurisdiction of the code. Th caesae Usually suprseded (muttled) by revisionsthe cods. I.e., the cas Iacme pert of thecods. In other Instances, th cae way bhrevered or dropped as an appliaeble method.
(11) Fatigue. l od oed-of-lifeproJections, 40 yor
rd bod.
Studios we undor my to aeess the senuItudeof the effects of ectust swirormmntconditionm. Code curvee are bed on moth
pecianse In air *t roes teretu re. wemssmteristl In sevice hov moch rouge r="a s md ar OapOsd to flowing coolant et
operating Th etu u al surf cese sis pow to creok Initiation. Studio
and resarch to _ee mgnituds of effeetof enviramat fectors could result In rnedfor mm Regulatory fulds, Repittory inetru-_ts ar'dr code revisiorn.
Priestry Piping
COMP(MEhl IWE-COLUMN I COf
SIRESS (contd)(12)
(13)
(14)
AEtG. lIMSTMM&IiIcaml 3
AShE (contd)Susection
teal
AGliilT FLALURESCaLti! 4
Provides for designtoads affecting thestrength nd integ-rity of the presourebotudary.
LIFE EXTEUSIONFEATURlESCOLMi S
aone-axplicitJprovides rutesfor repair i/orreplaceant ofcode conents.
CiRRENT INITIATIVESCOLUN 6
Section Xl Condition Asesosent.
TSO have beenexceeded.
Laaaitfication of Consideratil ofsysta end co devetlpnt of newponaents. -rticle tIn-MS
Reqatitfication forFatigue Life.0
SiW on (peratinaPlant Criteria isdeveloping nu fnorwatory apandfxosto ddres- return toservice aituatitiw,when MS have beanexceeded e
on. on.
ACll WEEDSCte 7
Sept led in the designcriter ia (a comnts).
Condition AosessmentInferuetion/dete.
ions.
UtFE E=ctlhI NEEDS CaeEeTSCLwta ii CoLLEri 9
Guidance Is need ASKE Code for Class I coeponents-pipingto cover the limits design required ahen corrosion or erosionof rponant de erio- is expected; the piping thicknese shall beration. increased over the other design requireaente.
Tita attlowar shall be consistant with thespecified design life.
Rutes cover design and construction require-manta but do not cover deterioration.
RLselification ofsyst and c0sponntsfollowing expiration ofoperating license.
ime. PiJ pipe crecks^ Priority - LW ESOLVED.^ Corrosion cracking In taw-pressure piping
Is addressed In C-7.
? Detached thermal sleeves - The thermal steaves wereInstatled In the safety injection sccsulatorpiping nozzle connections to the reactor cootentsystem cold tags piping. Found at bottom of reactorvassete.
7 Long range plan for dealing with stress corrosioncracktn in VA piping - solution available.
(15)"Is14
C-.
(16) ?3
Cracking in hih pres-sure piping In PMes asa result of corrosion.vibratory and thnermlfatigue, ad dYnricloading.
Fetiiue failure rob-tla connected withnozzLe-theral sleweasotibes.
ICSC camed leaks Inheat-alffcted zeiss ofthe safe-nd-to-pipewelds.
MoM.
(11) W6 Nore. 7
(58)
(19)
(Not mod)
A- 10 VA feedeter crackingdus to high-cyclefat i ge coned byfluctuations in watertearatura within thevessel in the nozzleregis.
Mons. ions. gm feedater nottecracking solutitmsvdor itproved repairmethods.
-- Primary Piping
(20)
119*
STRESS (cmitd)
REG. INSTRUMENT
GSIs (contd)
LIFE EXTENSIONMlIC FEEATATIES HEATURES C T UR iiTIATIVES AGING #ETDS LIFE EXlTENSION lEEDS
mt~.i 4 m S 6 C tOM 7 catm aCMENTSC01t a
(21)
(22)
A-IS Operation of LIt re-suits In stao corrosionof interior Mt Iur-face, of the primarycoolant stm, thenthese prodcts areactivated by neutrenftux old dWn circutatadthrouih the reactorptate-out occurs.
A-42 Pipe cracking duc toICSCC of aweniticstainless steel
ceptibie to this bybeing sanitized bypst-meld heat treat-Mont or by seruiliza-tion of a nerroe heat-affected oarf newaids.
E-6 Through-waLL cracksand fatigue crackgrowth.
M. km. Primary cooLant syste_ decontminaticn _rdSt_ gaurator chemiecl cleaning.
U".
kmo.
km.
km.
Ianc. Iore effective lDE toa*eure abenco ofIGSCC. especiallywider weld-overlayrepaired areas.
Evalrate nued toreplace susceptibleand/or weld-overtlyrepaired piping.
MOM.
Pipe cracks In 9iWs* Priority - RESltfD.
Loads, load cebinatior. and stress limits.* Priority - HIH.
see uEG-2800 SupI.
Piping Smduerk Problm.
PIE Syste Piping* Priority - RESOLVED.
ISI reseerch needs houtjld be Identified.Assisted effects (Note: exposura rates inex-vessel c enents may be too low tocaus an effect).
i-. (23)
(24)
(25) DYNAMIC EFFECTS* VIBATION* ITHERAL CYCLES
a. THEifil AGINGb. THEIRMA SHlM
* EROSIONa. COMBiNATION--
EfOSIDHEROIONi
3-25
C-7
k m .
km.
I
7Cobinatios of faril-catiorn stress ard
wnviro"RelaL corditlenae resulted in
isolated Instances ofstress corrosion crack-ing of loa-pressure 304piping.
Cas10 CFx 50.Appendlix 0,t. tt mid IV
ISI progre per AIECods raquirnts.
km. None. ISI coverigs may needto be increased.
III criteria my bedifferent far LicenseRamat.
Prixsry Piping
COMENT ISSAiXKUM~ I COLLWI 2
DYXMIC EFFECTS(26) (cantd)
(27)
(2d)
(29)
REG. liRSTMEtiT AGilS FEAfTtSESCOLumi 3 4OUS' i
INS3/' 0.5 Xor.3/4.4.10
3/4.4.9.1.1 RCS thermi cyclesare recorded duringheat-ups mid cool-domn.
3.9.2 Review the criterlatestiq procsuresnd dynemic enelysis.
5.2.1.1 Not met 10 Cf2 SO SS(i.e, met AM, SectionMii. red irmete).
LIFE EXTENS1OWFEA.IE OURMNT INKIETWIVES AGING NamO LIFE IXEMNSION lEEDSCOLM CDUM cCOtie 7 axU am =ET'S
M".
M".
eor.
IOne. Depende on ThetherSection Xi ISI repire-mants/reports we
mte vs. dast needeme attention.
eoM. Cycles we recorded.Hisht be ineful in theevelustion of thermlcycle history.
? Ntu.
Depen on wietherSection Xi 11 reqire-Montslreports anadequete vs. what needswre attention.
NW need to evaluatethermel cycle history.
This TS reWire ASE Section Xi, requirentconcerning ISi and mintenance for all RCS pipingthat is code time 1, 2, or 3 (161 TS. 3/S0.5).
Assur tructural and finctional integrityunider vibratory loadings.
Doesn't rse specific Issues; AESection Iti sot he followAd.
OM". tne. i1".
I.147(30) io explicit refereto aging; provides enitRC accepeaml listof AM15 aroved codecas spplic ble toSection Xi.
a~
(31) 1.89 ho explicit referansato esing; provides anXRC acceptable Ilitof ASK approved coedcases applicable toSection Ill.
meth loiplies life la rAsila we mumextenslon by provid- to Includ or excludeing ecceptance meth- appropriate Code Case.od for aWroved(ASE) Inspectionmathad using ,r-rent Code Ces.
The RC iptifee lIfe RC revisioas we ewdeextaulon by provid- to includ. or ecludeins ecceptmics mth- sppropreite code Cases.ad for approved(ASlE) Code Caseseterials indtesting acceptableto NEC staff.
V/A */A ABE Code Case re not mndatory. Code Casesprovide a mdanilm to use alternite methodswithin jurisdictiou of the code. The casesWe usually Sprseded ( aislltd) by revisionto the code, i.e., the se becomes pert ofthe code, In other inutakcss, the cas my bereeys or dropped as n alI cable thea
NM Code Ce" we not mesdtory. Code Casesprovide a mechanies to use alterntet _sthadswithin jurisdiction of the code. The casesre usually Sersreded (1ail lad) by reviloinsthe code. I.e., tih case becom5 part of thecode, In other instances, the cas my bereversed or rlopped as an alicable method.
5/A N/A
(32)AMESaction IliSubseotion
NC
Provides for designrequirmruts forilet load, earth-quake, vibration,RV thrusts , ightnid the effUcte of
thernl expermion ndcontrstlon.
Mi explicit;provldea rules forrpair riWorrepltcment of codeconents.
ispiled in thedesign criteria.
Guideice is neededto cowr the Ilimitsof ceonent deterio-ration.
AN* Code for Class I comqonente-pipingdesign rauired dean corrosion or eroe0onis axpcted; the piping thickness ehall beIncrmeed ovwr the othwr delin requirwnts.This allowance shall be consistent with thespecified design life.
Rules cover design nd construction require-_nUt but do not cer deterioration.
r- Primary Piping
DYNMIC EFFECTS(31) (cofltd)
AEG. INSTRUMEENT
ASK (corad)Section Xi
LI1FE EXTENSIONAGING=NTI*ES FEA1tWN
Corrosion aid Erosion.
CURRENT INITIATIVES AGING NENDS LIFE EXTENMSION NENDStOffllT 6llTAv COLL 7 CM" a
A ne SA en pipe 7will-thinning hasbeen estalished andwilt review thisissue with EPRE.Pain wat of cnernat this tips IS theeffect of erosion/corrosion on pipingin neornucler eppli-cations (ANSI/AYE*-311-1984). theRemaning Stra'gthof Corroded Pipelines.
tO9VNTS.t10W 9
The suc principtlly applies to secondery system.not prim".
The Section XI S~group on tolastructive Examina-tion is currently developing a Code Case and non-_IStory n dis on UT Detection and Mesuremntof Erosiantorroseon.
ANI11/ASE -1G-1v nal for Determining theemtinin Strength of Corroded Pipelines,
5
ddrese non-nueteer applications, but my hewapplication to nuclear ccments.
(34) (Not used)
"ts14(35)
(36) 73
(37) 86
Cracking in high pres-sure piping in PFAN esa result of corroeion.fatigue, and dynpmicloading.
Fatigue failure prob-tkef tcnnected withnozzie-thetml sleeveass"eblies.
IGSCC-c uud leeks inheat-affected zones ofthe safe-end-to-pipewelds.
Uwter hmer incidentsinvolving stem gWaiertor feod rings and pip-ing, emrgency corecooling system, Rimsystem. contairnentspray, service weterfeedweter and stemlines.
None.
Nons.
hon.
on. Detached thermel Sleeves
* Thermt sleeves mIntalled in the safetyInjection accumtator piping nozzleconnectiont, to the reactor coolant systemcold tlo piping. em found at the bottomof reactor vessels.
Long-range pltn for deating with stresscorrosion cracking In SM pipingo Solutien available.
1on. ene. PuA pipe cracks* Priority - tlW. PREStVED.* Corrosion cracking in tow-pressure piping
Is adsrssad in C-7.
None.
*Oon.
None.
(38)
(39)
tlot used)
A-1 1on. uater hmrfESOLfD 3/158.4 with pmbtication of1EC-0927. (Colett resolution of ltlwater h er protblm rntine se aded teble question.)
Primary Piping
COPOEN IS"UtDLL I COLU411 2
DYSSIIC EFFECTS(401 (contd)
(41)
MG6. INSTMA*NT
GSIS (contd)
AGIING FEtWSCa =i 4
ItFE EXTEN 101eFEATURE:0 OURRtNr INITIATIVES AGING NEEDS LIFE EXTENSION NEEDS COMMWST
MftI- 0
A- 10 6SW fet .tr crackingCAs to hilgh-cyclefatigue cased byfluctuattis in metertIFr&ture within thevssel In the nozzlregion.
k-l Ciperation ot LWt re-suits In strl corro-sion of Interior eetelsurfaces of the primrycool nt system, thenthee produts reectivated by noutrenflux and Wmn circulatedthrcsgh the reactorplate-out ccurs .
on. Nn. PA feetdwter noute cracking.
Here. Ne. ? Primey coolant systes decontasinetion mndstaae Generator edical cleaning.
t42)
(43)
(44)
(45)
(hot used)
(Not ued)
(Not ued)
(Not we d)
(46) STOWCURAAA INTEGRITY* PACTUhI* TOUGHINESSEM*ITTLEIIEaT* TNEEIINL
* SEISMIC (OAMAGE1FAILUnES* LANGE11, SNUBMSaS
AND AICCES
(47)
(48)
£18510 CFR So,Appendix A,General DesignCriteria (ODC)
Provides printipeldesign criteria for thetesting and per trequirenta forronents.
tr. xn. M/A, doennt chane overtim.
Does the existingdesign (generic or specI-fic), _eat the acrrnt(present ti_) acceptabletesting ard perforeentestandarde for life ex-tension?
Appendix A, Design of crqwnurt,should he bcc tighodwith censideration fornetural phenome.euch me esrthpukes,tornaes, end flows.
Design Is based anhistorical datefrom the tim oforiginal license;sacafacy ndinforaetisn myhave been altered.
N-.
N-n. £ew~irafiits May changever tit. gtrtwal
5
events mY slte thetdesign bse.
kn. Depends an adetherAME Section Xt ISIIrowirments areaedqmt vs. what needsmore attentin.
Anslyse of currantkawn conditions asapplicable will berequird.
Depands an bhetherAS, Section Xl ISI,raqirmusnts areadaqate vs. chat nnedxOst attention.
Generic or site specific research my be Criterion 2necessary.
this IS requires the requirmnts of l.S. 4.0.5.(ASK, Section XI; 1t1) be applied to RCS piping.
asS3/4.0.5 &3/4.10
saw.
- Priesry Piping
CayU I toUM Z
STRItETUAL INTEGRITY(49) (cntd)
REG. INSTEW"ENTCOtUM 3
TSs (ctntd)3/4.7.9
AGI*G PEATtWES
Reqires periodictesting of gaiters.
LIFE EXTEuSIOiFEATuRES CURLENT INITIATIVES MGING NPSCOUMz 5 aCttl 6 aOlLt" 7
LifE EXTENSIN NIEESCuOtUM a
Could be modifled toasure records weradeqete for Lt
s wnt.
teLr 9
Non.
(501 Ts5
None. ight need to e andto Include deed weightswuports. ndiors,ate., of necessary.Inspection are to bethe bis for Pwoorevelation.
working troup on rWorating Ptant Criteria;a proposed addition toArticle IU-S3l00 of Sc-tin XI uoutd containrutes and formulae forperforming in evltue-tion of e cnsnen sefitness for continuedservice ten eitherlSe or ltemnts ofits conatruetiouvdesign lieitationhbd been exceeded.
This TS reuire periodic functional teting ofSnubers.
(51)
1-4
ko 052)
(53)
(504)
(55)
Se3.6.2 Rlvaeu origtnel systa
design adequcy
STP PEN 3-1 Stress sd fatigueimits; deAlgn retuire-
vnts; Inspection ofwde.
3.9.3 nd Reference to ASPE33.93, Section III and DCAppeix A 1,2.4. M4 15.
5.2.1.1 mast _st 10 CPA 50.55a(i.e., Wt ASE.Section tII, require-ments for pressure
bosateriae).
5.4.3 fleting requirsentsof SRP, Section 3.9.1,3.9.2, 3.9.3, 5.2.3,ntd 5.2.4.
Yas. Nono. Non.
Non. None.
Neinty concerned with the consequnce of apipe brak (pipe whip and Jet forces). BYknowing wirs aid how a pipe is met Likelyto break, lopties providing adeqate design_argins to prevent such carreses (i.e.,the piping Nyotem Is analyzed thorotughy).
Brake ar uuanty at points of high stressnd ftigue (terminal ati ad nozzles).
Loading cmbintiton, systin operationaltralsient*, ad stresa limits.
Nene. (exsept fororiginal designarginr).
oae.
MOM.
NOne.
None.
Non.
Non.
None.
056)at1.31, Rev 3 Controi of ferrite in
stainless steet otdeto limit eferacracting.
bnt. Define level of ferrite Determine life expec-nd to resist nvi- toncy of wmd overleyrorsentattry rsisted repairs.cracking.
Intent of EC 1.31 _sn't to specify ferritelevel ned to reist erecting. Reitsfrom 6PTI MP T302-2 suggest currentlyaccepted ferrite levele my be too lam.
-- Priary Pipite
CEWVQMT IS"COL -- LxL
STRLU1TnU" INTEGRITY(5I) (contd)
(58)
(59)
(60)
(61)
(62)
REG. IMSlImAT AGING FEATURESCowLN 3 rcOlLM 4
RS4 (contd)1.46 Protection eairst
pipe whip insidecontairnmnt.
1.147 No explicit rhferecsto uire; provides antRC acceptable listof AE aproved CadsCaels appicablo toSection Xi.
1.46 Design nd eoadingcominatteon forseismic Category 1,fluid systan cownas.
1. aS no expticit referencoto aging; provides anRC acerptable list
of ASO approved crCoasts appitel@ toSection 111.
AgESection III Provides for designsuixection rectutraernus forhe ibpect ltod, orth-11C qjse, vibrations, KV
thrttts, weights ndthe effects of thermalexpaenion andcontraction.
14 Crackirn In high pra-aura piping in Me5 ana resuLt of corrosion.vitbratory nd thermalfatigue, Nrd dppasicloading.
a'
LIFE EXVENSIOFEAnleii CURREN IXITIAIIVES AGING MuS LIFE EXTEMSIO KEDScat w 5 COLuM 6 COLlil I COULN a
wilthdrwn 3/1/M. a"n.See 3.9.2
The MG isplies life xC revisions art _l dA MIAextenion by provid- Intiude or exctideing acceptance math- appropriate Code Cas.ad for approved(ASI) inspectionmethed using eur-rant Cde4 Case.
wil thdrawn 3/1/VM. .S.o SxP 3.9.3
The CC tpties tife to revisions are "eextesion by provid- to inctiue or ecltudeIng mpance math- appropriate Code Cases.ad for approved(AE) Code Casemotrilts andtesting Acceptableto Mc staff.
Mo exptcit;provides rutee forrepair anidorreplacsount of codscmonants.
K/A MIA
imsWilJIM 9
Cast Mtsinlass Steel is a Generic issue in primarypiping syateas, i.e., flanges. pW casing, etc.
AE Cade Cas ar not eNwWtorY. Code Cat"provide a machantas to was alternate asthodawithin Jurisdiction of the code. the Caere usually uersbd (isaited) by revisions
to the code. i.e.. the case becoms part ofthe code, in other Instancesr the cs may beravarsed or dropped as an pt licabte _thod.
Med Cade Cases re not madetory. Code Casesprovide a madisnias to ume alternate _sthodswithin jurisdiction of the code. Th caesre uwsuly sperseded (neetled) by revisions
the code, i.e.. the case bvcos part of thecode, In other inotances, the case my bereversad or dropped As an applicable mathod.
ASI Cade for Class I coponunts-plpingdesign, reqires dn corrosion or eras-ion Is expected the piping thickness shllhe increased over the other desin reuiranta. This allowance ehalt he coruistent
with the specified design life. Rules coverdesign nd construction requirents but do notcover deterioration.
Pvt pipe crechsPriority LOW. U /IS.LI
^ Corrosion cracking In law pressure pipingis addressed In C.?.
b-JC0
no led In thebsign criteria.
Nokm.
6uida Is nedeto cover the limitsof toeponewt deterio-ration.
"one.xore. None.
(63)
(6)
Long-rune plan for dealing with stresscorrosion cracking In VAS piping.
Piping review comittee recomendetiona . 'Noaignificant cag in put1ic safety witt resultfram resotution of this Iseue.
119 o n . Xone. Mao,. None. M1".
- Primary Piping
UFE EXTtVSImNcap" MT I REGaf . hNSItUENT AING O fEAIEO FEATLNUES CaLRRENT INiTIATIVES AGING LIFE EXTINSIN NEEDS
Gan I COLllt 2 Cr COLUM 4 CCCUJ 5 UN 6 OLW 7 COLUIM a
SITUIIAU INTEGRITY G 1s (contd)(65) (Comtd) A-1 ater ir Incidnts ibns. Non. 7 7
iivolvini ates Samra-tor fed ringS NWPiping. emergency rcost ings ystem, OHNeyetem, centai Ptospray, service weterfeedter nW steminnes.
(6) A-if Om femchter crereking l . b nra. 7Oe to himih-cyclefatigue cammed byfluctuations In moterterature within thevassal In the nozzleregion.
(67) A- Is peratien of LW re- thnr tons. 7 7sults in atom corrosionof interior Metal ur-feces of the primarycolant system, tn
thmes product areactivated by neutronftus and whon circutatedthrough the reactorplate-out oc"".
(6a) 4-42 on. ions. o. tons. tkw.
(69) *-6 Nong. o, lins, ge". gone.
(70) 5-25 7 lons. I 7 7
(71) C-7 lone. 50n6. gene. 7 7
COIla 9
waterhe r* tSocn 3/15/84 with publication of
11MG-0927.
mm feedwater nstzzl cracking.
Primary coolant evetm decentaminatien andstem gnreator Chemical ceaning.
Pipe cracks in WAS* Priority - RESMVED.
Loods, load combinations nd stress limits* Priority - 5IGN.
Piping ienciwark Proems.
P"a ystas Piping* Priority -ISOL.ED.
C-4
I-A
Primary Pipinr
COMPONENT ismE
WATERS GSENISTRYIPIURlITIES
*INTERGRAMaLARATTACK (lOA)
*CcjiBMAT I O--CORROSION-EDSHMIO
*IsRanAllAIOASSISTED 5.2.3EFFECTS
(INCREASED RADIO-LYTIC DECaOS MITIONOF WiTER)
REC. IibSTRirgNTCOLUMN" 3
Cf10 CFO 50,Aeodis AGeneral DesigsCriteria (CDi
AGIN6 fEATiRE5cd.aui 4
Provides principaldesign criteria for cor-porent testing end per-fornce reqwirrts.
LIFE EtIERSIGIFEATURES CURRNT INIITIATIVES AIIGBE EDS
=ii70
iorn. MoMu. B/A. doeen't c~eover time.
LIFE ESXTIB51i IksS
Gos the existingdniu gnleric or speI-fic). met currentlyacceptable testing endperformance stuoierdsfor litf extlenion?
~gcisSSLIMM9
(73)
174)
TOO3/4.0.5 &3/4.4.10
Reqwires ASEK SectionXl ISt for code class1, 2, and 3 crtents.
hon.
Mon.
own.
Mwn.
B/A
I/A3/4.4.4.7 Requires chemistrycontrol of the primiry(RCS) coolant.
Depmna oan wetherreports/records ofAAIE section XI, Mre
dqeete to be w"ful.
RCS ater chemistryrecords are retained.Perhaps useful Inevalusting piping his-tory with regerd to(RCS)
this TS reWireu the requirments of T.1. 3/4.0.5(ASKE Section Xl ISII to be applied to code class1. 2, 3 piping. (hate: closs 2 & 3 are Generallynot primary systems.)
KC chemistry limits are show below. Are theseadequte for the corrosion lIeu?
Steady StatePaaeter Limit Trani nt Cialt
(dissolvd 02)* 4.10 AN 0.00 Wm(Cl)5 .<0 15 p '1.50 ppe
A i^ *S t . i4s .2 5P 50 Wm
M/A if RCS temp. is -250-F.
I-.I'M
(75)-S5.2.1.1 lst met 10 CFR 50.55.
(i.e. met ASESection III reir.-ments for pressue-boupdiae ).
Revie. suitabilityof materials chosen.NiOE testing per ASNESection I, ii-2500.
1on. Bor. Men. oan et address ecifIc issues; ASiESection II at be followed.
(76) 5.2.3 Born. 7 ge. Covers slt rector coolant pressure bouxbrymaterials.
a"1."(77) Process controls to
minimie sensitizationin stainless ateetwetds.
Bor . ione. Setter understandingof retltionshiptween welding proc-ess eWd sensitization.
iGternine life expec-tancy of sen itizedmateriel *nd rAeiser-grade stainless stOel.
MAC Prorr_ on OEvalnution of tillded andRepair-Welded Staintess Steal for ULWService Initiated work in this er" but wasnot coepleted. A well dfort My be ongoing.
-- Prioery Piping
COMaONET IS"M
CORMSoCIA (coitd!)(?S)
"a6. INSTIMEMT
SON Ccantd)1.56, Rev. 1
LIFE EXTENSIONAGING FUTURES FEATURES OMURNI INIT IATIVES
Cantrotl vof ter 1P". CcL i. rogorm an MA*puri ty iNMI15. pipe crack rmSodies.
ci9)
(AG)
AIMISection IIISubsection
awl
NC
14
73(81)
Provide. for desinloo affecting thestrength and intg-rity of the presasrebtndry.
Cracking In hish prae-s" piping In Puts *a remutt of corrosion.vibratory and theretfatigue* and demlocloading.
Fatigje falturI prob-tm eenneted withnmtle-thett Stoe.asethliee.
IGSCC-csmd ltee inheat-affected onne ofthe cafe-ahd-to-pIpa
Stree corrosiod crack-ing in stem _ terer.
"GM.
Ne.
Ne.
Ottr nowtod" ofaffect Of ipurities
an cracking.
141 led in the deslgncriteria (aes Coents).
1one.
(azi 86
Man eaplicit;provides rute foereeir ndor replace-ent of codeceanant$-
Nn.
Ne.
None.
.ono.
NorM.
"One.
M.
Mn.
NOM.
Nam.
Nam.
ttFE EMSVIONg INEEDS W TSCltl B _ NES 9
Life epectancy of 1 1.56 limit. enly coithtivity, pil adcracked pipee on Chloride content of water. Other apeciespresune of isp-itles. need to he cuwidered Secant recearch
amegeete lifits y not be tow enouh.a*RE-0313 inclesbe guidetinre for 5WR piping(IGSCC sitigation).
Cuidence is nd AN Cade for Class I cments piping designto cower the tinits rqired then corroeson or erosion is epected;of compnet deterio the piping thickness ehelt he increased ovr theration. other design requirents. This attloence shall
be coiatont with the specified desigan ife.
Nutee cover deain and construction rajire-innts but do not cover deterioration.
liw. P1A pipe cracks* Priority - LO. RESOVED.
Corroieon cracking In ltwpreaure pipingIs adreasa in C-7.
7 Detached therial sleav* Priority -^ the thert see Ins talled In the
eafaty Injection accumistor piping mnlecornectiena to the cold teg piping werefotnd at the bottem of reactor veesetc.
t Lon-rase plan for deating with atresscorrosion cracking In PAi piping.* Solution availeble.
t Stros corroelon cracking of pressurmHunabry ferrItIc stsil in selectedanvirom rts.
None. Piping review c ittee recudetions - ftoaignificant chawe in ptblic safety wilt resultfrin resolution of this flws..
Nam. Water hemor.
Name. KR fhedater nestle cracking.
(83) lit
(54) 119 N".
Nm.
NOne.
Ne.
Na.
flr.
(M5)
(86)
A-i
A-10
Primary Piping
(87)CORASION tcW~td) Ills (cantd)
A-15
LIF E XTENSICO CRSNAGING FEATMI*S 941*1 *M I IVElIS AGING NOEM LIFE EXTENSION KOS1
tC.UiW 4 (JLL 5 CLIMN ttiUM 7 tG iii aComm'TsCOUSIN 9
Operation of LWR rMsuits In slow corrosionof ainter aosmtalsurf acm of the primarycoolant system. Oenthus. prjutsN aweactivated by nasatranlima an shenf circulatadtrugh Ome reactorplate-out ccurs..
hem.
None. hons. Primary coolant systsm dscantasinstlio andstem Generator chasical cleatnin.
(SO) M". Ne. NE. None. Pipe cracks in WAsPriority - eSOLVE0.
(89) 8-6 ns. W". bore. ne. Load&, loud c InbtiOW, old aCres. limitsPriority - Mail.
(90) *-2S Ne. hone.
(91) C-? a". NE. 161 . Pit Syom Pipins* Priority RESOLVED
(95) SluNGILLAOICE:* 1111189* IMaPECtIati
REPAl AS* IN8
CTs10 CfR SO,Appenix A,Genural oesignCriteria (UC)
Provide. principaldesign criteria forthe txsting and per-foracs reqwiroentsfor coonints.
Ne. bo. V/A, dIeIn t chaover tim.
Ooe. the exlatinsdeelan (atwric orSpecific) met aur.runtly aept-bltestin aid perform-mace steviards forlife Nxtanieon
Anlyue of currentknzAn emiditiorn aepplicale will be"Wired.
(93) Appidix A. Design of compontaCriterion 2 should be accmpished
with considaratlon fornatural phauoirsuch as* etthqakes.torndoes nd floo.
Oesign is booed anhlstorically data
rrm the time oforiginal license;aceuracy aminforsution my havebeen altered.
Noew. N jirsr nt r my cherwaoWr tim. "ssturannt& my alter the
deslgn base.
Gonvic or site specific research my benecear .
(94)TOO3/4.0.5 &3/4.10
R*sjres ASE,section xi, treatmtof piping with reardto mIitrnce and ISIif code class 1, 2.or 3.
.s. NE. a/A TS requre the provialens of TJ. 3/4.0.5(ASE, Section XI. Insrvice inspction) beapwlied to Code Class 1, 2 * 3 Piping.
-- Prisary Piping
LIEEXTENSIGNOMMlTS is"1 PEG. INSTOMTE Mi1sS FUAURES FEAUIWES CURRENT INITIATIVES AGIN NEEDS LIFE EXTENIiON lEMI
(95) SIBVEILLANCE Ccontd) TS& (contd) NIPE. 12-4311 WILXreport to be pre-pared an reactorcoolest press~uebourdmry piping(me soments).
5.2.1.1(S6)
(97) SZ.4
WIIt met 10 CFt 50.55atl.*., met ANE,Section III, reqire-snts for preemiebosoiderles).
Reire III Progree afMO (CUC-32) to sthe structuretl teak-tight Integrity.
leptnmt OR progur.
Visra Impection ofIntruint lines.
Systus for detectionof toek eg In the M.
None. Moo. Non.
ton.
(90)
(99)
(100)
17.2
1.11
1.45t-i
U,1
(101)
(102)
1.5a Rev I Osullfication forinpection personel.
1.147 Mo expticit re esto aging; provides aniC tccept lbt listof ADe opproved cocecas e plicble toSectiot XI.
XNa. ? "na.
MonitorinQ. Mo. gone.
Mono. AWL devt t Correlate teak rateof aceaitic leek with crack size toaonitoring. dbfina acceptsuce
theits.
IAtitoritq. AKE Section XI Better detection wddoevloping criteria sizing of crack-typsfor perfohece de- defects.stration qultiflcationof Inspectore.
The AN pItmis life S1 revisions oe sede V /Aettnsion by provid- to Include or excludsIng atccptance meth- propriste Code Caes.od for approved(CAE) inpectionMuthode uing sur-rent Code Cas.
10".
pone.
etter training metqualification pro-cedres. Io vd in-spection mthod forcoers-grln _terisls(wide, east 55, etc.).
N/A
uN seme 9
Description: Perfoen walt thickness trrelqng onprinary/aecadary pipinE syste. Aleo requ.irewntafor tronalont niiitoring of priesry pipinq high-stress tocationa snd theret dty. Estabtlohpiping vibration and dnric effects ntpiping/stidin spprt locatitna for war/corrosion.
Could toed to ISs modificationa of PeC rule changesor codes mat Stantorde.
Dosn't ad*e"spepcific issues; AWESection III at be folltead.
Based on requiresents of 10 CPR 50.55. arddetailed in AWE, Section XI.
Ooennt dees aging per a; just statesthat a CA progres s required.
AKi hoe devetoped in acotatic leak moitoringystn f roe taboratoy experiownts. The sys-
te n field validetion.
AWE Cod. Case we not mntory. Code Caesprovide a mcluonlo to ue alternate athodewithin juriadietion of the code. The came
uwe uially aepersedad (wuttld) by revisionto the code, I..,* the cue becom part ofthe code. In other inatonss. the cas my bereversed or dropp d ee n ppticabt _ethod.
P- Prhery Piping
LIFE EXTENSIONCO"P111XT MA0 55. IMISTALANMT AGIMG FEATME FEATURES CURRMN MINITIATIVES AGIMG humD LIFE XTESISION KOSQW I a COLUMN 3. CZUMtIM 4 ......... AKM.L..... C)j........ OLa 7 C OLUMN a
COMMETSMLoo 9
MS ILLAMCS (contd) R0c (cantd)( 103) MUReG- liol USPE-12-4240 MOEX
rport tO be pre-pared an rtsctorrecirculation tines(see crnts).
Dcesriptinmi iner eas rceircuattion pipinginspection Intervts nd pereontaee tocr ply with tAtai1Dol. Dewelp crack growth1uvee for motonitic xs in SiC uwirroent,
considering 1121 nd other wld tretLmnts.DewLop nrpectiraV ntoring prorvin forthetI aerittlemnt of duplex cast S5 pmpnld valve bodies.
Early plants deeignsd to sieplif ed criteriaof AMEO VI II rd WS. .
(104)ASKSection III5-3600
Codr rqwirmntsupdated to Inceltutransiont cnsidera-tons starts4 testingfor vibration andthermal diSplact entsrqui red.
(105) Section XI lMIterial nd cero- ef. Info./dotsnwnt cidition bsese xx they Wpy28aes$MKt. to raqasats for
I cence extension/raniits.
Mo nonndetory Sam other cotuirs.appendix an record-keeping has passed"C-PtLE.
xdf. Intfo/dotbvee to im rtextnsiau/rurraats.
As natarialO MId cQ.Wits ao, thtpredictive cepebilitias for physical andmchanical prtperty chne ant Improve.Since, ruino a plant' service life, n In-creasing _ t of informatiaVdats will beeveileble frow surveillante pro"rS betterprocxduree to evaltute end uss this Inform-tion'dets can and mat he developed.
(104) Sutveitllnce. e.. basetlin Smi- A nw task Mrip an See other columns.ration rouirommnte. besetine eSamination
has baen astebtishad.
Possible need to rerair A now basetine
eamination for aticonse extenionreqIust.
(10o) Altlow far Inspae-tioer beyond 40 yevrs
Ch(nse to inupec- PA has ioplinnted 'xtended nd*or,tion Plans A And S revisisne to ttA- arionced surawiln te
which ae currantly 2400 wshich Mill beyand 40 yer.based an a 40-year delete the 40-yearoperiting Life based limit currently con-n four Intervals, tained In Section XI.
the m of which Also revieSing naed* 40. for mre frequent _ nd
extensive inspections.
Suveillane beond40 yeas.
(106) monitoring Andtesting.
Inforatioidsta Deval4 t of now Information, data,for trend curves. axm technilrms to aid asasoeants.
detect see-relateddaoradtion nrdfatissa being can-sidered.
Itcorda, ineorem A t is coreidering Inforemtion And datetion/data. developnt of a non for trand curvs.
mandatory Appendixfor rfcr, dFpinr.
hanitorinefteetingt -ehnu.
(109) Information anddata for trindprojections.
Records. InformationVdots.
This appendix amtd provide the utilitywith ouildne as to the records needed tomuprt a license extension request.
-- Primary Piping
LIfE EXTENSOlNOEgMP t ISCJE RG. INSTRUMENT AGING FEATUEIS ffUNES
t XUM I COLUMN 2 anu~l 3 EOL"n 4 COtt= 5
SUVIUANCE (contd) ASME (contd)(10) Fatima failures. Anticipate aid
avoid fatiguefailures.
CL0M T INIIIATIVES AING NEEmmCIUMt e _ COLUNtt 7
fatigue monitoring iEperience ad testtedIlogy developed dat f or high-cycleNW d troted; effects.several utilitiespoe aiing.
LI Ft ttte NEEDS
tgulatory accptanceof alt te pahto design baees.
COMETSCOLUMN 9
a) Failures unikely from cycles consideredIn deaipn. nseip a h is caw rvativa.Cronent features loltuded to precludefatigue failtur. Ceononta have highte'ree to floa..
b) Fatigue cracking ha_ ecurred eirnqoperation:. vibration* rapid thiet cycting. pro-existing ft_. other c 1dtio nrot conaidered In deign.
W1414(111)
(112) 73
(113) 86
Cracking in hig pres-eta piping in PW* asa reault of corrosion,vibratory wd thermalfatigue, and dynmicloading.
fatie failure prob-let connected withnozzle-thermat ateenwzseetlIes.
ICSCC-camed tlek* inheat-affected zone ofthe asfe-end-to-pipewide.
Stress corroslon crack-Ing In SteiN gaertOr.
am.
*OM.
Non.
Mom.
Mom.
None.
3mwe.
3mwe.
Nn.
Non.
Mom.
M".
0o.
3m.
Wm.
Detached thewt *l elev - The thermat atevmin teliad In the cafety Injection accumulatorpiping nozzle connuctions to the cold tl pipingasia four at the bottom of reactor vessels.
Lonw -wne plan for dzaling with stres corrosioncracking In GM piping - solution available.
Stres corroeion cracking of prssure bwkeryferritic toelts in Selected awirormehto.
3mw. tl. Pull pipe cracks* Priority - LW RSLVED.a Corroeion cracking in tow-prisacre piping
is addsed in C-7.
(114) I11
(115) 119 Nam.
Nom.
Gon.
sae. Piping review cmmittee io3 tiomn - -Nosignificent chang In pubtic safety wiit resultfrom resolution of this Isee-
one. vater h .
Nn. M fllOI dter nmzzle cracking.
(116)
(117)
A-1
A- 10
-- Priery Piping
LIFE EXTEISIMCUeQEXT Is"J MEG. IMMANJENT MING f&ATUMS FEATURES OUSMii IMITIATIWES MGIMIS VME LIFE 6)(rsINi lEWS
SABEILLAIC Itmond) "I1s Ccontd)(118) A-iS ~~~~~~~peartlio of LUR r.- hnm. kmw.
muits in slow corrosianof Intarlor mmctl Sur-faces of the primaycoolant syat.m thaithese produts weactivated bi' neutronfluxt NW m~en circulatedthrough the reettrPiae-cut occurs.
(119) ~~~~~A-g2 hoe.b . pam. Mine. Mons.
(120) 1-6 hone. ha, lione. Nomw. Nam.
CDLUMNi 9
Primary Coodmnt sAt_ dacntmintlrn -dAtm Or tator dwalcel cleaning.
Pipe crocks In ism' Priority - AESID.
Loads, lead comtination5. aid stress limitsPriority - A101.
Piping Sntimark ProEems.
Pg System Piping* Priority - RESLIOD.
(121)
(122)
3-25
C-7
bons.
hat.
Momo.
'man.ah.
O-4
I-.
Primory Piping
APPENDIX V
REGULATORY INSTRUMENT FOR PRESSURIZER (INTERNALS AND SUPPORT PIPING)
Understanding and managing agingof pressurizer, surge & spray lines
Materials Vesse * shell, A-33 GL. B. Class 1.Cladding, Type 304 SS & NIr-Fe Alloy
Heater * Sheath, In1o Insulation MgO
Fittings Statically cast 8S -GrC aF8A andCF8M MW) SA 516 Gt 70, Tpe 309LSS PE.C BS&V Type 306L ss tSbY
cladng * lype 306L 88 (CE), Type 304L 803W"
Spray ftn
/ t D
Clrcumferantial . IweldsI Wolof
leve
N eater support
surge line- Elecblcal heater
7T.plca W pressurizer andcontin
Heater mndcoed! by 4 ]
Clad MM
Lo head fM f
eleaen (N-Cr-F.)-0
Defier
S blee to heater wd
sleene to clad weld
r shing
Surge one * Type 316 8S cast SS 3r CF8Mtome (CE plants)
Spray Una * Type 31 SSNozzles on main coolant pipe * SA 105 G3t 2 CM, Type 304 N SS (V%)Thermal sleeve * hnol BB16
Operational bansent temperature, flaw Induced vibrats,strtifed flowe, thermal sbipping, thennrd shocks, heatermechanical wear and element burnout and erosion and corrosion
Typicl CE heatr equipmentStressoreendEnvironment
UNDERSTANDING AGING MANAGING AGING(Materials, Stresors, & Environment Interactions)
Sites Aging Concerns Inservlce Inspections, Surveillance, and Monitoring Mitigation
Nozzles and thennal sle. Low and high-cycle thermal NRC requirements Recommendations Maintain full flow In spray One endoperate It continuoualy to prevent
* Instrumentation Eroaion Volumetric and surface examination of 25% of Perform more frequent examination of nozzle welds having sbatfled flow and thermal shock
Surge butt welds Including the following welds each high cumulative usage factor. conditions* Spray Inspection Interval 10 CFR 505sa. IW-25W0:
Determine fatigue damage by on-lOne monitoring of coolant eplasce horizontal section of spray* Al dissilaer metal welds and piping temperstures, and flow rate In nozzes and One with eloped ection to prevent
Terminal end dhsImIlar metal Low-Cycle thermal and * An welds having cumulative usage factor horizontal portions of piping during operational transient, stratfiled flow condition
wslds (between carbon teel mechanrcal fatigue equal to or greater than 0.4 stratified flows, and thermal ahocks.components and staInless * An welds having da Intenslty range of Redesign piping to ellminate valve
teel piping 2
4 8m Perform nondestruwtive eaminations and Ioea parts leakagemonitoring to assess status of thtermal gleeve develop
Same welds are required to be Inspected Improved NDE method to delect crack growth In te baa Preventhiv or predictive
during each Inspection Interval metal and welds maintenance far heater replacement
Csst shainls steel piping Low-cycle thermal and mechatnl-Cal fytiguem Aw detectbu end evaluation 10 CFR Develop techniques to monitor actua degree of thermal se Improved stem pecling
* Sul" nn Thermal embdrtement 50.559, NB-3000 embrItiamlern ag.. develop Improved NDE methods and matehria* pry lne Erosion spray valve tools using magneti properties measurements and
V EBori acid Corrosion Leakage Hydrostsac pressure tests 10 CFR acoustic emission
Fillings Stem packing/wear and 50.558, IWB5Z0degradation with age and Monilor valve Wea
Service lfe ASME Section m, N9-3210 and ASME SectionBellow degradation )U, aI Develop UT to detect flaws on cast stainless steel piping
Cycle counting of specified design transenls
Header sheth filurs Small LOCA via healer ebement Tech Spec's requframenteand heater sleeve
* Cycle counting of epaciflad designtranelents
Vag" wan High and low cycle thermal * Leakage rate.
ht1gw * AT lmits for heatup/coodoown
COPOENTs is"ODU CLV
REGULATORY INSTRUMENT REVIEW FOR LWR PRESSURIZER VESSEL
LIFE EXTENSIONACE. INSTSRiUET x lit FiTxtES FEATLURES ClUUExl ISIl1AIIVES SAM56 t.l E xIF ESImI NlEED'S
COLUMN 3 C 4 CiILU 5 coI oJ C1iV 7 COLtLN a
come
MOW'1COhLUMN9
PRSSMaIZE1CLtIMTED TOINTERALS ALSPECIALITTIThEM)(I)
WEATER(E) PROLElSTHIESNAL IND:AMECHANICA. WEAR,ELEMEN SLIRMLIT(S)
(Geralstatesant).
a"e. iot. segulatiuu are neededthat dross aging ofpreemur bassry cowFMnts.
Regulatlon wra neededthat ader. u tiensrao.w.
(2)
(3)
IO CFit 0, the SO I shatt be de&si-Appendix A, ed. fabricated and testedCriterion 14 so a 'low probability- of
abormol tlekae endro" rupture xst. The
criterion ilpt lez thatthe design shalt sccaoutfor mechanical deereationof the heater shdsthi andstems.
Scn. Preest,. bouadry inter-nets of the veeselsshould be adzessed Inthe regulations.
Preset,. butn-ry Inter-nlts of the vessel.should he aessed Inthe rasulatione.
Provides record ofheeter replacmnt, i.e.,operating history goador bad for the specificpresurizer.
The Code of Federal Regulation (CFft) dese notexplicitly dees the Intervals of the pressurlzeror the vessel n t ortine wPy/surge piping.Since the preesurizer is pert of the act prMe~botmdsry, the rules set forth by the Cm principallyapply to the vessel shall, the - rto NWd spray/surge line. for deeimg. fabrication, operation andpreoperationt testing. Applicabl* section noted forthe pressurizer deeredetion isste wre ibplled agingfeeturee for the internelsand associated piping.
Failure of the heater sheath and heater steevehew rezutted in presse boaadery leaks. oasterbun-out is not a safety issue me thee my toreplaced. Neeter leakag, however, is a safetyIsomu.)
Providea seine muet by reqiring replace-aent of heaters to maintain a level of power(heter) irput capacity. i.e.. the hater* mustal*vys perform at a prescribed leveln th forc-ing surveillance an repeir.
TS63/4.4.3 Providts adatory res-
toration rolirmontsfor heater *t 'ta.
Iandatory stu l-tlnce could providerecord for pres srecycles.
a/A
(4)si
(generalstatmntl
1one. Nn. SAI need to ddrssfailure mechanism ofthe beeters. i.e., Isreplacesmnt the onlyeffective agIng mewwmmt proieduro forthe heaters?
laoundency and ese of The presurizer heater, ere not explicitly adressedheater replacsnt should in the Ms5 . eater alsvo failure, hav resultedbe vatsuttd for ticam In pressau e bsundary iCt fahilurs. Detective hest-rutml criteria. Test- ora ad poor design e the probable cames for themn of heater. should in- preesca. bootdary failures; however, sinel my be actuds exceasiw current factor In the failtures, e.g., sering and Thinningleakage. dee to rubbins action with soewrts caused by
thetml growth. Although heater. ar easy toreplace, a technicat safety issus extsts become ofthe potential tehzok peti that could reoult in aprimary contailrent leak.
Verify that the inspc-tion la sdote fortlica ruveel.
(I) Ceqtree taI proeramto ae0s leaktightIntegrity.
ir. Provides for selectedIASIE Section XI) codeinpection of meds forthe life of the plant.
Ge er sl t Motes:1. A ?7 indirmtoe further stuy/tinvoetigation is needd.2. For the MSI, areolve me the generic eafety I1aue to reotlved, not necearily the aging is'ta.3. For meaning of ton ero and initiatle tsed throughout, see ecranr on page i, xii, and x1li of the rmport.
- Preurizer Vesset
COPUExT IS=uECLUMN I c L 2
NEATERS (contd)16)
(7)
(a)
(9)
(10)
(11)
FEG. INSTtMNETtCOLU 3
(Gareralstattnt)
AM codsSection 1II(GeraL)
elseC51 13
51.1-1983 Plt
55.11
ICEE3ZS
AGINt EAREStClm 4
lne explicit.
Man explicit.
LIFE EXTENSIONFEAUWRESCOLici t
Noeeplicilt.
CURENT INITIATIVES AGING Nu"DCOLUtN 6 S"UMN 7
7 Rovislona roe" thatexpleictly srees theagIng of plant cage-Mants Ned systm.
own explicit.
LIFE EXtiErmo NmEEDSmthW S
Nelesorsise that*etiiletty ddresslife extensian ndlicens rmmwt.
Aesursinc that thtcurrent rqetentinethoa/repeir offai led heters Weadequte boyce thepleat lieatsereneals date.
Effects of procmirorrellebility on liceseextanelon.
Mar.
COMNTSCOLU. 9
The UC Rewlttory Guldon (aft) do notexpticitty ed*,a the internotl of thepressurizer.
ASE caiea raeurints re priarityCaered wil preseus. bmatry Integrity;e , *ectia of the code, howeve, coverother conerns such aa Section I IIWthat cowe reactor eore Intermis, notthe presure boundary.
_tt t Ir LOCA from extu-ed rheating of presurtlar heater,.
Operatlons wintm e, ad testing roWire-mwnts ae ed only to the extent that theyeffect deeign provision.
Extended overheating of Iae.heaters, cyclic fetiga.mid service Near.
Estbtlihea the eactoer riginel deeignsafety criterie mnd fhne- criteria couldtianwt design recoire- sport LK.wants of structwesesyst_. mnd cpnntsof stetiatwy 1im .
Providee deelig criterie Addroeaes cefetyfor "yta and oIpmit fnietliaw that anecassery to achi mnd closely alignedMintain a safe shiutdoin with aging If niof the reactor to cold Correctly con-shutdesn caidition from trolled, e.g.,a hot standy or poet reactivity MCE.accidant canditlon. heat remval. o
mam; sm Wee Effects of overheatingdropped. on pressurler
relIabilty.
1 None.
ire
it
Nor. w.
Ability to pe rfor sfetyfhrction dur to the affectof aging at he ed:Issd.Types of aIng incetudovibration and eer.
Provides crIteria for pro-tctions requrmnts forCtns IE pawer systin.Protection from electricalor eha cal l e_ orfeilures within a tIesfrse too short for aprstar action. Doesn't In-cude rpysic al designfectars such in fires,pipe whip, etc.
iCS integrityIneltding pres-surenmrd Iwen-tory control.
Acceptce andqatifyine records.
Maw. mom. IEEE stadhrde 323 c oped to other Instriantsrevlewd recagnize the nwed for eging and deffneeetepe to addrea, aging sc he age conditioningand netural *ping criterIa.
The protection refdrs to swe c nd end executefeetursn, e.g, switch gear protection standypower protection ond sage protection. Protectionshell be designed to slime for periodic testing.
(12) 741
'' Pressurizer Vessel
LIFE EXTENSIONCtuPENI ISSUE R. INSTRUMENT AGING FEATLRES FEATUiESCOLUMN I COLUMN 2 COLUMN 3 CUOLLAt COLUMN 5
ilRiRENT INITIATIVES AMII NEEiDS LIFE EXTEuslaI WADSOLUN 6 ODcrLL4I 7 COLUMi a noteS 0
(13) 934
344
Provide crte ria forreoplacnt parts, bothconstruction ad rra-tion. Reiqures Inspectionad testing of perts priorto release for service.
Acceptance testingad records thatwy be applicableto Lit e.g..failure revite forWar. fatisue.original dafects,insutation breakdvoa etc.
San.
Ao".
Non. Stadard detlaminsr selection of required partsfor Clat II equipswnt, e.g., Identification adfailwe revite. However, required design chare outside the scope of this stadard.
Niow.(04) EsteS lakes recoindd Acceptace ardpractices to obtain data qualifyingto wulify that the quip- records.sent witt Perform en SSEafter - ON. Includedre taets for vibrationel
egtng, mimic sping ptaSnarmt operation toads.
(tS) SURtE SRAY LINES,NOZZLE PRiLEMSo STRATIFIED FLOW,
TRAXSIEST THERMALLOADS, TtlElALSHOEK; hSULltIGIt LOW-CYCLE 1tlEi-
C9-- %AL FATIGUE
Csa10 CAi so,Criterion IS
tCS shalt be designed forsufficient Hargin toasar that the designcordition rot be exceededduring noral operationor anticipated operation-at occurrces. Thiscriterion teplies thatthereat shack rd otherfactors in the design ofthe pressure bota"ryshould be inclusde.
Nn. Reviason needed toeging or life of plantconsiderations.
Revision heeded toaddress operatiawbeynd the plant'stices rmeel det*.
(16)I1a3/4.4.92 Providee for control
over the ray eaterATs; restricts AT toa a". differentialof 3201F.
Addresecs tructuratintegrity of pressreretaining capnents.
Records for cycles. a/A Could provide a recordof comoent serviceptlicobts to llacma
renet, I.e., has theervic _aceed TS
Temearture lailis?
None. Are the originat design_asamtioen valid fort icene rammat?
Provides aging mnient by restricting thetemprature AT.
(17) 3.9.3 Design in accord-ane with ASHE III& 10 CFR-SO, GeneratDesign Criteria1.2,4.14 ad espec-tally CDC #15 that
stipulates thedeign shalt hovesufficient marginssuch that operationsincluding loadingcominations adtraisients witt rotsxeed the originaldesign cuditions.
-- Prentsi-er Vness
COMhEMT I=E I ag. iNSTOIEES
PAWG It SPRAY LISES Ti Ccomtd)(is) (centd) 3.9.1
LIFE EXTENSIONAMilS FEATUEES FEATURES CURENT INITIATIVES AGING NEEM LIFE ESISEEIDS NEMD
CLUMNI 4 - OUM5CL CINU11 7 UUJE S$OIENT2
cous 9
Adreses ftigum awlsty... ad Meeting therequiresants of 10 CFR-50GEC n15. Specificsatydess the acceptability
of the design relativthe nub r of cyclee endnavals expected emr tie
tfe of the plait.
No explicit referanceto seinr; hese. pro-vides an NEC accepteble(ftt Of drov ASKCode Cam for SectionXi.
Provides _cceptae 7criteria applicableto licene ramevet.
Tb. PC Imixp Il Iife, RC revisions we madbextemion by pro- to include or sextudeviding acceptane apropriate Code Cee._sthod for approved(UE) in4pectionesthode usine eur-ren? Code Can.
1.147(19)
verifictiotn of therur of cycles adWaits.
NIA
letter Usderstamdingof tie rtationrahipatmeen welding processWA senitizatin is
Neeuaresnt of _eterietfatigue life.
Adeqate event rOeW opeptine historyn_< ethodr neddto predict the *naitdtfatigue ltif of theeprey/surge lIn ca theawd of the plant elicee rameet dete.
(20)
(21)
144 Repir of PM tines.Proem controts tominimize sraslizetionin steintise *teetmaide.
No. Noe. I
N/A
Daterminstion of lifeeepectamcy of sensitizedeterielt ad nucelsrgrab stainlese teoteis nd.
iep re d-of-tiftprojectins, 40 yesrsawd beyand Accuraterecording awl recordsfor pressure awdtht traswients weneeded to deterinefatigue dm0. tospray awd surge tine.
LE Code Cas We nrt es.dtory. This AGpresants a NC staff a cable list of ASHEcouncit pproved Code Cae for use In inspec-ti1 ard repeir of cosepm a as required by10 CFQ 50s, Appndix A, wd Section 50.515.
INC progrge an -vsltation of Melded andRepqir-Meid Stainless Steat for ListService Initiated sork in this roo ebut manot coopleted. A Smlt effort my be Ongoing.
Studies wm under may to assess thie msnitudsof the effects Of ectual moirarmxntelcomditions. Code curves re based on sothopecimmna In *ir at roa tprsture, idees_e _steriels in service have muih roudhersurfscesa ored we osed to flowing coolant atoperating teeperatoes. The sctusl surfaceswe mm prom to track Initiation. studiesand research to mesxs xnitud of effectof nwviroent factors could result in needfor mrw Regulatory Guide. Regulatory instru-entos xnor code revision.
a CocSection III Aresses fxtigue.
0,
Fatigus cur Section Xi, SVA anrevision. Operating Plane Cri-
teris Is reviewingftisus curves inSection III to deter-mine If they can berevised to Acc sdeq lreion btyand 40ye r . U S E S o nfLEX hts rc d
that _ppropriate XId tteto investigateacre frnt NEE asure. tine mIds thancurrently reuired bySac. Xi, 15.
(22) ^ eoelon (mtt 0-3210 Specialthiminni) cosaideretione
of 55-3121(Sectiam Ill)
IlterIlt "Jetct toerosi0n corroslon awn
_nkhaxicat ebresion nath e silitionr t atlthiicknee to account forthee anticipsted con-osditilone.
None explicit; bowdesign should provideculda for the ade-qawy etof t designbyrd the 40-yearInterval.
7 Iptled In the deelin
criteria.guidanee is needed tocover the limits ofc I t deterioration.
1t-3121 states 14terist eoEct to thinning bycorrosion. erosio, mnicat xtrosion, orother awrovmnat effects shalt have provisin
tD for thee effects during the design orspecified tiff of th crponant by a sitablIncreese in or sddition to the thickness of thbe Meta over that determined by the designforaulxs.
0
multe vr design and construction require-sants but do not cover deterioration.
-- Presgurizer Vesset
~COMOENTs Ia.COLMI I -- mKL
SLOGN & S1PRAY LINES(23) (contd)
AEG. IbSTEIIENV
Gil 47
LIFE EXTENiSIONAGING FEATIRES FEATURE aRREsT lotITIATIVES AGING NEEDS LIFE EXTENSION NEEDS
COLmin aCOMEENTSC tLje 9
Therat streU resultingfram scatained operationof UIPI.
te. a"e. Effects an presamricerreLiability at pt ntsat ehich presasizerhas ben over heatedand cootod
Mec concluded there IS no direct safetyitplicetion of overfeeding nd over-cooling prerwier with lPI.
(24)
(25)
AMB51.1-1933 PW EstebtiAls the raeleer Original design
safety criteria nd criteria couldfunttionel design roqire ar t a.wnts of structus,syste, art d cowuntsof stationary Pt.
58.11 Provides design criteria Addresses satyfor syst mnd eqipmnt fumctions that arenscessary to achieve ad closely Alignedesintain a safe shutdWan with aging If rotof the reactor to cold correctly controlled,shutdown conditions frem *e.., reactivity, KSa hot Stfaby or post heat rmoval. nd tCSaccident condition, integrity including
prassmra ad iran-tory control.
tone. ono. 51.1 is for Pta nd 52.1 is for Mis. Thestanderds are essentially the am. operaties,eintence, and testing requiremnts are coveredonly to the atent that they affect designprevisions.
ton.tons.
SPUAY MEMD CR5B(26) * THERiAL .INUCEO, 10 CUR 55e
EtWirTLET.ENT Codes and* ESOSIOS Standards
(21)Tse3/4.4.9.2
Regulation refers to ASESection III for design ofcloss 1 cmonants.Ipplied that erosion willbe adkessed in pipingsystes design.
Provides for specificAT (1OOf) heatup adAT (200F) cooldes inany 1-hour period ad mxpry ester differential
at 320-F.
Vonet.
hsterial subJect toerosion, corroeion. ad_esidnicel abrlasln anthave additional talithicnes to actmntfor these anticipetedconditiono.
Meoa. tevision needed to Revision needed totddress aging. ae operation
beyond the plant'sIliceise ranaweldets.
REcorde for cycles. OVA Could provide a recordof ceonent *erviceapplicabl to litensrenewal, I.e., has theservice _xceeded TSteerature limits?
Provides aging eanagmit by restricting theteerature Ala.
(28) Section III Non.
oNam.
(29) NR-3210 Specaltconsiderstionrof t-3121(Section 111)
Mn eplicit; hb.-ever, design shouldprovide guidence forthe aiaeocy of thedesign beyaid the40-year interval.
Implied In the designcriteria.
hone.
Guidsnce is nde tocover the Imilts ofcrwnt deterioration.
AVE cods roqirmnts are exclusivelyconcerned with pressure bonderyintegrity.
58-3121 states 4wateriatl sbject to thinning bycorrosion, erosion, mehanicsl abrasion, orother anvirornentat effects shall have provisionmod for these effects during the design or
specified titf of the ceonent by a suitableincrease in or aeddition to the thickness of thetse metal over that determined by the design
formute .0
Rule cover dlsign ad cesatruction reqire-ments but do not cover deterioration.
-- Pressurizer Vessel
SPRAY HEAM (cantd)(30)
NES. IHSIRMTHH
SRu 47
LIFE EXTENSIONMuGsN REAI$ FEAni*ES CtNREX INITIATIVES AGIm NEEDS LIFE EXTgwuOw NEEDS
calmCOLO" 5 ODUM a~m. 7 cOaum" aMHETS
COUSIN 9
thmrol stress resultingfrre siutained operationof IPI.
Ne. Effects an pres uri erreLiability at plentset idieh preesurizerhas been overfed Mndcoated.
NRC coicluded there Is no direct Safetyitplication of overfaeding end ov r-eooling pressurizer with HP).
(3t)
(32)
vM51.1-I30 FUR52.1-1903 "o
58.11
Estai btt the nsutolrsafety criteria Wdfunctienet design requfreMonts of structuresSyste NW cnd ernntsof etatirey HoPs.
Provides deasgn criteriafor syste nd wipeentnecessary to Aehi" andmaintain a safe dwtdounof the reactor to coldshutdoan csnditiens froma hot stwdt or postaccident cendition.
Originel digncriteria couldsport LA.
brne. 51.1 is for fet nd 52.1 is for Suis. Thestndrde ae sentiauiy the sw. erations,_iinteswece, ad testing requirements er coveredrnly to the extent that they affect designprovisiorn.
Addresse safotyfuntti0w that arecloaely aignedwith eairg If notcorrectly controllede.g . reactivity, KSheat resa. rnd KCSIntegrity inctudinepresaue ard inverrtory control.
(33) SIELL uetERsAtSHELL BARRLIt 1STEM SPACE: lItG& LOW CYCLE THER-PAL SENDING ATATYER TO STEAMINTERFACE
Csse10 CPU 55e.Codes aidstwndrds
Regulation referencesdesigniIn accordencewith AIE Code Sactitnuuu for clm I ccp-mtsa. b pliad that the
design will dre high-nd low-cycle fatigue.bendinf stress. etc.
Hon. Regulatian revisionn d to addressaging.
Regulation revisienneeded to adesscpretins beyond thepltnt s license re-newat date.
3/4.4.9.2(34) Provides for apecifIcAt (10t0F) heatup ndAT (2003F) cooLdenin an y hour periodnd Mx. say waterditftrential at 320F.
Records for cycles. H/A
(35) 2.1.1 Establishes madatoryhidu-tturetue tlidtfor the pressuritzr(highest reactor cooltnttauperature).
2.1.2 Establishes diatoryhighprnessue iadt forthe reactor coolentysytem,
Auto trip provideerecords of traneientcoruitions.
Auto trip providesracords of tren ientconditiosn.
i/A
H/A
Could provide a recordof compoent srviceapplicable to licerserenewal, i.e., has theservice exced TSteweraturs limits?
Could provide a recordof transient corditionrend o nitaring ofcyclic events.
Could provide a recordof trensient corditionsed monitoring of
cyclic events.
Provides aing _nsont by restricting thetemperature Al.
Provides *ging mewag t by establishing the uppersaterial terstura limits.
Provides aging ingeet by establishing thehigh-press" limits.
(36)
-- Pressurizer Vessel
COMPONIE
(ST)
Is"
SELL. INTERNAL.(wiltd)
RE5. INSTeEMMT
SOP3.9.3
Lift EXUE5SIMNAGING FORTUNEIS 'EATURES OMOEMY inTIATIVES AGIN6 NEEDS
COUSIN 4 OUI ...... Lj..... C 7l _LIFE UTIEMIN RUGS
Are the originial deelenassumptions valid forlicenee toweul?
IU1ENTSCOLaS 9
Addres structurtlintegrity of pres"s-retaining coronts.
Decisn in accor-dance with A51KIIl mid 10 CII SOGenral DesisnCriteria i. 2, 4.14, 15. mid N eciltty GDC *15thet stipulatecthe dusign shallhe sufficientertin such that
that operationsincrtufiN loa'ingloading crabine-tins mid tran-ient will ratexceed the originaldesign cerditione.
5m.
(38) 5.2.2 Ovepreture prot ction. Overpresmurprotection.
V/A
(39) L9.1 Adde es fatigue mid*trew ard meeting the
requirmnto of 10 CEO50 0EC *5. Specificat-ly aess the accpts-bility of the design reta-tliv the nubr of cyctesaN events epected overthe life of the plant.
Prwvide acceptancecriterIa apticaleto tircan renasal.
verificetion of theraber of cycles aiOevnts.
Probebty adsate forticuiae renewai for thisspecific ~et. Suirosprotection for the lifeof plant events.
Adqute event recordsWet operatinr historyneeded. alth de rerim to predict theaveltble fatipa lIfeof the presrurixr daoltAt the id of the plaitnslictms reneat dote.
tequalificetien Rutcefor crpnents.
*evilw stipuletee that ovarpressure protection outbe avattabtl (ahfety/retlef valves) for the prec-suriw SIO S of atltrabte pressure for traml nts
or operational occurruae woe or mr time duringthe life of the plant.
;0
A CoseSection III(40) Iseq~lification of Itemtification
compoents. of comonents.A tus appbidis Isundor caidereltionwhich may be used tormqulify coonentswuich hwv exceededthe rulsa for cyclicoperation in Sec-tion Ill. d-3222.4.A tlek rcup hasbean IoIu to Adresthe iss. This olsoapp le to Section xi.
evaluate nru nAidix.
-- Pressurizer Vessel
LIFE EXTSNSIWILF ETNIO EDU*PUCENT Is". VEG. l115tRtiIfET AGINIG FEATI)RES FEAIWSS CURRENT INITIATIVES Atiet NEEDS1 MUEMVESI5 at 01915 CII
011Cm 9
SHELL iiNTERL ASME Code141) (cantd) (cantd) Fatigue. Fatigue cwe Section XI, VA on
revisions. Operatin Ptnt Cri-teri is reviewingfatigue curves inSection III to deter-min if they can berevised to o rcoo-dote operation beyour40 yews.
Moe. Improved mndof-lifeprojecthone 40 years
nd ed
ttudles ae uwder way to assess the Meunitude ofthe effects of ectiat evirorwmntat conditions.Code ctves we based an smooth specimen In air atroc teeratuwe, vhreas Materialts in service haveMuch rougher aurfates and re exposed to ftowilrcoolrnt at operating tmyeratures. The actual sur-feces are mr pron to ractk initiation. Studiesand research to mess Magnitude of effect ofof nviusesntat fectore could result in nred fornew Regulatory Guide, Regulatory Instruewnts wor code revisions.
(42) Section XI Condition assessment. Reatification Consideration of Condition assesomt,of stem and devlicpment of nre Informatlon/dete.canants. Article 11X-8GW
Rteqmlfictlon forFatigue life. An AiSKKt has bein formed onFatigue In lif. Themoal of the US Is toprovide a mecmenlmefor rtelief then thefatigue design limitIs reached. (TMe limtwould be deterined bydeveloping Monitoringand evaluationtechniques.)
Requatifitation ofatys rnd componentsfollowing eapiration ofoperating license.
(43) 151 47 Thermel stress resultingfro susteined operationof liPt
Na . Xone. Effects on presourizerreliability at plantsat which pressurizeshas been overfed andcooted.
mRC cwctuded there Is no direct safetylepti catin of overftoding aid over-cooling pretr oaler with "PI
Zi
(44) 51.1-1963 P1R52.1-tse3 VAR
Establishes the nuclear Original designsafety criteria and criteria couldfunctionalt design rewpire- IIort La.
wits Aof tructures,systems, ard coonentsof stationary ffs.
"One. Cone. 51.1 as for PF~s aid 52.1 is for Mis. Thestndrde We essentlatty the o. Opperation,
inte te, and teatinil recpuirnta re covmdonLy to the atant that they affect designprovisions.
(45) 58.11 Provides design criteriafor ayst_ nd quipmntnecessary to achieve andmeintain a aet ehutdmnnof the reactor to coldhutdown condition froe
a hot standby or postaccident condition.
AddresseS asfetyfiuction that arecloseLy aligndwith eging If notcorrectly controlled.e.g., reactivity, IcCheat rval, mid KCSintegrity Includingpressure and Irn-tory control.
Cone.
- Pressurizer Vessel
COMPONENT IS"ECOUM COLM2
TMERMAL. SLEEVE(S)(4) * TMEUIAL STRESSt
FAT IQE
(47)
(48)
149)
AEG. IiSTALMllTCOLUMN 3
AGINGPETIEMSlLIfE EXTENSION
FEATURES OERilNT IMIITIATIVES AGING NEEDSCOLUFA 5 COLUMN 6 aOLtlM 7
IS&3/4.4.9.2 Providaa for specific
AT CiixJF) heetip andAT (200) toolgdounin any I-hour periodend mx. spray Diterdifferential at 3Z0P.
2.1.1 Estebtlisha _adtoryhish-teerature limitfor thi pressurizer(highest reactor coolanttemperature).
3.9.1 Addresse fatigue endstress and mating therequirmnots of 10 CFXSi GDC 15. Spcifical-ly ddrerc the accept-ability of the designrelative the nunerof cyctes nId evntsexpected over thelife of the plant.
Section XG Fatl_.
Records for cytles. 1 /A
Auto trip provides 7 I/Areords of tranientscondittions.
Provides acceptance 7 Verification of thecriteria eplicable nuer of cycles idto license rasmal. events.
fatigue curve Section XI, Sv on Measuremnt of materialrevisions. Operating Plant Cri- fatigue life.
teril is reviaeingfatigue curves inSection III to deter-sine it they can brevised to accoateoperation beyond 40years.
LIFE EXTEhSI hEDS
Could provide a record oftcmont service app0ic-able to tgiar renmwal.i.a., has the Service ax-cedod 1S teraturelimits?
Could provide a record oftran Int conditions andonitoring of cyclic
events.
CiaETSCoUi" 9
Providem aging menaement by restricting thete4 aratura ATs.
Provides aging moa5mnt by estlablishing the uppermaterial tesrsture limits.
Adequate event recordsmnd operating historyneeded. Methods areneeded to predict theavailable fatigue lifeof the pressurizer shellat the end of 40 Vors.
Improved mId-of-tifeprojections. 40 yersand bhyind.Accurate recording mndrecords for prasaure Athermal tranients erneeded to deteinefat igm de tospray mnd surge lines.
Studies are uider way to assess the mognitudeof the ef fcts of actual envirocmntslconditions. Code curvea e based on smoothspecimmen in air at roin tuqperature, dhereasmaterials in service have much roucjhorsurfaces and are exposed to flowing cool nt atsperating temperatures. The actual surfacesare sure prgr to crack initiation. Studiesmnd research to _m e magnitude of effectof anvirontstat factors could result In needfor ns Regulatory Guide, Regulatory Instru-m*nts meler code revision.
0
(50)ANSS1.1-19i3 PWR52.1-1963 Mm
Establishas the nuclear original designsafety criteria and criteria couldfuhctional design reuire- spWrt Lt.ments of structures,systam and cooponentsof stationary UPs.
None. Mone. 51.1 Is for PMe nd 521 Is for SEis. Thestandrds er essentielLy the sam. Operations,maintenance, and testing requiremants re coveredonly to the extent thet they t fet designprovisions.
(SI) - SHEATHES; CEMtii-CALLY INDLICED)tGSCC & FATIajE.
I GENERAL:s WRATEDCOOLANiT LEAKSI
IIgaT~Ii/CLOUEES;$CC, LUMNICA-TtION. MOISn"EgINVIRCOsEIT
Ma10 CIR SSa,Codes indStandards
Regulation requires de-ign, fabrication mnd con-
Otruction in ccordencAsIE Code Section lit,class I components. Codereqiuires ttention given tocorrosion, erosion. emnvironsental effects; thisIsplies the regulationaddresss the aging issue.
Mone. None. improvements in the ASYE Code are needed to ddressdeteriorstion of materials.
-- Pressurizer Vessel
(52)
ISSMI
:'I WOMl~ (contd!)
LiFt EXTENSIONREG. INSTRUMiENT AGING FEATNEES FEATURES CURRENT INITIATIVES AGING NEEDS LIFE EXTENSIONi NEEDS
COLYM CtOtLLIN 4 taiOLei S COUM 6 iOe 7 taLU101 aT5glNTS
Caiteri
am5.2.3 ateriel arwe roviused
for suitability for theservite. Iaview ofmeaufecturaing nd weldingis also inctuded.
eone. Nn. Wane.
a."(53) efin teak detection_thods for RCPI leeksthat ewortor potentlilchanges in conialrmntenvirornwit. osch asincreesing hueldity.
Should providerecords of pestplnt coneditlonsAnd current Leakstatus forevaltution ofLicense recvlapptlications.
AIM. has developed In the current RGen ecouetic eathod position adeqate forfor teek wonitoring. eging oenegemt?
Is the current RC The AL acoustic laoratory experimantetposition edequete for _ethio need to be verified by field tests.license ranewel?
(54)ASE Ce16-3210 Specialoensiderations
of 1N-3121(Section IM
Reeqiirmnts ipliedfor the specific pressr-rizer perts. The intentof thl code is bt esaterial ubject toerorion. corrosion, andmachaniclt ebrbsiln thatmat hove additional etlthiCknesS to account forthe gnticipetedconditions.
1Ne expticit; how-ever, design shouldprovide guidence forthe adequecy of thedesign beyond the40 year interval.
7 Implied in tie designcriteria.
Guidence Is neded toCover the limits ofcosmnt deterioretion.Adeptete eonitorinu isneeded to detect boricacid leakage endcorrosion.
11-3121 states _Materiel subject to thiming bycorrosion, erosion. mechenicel abreeson, orother envirme*nta effects shall have provisionmide for thes affects during the design orspecified life of the Ceponent by a suitableIncreae in or addition to the thickness of thebas metal over that determined by the designfonoule".
Rutes cover design nd construction require-ments hut do not cover deterioration.
See MAEG/CR-2963.
(56)
CSI A-16 Plhterut of activationproucts; increase inoccu tionhrl doses.
Am51.1-193 PVR Establishes the nueclear
saftty criteria ndfunctional design repire-wente of structuresnsyste. nd c nentsof stationery kaps.
58.11 Provides design criteriafor systeme Ad eqiuipeentnecessary to ealfeve aidMintin a safe shutdounof the re etor to coldshutdtue conditions froma hot stmdy or postaccident cndition.
MOMw. Issue t resolvedupon isecae ofpidence toutilities.
Original designcriteria couldseport Ii.
Adreas sefetyftuntisns that areclosely alfgnedwith aging if notcorrectly controlled,*.g., reactivity, ISheet rvel, end RCRintegrity Includingpresure end Invwn-tory control.
Long-termo effects ofchemical decontamln-stion agents on theprimary coolent system.
11". Ione. querations, mintenance, ard testing requireentsare covered ornly to the extent that they affeetdesign provisions.
(57) sons.
-- Pressurizer vessel
SURVEILLANCE:(56) *TEST ING
*INSPICTIdsM AINTENANCtE &REPAIRS
*MDE(59) *INMPUITIOM/DATA
:FRbEQENCYDATA. COLLECTIONE
-DATA EVALUAT 011-TREND CURVES
(60) -REWORIRG 9EElING
REC. INSTRUiENT AGING FEATL*ESC~OLUM 3 COLtrAi 4
CMS10 Cfx-SO Regulation rquires theApperdix A. VPC be deaiand toCriterion 32 faciltete periodic in-
spections.
10 Cfe-50. Regulation reg.irs a DAApperdiu E plan for design, per-
ations and testing.
10 CfR-SSG, Reulation require $ISCodes and in accordrnce with ASlKEStanderds Section XI.
LIFE EXTENSIONFEATWRES CURRENT IRITIAWIVES AGING NEEDSCOLLM SOaUiNo COLUW 7
Inspection records 7 N/Acould establish in-terity or canditionof the compnt.
GA documentation t X/Asill assist inlicense renewalprocess.
III records sill 7 N/Aasist in licenserenlewa proesses.
lf1)ism3/4 4.0.2 S4.0.5
(62) 3/4.4.3 &Including4.4.3.14.4.3.24.4.3.3
6.0 (Adminis-trative con-trots) 6.10.1
(63)
I-r'o
Provides surveillanceintervals and reforencesASNE Cods Section XIfor class I copnents.
tS with its surveillancereqireents dictate theelectrical hester cp-city and water levet ofthe pressurizer.
Lists mandatory 5-yearretention records list.
Lists mandatory life ofplant period for plantretention records. Prin-cipal interest is item6.10.2 *. shich specifiesthe rscord keeping timfor traieints or ope-aing cycles.
Compent statunrecords.
M/A
Crnpnent statusrecords.
N/A
Provides recordhistory of ceomn-ants ad sytem.
I/A
LIFE EXTEBIOII hEEDS aEhIlS_ COW.5I S CoLtoe 9
Verify that inspectionrecords ae adequate forlicense renewal.
Verify that the DA dau-swntation is adequate forcurrant licane renewatneds.
IS1 Intervals and *xcep-tion allowed my notfully address ticrenewel concerns orremjirments.
Records could be u ed for Should provide history of corponant for licenelice renewal, I.e., renewat application.verity the history ofcsoent integrity.
Records could be used forlicense renewal. i.e.,verify the history ofcqont Integrity.
May rewuire longer reten-tion period than S ywrsfor principel inspections,Sta 6.1i1.b. ad d. tobe ppicable for licenserenral.
Could provide sufficientinformation nd recordefor GA, ISl. water quityand otherse includingapecific records for com-ponant transient cardi-tions, i.e., TS table 5.7.1"Coonent Cyclic or Trcm-ient Limits.e
Is inspection adequte Inspection are to be in accordance with 10 CfR-SO,for liceras renwl1? Appendix A, Criterion 32 snd 10 CfR-Sh and es
detailed In AKE Section XI.
Is the bA plan adeowte th SRP dom not explicitly addres aging orfor license reneal? license renewt, only that a be plan is repirad.
(64) 6.10.2 Provides record history of componentsnd cestm.
N/A
(65) 5.2.4 Requires 11 prograto asees teaktightintegrity.
17.2 Addresss maintenanceaid testing retativethe isplt entation ofa Quality Asourance plan.
None.
Records of minten-mnce and testing.
Provides for selected(ASiE Section Xl) codsInspection of welds forthe life of the plant.
Is in-place be planand record keepingadeqste for agingmnsgent records?
(66)
-- Pressurizer Vessel
COMPONENT ISSIE ME. INSTmMIEIGT AGING FEATURESSCOLMN C LU 2 COLUM 3 X 4
LIFE EXTENlSIONVEATLIRES 035R551 INITIATIVES ACING NEEDS LIFE EXTENStION NEES
COUMN 5OUN6CKmIi 7 CQUIRM aNETS5
SUMVILL.ANic (tontd) RonI.50(67) Esteblobes guidance
for the qalificationof IDE staff ihoperf01 inspectinsr.tests and exasinationsfor Nfp.
Pr.v"ids dsucnt-stion of staffquaitfcatitns ndquality asstrm*erecoids (of staff)for the plantyA pl n. i.e..records 'eed forlI fcense reemi.
GA docuentetion.
7 Improl d qualificationguidance my be neces-s*ry to fully ddress*ging coneoe.ne.
Irlmpod qualification Saferarm ANSI 115.2.6-197.ujience my te neces-
sary for Lt.
(66) Sfety Guide 30 Estabtishes regulatory(Ns AG 1.30) position for 04 require-
mnts relative to test-Ing of electricaleqipment.
None. On. Neferences 10 CO 50 pnditx *, OR criteriafor Mm.
(69)ASK CodeSection Xi(gral)
Metedf 1 Wi ctp-nent ctnditienAssesismnt.
*ef. info./dteUbses as theyapply to repastsfor exteiions/renewles.
New nadrtory Soe other coltns.appardtx on rtcffd-keeping hea passedthe SUG-PtEX.
oef. Ilifojoaetaseem to spot
extaiosiorm/raeneaLs.
As materials and coonents age, thepredictive cepebilitias for physical and
techenical property changes ust leprove.Since. uring a plant's service life. in in-creaing amlunt of inforMation/dats will beavaltable firs surveillance program, butterprocedures to evaltute aid Use this inform-tion/ata can nd mat be developed.Stratified flow nd thermet aacEk aremajor stressors In the base natat nd welds.laed mtcl inspectionr atone are Insufficientfor aschonicel property changes.
(7D) Section Xi Sutveillance.
i-
Ne baseline exm A now taSk grouptnstion require- on baslfinements have been examination.estebt ifed.
see other columns. Poesibte need to re-quire a new baselineexsamnetian for alicense extiensionreqest.
(7t) Allow for inepec-tione beysd 40 yers.
thenes to Inspec-tion Plans A andS wihch we eur-rntty bsed on a40-year operatingtlif besed on fourintervals, the *ufof which * 40.
SW3 has Implementedrevision to IWA-A4O. which twilldelete the 40-yearlimit cwrarntly con.tamed in Section Xi.Also, reviewing needfor e frequent wdextesiwe in aections.inopectior AM PLEXm is also reviewingInapection Plan A for4ptlicetion to PIESor should a new plan(of higher retimbit-ity) be devaloped.
Exted Uadorwrdiced srveil ttncebeyond 40 ypers.
uwrveittltce beyond40 yees.
The £SE PtEX SuR is reviewing the I npectionPltn A to determine if it should be wed.
-- Presuriwer Vessel
COMONETt
(72)SUREWILLANCtE (contd) ASME Code
(Conltd)
LIFE EXTENSIONMrING FEATIRSl FEATURES ClARMMY1 IgTIATIVES AGING NEEDS LIFE EXTENSION NEEDS
COLLM 4 - OLM 5 OLM COLUMN 7 COiMNs a wigMEMI"COLUMN 9
Monitoring ndtest ing.
inforsatiorV'Dets Dvtarpent of new Informat ion, data,for trend curves, exa. tectniiqoxs to nWd aao.se saenta.
detect tso- relateddegrtdttion aidfatigue beingconsidered.
NoriltorimW/teatingtochniiipmt.
(73) Information and datafor trard curvitprojectites.
Fatigue faiLures.(74)
Records, Infors- PA Is considwringData. develipment of non-
modrtnory appeindixfor recordcilwiping.
Anticipate and Fatigue manitoringfavoid fatigue technolegy developedfailures. and doanostrated;
$sv~ral utilitiesprocedhing.
Informat ion and datafor trend cuve.
Experience and testdata for high-cycle*ffects.
Recorde, inforuat ion,aid data.
Regulatory acceptanceof atternate atprodhto design baas..Addition of fatiguecurves to high cyclesis needed for litfxtenittn.
This Apptndix would provide utilities iithguidance as to the recordr needed to supporta titer" extension request.
a) Faitures tunlikely froe cycles conaideredin design. Design approach is conservative.Ctponwt featurs irncludd to pretludefatigue failture. Ctonents have hightoleraince to flaw.
(75)
(76)
a iW-25Wt Weld integrity ofheater penetration weidere qire visurt inspec-tlion.
R-47 Lonrg-term degredation ofCilas 1, 2, 3 coponentrxa. ts.
Provides criteria forselection, qualification,Kd training of persicnttfor statlionery nuclearpowaer plents.
Recrs and accept-ISce staiderds.
ISI raquirsonts.
Xon.t Frequncy ofexaminat ion.
Issur me dropped Characterize long-tenrfrem further degradation of cte-consideration. pneant supports.
Juatify the chtngtie inISI tntttrnat. Thetexisting frequincy mynot be sufficient forlicente renewal.)
Lentv of 11 insPec-tion needed to verifyadequacy of 5cprts.
b) Fatigue crackiting has occurred duringoperating:* vibration. rapid thermal cycling. pro-existing flaw. other conditiona not considered in design.
Section XI in Table ILi-250D specificallytaddrett the pressurizer; however, onlythe pressure vessel, piping, nouties. bolts atdhydroastatIc/llakag test. re ddresed. Thiecode do"e not address the presaurizerinternals.
NaC referwencd ASK Code. Section XI endCA Progrs before dropping isaue.
DAS(77) 3.1 Providee record
on training ofstaff.
gonm.
(78) 3.2 Provides recawodetionmsrmd recquiroments for ad-ainitrative controts,including oritten pro-cedres, snd EA progrmto help asture that activ-itimes of IiPs ore carriedout without risk to healthend safety of the pubtic.
Administrativein-ptlce controleswill probably berequired for LR.The essociated OAdocumentation Wittbe useful for Lt.
Mons. lins. Aong the activities covered under thls standard aredesign chongoe, f bricating, cteening-decontaming-tien inspecting, testing, eaintaining, tAdreptiring.
-- Pressurizer Vessel
LIFE EXTENSIONICOMPONENT ISSUE REG. iNSTNUMENI AGING FEATURES FEATUMES CURRENT INITIATIVES 841St OEMD LIFE EXTENSIONNE MSS tOuENTS
nxim 9
(79)2"ZLHANCS (centd) ANS Icentd)
51.1-1983 Pli Estishes the nuctear Original designsafety criteria Ed criteri coutdfunctioal design reqitre- suport tR.*ants of structure.syst. *nd co entsof stationary NPPs.
lnlr. Operatioif *intterte, and testing requir cntsae covered only to the extent that they affectdesign provisiese.
(f0) 55.11 Provides dsiegn criteriafor syste m d a eripemntnacessary to achieve Namaintein a *ea shutdoswof the reactor to coldshutdon coiditlons froma hot sttndby or peataccident condition.
Addreses safetyfiaotienz thatwe closelyalineda with aginaif not corvretlycontrolled, e.g..reactivity RSC heatreval. and RCSintegrity inclueFint pressure andirnentory control.
Is the design criteriava Id for Lt?
Tom(81) Provides minimu re-qtirmnts for Inepse-tien aid testing ofClass IE poerintrunttation ndcentroL etaient &a-Ing c isttrtotien plas.
Records of con-struttion ay beaW leable to LR.
7 Nam. None. Provides a criteria for correct instellatiesn oAehcould of ect agfng aspects of the aquiPeent after
tart-up and operatien. Cias Ir Is eaiupent thatIs essential to _rgency wutd4n. eontsirmentIsolation, OCC, mad CIO.
Gn
-- Pressurizer Vessel
APPENDIX VI
REGULATORY INSTRUMENT REVIEW FOR EMERGENCY DIESEL GENERATOR
Understanding and managing agingof emergencey diesel generatorsPrincipal Diesel Engines In Nuclear SeiviceManufacturerALCOAllis ChalmersCaterpillarCooper BessemerFairbanks MorseElectro-Motive DivisionNordbergTransamerica DelavalWorthingtonOthersMaterials: (typIcal)
Aloy steels, welded steel plates. castiron includng,gray. alurnun, stellite seats, forged steels,ductive Iront, non metallic gaskets, hoses, seals
Capecities:HP 215 to 670 per cylinder or 8o0 HP to 8390 HPKW ratings 50, 500,1200, 3000, 6000
Stressors:Cooling water, lubricating oil, fuel oil, starting air,Intake and exhaust, deterioration, dynarmic stress,vibration. themWl fatigue, wear and harsh testing
C-
UNDERSTANDING AGING(Stressor & Enviroment Interations) MANAGING AGING
Sites Aging Concems Inservive Inspection, Serveillance Mitigation* Instrument and control systems Environmentally induced: dust water. NRC Requirements Integrated EDG program of testing,
Governor heat. oil chemical. etc. * RC 1.9...surveillance, maintenance, periodic testing inspection, monitoring, trendingSensors * Maintenance errors: inadequate training, * RG 1.108 ... routine testing, maybe with drawn due and maintenance activities:Relays maladjustments, etc. to RG 1.9 revisions Tesbng/trending, change testing
* Startup component a Fsst starts and other regulatory Induced * General letter 83.41...fast cold' starts to a slower start test and* Fuel system factors * 10-CFR-50, appendix A. criterion 4,5,17,18 A 50 acquisibon of these testng
ipipng on engine * Design Inadequacy, wrong application. ... pendix A tern .5. prameters ftore tendingInjector pumps or poor component 10 -CFR-5, appendix B. section XI requires...
* Starting system -Operation Induced: Inadequate training components & system to perform satisfactorily Improved inspection of weekly.Controls and skills - 10-CFR-50, 55a Codes & Srd -ASME BPVC monthly, and yearly to determineStarting air valve * Vibration induced section Ill, IX, IEEE STD 279 envioronmental stressors moreStarting motors * Fuel or lubrication degeneration * TS 3t4 8.1 surveillance/inspection for operation & effectivelyAir compressor * Gasket. seal, or organic material degeneration shutdown status
* Switchgear system Inadequate spares: quality, strorage, ordering GSI B-56-improve reliability of Eng. Maintenance responsive to testBreakers problem data and specifications * IEEE standard acceptable for use by NRC-RG 1.9 & Inspection. e.g.. do not over haulRelays * Corrosion. oxidation unless inspection and trendsInstrument and controls * Thermal stress indicate the need
* Cooling system * Manufacturing or quality problemsPumps * Fatigue not related to vibration *IncresedtrainingforEDG
Heat exchangers Metal fatigue Staff in on-site maintenancepiping -Wear
* Lubricating system * Bacterial action Systen motifications to mitigateHeat exchangers stressorsPumpsLube oil
REGULATORY INSTRUHENT REVIEW FOR ENERG
LillEXSTENSIONCOMPEi NT MG. IhST5AjUt AGIN FEATWtES FACSURRElNT IKTIATIVES ArIas I
CeLUX~~~I 2 COlUM 3 COLUMM 4 m u ul5mLLIbm
ElERGENCT CYCLIC FAhIIUE, CFODIESL I1LUIU VIBRATION 10 ChA SO Section Xi of Appendix S Provides records lem. Nam.GEAiAATU AND SERVICE AAperdls Ix requires test progras to id perforxwne(t) "Sure that c ents history for Et.
erd systes performcorrectly.
(2) Appendix A General Dealin Criteria Provides records Interpretation of ho..including criterion 2. 4, nd performance this CIM may x-15, 17, 1s, Nd so. Of history for OGs. If the mgeettdths. I s mt leper- revisior to 1.9 wetent U It provides aging proved.guidance by reqiringperiodic testing NdInspection to evaleuteceonent condition.
(3) 9.5.7 E0t lub oil systes hu. bons. hont.review odrese drystarts or lack Of lubduring starts. The UPreqirer a dedicatedsystes for _riitg pert .
(4) 1.32 gultory position for hens. hone. MGM.desimn. construction Nrdoperation of xPt; agirgfeatures iqplied.
AMi Cods(5) Section III EDGt by definition are hum h/A h1 .
SectIon Xi Clux 1 2. Nd 3coeponants; howeer, theEVA w not pressurevesals or piping. etc.
(6) 300 Design bes criteria for Provides en 1 ans. hom.Claus IE WIpuint to aceptable deslxnenbl th_ to met their base for possible
fhaatiule roqirmtents. La.
(7) 32 *Ability to prt.o safety Acceptae a nd Xana. hone.fuxction OA to the ef- uatilfyingfect of aging not he ad- records.dressed. typas of seinginctuds vibration Nd_ ar.
"Weiea Motes:1. A e7e Indicates further study/inveetigation Is nudd.2. For the SIX, *rosolveda men the generic safety Issue Is reeolved, not nesaritly the eging Isaus.3. For meaning of abarviostiar, acronm, aid Initialim, used thraeghout, ei acresm on papg xi, MI, nd xsii of the report.
ENCY DIESEL GENERATORS
LEEDS LIFE EXIEX101 xEDS KIDSISC7LLS am=S 9
Are test documents/ Reuires that written test procedures that sddreearecords adequate for Lit? proof test prior to installation. Preoperational
tests Md Operational tests.
Norm. 10 CA SO, A4pepdix A DC, criterion 17. require anwaite EM to provide cnmite poeer to ahfety-retatedccwiants Nd syst_.
The records (history) ofthe EDG hould Indicateadete performance topermit ue beyord 40Yvas.
Sea cet.
bons.
1-a
Refors to IEEE stedrd 30e-74 as acceptablecriteria for design, gevrat operation. Nd testingof OPPe. The RC doee not ddress license renewAl.
The AlE cods As rewired In 10 CF 50.55e xndsteISI. thes reWiruemts rarely involv EDC 'nltoa aspecific pert is dxsisned nd mioufecturad inaccordance with the Cods.
hone. Includes pewer syste. *.. , diesel goenrators:design base includis malfuiction, accidenta oroperating modes that could lead to dsgrsdetion ofthe *ystu. ialfunctiona re defined Ue nsturalph ow, e.g., enwironeental factors of pressure.humidity. teratures. nd accidents. e.g., fires.
M"e IEEE *standrd 323 as opposed to other instrumentsreviewed recosnizes the need for aing Nd definesstV to udree aIng scb as age conditioning Ndnatural aging criteria.
Emergency ieesel Generators
COMONIITe ISSUE REG. Iii11111JR5TCOJ I iAIM COLUP
IEEE (contd)(a) 3Su
c".U 4146111"
LIFE EVfERSIONFEAIUnEI CURRENT IWIIIAiIVES MQI1K OtEM LIFE EXTENSION N M l
...**.ummt******. ML COLUM ? COUMN a COluU 9
Provide principel design ride. ancritonr for rocs to set eptolbte designtheir functlanet require- bse for possibtemate undr deegig bse" I.cditiens.
IEEE 387 is turrent-ty beln revised.witI incorpor teItr. ntdrd 749ro mml a. J IEEf-387 lead aentoensaging 0n "irn
_ t techniques.
sn. Provides the tinim= service r~err mnte for thedesign staff (ME) inctudir operatiormt cycles.operationaet hour teratures (Me. nd Nor)-Wteooe eiore me. radiation, isuidity, air qt'ityetc., i.e.. itt the conditoris that houeld be con-iderd In the deslgn. fortysewn (47) design nd
QePPletotn considerations ar given in thestwbrd.
(9) EXTEuiMt EFviOM-WNETAL FACTO3I,INCLUDING:*CHEMiICALS
*OIL$ AND (DMW-TiIN PROUCiTS
PATENIA. amNFLATS/(DITACTS
*NATURAL PiWKMi-ESA-EAMTNWgMte,FIRE ANDi FLOWS,ETC.
, eit10 CF1 50.49 Provides that UWirFon
mental specifications bemkitted for electricatafety-retated aqui _tthat sderee viron-m*ntat f etors. e.g.,agirq, radiation, teoper-sta, axd buMxdl Cty, aother condition, e.g.,tee of wristiine,vibrations, ed pipebroks.
Adreaest aging.nd degr dxtionIssues eomelcabieto enitl*rr ofpiant for Li..
11n. Are the epecifictioensufficient for urrentrgat-tie cedititl?
10 CFOt 50 CDC of ApptodIx A inetud- Addess sturatAPPndix Ir47 2 and 4 reptre ptnin
design hss for naturalptenn, e.g., flona4n earthmkeo. rndeffeiles,. e.g., En0 notbe coetibte with normtOperation, accidents sdpostutated sislf tIn, sodpipe dhip,
2.4.2 Refers to 10 Cn! sO MC, (iginit designCriterion 2,
5cmonots conaiders flood
iepxrtont to safety beins design sod localdesigned to siofetond the pracipitation,affecta of iurricones, I.e., this wiltfloode, teou4al and provide rOoltheb.n Ato referm to history. A flood
10 cPR 150 for Identify- history up-dete isInse and wlustirm alto required.hydrologi featurese ofthe dite.
#/A tn. tI the ptent a urrentstotla the so or he achange in selsic cate-gery developed sinceoriginal tlicene?
U". Na. is the origin t design ThM CRi principelly provides the criteria for theodb~te for curront orilinal design. the CnU deft not adress the agingconditiaw, i.e., hai Issues.the history changed
-- Romergy Dieel orwators
(12)EXIERMAL t£YftI-MSEJITAL FACTORS(contd)
LIFE EXTEMlSWmAE6. ISSTtsoiWo AGING FEATURIS FEATUREli CLUUNT INIIIAIIVS "Jim WANo Lift fAT&shiW VMtS =UOEMT
laft (santd)
3.5.1.1
Relfor to 10 CII 50. Ap-pnidX A, QDC, Criterion2, for leiteic clossifi-cation to withstandearthntaes without atoe of obitty to per-for. safety functions.AMoo refers te 10 CiItO, Apondix A. for theptrforoc* tsE).inltuodirn standl aetlgenerator suxiliarysystm.
Provides for reiew. andAcceptance of Intenetand "tstarl m1ssi1eprotection for osfetyreqirad for sofe i"th-don of the plant. Thiultimatly mitivetes
e or deradtion tothe i00 ystem fr0*01*"11.6.
010M.
The protectionmat be for thelife of the plant.
limo. verify that the Ca The tIi principttty providoe the criteria for thenonts xSismic catWorJoe original dtsignr The CiI do40 not m s the &gfrahuie not chwreed. 'Iwe.
(is) a. SO.,. lone, untles densin hose thiea rqirmnta are princilpely stert-uphoe chaned to marrant rawiroeta, bit rmIn in effect for the lIfe ofad4itionlt protection the plant.from miassie.
(146 3.11 Provides for eccaptneocriteria stipulatigr thetthe sechanical coaponmotill ptrfrom stisfac-
tority for the 0tewth of
tifs for 1rh41 its func-tin is raiired forhard iA tdawlvosant- .
7.1 Provides acceptancecriteria of Inotrun-tatien nrd controls.Refers to ID Cl so. wteanr 56E 279 for designbasis for noturol t i-£o, and amwlrnsentotca eo .
Provides recordsfor onvirormntatacceptane andwatiftfation.
S/A Should he oacifitc inetotine thet sccepteraebcitd he esintainod
swar the (ift of plant.
Accaptaas criterioneodsd for Lit.
Acceptance crilorionrmW for La.
This Is principally an acceptate criteria star.dd;the sP 0do not odorosa the life of plant lasuts.
Althougi the W do" not discuss seine or Li, theW r lrmesnte whoutd bo usaful to apinr mleenet L Oif adpoIt records re mIntolnod forthe tife of the plant.
(15) Provides accp-trnce criteriarecords. $04table 7.I. t Acctance Criteria.t
Should be specifit InSattin that accptanceshpuld be mintainedenr the life of plant.
(06) 9.5.4 EDO tatartino) enstnfuel olt - raview dater-mine the watity of thengrins fust Oit. System
shoutld h free from oildegradation to preventaetins fsilote.
ProvIde s coptawe criteria mdrecords.
Son. Sons. Accaptance criterieneeded for LI.
Attouoh the SO doeo not discuss wing or LI. the9 reiiremsnta should be useful to oaslow mae-et and LI if the raquirsent we aet ad adowats
records w Ie Mintained for the lif of the pint.
Atthough the SW dons not discses wain or Ia, theW reoirominta Should be useful to seinl _we-ont end La if the rCtwirnt are aet end seopateretOrdt WIe sinttain d for the lihf of the plant.
(17) 9.5.6 DC mrins stort-systm - Provides recordsreview rCairx drter- for syste_ st*tus.minieg the adsqjscy ofthe qoelty snd conditionOf the air 04pVyClan, dry ait reuired.
Ma . Acroptance criterianeeded for LO.
-- Ircy Dieel Ganorstors
(XV1tRET
(OM) EXTERnAL tINVIMMYIPACMKS (contd)
RED. IVS715tMIN AGN EAUE FEAMS! (tU INIIIATIVES ACIMQ NEEDS LIFE EXIENSICE NEEDSCto MS moscmut,
SRic (contd)9.5,.
(19) 1.29
1.100
EDW Ongin ib systm -tIb oilt temperatue matbe meintained.
EDC not be designed forseismic cateory I for55E occurrnes.
Seimic qualifications.principtes, prte* es
nd _ td .
1Mor.
1mwe.
NOMe.
5m.
KfA
P/A
Systm records.
The originel designat be adaquet, for
Current known seismiccondition or postulotedconditions.
Li queetios shuld beaddresed In the M.
(20) lefers to IEEE *tanhrd 354-87.
(21)AI CodeSection IIISection XI
ED1I by definttion areClose 1. 2. ad 3 comPalosz haer, theoft arm not presetrevessels or piping. etc.
11". 1mns. M". Nons. The LASE oe ae required In 10 CPU 50.55e gumistoISI. The reqirawnto roely Involve iD Lunm aspecific rt is designd ad _ut muctured inWco, . with the Code.
2.2(22) Minim Instetntationfor syt" irPA ofgroand rotion to paroideevalustion of dstswothuer or not vitrtoryintiw hve botnexceeded.
InatrLountationhcdd provide
records of pltntservice.
M".
N/A MO.
I-
Zri(23) 2.8 mesthodology Is described
to vstaute the fl1o0dhaving virtually no riskof etceedonce that Vy bemaod by precipitationund nsraalt nrd dofaitures.
I/A rm.
Nona.
1mw.
None.
Nam.
(24)
(25)
2.10 Defines tE typ of tim- eords of pianting of plant ower activ- activities thatitie requsired in the my assist In LU.ont of on *artiunkend includes specific
procedures for the evetu-otion of records obtalindfros seismic inetruRenta-tin specified In AN.2.2-19Th.
W/A Mons.
2.12 provides gufde(Iewe thatsllom reactor designerto select hazards. e.g.,neturat, _t-de orcdabinetione of hazards.that effect thE design ofsyston and comonts.
NO. X/A M".
E- tergy Dieslt generators
ar
(26)
(21))
(25)
(29)
iE5TA. FACTORS(contd)
REG. sesrosesmr
306
LIFE EXTENSIONA01.5 FGAV1R1 FEA1IRES a*ISMINTIiTIATIVES Asieg NUN ~ LIFE EXTEsSIWN NEESO
COaUsa A OUI CO M AcDLlsI 7 (aCuLM aCOMMENS
9OL
Design be criteria for Provides an eccrp-tins IE qwipmnt to toble design beeende the. to met their for possible I.Rfurctenak rsqaltmaats.
bone.
3Z3 Se~ adro s ability to Acceptane andperform safety Function lmtifyinsth_ to agisg, itetudins records.factors of nerteal nduwirormental cordttioasthat mat be addresd.
344 Entabttshe. reced Acceptcand _ ndpractices to obtain dtu rpatifyingto quatify that the recorde.etipmmnt wilt performone SE after an CE.inclusd ae taste forvibratiornl aging. eis-sic asten plus noermoperation toad.
3d7 Provide. prisnipet design Provideeson Accri-criteria for EDli to _est table design basetheir funtianal require- for poesibte LA.mtts under design beconditiors.
Mon.
More.
Ibse. Inetinc ud pr systems, e.g.* diesel generators;design bas includeb matfirctierm. accidents oroperating mdee that could lead to degradation ofthe syst_. Ntlfuctionr are defined as uturtlphutume. e.g., serthqa kee ndml tooas rdpoDtutated peen merm. e4.*evrormantat factor. ofpresser hamidity, trpenature.. and accidents,e.g.. fires.
Nam. IEc Rtamird 323 an aopd to other instrnewntoresvid recognitz the need for aseie and definestepe to 6eee atgre ouch as s conditioning ndnrtural aging crit rie.
Sa.
lone. Proridee the *iMA service reqirmente for thedesign staff (AU) Including operational cyctes,operational hours. ta" tures ("K. end min.),saelsic roop e. radiation, hueidity, and air"lity, i.e.. alt the oandittoe that should be
censidered in the design. Fortysevon (47) designand epplication cormiderationr ar given in the*tand"r
Stndeard as beingrevised by 111uorking group 4.2.
M.
..
I-
lNerasuAL thElItCAL.(30) PCYSICAL PROCESSE,
* COK505IWN IN All
* TKANhUL 5lOCK
f-9.5.7 EOt engins tuthe aystm- ecordr of accep-
revie. determines if the tems criteria.tub syatce preventedeteterioue Mtertal frothewt shock enteringths tab olt system.
tDC air intake syste - lecorde of accep-revie. determines that no tan, criteria.tern dearadation wiltbe e*perienced during
fmel.. pomep output(contitrexe) etttngs.
one. lebd. acceptanecriteria re-established.
one. "Ofd 409"ptmcecriteri re-ertablishad.
(31) 3.5.1
' leretcy Diesel Generators
coa1t ISSUE REG. INSTRUMEIIT AGING FEATURESCOUMNI 1 OMt 2 CLUM 3 CLMN 4
LIFE EX5755IONFEATWRES OURKET IN ItIATIVES AGING NEMS LIFE EXTENSION NWV"CO~LON COUM COLUMN 7 taCLUNI a
WTIliles 0
INFESNAL CREMICN.(32) PlIISICAL PNOS5SSES.
AND ttflNOSIOi(contd)
ANE CoSection IIISection Xi
EDGt by definition areClons 1 2, ma 3 cor,penrts; however, theEDGs art not presurev ssels or piping, etc.
ProvidM design becriteria for Cless IEquipmnt to enebl the
to met their functionalrewiramonts.
ir. Wr. The AHE codes as raqtred in tO CFt 50.55. ondeteISI. Thebe requirents rarely itnwolve EGG untensgecif ic pert t desind And swif actured in
accordulce with the Code.
IEfE306(33) Provide. on ncc_
table dekien bieefor poesible Lt.
iMa. Nam. Inludne power eyet_, e.g., diesel gueeratorsdteign be" include mlfueclions. celdents, oropereting mxs that could tod to degradetion ofthe stems. eltfunctione are defined oS naturelphanaens. e.g., eertheakes _nd flooh, amd po.-tutated phermam. e.g.. aiviramental tfactors ofpreesue, huidity. terature nad eeidents,e.g., fires.
(34) 38? Providee prienipel deelgncriteria for ENO to _ettheir fiactionsl reqoire-wente unuder denimn bnecondititons.
Provides an scco Sta.dird Is beingtbtle deslgon bne revised by IfiEfor possible it. working group 4.2.
Nar. Iont. Providee the minimum eryice reyiresom" for thdeign staff (AE) including oeprtionel cycles,operationl hours, teturen tox. and min.).aimagic reonse, radiation, humidity, air qeatity
etc.. I.e., all the conditionr that should becontidered In the desipn. Fortyseven (47) deeignand appticatien considerationn are given In thestedrd.
(35) 323 Ability to parfors aefetyfiwetion do to theeffect of aging at beadereeed. Types ofeging Include thereacondition.
Acceptmnee endqielifyingrecords.
Worn. Now. IEEE Ctmuderd 323 os oppoed to other Instrumentsreviewed recoomizee the need for aging and deMineset" to av eea aging such os age conditioning andnatural aging criteria.
(36) * lINSPECTIONEXCESSIVE, HANStS
TESTINGK ALADJUSflENT/
DIISASSEMBLY FOR
(3?)
TIS3/4.8 None. ono. PIIL stlff through The TUe should consider
the NPAR program aging eeduaniaes/agingTechnicl Sppecifl- Ication Aging Taskare adreseing theTe for aging_ie esnt.
Provide evidence thatthe Te rwe adequet. forticee rel., i.e..are chengee needed inthe Tie for In
Oeacribee einlIs AC electrical power requirementsfor operating Red shutting doun pl nts.
3/4.8.1 oper-eting stetuimd 3/4.8.1shutdoen stetus
Surveillane efforts Inspectionwould detect on Ioeor- record.abl. arerstor by virtueof the necessity toessure on operableGenerateor, _rgant ofaging sle iplied.
None. Not o it cble. Records of _intanmeoInpection eould provideevidence for setmdLue of the dienatgenerator.
Seergmncy Dieset GeneratorA
a2,01T Is"I
SO*ILLANCA (contd)(38)
(39)
(40)
(41)
(42)
(43)
MG. INSTRUMEN AGING FATtiESCO)LUM I Calum 4
UT58.1 Appwidis tis of gnrator far8-A Posting p06e4 1s notTP ICU(PSB)-B alttWAd; pr*itS ue of
Ger-tor In noergencysituatiore.
8.3.1 Provides review nidoptiam criteria for
Operation of stmntbygegrstor sets, as
ailty me related cpe-ation at tee than fulltoad with no dearedationfor extendmi periods enthat no load conditionsshltt be minlimid.Stipuastes that stafftraining, testing, pra-ventative mintonance aidrepair procedures mitt bematntained.
8.3.1 STP-8 Provides restrictions for(PSS) using the too for peak
poer situatlion aidrestrict& ovarie of theEBD.
9.5.5 iSC ogine cooting eatersystem - review deter-sines the adequcy of in-pection aid testing of
the tooting weter System.
9.5.6 106 starting systm -review deteridnas ada-qjaty of the inspettionAnd testing of startingsyate_.
9.5.4 MAo fuel oil syste -review doteruines ada-CIANy of insection andtesting of fuit oitsystow.
9.5.7 EDO aigine tue syste_review determines theodeqiacy of the Iapet-tit0 Ad testing ofengine lub system.
LItfE ETEhSItiFEATLREIS ClAst itNtItATIES AGING IM10 LIPF EXTENSliON IEtSa S .. tOlLM 6 . ttClUi 7 CULeIN a
Should provide 7 /A I/Arecord of uwei.*.. totalesrvice hurs.
Provides records 1 n. Is the acceptance cri- For LK, the rtdfor tcce ace of lret usefut for tlng- _itntee trainingstand-by power tern 7saurM that the mat he ahOsn to he ada-spplies. EN0 witt be retlb bt, quate for rolltifics-
not derade over time. tic" of the to".
�eiaiSauau 9
The UP does not seScificaiy address aging or L*;however, strongly implies aging Mangegmnt ard Labecahe the Mt gtatft the EiO shell not be oa-j)eted to degradation. This my he aased to coverthe life of plant mAd heyod.
Limit* deargrationof owimint ordprovides far alonger and wefutlife.
should provide-demc recordeWd status for
cooling water eye-ts retative toLa.
should provide- records
and statue forstarting syste
Should provideadquc recordeand statue forfaiul oil syst.
Mould provideadequscy recordsand status forengine dai system.
bone. ban. Per Li, the rfw iredoperating restrictimaaet be sham to heusefuh for lifeextonmim.
gon.
The aiP provides aging Manegment by Specificallyrestricting the wu or peek power needs Andcntrolling nrwancy ue of the EGG. The BTP
ressae the prevention of com falilure mode ofthe EN me related to win or off-site power.
Although the GAP does not xptlicitly discues aging_ngn or Lk, the reqirints should rt La
ISadec records we eintalned throughout theIIf of the Tplant.
arn.
t1e.
bane.
gne. Atthou6h the AP does not explicitly disouga agirn_nmeinnt or La, the raqirents should i rt it
if adm*te rcords ae esintined thrWusht thetife of the plant.
arnie. Atthoudh the SP dose not explicitly disass aging_mgmun or La, the reqiremants should a ot Lit
if adeate records Are esintained throuxot thelife of the plant.
bin. Attheoih the SW does net explicitly disuss aging_ _neeft or LI. the reWqironts should e.port LI
If adeute re ord _ainteined thrmuihout thelfe tof the pi nt.
-- Eergency Diesel Gineratore
MM 1
(45)
Is"E
gtWALLAiit Ccmtd)
LIFE EKTEWSIOHREG. tnNSTKWT AGING FIARREE FEA1WES CURRNTr INITIATIVE AMING NEMD LIFE EXIIINSIDO Muns
M1.10. iISa 4 - CLUN COUM 6 MM 7 MtOON a1TE
COLUMN 9
MiPs (Ccntd)9.5.6
(46) 13.2.1
EDG agine cosea timn -vi determines the
adequacy of the Inspec-tim ard testing ofnirn*e tobtian systes.
operators and ethernonticansed plant staffttainini - the pantstaff w, to be trainedto us the EGxs correct-ly. This lopli.. seinemgeesift.
Should prvdesdv y recordsand statum for thenuine celastion
systet.
Should provideplant staff per-foreance trainingrecords, I.*..adeqacy of our-rent staff.
on. Ine. AMOht the sRP doen not explicitly discuss swir4MO_ it or LK, the nqeirnt sheutd agprt Laif adeqate records re seintained throughout theif e of the plaint.
Gone. Anr the aernnt recordsip to dote for present
staff for adequate LUdocumentation?
The plaint staff re expected to bnmw how the EDOoperates and performs; frthermore. they areexpected to 1m how the fDC Interacts within(Other) plait ntafety-relted Systm. DoCsewntatimof training and d trations of trained staffcould anhdee eing nIt aid L apptlicatiens.
1.9(4?) Provides quilificationand periodlic testing,teat _hje and sur-vitl anea ard sintee0jidence.
Provides recordsNd records -keeping criteriaand reportingcriteria.
ey be impacted bySPAR EDG studins byPiL. The aiC hxaIaued 1.9 Rev. 3for eoints,Nove r 19i .
" Mellato of featstart testing, Start-ri-ceolddome raeire-wits era need tondn agine streseora.
Corrent statumeconition No 1.9 referencen 10 CMR 50 Apeedix A. Criteriemnof the quipent shoud 17 and 12S aid Appaidix *, Criterion Xl.be -adesesd for Lk..
(48) Safety Guide Ettblibaes regulations OA docurentation.OWr 30 for GA relative to
testing of electricalewipment. ReferencesANll 145.2 and IEEE-336.
1.33 Lefere to overal i earat lptied bycriterion for NPP documentation.operatioL
Status of r ecd adrecordieeping _ethodneed to be verified forLa.
Safety guide referente tO Cx 50 Appendix N, 01criterion for epa.
(49) 2/A A need exists to deter-mine If the exitingrecords aid Oh doern-tation are admsato forLa.
(SO)
(51)
1.41 Provides quidune fortenting after a _Joermodificatio.
1.58 Establiee nguidance forthe qemLification of MDEstaff tho perform I In e-time, tests Nad *xsina-tlin during the opera-time of OPP&.
Provides recordehistory of nowNodlficatials
Provides docuamn-tation of staffeul ififatfen andOA records, I.e.,that is the statusof pest NIEperformance?
7 Pefern to AuSl 145.2.6-75.
(52) 1. 10T Estabf ibtel that the FDdesin should allow teat-ing. The G *lso definesthe periodlic pr-opera-tioenl 1S- th testingrguirmnita
Esteblishes guid- The NIC intends toance for recorde delete xC 106.aid recordkeeping. Guidelines will be
In revised NG 1.9.
Testing should be Ioproved and iteiehnged to a selm start streesful starting
to avoid fast-start prceirxe accoipa iedstreauorn. by a progres of per-
forms onitoring andtrouiding are ned.
gee ogecoeuided Practice for Aging Nitigatimn andleqroved Program for Nuieatr Service DieselGenretonrs. AImEO-Ci-t-SO0PO-6309.
IMrmegty Dieeln Camrators
tINKNT ISSlECOLUM I CO tM 2
SURVEILLANCE Icontd)(53)
tS4)
(55)
(56)
(57)
(58)
(59)
iEC. INSTRUlMT AGING PFEATURESOLUI I~ 3 COLuMM 4
K CodeSection III EDCs by definition oreSection XI Ctlee 1. 2 aed S
Coonents; however, theEVA6 are not prCOarWvesels or piping, ete.
"la 5-56 Program to Improv thereliability of EDG;gl of 951 successestabli loed.
CSI-91 Continuad reliabilityand operability ofTrnsamerica Die vlvInc.. EDOG.
ARSo3.1 Provides criteria for
selection, qlification,and training of persontelfor statio nry nctlearpower pltets.
3.2 Provides recaedstioreend reouirents foradeinistrative controls,including oritton proca.dures, and GA program tohelp "ere that activ-ities of iPP* are carriedout without risk to thehealth and safety of thepubttc.
338 Provides desigi endoperational criteria forperielic testing ofafety aystem.
336 Provides minilm reouire-wants for inapection andtesting of Clate IEpower, Instrumrenttion,and control eqoipaintduring constructionpiree.
LIFE EXlTENSIONFEATUaRES
Catol
CURRINT 1511 EITIVES
SOns.6
Dilset reliabilityprogr-n with miiC.
TransesaricaDeLaval. Inc.,Darers Croup.
ACIX C LIFE EXTEISIOA NEW5DS tesrW ,il lE _ COLUMN a WL.e15 9
Dcne. rone. The ASK cde as reqired In 10 CiA So ffa _rteISI. The. rqlrents rarely involve 04 unole aspecific pert as desllgd and _utfctured IneccordMc with the Code.
Reliability of £0 as a Effecta of reliability de aleo Regulatory Guidoe 1.10Dt iM CO-O660.functlon of ae; at decreaean licensing.re effects of ag
effects of testing overtime?
Effects of Stress, Can plants with T10 EC issue involves potential min crAhaft failures.fatituet testing on TDI contirae to operate; km See laso SED8-534, IIH-113-58. nd NW sM-1216 andtOG reliability - do T0I to verity operability of other madts)EN show aging effects TDI E C after thirtyfaster than other years of service?models?
eon. Sate.Provides record ortraining of staff.
Administrative In-place controisillt probbly be
required for t.R.The essociated OAdocumentation ittlhe useful for Lit.
C-
C.-
ac .
a .
Nn.
i1".
.ons.
hon.
A" the activities covered under this standard aredosimn changes, fabricating cltwning, dacon,Inspecting, testing, maintaining, sed repairing.
This stsrdard doe not _ndresa esintence.
Provides a criteria for correct Installation whiehcould effect aging aspect of the oaopmet afterStartup aid operation. Clan II a Wip nt thetis esaantial to _argecy shutdon, contaIraentisolation, CC, nd CM.
Acceptance testingof conents fori.R
Racords of con-struction may beApplicable to La.
Emergency Disel Generators
LIFE EXTENSIONCOMPONNT ism REG. INSTEUIHENI AGING FEAfIONES FEATIE COHRENT INITIATIVES AGING NEEDS LIFE EIITNSI NEEDSCJ... I COUSIN .....OL" .3 MY" 4 .. LUM .. COU COLN5I 7 caumo a
SAWWIILANUc (eestd) IEEE (Contd)(60) ?49 Provides stersierd for Recotde of post Standsrd mitt be Leos stressfuL. starting Less Stressful stat~ing
assVENtsCTiTm
perledic testinq of EDC perforence.inctudit availablitytests. systen operatloneltests. are irdapendenceverification tests.
Impacted ty KG I.e. piwemfues am tests. Procesrwe VWD rest.IEEE ptgmm to deletethis stanrd.
(61) 934 Provides crit ris forreptlcemnt parts, bothcon truction aed oper-ation. equires lIspec-titn aed test of pertsprior to releass forservice.
Acceptance testingmnd reords thatmay be otpleasbteto LI, e.g.. fat-
rs revies forre. tatfupe,origint defects.md inuleatient .eklowm.
tore. None. Stmndard determies selection of reWired prts forCleas IE equipment, e.g., identificatimn mrd failurreviar. Ibreve . required design chins sre Otsidetre scope of this stmerd.
IC-
-- Emerency Diesel Smrwttors
NUREG/CR-5490PNL-7190
R9
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M. Vagins, ChiefElectrical and Mechanical
Engineering BranchDivision of Engineering
TechnologyOffice of Nuclear Regulatory
ResearchU.S. Nuclear Regulatory
Commission6550 Nicholson LaneRockville, MD 20852
30 J. P. Vora, Section LeaderAging and ComponentsDivision of EngineeringTechnology
Office of Nuclear RegulatoryResearch
U.S. Nuclear RegulatoryCommission
6550 Nicholson LaneRockville, MD 20852
V. N. ShawEG&G Idaho, Inc.P.O. Box 1625, WCB-3Idaho Falls, ID 83415
ONSITE
49 Pacific Northwest Laboratory
S. H. BushJ. A. ChristensenM. E. CunninghamA. B. Johnson, Jr. (20)L. D. KannbergJ. W. NageleyW. B. ScottJ. C. SpannerS. SomasundaramE. V. Werry (15)Publishing CoordinationTechnical Information (5)
C. Cerpan, ChiefMaterials Engineering BranchDivision of EngineeringTechnology
Office of Nuclear RegulatoryResearch
U.S. Nuclear RegulatoryCommission
6550 Nicholson LaneRockville, MD 20852
Dist.I
NRC FORM 335 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER12491 (Assigned by NRC. Add Vol.. Supp.. Rev..NRCM 11032, NWiAdndum Numbers. If any.)3201.3202' BIBLIOGRAPHIC DATA SHEET
(see instrctionson t versl NUREG/CR-5490, Vol.12. TITLE AND SUBTITLE PNL-7190
Regulatory Instrument Review: Management of Aging of LWR 3. DATE REPORTPUBLISHED
Major Safety-Related Components MONTH I YEAR
October 19904. FIN OR GRANT NUMBER
B 28655. AUTHOR(S) 6. TYPE OF REPORT
E.V. Werry Technical7. PERIOD COVERED lone/surn Datesi
6. PERFORMING ORGANIZATION -NAME AND ADDRESS Nf RC povide 0/v/on. Off/c or Region, U.& Nuclear Reguitorl Commitsson. and mAilfngsdress. :U contracto,. Providemrm aid mailgF adJmo)
Pacific Northwest LaboratoryRichland, WA 99352
9. SPONSORING ORGANIZATION - NAME AND ADDRESS Ill NRC. ��pe e as sO v.�/f consecwr. provIde NRC Div/s/on. 01/we or Region. U.S� N Regu/ator� Comm/u/on.9.SPO~NSOR jNG ORGANIZATION-NAM EAND ADDRESS JN~cw -. ffaove-ifcracw, pe o tro pubNfCIiC tkbn. Oak- or fgion, U.SN SkvRkw laut tort Cnkon.
and ma/hg addrs.J
Division of EngineeringOffice of Nuclear Regulatory ResearchU.S. Nuclear Requlatory CommissionWashington, DC 20555
10. SUPPLEMENTARY NOTES
11. ABSTRACT W0O wdor JmThis report comprises Part I of a review of U.S. nuclear plant regulatory
instruments to determine the amount and kind of information they contain on managingthe aging of safety-related components in U.S. nuclear power plants. The reviewwas conducted for the U.S. Nuclear Regulatory Commission (NRC) by the Pacific NorthwestLaboratory under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selectedregulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations,were reviewed for safety-related information on five selected components: reactorpressure vessels, steam generators, primary piping, pressurizers, and emergency dieselgenerators. The focus of the review was on 26 NPAR-defined safety-related agingissues, including examination, inspection, and maintenance and repair; excessive/harshtesting; and irradiation embrittlement. The major conclusion of the review is thatsafety-related regulatory instruments do provide implicit guidance for aging management,but include little explicit guidance. A major recommendation is that the instrumentsbe revised or augmented to explicitly address the management of aging.
12. KEY WORDS/DESCRIPTORSIst wt os that iag/t , ie n locating the wport.i 13. AVAILABILITY STATEMENT
unlimitedRegulatory instruments, safety-related components, codes and 14. SECURITYCLAMIFICATION
standards, guides, general design criteria, life extension and fr~s,,
life extension needs, aging management and aging issues including: unclassifiedcorrosion, erosion, environment effects, harsh testing, wear, (Th/sRaporJ
embrittlement, fatigue. unclassified15. NUMBER OF PAGES
16. PRICE
NFRC FORM 335 1249)
THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER.
UNITED STATESNUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 2055
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PERMIT No. G-ti7
