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EGG-EA-7181March 1986

INFORAfALREPORT

SHEARON HARRIS 1 SORT VISIT REPORT

J. N. SinghT. L. BridgesB. L. Harris

Prepared for theU. S NUCLEAR REGULATORY COMMISSION

Na. D&AC07-76ID01670 "; '~.;i,;;-.'~",.'+'"..''6osxeoam

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EGG-EA-7181

SHEARON HARRIS 1

SQRT VISIT REPORT

J. N. Singh'. L. BridgesB. L. Harris

Published March 1986

EG&G Idaho, Inc.Idaho Falls, Idaho 83415

Prepared for theU.S. Nuclear Regulatory Commission

Washington D.C. 20555Under DOE Contr act. No. DE-AC07-76ID01570

FIN No. A6415

ABSTRACT

EG8G Idaho is assisting the Nuclear Regulatory Commission inevaluating Carolina Power and Light Company's program for the dynamic

qualification of safety related electrical and mechanical equipment for theShearon Harris unit 1 nuclear power plant. Applicants are required to use,.test or analysis or a combination of both to qualify equipment, such thatits safety function will be ensured during and after the dynamic event, and

provide documentation. The review, when completed, will indicate whetheran appropriate qualification program has been defined and implemented forseismic category I mechanical and electrical equipment which will providereasonable assurance that,'uch equipment will function properly during and,after the excitation due to vibratory forces of the dynamic event.

SUMMARY

A seismic qualification review team (SgRT) consisting of engineers'romthe Equipment gualification Branch of the Nuclear Regulatory

Commission and Idaho National Engineering Laboratory made a site visit tothe Shearon Harris nuclear power plant 'of Carolina Power and Light Company

located near Apex, North Carolina. They observed the field installationh

and reviewed the qualification reports for twenty-two selected pieces ofseismic category I electrical and mechanical equip'ment and their supportingstructures. Two generic and one equipment specific concerns were

identified for which additional information is needed in order for the SORT

to complete the review. These are referred .to as open items. The reviewindicated that the equipment was adequately qualified for the dynamic

environment pending resolution of the open items.3

CONTENTS

BSTRACT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~A

SUMMARY

1. INTRODUCTION .

.2. NUCLEAR STEAM SUPPLY SYSTEM (NSSS) EQUIPMENT ...........2.1 Auxiliary Feedwater Controller-(NSSS 1) ..........2.2 . 3-inch Diaphragm Valve (NSSS 2)

2.3 Four-Bay Two-Train Solid State Protection SystemTrain A (NSSS 3)

2.4 Process Control Cabinet (NSSS 4) ..

2.5 Component Cooling Water Pump (NSSS 5) ..........2.6 Main Steam Relief Valve Controller (NSSS 7)

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

10

2.7 ASCO Solenoid Valve (NSSS 8) ..............................,2.8 Residual Heat Removal Pumps and Motor (NSSS 10) ............2.9 14-inch Motor Operated Gate Valve (NSSS ll) ................2.10 7300 Printed Circuit Card'AL2 (NSSS 12) ...

3. BALANCE OF-PLANT (BOP) EQUIPMENT ..;..............................3.1 6900 V Switchgear (BOP 1) ..................,.....3.2 Auxiliary Relay Cabinet (BOP 2) ............................3.3. Instrument Cabinet (BOP 3) ..............................3.4 Containment Vacuum Relief Relay (BOP 4) ....................3.5 Containment Cooling Flow. Switch (BOP 5) ....................

12

13

17

19

19

21

22

23

24

3.6 Centrifugal Fan and Motor (BOP 6) ..........................3.7 1"1/2"inch Three-Way Valve (BOP 7) ..

25

26

3.'8 Main .Steam Power Operated Relief Valve (BOP 8) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 27

3.9 Control Room Cabinet (BOP 9) 28

3. 10 Emergency Screen Mash Pump and Motor (BOP 10) ............... 30

3.11 30"inch Butterfly Valve (BOP 12) ........................... 31

3. 12 Hydra Motor Valve Op'erator (BOP 2A) ...;.......'I

4. FINOINGS AND CONCLUSION .............................31

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 33

4. 1 Generic Issues ............................................. 33

4.2 Equipment Specific Issues .................................. 33

.3 Conclusion o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 344

TABLE

1. List of Attendees .:....................-............. ~ ~ ~ ~ ~ ~ ~ 35

1. INTRODUCTION

The Equipment gualification Branch (EQB) of the Nuclear RegulatoryCommission (NRC) has the lead responsibility in reviewing,and evaluatingthe dynamic qualification of safety related mechanical and electricalequipment. This equipment may be subjected to vibration from earthquakesand/or hydrodynamic forces. Applicants are required to use test oranalysis or a combination of both to qualify equipment essential to plantsafety, such that its function will be ensured during and after the dynamicevent. These pieces of equipment and how they meet the required criteriaare described by the applicant in a Final Safety Analysis Report (FSAR).On completion o'f the FSAR review, evaluation and approval, the applicantreceives an Operating License (OL) for commercial plant operation.

A Seismic gualification Review Team (SgRT), consisting of engineersfrom the EgB of NRC and Idaho National Engineering Laboratory (INEL), made

a site visit to the Shearon Harris 1 nuclear power plant 'of CarolinaPower and Light Company near Apex, North Carolina from December 3 throughDecember 6, 1985. The purpose of the visit was to observe the fieldinstallation, review the equipment qualification methods, procedures(including modeling technique and adequacy), and documented results for a

list of selected. seismic category I mechanical and electrical equipment and

.their supporting structures. This report, containing the review findings,indicates which of the items are qualified and require no additionaldocumentation.. It also identified some equipment and certain general .

concerns for which additional information is needed in 'order for the SgRT

to complete the review. These are referred to as open items. The

applicant is to further investigate and provide additional documentation toresolve these issues.

Table 1 contains a list of personnel who attended the site visit.Subsequent sections of this report give a brief overview and identify theconcerns, followed by the findings, for the selected seismic category Iequipment.

2. NUCLEAR STEAM SUPPLY SYSTEM (NSSS) EQUIPMENT

2. 1 Auxiliar Feedwater Controller NSSS-1

The auxiliary feedwater controller (MPL No. FK-2051A1) was supplied by

Westinghouse with model No. 2445D69GOl. It is a 7300 seriesmanual/automatic controller which provides a control function for,.theauxiliary feedwater system flow contr'ol valve 2051A. It is panel mounted

to the main control board panel in the control room at elevation 305 ftusing two mounting, bracket assemblies.

This controller was qualified by testing performed by Westinghouse

documented by Westinghouse report WCAP-10802, dated March 1985. Testingconsisted of testing several 7300 series manual/automatic controllersrepresentative of the entire line of 7300 series controllers. They were

mounted to a panel and tested simultaneously. They were all mounted using

the two mounting bracket assemblies supplied with these controllers. The

qualification tests consisted of low level (.2 g) resonance search from

1-50 hz and 5 operating basis earthquake (OBE) level and 4 safe shutdown

earthquake (SSE) level pseudo triaxial sine beat tests. The SSE pseudo

triaxial tests were run in four different orientations so the coherent testmotion would be both in phase and out of phase. No natural frequencieswere detected below 50 hz. The SSE test response spectra (TRS) enveloped

the required response spectra (RRS) with a margin of at'east 2. The testzero period acceleration (ZPA) was 5.6 g. The required ZPA is .95 g. The

7300 series controllers tested, maintained their structural integrity, and

did not change their state during any of the seismic tests, and were

functionally operable following the earthquake simulations.

Westinghouse developed the required response spec>ra for the Shearon

Harris main control board by performing a three dimensional time historyanalysis of the main control board. A generic device RRS was developed by

enveloping the spectra for ten different model node locations. A response

spectra analysis of the main control cabinet was performed to qualify the

cabinet. The minimum safety margin for the cabinet was calculated tobe 1.28. The main control board analysis is documented by WCAP 10469,

dated January 1984.

Based'n our inspectioh of the field installation, review of thequalification documents, and the applicant's responses to questions, the

auxiliary feedwater controller is adequately qualified for the prescribedloads.

2.2 3-inch Dia hra m Valve NSSS-2

The 3-in. diaphragm valve (MPL No. 2-WL-D650SB1) was supplied by ITT

Grinnell with Serial No. 78-6225-15-1. This valve was purchased tospecification G-678845. It is line mounted in the liquid waste process

piping system just outside the containment in the auxiliary building atelevation 230 ft. The valve has a vertical pneumatic actuator supportedonly by its attachment to the valve. Loss of supply air to the valveactuator will result in the valve position remaining at or returning to itsfail safe condition.

This valve was qualified by a combination of testing and analysisperformed by ITT Grinnell, documented by report No. 1612 Rev. 2 dated

August 14, 1985. The valve was analyzed in accordance with therequirements of ASME code 'section III for class 2 valves. This analysisincluded an evaluation of valve body stresses due to pressure and seismicnozzle loads. The specified seismic nozzle loads were expressed in terms

I

,of the attached piping yield strength. The specified axial stress was 2%

of yield strength and the bending stress was 205 of yield strength. The

valve and actuator assembly were attached to a bookend test fixture forseismic testing which consisted of resonance search tests and staticdeflection tests. The assembly natural frequencies'were determined tobe 12.9 Hz side-to-side, 16 Hz front-to-back, and rigid vertical. The

static deflection tests consisted of putting a 9.0 g static force on theactuator center of gravity in each direction and operating the valve and

actuator. Valve stroke times and leakage were monitored during the tests.Operability of the valve and actuator was demonstrated with no observed

failures or anomalies. The valve maximum accelerations for SSE loadingwere determined to be 1.0 g side-to-side (s/s), 2.3 g front-to-back (f/b),and 0.7 g vertical (v) from the piping analysis. This piping analysis

(stress calc. 8250-1) was reviewed and the modeling of this flexiblevalve-actuator assembly was consistent with its mass and stiffnessproperties.

The applicant was asked to provide the maintenance proceduresproviding the valve nonmetallic diaphragm replacement requirements. Theirresponse was that these valves are listed in the NSSS ME/ program as

requiring routine maintenance; however, the maintenance procedures forthese valves have not been prepared at this time.

Based on our inspection of the field installation, review of thequalification documents, and the applicant's responses to questions, the3-in. diaphragm valve is adequately qualified fm the prescribed loads.

I

2.3 Four-Ba Two-Train Solid State Protection S stem Train"A NSSS-3

The four-bay two-train solid state protection system train A (DWG

No. 1059E45G01, serial No. 0001) was supplied by Westinghouse according topurchase spec. No. 952591:. It was located in the reactor building at the305-ft elevation. This four-bay unit is obtained by bolting together a

standard three-bay and a non-standard one-bay unit on its sides. The

resulting four-bay cabinet is in turn bolted to a common base with 16 boltsper bay making a. total of 64 bolts. This is an incre'ase, in number of boltsdictated by looseness during testing. The unit is then vertically mounted

on the floor with 16 3/4"in. diameter bolts. There are four bolts (one on

each corner) per bay. It is a part of the reactor protection system and

provides reactor trip and safeguards actuation.

The unit is qualified based on a combination of tests and analysis.Seismic loads are considered in the qualification. The details and resultsare documented in the reports: Seismic Testin of Electrical and ControlE uf ment PGKE Plants; No. WCAP-8021, Rev.s 0, of Nay 1973 and ~Euf ment

ualification b the Combi~ed Anal sis and Test A roved for the-Four-BaCabinet of the Two-Train Solid State Protection S stem, No. WCAP-8687

Supp.. 2-E16B, Rev. 2, of April 1982. These reports were prepared by

4

Westinghouse. The basic qualification consists of testing a standardthree-bay cabinet and then extending the results, with analysis, to cover a

four-bay configuration.

The tests performed on a standard three-bay were as follows. A

three-bay cabinet was mounted on a single-axis table with 12 3/4-in.bolts. In each of its principal axis direction, a resonance search with a

0..2 g input indicated the following frequencies between 1 to 35 Hz.

s/s f/b

9.8 Hz 10.8 Hz >33 Hz

The corresponding frequencies by analysis for a four-bay configurationwere:

s/s f/b

11.7 Hz 10.2 Hz >33 Hz

Subsequently, a series of sine beat tests with 5 beats and 10 cyclesper beat were performed at 1.25, 2.5, 3.5, 5, 7, 9, 11, 13, 15, 17, 19, 21,23; 25, 27, .29, 31, 33, and 35 Hz. These had adequate magnitude for thequalification against a generic Westinghouse requirement. It was comparedto the requirement for the site. The input was more than required. The

structural integrity and operability were verified. The followinganomalies occurred but were satisfactorily resolved.

No mechanical problems occurred during the vertical axis tests. Inthe side-to-side axis tests at lower "g" levels, the two left end

cabinet-to-base bolts repeatedly loosened and were deformed until it became

necessary to replace these with more hardened bolts.. During subsequenttesting at these "g" levels in the side-to-side axis, these bolts failedcompletely on the, last sine beat test although testing in this axis was

completed. Before performing the front-to-back axis tests, twelveadditional cabinet-to-base bolts were installed making a total of 24 boltsfastening the cabinet to its base. In the field, there are 16 bolts/baymaking a total of 64. Also, during the front-to-back tests, several door

latches failed, thus allowing these doors to open. This had no effect on

the proper operation of the system; therefore, no modification was

considered necessary.

The functions .monitored by recorders were "UNDERVOLTAGE COIL", "TRAIN

A TROUBLE (K524)", and "SAFETY INJECTION". Test switches were operated

during the third seismic beat simulating a reactor trip and safeguards

actuation, causing a change in amplitude of the "UNDERVOLTAGE COIL" and

"SAFETY INJECTION" recorded signals.

At 5 Hz and 13 Hz in the front-to-back axis, the "SAFETY INJECTION"

(SI) signal indicated several momentary trips (contact closures) before the

test switches were operated. Also, at 7 Hz and 9.5 Hz, this signalindicated a momentary trip and then a permanent change of state (latch up)

on the first sine beat of each test frequency. Investigation revealed thatthe momentary trips were caused by contact bounce on the output (slave)relays, and the permanent change of state was the result of the armature ofthe same relays bouncing closed, allowing their mechanical latch mechanism

to operate. These malfunctions could have initiated safeguards actuation;however, they would not have negated a valid safeguards actuation, orreactor trip. Although SI was prematurely actuated, the undervoltage coiltripped as required when called upon to'o so, verifying that no.associatedcircuit damage resulted.

During tests at 7 Hz and 2 g in the side"to-side axis, two capacitorsin one of the two dc Power Supply chassis came loose from their mounting

and shorted its output voltage, thus causing that power supply to fail.This failure was recorded on the "TRAIN A TROUBLE" signal. Since the

output voltages from the two dc power supplies are auctioneered so that in

case of failure of one supply the other continues to supply the dc voltage,the reactor trip and safeguai'ds actuation functions were not affected. The

two capacitors were replaced in their holders and clamped. Subsequent

testing in the front-to-back and vertical planes was completed with the

capacitors remaining securely in place. There were no problems with the

capacitors in the other dc power supply chassis. Considering the overalloperation, including the above malfunctions, the system successfully met

the criteria of the seismic tests.

6

During the field inspection, it was discovered that cabinet hinge pinson the doors were falling out and the doors were not secure. These

door-hing~ were repaired with welds and the applicant subsequentlyascertained that it was an isolated occurrence.

The qualification review indicated that the life span of thenonmetallic parts, in general, has not been evaluated. It should be

evaluated.

Also during the field observation of the four-bay, two-train solidstate protection system train A (NSSS-3), it appeared that the'clearancebetween this unit and an adjacent one was not adequate. On inquiry, it was

learned that this problem may be associated. with many cabinets. However,

the applicant was aware of the problem and started a program to analyze and

correct the situation where required.

Based on our observation of the field installation, review of thequalification document and applicant's responses to our questions, thisunit is qualified for five years life.

2.4 Process Control Cabinet NSSS"4

The 7300 series process control cabinet (model No. 2447D63), suppliedby Westinghouse, is located in the auxiliary building at the 30S-ftelevation. Although this cabinet was supplied by Westinghouse, it is beingused to perform a BOP safety function, i.e., control the HVAC for safetyrelated equipment areas.

The cabinet and printed circuit cards were qualified by separatetesting. First, 0.2 g resonance search tests were performed on a fullyloaded 3-bay cabinet, as reported in Westinghouse report WCAP-8687,.

supplement 2-E13A, Rev. 1, E ui ment uglification Test Re ort —ProcessProtection'S stem Seismic Testin , dated July 1981. Natural frequenciesof 10 Hz side-to-side and 7 Hz front-to-back were found. No verticalnatural frequencies below 33 Hz were found. Multi-frequency pseudo

triaxial qualification testing was then performed as reported in

Westinghouse report WCAP-8587, EQDP-ESE-13, Rev. 5, E ui ment QualificationOata Packa e—Process Protection S stem, dated June 1985. Five OBE tests

and 4 SSE tests were run on the cabinet. Generic TRSs for each of these

tests enveloped the Shearon Harris specific RRSs. The damping was

4 percent. The test mounting was the same as the actual in-plantmounting. No damage to the cabinet occurred during testing.

Accelerometers were mounted at the device locations in the full'yloaded cabinet tests described above. The output of these accelerometers

was used to establish RRSs for testing of the printed circuit (PC) cards to

be mounted in the cabinet. The testing of the PC cards is contained in

Westinghouse report WCAP-8687, Supplement 2-E13D, Rev. 1, ~E ui ment

ualification Test Re ort —Process Protection S stem Su lemental Testin

of Power Su lies and Circuit Breakers , dated April 1985. The in-cabinet

generic RRS for the PC cards was developed by enveloping the response

spectra generated from the accelerometer output from the cabinet testing.Five OBE tests and 2 SSE tests were performed on each card. The TRSs

enveloped the RRSs for all tests. Operability of the PC cards was

monitored during the testing.

Several PC cards showed voltage inaccuracies greater than „those

specified in the original test plan. A list of the PC cards installed in- the process control cabinet at Shear'on.Harris was reviewed. Four cards

(NC03, NCH1, NSC7, and NSC3) showing inaccuracies were installed in the

cabinet. Westinghouse qualified these cards by test (see Westinghouse

letter CQL-8801, Carolina Power and Li ht Co. Shearon Harris Nuclear Power

Plant 7300 Series PC cards Re uirin Anal sis) and found them to be

acceptable for their purposes. However, since these cards are being used

for a BOP function, EBASCO is required to make a similar evaluation. This

issue was raised during the audit. EBASCO is currently working on thisevaluation and is about 70 percent complete. Shearon Harris plant

personnel agreed to inform the auditor when this task is complete.

Thermal aging of the PC cards was also performed as reported in

Westinghouse report WCAP-8687, Supplement 2, Appendix 1, Short Term

A A 2( h )~1AThe qualified life of each PC card is 5 years.

Based on the observation of the field installation, review of thequalification documents, and the applicant's response to questions, theprocess control cabinet and associated PC cards are adequately qualifiedfor the prescribed loads.

2.5 Com onent Coolin Water Pum NSSS-5

The component cooling water pump supplied by Pacific Pump (model

No. 'DSK 16 x 18 in.) is located in the auxiliary building at the 236-ftelevation. The motor was supplied by the Westinghouse Large MotorDivision. The. safety function of the pump is to supply cooling 'water tovarious NSSS safety related heat exchangers.

The pump was qualified using a combination of test and analysis.Natural frequency testing of the pump was performed and reported in PacificPump Shop Order D-49273, Natural Fre uenc Test, dated August 12, 1977.

The test was performed on a pump motor assembly using a shaker. The shakerapplied a 200, lb force over a frequency range of 10 to 220 Hz. The pump and

motor were mounted on' common base plate. No piping was attached to thepump flanges. The base plate was clamped down through the grout holesrather than being grouted. These differences were considered to have no

appreciable effect on the resulting natural frequencies. No major responsewas seen below 35 Hz.

Calculations demonstrating the structural integrity of the pump arecontained in Pacific Pump Shop Order No. 5D-49273, repo'rt No. K"387,

Rev. 1, Nuclear Service Pum Desi n Anal sis Re ort Class 3, datedJuly 29, 1976. The seismic load used in the calculations was 3 g

horizontal and 2 g vertical. Shaft deflection calculations showed that thedeflections were less than .the clearances available between the rotatingand stationary parts. Holddown bolt calculations showed that bolt stresseswere below allowable values. Pressure boundary calculations showed thatstructural integrity was maintained under worst case design conditionloadings.

The motor was qualified by

Thermal aging, radiation aging,reported in Westinghouse reportE ui ment ualification Test Re

a combination of test and analysis.and qualification testing were performed qs

No. WCAP-8687, Supp. 2-A02A, Rev. 2,ort Westin house LMD Motor Insulation,

dated March 1983. Resonance search tests were performed from 1 to 70 Hz.

The lowest natural frequency was 52 Hz. Five OBE tests and 4 SSE testswere performed for various horizontal mountings on the test table.Multi-frequency pseudo triaxial input was applied to the table. In allcases the TRSs enveloped the RRSs. The damping was 5 percent. No testanomalies or structural damage occurred.

Operability was not monitored during the testing. Therefore, furtheranalysis was performed to show that the motor shaft deflections were lessthan available clearances. A summary of this analysis is contained inWestinghouse report seismic shop order 74F31249, Seismic Anal sis ofCom onent Coolin Pum Motor for C L, dated December 23, 1976. A

conjugate beam analysis of the pump shaft was performed. The loads

considered were gravity, operational 1'oads, internal forces, externalthrust, and impeller mass effects. The analysis showed that 'the rotor didnot rub the stator, radial ahd thrust bearing loads were within allowablelimits, and all stresses were below allowable values.

The minimum qualified life of the motor was reported as 5.68 years inWestinghouse Gale. No. f040301, S.0.206, Minumum uglified Life of 5 ears

for W LMD Su lied Class 1E Motors, dated July 29, 1982.

Based on the observation of the field installation, review of thequalification document, and the applicant's response to questions, thecomponent cooling water pump and motor are adequately qualified for theprescribed loads.

2.6 Main Steam Relief Valve Controller. NSSS-7

The main steam relief valve controller (MPL No. PK-30B1) was supplied

by Westinghouse with model No. 2445D69G05. It is a 7300 seriesmanual/automatic controller used to control one of the main steam relief

'I

10

valves. It is mounted in the main control board panel in the control room

at elevation 305 ft. It is panel mounted using two mounting bracketassemblies furnished with the controller.

Dynamic qualification of this'tem was performed by testing performed

by Westinghouse. This item was qualified identically to NSSS-1. See

NSSS-1 for a description of the qualification testing.

Based on our inspection o'f the fi'eld installation, review of thequalification documents, and the applicant's responses to questions, themain steam relief valve controller is adequately qualified for theprescribed loads.

2.7 ASCO Solenoid Valve NSSS-8

The solenoid. valve (MPL No. 2RC-0525S-B-I) was supplied by" AutomaticSwitch Company (ASCO) with model No. FT-831654. This solenoid valveprovides supply air to a pneumatic actuated valve identical to NSSS-2. Itis located at elevation 246 ft of the auxiliary building. It is bolted toa horizontal channel with four 1/4 in. diameter bolts.

This .valve was qualified by testing performed by ASCO, documented by

report No. 103, dated August 27, 1975. Testing consisted of a resonance

test and two pseudo biaxial sine sweep tests. No natural frequencies were

detected below 40 Hz. The pseudo biaxial tests had a double amplitude of0.148 in. with test frequencies from 9 to 40 Hz.'. The corresponding range

of peak acceleration levels was 0.6 to 12 g in the axis of test motion.The plant generic input level is 2. 1 g in each direction. The testacceleration values are well in excess of the required test levels. The

valves were tested in both an energized and deenergized state. No valve'eakagewas observed during or after the tests. Operability of the valve

was demonstrated with no observed failures or anomalies.

Based on our inspection of the field installation, review of thequalification documents, and the applicant's responses,to questions, theASCO solenoid valve is adequately qualified for the prescribed loads.

2.8 Residual Heat Removal Pum and Motor NSSS-10

The residual heat removal pump, supplied by Ingersoll-Rand (model

No. 8 x 20 WDF) is located in the aver<i liary building at the 190 ftelevation. The pump motor was supplied by Westinghouse Large Motor

Division. The safety function of the pump is to provide low head safetyinjection.

The pump was qualified by analysis in McOonald Engineering AnalysisCo. report ME-174, Rev. 9, Structural Inte rit and 0 erabilit Anal sis ofResidual Heat Removal Pum , dated October 9, 1979. A finite element model

of the pump casing and shaft was developed. The lowest natural frequency

was found to be 40e6 Hz. Seismic accelerations of 3 g horizontal an'd 2 g

vertical were applied to the model. Stresses from nozzle loads caused by

these accelerations were shown to be below allowable values. Differentialdeflections between the rotor and stator were found to be less than the

available clearance.

An axisymmetric model of the pump casing was made to evaluate stressesdue to pressure. The pump casing consists of two "halves" held together by

bolts. These bolts were included in the finite element model as an

axisymmetric ring. Stresses in the pump casing and bolts, assembly

support, and holddown bolts were found to be below ASME section IIIallowables. Some further finite element analysis to obtain a more refinedstress field was performed and is contained in Ingersoll-Randreport TR-8418, Rev. 1, 8 x 20 WDF Pum Structural Inte rit Su lement toRe ort ME-174 of McDonald En ineetin Anal sis Co., dated July 5; 1984.

The motor was qualified by a combination of test and analysis.Thermal aging, radiation aging, and qualification testing. were performed as

reported 1n Mest1nghouse report WCAP-8687, Supp. 2-A02A, Rev. 2, ~E u1 ment

ualification Test Re ort Westin house LMD Motor Insulation, dated

March 1983. Resonance search tests were performed from 1 to 70 Hz. The

lowest natural frequency was 54 Hz. Five OBE tests and 4 SSE tests were

performed. for various horizontal mountings oa the test table.

12

Multi-frequency pseudo triaxial input was applied to the table. In all~

'asesthe TRSs enveloped the RRSs. The damping was 5 percent. No testanomalies or structural damage occurred.

Operability was not monitored during the testing. Therefore, furtheranalysi.s was performed to show that the motor shaft deflections were lessthan available clearances. A summary of this analysis is contained in.Westinghouse .report Seismic Shop Order 74F12803; Seismic Anal sis ofResidual Heat Removal Pum Motors for Shearon Harris Nuclear Station,dated March 27, 1975. A conjugate beam analysis of the pump shaft was

performed. The loads considered were .gravity, operational loads, internalforces, external thrust, and impeller mass effects. The analysis showed

that the rotor did not rub the stator, radial and thrust bearing loads were

within allowable limits, and all stresses were below allowable values.,

The minimum qualified life of the motor was reported as 5.68 years inWestinghouse Gale. No. f040301, S.0.206, Minimum uglified Life of 5 ears

for W LMD Su lied Class lE Motors, dated July 29, 1982.

Based on the observation of the field installation, review of thequalification document, and the applicant's response to questions, theresidual heat removal pump and motor are adequately qualified for theprescribed loads.

.'.9 - 14-inch Motor 0 crated Gate Valve

The 14-inch motor operated gate valve (IDNo. 14002GM84FEB03000S740002; MPL No.-2SI-V574-SB1-06035) was manufactured

and supplied by Westinghouse according to purchase G678852 Rev. 2 and

952065 Rev. 5. It was butt welded into a 14-inch pipe located in the

auxiliary building at the 193-ft elevation. This valve is a part of safetyinjection system and its function is to isolate RWST from RHR pump No. 1.

It has a Limitorque type SB, serial No. 305490 operator with a motor from

Reliance Electric. The motor identification number is 1YAB02536A2PE with215TRl frame.

13

The valve was qualified by a combination of test and analysis. The

tests details are in the Westinghouse report: 0 erababilit Test Report

Nuclear Valves, No. 4995, Rev. 0, dated January 28, 1977. The analysisportion of the qualification is documented in the report: Stress Re ort For

Westin house Class 1 Nuclear Valves 6 Inch and Lar er, No. 5405, Rev. 1,

dated May 5, 1980.

A static deflection test was performed to demonstrate stroking of -the

valve. The laboratory mounting consisted of welding the valve to a pipestub which was then bolted to a test fixture. The required acceleration ineach direction, as determined by piping analysis, was;

s/s f/b

OBE

SSE

GenericPlant Specific

GenericPlant Specific

1.1 g0.21 g

2.1 g0.43 g

1.1 g0.53 g

2.1 g1.05 g

1.1 g0.22 g

2.1 g0.45 g

The applied equivalent accelerations were:

s/s

4.5 g

It operated successfully.

f'/b

4.5 g 4.5. g

The analysis portion of the qualification,was performed with a two-D

model using the "WECAN" computer program with a 4.5 g acceleration in each

direction. The calculated lowe'st natural frequency is about 79 Hz. The

calculated stresses and deflections are shown-below with the allowables.

Identification Location Loads

Totalcalculated

stressesAllowablestresses

Sourceof

allowables

Yoke

Yoke"bonnetbolting

Yoke-operationbolting

Seismic 8

Operating

Seismic 8Operating

Seismic 4Operating

16065

50917

46304

31425 ASME code

54200 ASME code

81850 AISI

Identification Location

Stem/gland

Loads

Seismic 4operating

Al l owdefi.

~ln.0.003

Allow Sourcedefi. of

~fn. al lnw defi.

0.013 From partdrawing

15

OPERATOR

The Limitorque motor operator is qualified based on tests performed on

two similar operator s (SMB-00-15 with Reliance motor and SMB-1-60 withElectric Apparatus motor). The one in the field is SMB-1-60 with Reliancemotor. These tests. including the results are described in the

'estinghouse/Limitorquereport: E ui ment uglification TestRe ort —Limitor ue Electric Motor 0 erator Environmental and Seismic

Testin Outside Containment , No. WQAP-8687 Supp. 2-H04A, Rev. 2 ofMarch 1983. The laboratory mounting consisted of bolting the operator to a-

test plate using eight 5/8-in. socket head screws. Resonance search

performed with a 0.75 g magnitude sine sweep between 5 to 200 to 5 Hz at'2 octaves/minute indicated the following frequencies:

s/s f/b

190 Hz 170 Hz )200 Hz

Following this, single axis sine dwell qualification tests were

performed at various frequencies between 2 to 35 Hz. The input levels were:

s/s f/b

OBE

SSE

5.0 g

7.75 g

5.0 g

7.75 g

5.0 g

7.75 g

There was no anomaly detected.

16

NAMCO 'LIMIT SWITCHES

The Namco limit switches [Model EA170 12302] were qualified by testsperformed by Franklin Research Institute. They are described in theirreport: Seismic uglification Re ort of Limit Control Switches,

No. FC-3879, Rev. 0, of September 1974.'he resonance test between 1 to 35

to 1 Hz at one octave/minute did not indicate any frequency below 33 Hz.

Subsequently, pseudo biaxial sine dwell of 30 seconds duration with the

following magnitude were performed at various frequencies.

s/s f/b

OBE

SSE

3.5/6.4 .g

3.5/6.4 g

3.5/6.4 g

3.5/6.4 g

3.5/6.4 g

3.5/6.4 g

a. 3.5 g up to 15 Hz and 6.4 g from 15 to 33 Hz.

c

There were 5 OBE, 1 SSE and 10 other level tests performed. The inputlevels were higher than plant specific. There was no anomaly detected.

Based upon the observation of the field installation, review of the

qualification reports and applicant's responses to our.inquiry, the 14-inch

motor operated gate valve is adequately qualified for the Shearon Harrisplant.

I

2. 10 7300 Printed Circuit Card NAL 2 (NSSS 12)

The 7300 printed circuit (PC) card (ID No. FS-1SW 7050 Al-SA-01632;

model No. NAL 2) was manufactured and supplied by Westinghouse according topurchase specification No. 953501. This card was mounted in a card frame

and secured with. two restraining screws inside the 7300 process controlcabinet (PIC-C09). This cabinet was located at the 305-ft elevation of the

reactor auxiliary building. The PC card is a part of the service water

system. It provides the control room operator with component cooling water

heat exchanger A high flow alarm indication. This device was qualifiedbased on test. Seismic loads were considered in the test.

17

k

The qualification test for this item was performed by Westinghouse.

Its details are in the reports: E ui ment uglification TestRe ort - Process Protection S stem Seismic Testin , No. WCAP-8687

Supp. 2-E13A, Rev. 1 of July 1981 and E ui ment uglification Data

Packa e - Process Protection S stem, No. WCAP-8587, EgDP-ESE-13, Rev. 5 ofJune 1985. The card was tested to the RRS generated from the cabinettest. The laboratory mounting of the cabinet consisted of 12 3/4-inchdiameter bolts of mild carbon steel. The first series of tests was

resonance search. It was performed with a 0.2 g magnitude sine sweep from1 to 50 Hz at one octave per mihute. The following resonances were found:

s/s f/b

10 Hz 7 Hz 733 Hz

The subsequent tests were pseudo-triaxial sine beat. From these testsRRS for the card location were generated. The card was then tested tothese requirements. The input to the cabinet enveloped the site specificrequirements. During the PC card tests the following anomaly was

detected. Prior to the start of the SSE test in direction 4, one of thetwo NAL PC card circuits was unable to be cycled due to the short-circuitprotection on the card detecting a short in the circuit. The output was

latched in a deenergized condition. The other circ&~ t did not detect a

similar short-circuit indication and demonstrated the capabilities to tripand reset. The circuit that had de'tected the short was reset after testingand functioned properly. Results were considered acceptable.

Based. upon the. observation of the field installation, review of thequalification documents and applicant's responses to our inquiry, the PC

card is adequately qualified for five years.

18

3. BALANCE OF PLANT (BOP) EQUIPMENT

3. 1 6900 V Switch ear (BOP 1)

The 6900 V switchgear'ID No. 6900 V BUS 1A SA(1) 08873, Model

No. FB-500A-1) was manufactured and supplied by Siemens Allis according topurchase Spec. No. EBASCO 255-72. It was located in the'witchgear room atthe 286 ft elevation. of the reactor auxiliary building. It was floormounted. The mounting consisted of plug welding through 5/8 inch anchor

holes. There were four holes per cubicle. It is a part of the ac power

distribution which provides emergency 6900 V power for class 1E equipment..

The unit is qualified based on tests performed on a similar unit. Seismic

loads are considered in the qualification.

The qualification tests were done by Wyle Laboratories. Details ofthe tests are in the Wyle reports: uglification Test Re ort on 6.9 kV

~Switch ear, Rn. 44597-1, Rev. 0 dated January 10, 1980 and Seismic

Simulation Test Pro ram on a 6.9 kV Switch ear, No. 45237, Rev. 0 dated

July 10, 1980. The first report has structures, breakers and structuremounted devices. The second has panel mounted devices. The field unit has

13 cubicles connected with each other on the side with four bolts each. A

three-cubicle configuration was tested. The test mounting consisted ofplug welding, through the 12 anchor holes, to the test table with thefront-to-back axis colinear with the longitudinal axis of the table. For

each of the two-tests there was a resonance search done. In the first the

input magnitude was 0.2 g and in the second 0.15 g. In both cases,

however, the input was biaxial sine sweep from 1 to 50 Hz at one

octave/minute. The following resonances were detected:

s/s f/b

5 Hz 7 Hz notavailable

Subsequently, a series of qualification tests were done. The inputswere always independent, biaxial and random. The input ZPA were:

19

OBE

SSE

s/s

1.45 g

2.7 g

f/b

1.37 g

2.7 g

1.22 g

2.6 g

The required ZPA were:

OBE

SSE

s/s

0.3 g

0.5 g

f/b

0.25 g

0.4 g

0.5 g

0.85 g

There were 13 OBE and 5 SSE level tests. TRS were generated and

compared to RRS ~ The comparisons were satisfactory. Structural adequacy

was demonstrated.

However, the unit in test had major anomalies with respect toelectrical functions (potential transformer). According to Siemens Allis'srepresentative, the potential transformer was to be modified or replaced.On inquiry', the applicant confirmed that indeed modifications were made and

further tests performed. The results of these tests were satisfactory.However, the qualified life span of the unit was reduced from 40 to20 years. It is not clear as to what prompted this? There is no evidence

that a systematic life span evaleation of nonmetallic parts has been

performed. This should be done.

The question of evaluation of the life span of the nonmetallic partsis generic in nature and will be handled as such.

Based upon the observation of the field installation, review ofqualification documents and responses to our questions this unit isadequately qualified. The resolution of the life span issue fornonmetallic parts will continue.

20

3.2 Auxiliar Rela Cabinet (BOP-2)

The auxiliary'elay cabinet was custom built by Systems Control. Itis located in the auxiliary building at the 305 ft elevation..Instrumentation in the cabinet provides a signal to the safety shutdown

panel in case of a high radiation condition. The cabinet did not have a

tag showing the manufacturer and model number. Shearon Harris plantpersonnel'xplained the quality assurance procedure by which each piece ofequipment and its location in the plant are correlated. The auditor isconvinced that the procedure is working properly.

The cabinet was qualified by analysis as discussed in Acton

Environmental Testing Corporation report AETC-17917-83N, Rev ~ 3, Seismic

ualification of the Auxiliar Rela Cabinet for Carolina Power and Li htCo., dated August 11, 1983. A finite element model was made using theSTARDYNE computer program. The cabinet is bolted to a channel which iswelded to a plate embedded in the concrete. The plate has Nelson studs toanchor it to the concrete floor. The channels were not included in thefinite element model. A calculation of the natural frequency of the

channels showed that .the first mode was over 1000 Hz. Therefore the

channel sections are rigid and need not be included in the model.

The program found five natural frequencies below 33 Hz. The

side-to-side natural frequencies were 23.05 Hz, 23.07 Hz, 25.43 Hz, and

25.89 Hz. One front-to-back natural frequency (13.27 Hz) was found. No

vertical natural frequencies were found.

Three load cases were analyzed and the resulting forces,displacements, and stresses were added by square root of sum of squares

method. The three load cases were: (a) floor vertical and,horizontalspectra (dynamic), (b) 0.6 g horizontal ZPA acceleration (static), and

(c) 0.7 g vertical ZPA acceleration (static). Forces, stresses, and

displacements from a 1 g downward acceleration (to simulate dead weight)were then added algebraically. The damping was 3 percent. The higheststress (61648 psi) for this very conservative loading, occurred in the

mounting bolts. The AISI allowable stress was 69,300 psi. Five OBEs and

21

one SSE were assumed to produce 2880 stress cycles. This is well below theallowable number of cycles found from the fatigue curve of the 1980 ASME

code section III. The output of the STAROYNE computer program was used toproduce required response spectra at the device mounting locations.

A minimum spacing to prevent interaction between cabinets or between a

cabinet and any in-place equipment of 0. 183 in. was specified. Severalcabinets were mounted closely together in the plant. EBASCO is performingan evaluation of these cabinets, as discussed in EBASCO letter EB-C-18912,Shearon Harris Nuclear Plant Assessment of the Effect of Ga s Between

Safet Class Electrical Cabinets on Cabinet Seismic uglification, datedMay 23, 1985. Five cases of closely spaced cabinets were identified. The

cabinets will be connected together to prevent interaction during a seismicevent. No further qualification analysis is planned for these cabinetssince the natural frequencies in the side-to-side direction are 25 Hz or

~ ;-„ higher for the connected cabinets and the accelerations at thesefrequencies are about 0.2 g. No-field modifications had been completed atthe time of the audit.

Based on the observation of the field installation, review of thequalification document, and the applicant's response to questions, theauxiliary relay cabinet is adequately qualified for the prescribed loads.

3.3 Instrument Cabinet BOP-3

The instrument cabinet (MPL No. Y21-Cl-ESF-AEB) was sup'plied byMercury Company of Norwood, Inc. It was custom built to drawingNo. PC-N19623-731 Rev. 5. This cabinet was purchased to specificationCAR-SH-IN-06. Its dimensions are 3 ft 6 in. wide, 2 ft 6 in. deep, and

7 ft 0 in. tall and has a weight of 1875 lbs. It is. floor mounted atelevation 262 ft of the emergency service wats. intake screening building.The base of the cabinet is continuously welded with I/O in. fillet weldsfront and back to embedded floor plates. This cabinet provides structuralsupport for two class 1E .instruments, a Rosemount model 1153 series B

pressure transmitter and a Transamedic Oelavil model RE-36562 levelindicator transmitter.

22

gualification of this cabinet was performed by analysis performed by

Simpson Gumpertz and Heger Inc:, documented by report No. 9449 dated

April 5, 1983. A three dimensional computer model using beam and plateelements was developed to analyze the cabinet using the computer code

stardyne. The cabinets natural frequencies were determined to be 37.9 Hz .

side-to-side, 50.3 Hz front-to-back, and rigid in the vertical direction.The cabinet analysis was perfqrmed using a horizontal static coefficient of.52 G and a vertical value of .59 g. The corresponding required floor'ZPAsfor this building floor are .4 g and .2 g. The maximum stress was

determined to be 1,550 psi compared to an allowable of 18,000 psi. The

qualification of the safety related devices in the cabinet will be

quali.fied separately by testing using the building floor spectra .as a

required response spectra since the cabinet was determined to be rigid.

Based on our inspection of the field 'installation, review of thequalification documents, and the applicant's responses to questions,'heinstrument cabinet is adequately qualified for the prescribed loads.

3.4 Containment Vacuum Relief Rela BOP-4

The containment vacuum relief relay, supplied by Potter Brumfield(model No. MDR-137-8) is'ounted in a cabinet in the auxiliary building atthe 305 ft elevation. Another similar relay, the auxiliary relay (model

No. MDR-134-1), is mounted in the auxiliary relay cabinet: Both cabinetsare identical. Therefore, the qualification reports for each cabinet and

each relay are the same. The auxiliary relay provides'n input signal tothe safety shutdown panel in case of a high radiation condition. Other

relays provide similar system support functions for various class 1E

systems.

The relays were qualified by test as discussed in Acton Environmental

Testing Corporation report AETC-15761, Rev. 3, Re ort for uglification ofClass 1E Electrical E ui ment for Nuclear Power Generatin Stations

er'EEE-323-1974and IEEE-344-1975, dated October 10, 1984. The r equiredresponse spectra for the testing was found from the results of the cabinetanalysis (see BOP-2). Output from the finite element model of the cabinetwas used to develop spectra at device mounting locations. The spectra were

23

found using a method developed by Kapur and Shao. This method does notrequire a time history analysis to be performed. An output spectra isdeveloped directly from a response spectrum analysis.

~

'iaxialmulti-frequency input from 1 to 100 Hz was applied to therelays. An inherently similar relay to the HDR-134=1 relay (model '.

HDR-163-1) was used in the tests. The test mounting was the same as thein-plant mounting. The relays were tested in both the energized and

nonenergized states. Five OBE tests and three SSE tests were performed.All TRSs exceeded the RRSs.

T~ D

Contact chattering was monitored to detect short term opening ofcontacts. No chatter greater than 2 ms was detected. No damage occurredduring testing and the relays operated after testing. No test anomaliesoccurred during testing.

Based on the observation of the field installation, review of thequalification document, and the applicant's response to questions, thecontainment vacuum relay and auxiliary relay are adequately qualified forthe prescribed loads.

3.5 Containment Coolin Flow Switch BOP 5

The containment cooling flow switch (MPL No. FS-KV7571AS) was suppliedby Fluids Components Inc. with model No. FR-72-4R. It was purchased tospecification CAR-SH-IN-35 Rev. 8. This switch is enclosed .in a

rectangular steel box 9 in. wide by 6 in. high, by 3-13/16 in. deep. Ithas an approximate weight of 9 lbs. It is wall mounted with four 1/4 in.diameter bolts.

gualification of this switch and sensor was accomplished by a

combination of testing and analysis. The switch and sensor assembly were

tested by Wyle Laboratories, documented by report No. 58249 dated Feb. 16,1978. Testing consisted .of sine sweep resonance search and pseudo biaxialOBE and SSE level testing. No natural'requencies were observed below

40 Hz. The test motion for the 10 OBE tests and 2 S5E tests was random

24

with superimposed sine beats. This switch was tested as though it was a

line mounted piece of equipment, even though it is wall mounted. The inputZPA was in excess of 5 g's each direction for the SSE tests. Operabilityof the test 'specimen was demonstrated, with no observed failures oranomalies. A calculation was performed for a flow switch sensor extensiontube shorter than that tested. — This calculation showed the component tohave higher stiffness and natural frequencies and lower stresses than that.tested. This calculation is documented by Fluid Components Inc. reportNo. 708058.

Based on our inspection of the field installation, review of thequalification dbcuments, and the applicant's responses to questions, thecontainment cooling flow switch is adequately qualified for the prescribedloads.

3.6 Centritu al Fan and Motor BOP 6

The centrifugal fan and motor (MPL No. E-61-1B-SA) was supplied by

Barry Blower Co. with model No. 7245. It was purchased to specificationCAR-SH-BE"13, Rev. 9. It is a 5 horsepower centrifugal fan with a flowcapacity of 6300 scfm. The fan and motor assembly has a total weight of507 lbs. It is located at elevation 292 ft of the diesel generatorbuilding. The base of the fan assembly is attached to a concrete base withsix 1/2 in. diameter embedment bolts. The fan moves air for the dieselgenerator building ventilation system.

This fan was qualified by testing performed by Wyle Laboratories,documented by report No. 46349,. dated October 6, 1982 'hree Barry fans,models 7200, 122, and 7245 were -tested simultaneously. Model 7245 was

bol.ted to the test table with six 1/2 in. diameter bolts. Testingconsisted of a resonance search test, OBE, and SSE level Vibration Tests.No natural frequencies were detected below 33 Hz. The seismic vibrationtest motion was biaxial random. The test specimens were subjected to10 OBE and 4 SSE level tests, half of which were in each test direction,side-to-side/vertical and front-to-back/vertical. The input motion TRS

enveloped the required response spectra. The ZPA for the diesel generator

25

building is .4 g horizontal and .37 g vertical. The test ZPA was 1.9 g

s/s, 2.7 g f/b, and 3. 1 g vertical. The fans were demonstrated to have

sufficient integrity to'ithstand, without compromise of structures and

functions, the prescribed simulated seismic environment.

Based on our inspection of the field installation, review of the

qualification documents, and the applicant's responses to questions, the

centrifugal fan and motor are adequately qualified for the'prescribed loads.

3.7 1-1/2 In. Three Wa Valve BOP-7

The 1-1/2 in. three way valve, supplied by ITT Grinnell/Hammel Dahl

Oivision (model V830), is line mounted in the auxiliary building at the305 ft elevation. This valve is operated by an ITT General Controls Hydra

Motor Actuator. The review of the qualification of the actuator iscontained in section 3.12 of this report (BOP-2A). The safety function ofthe valve is to modulate flow for cooling of the service air handling unit.

The valve was qualified by a combination of test and analysis.Results of the testing are contained in ITT Grinnell report 3603,

Attachment A, Test Re or t on Resonant Search Testin of 1-1/2 Inch150 Class V830 Valve with a H dramotor Actuator, dated March 21, 1983.

Resonance search tests from 2 to 100 Hz were run in each horizontaldirection. One natural frequency in each horizontal direction was

identified: 22.7 Hz and 26 Hz. The valve assembly was bolted to a bookend

fixture which was then bolted to the test table. The valve actuator was

not supported in these tests.

The actuator is supported in each horizontal direction in the Shearon

Harris plant. A SAP-IV model of the valve and actuator was made. The

lowest natural frequency with the actuator supported was 180 Hz (see

Appendix B of ITT Grinnell report 3694, Seismic Anal si's of 1-1/2 in.150 lb Flow Control Valve with a H dramotor Actuator, dated March 16,

1983.)

26

Stresses in the valve body, yoke, and flanges are contained inAppendices D, E, and F of ITT Grinnell report 3694 mentioned above. Allstresses were below ASME Section III allowable values. Operability of thevalve is assumed since stresses are low.

Based on the observation of the field installation, review of thequalification document, and the applicant's response to questions, the1-1/2 inch three-way valve is adequately qualified for the prescribed loads.

3.8 Main Steam Power 0 crated Relief Valve BOP 8

The main steam power operated relief valve (MPL No. 2MS-P19SB-1) was

supplied by Control Components Inc. with model No. OXG 9-X8-XBBW-10BW. The

valve and operator were purchased to specification No. CAR-SH-M56 Rev. 7.It is a globe drag valve with an 8 inch inlet and 10 inch outlet. The

operator is electro-hydraulic supplied by Paul Munroe Hydraulics Inc. withmodel No. PD25210. The actuator is supported vertically off the valve.The valve is pipe supported at elevation 261 ft in the main steam tunnel ofthe reactor auxil.iary building. This valve provides pressure relief of themain steam piping at a desired set point.

The valve and operator were qualified by a combination of testing and

analysis, documented by Control Components Inc. qualification reportNo. 21739 Rev. 3, dated February 21, 1984. The valve and operator assemblywas placed on a test table at Wyle Laboratories for testing, however, due

to the combined .weight it was not possible to conduct the seismicsimulation tests. The natural. frequencies of the assembly were determinedby modal analysis techniques. The natural frequencies were determined tobe in the rigid range in all directions. This testing is documented by

Wyle report No. 58649, dated July 22, 1982. Control Components Inc.performed a stress analysis for the valve in accordance with therequirements of ASME Code Section III for class 2 valves. The analysisevaluated normal operating loads in combination with seismic inertia and

nozzle loads. The highest stressed component was determined to be thebonnet bolts with a stress of 18,591 psi compared to an allowable stress of50,000 psi. The valve stem deflections were evaluated to assure

27

1

operability of the valve during a seismic e'vent. The calculated stem

deflection is .064 inches compared to an allowable of 0.136 inches,

The operator was. qualified separate+ by testing performed by Myle

Laboratories, documented by test report No. 58388-2. The actuator was

mounted to a test fixture to simulate normal service conditions as closelyas possible. The test fixture was .welded to the test table. The operatorwas tested to 6 OBE level tests and 5 SSE level tests. The OBE tests were

single axis sine beat tests with a maximum input acceleration level of3.0 g. The SSE level tests were with random biaxial test motion. The

maximum input levels for the SSE tests were 7.0 g s/s and f/b, and 8.6 g

vertical. The plant required input SSE levels for this valve are 3.0 g

horizontal and 2.0 g vertical. During the first OBE test, three operatormotor bolts broke. This was attributed to the bolts not bei'ng properlytorqued. The bolts were replaced and all tests performed without any

additional anomalies. Operability of the actuator was demonstrated duringand after each test with no evidence of structural damage.

Based on our inspection of the field installation, review of the

qualification documents, and the applicant's responses to questions, the

main steam power operated relief valve is adequately qualified for the

prescribed loads.

3.9 Control Room Cabinet BOP 9

The control room cabinet (ID No. RMC-1-10674; model No. 0352-0501) was

manufactured by Sorento Electronics and supplied by General Atomics

according to purchase spec. No. N-29. This cabinet was located in the

control room of the reactor. auxiliary building at the 305 ft elevation. Itwas floor mounted with I/O in. continuous weld both in the front and back

(outside only) channels. The channels are then attached to the embedded

plate with 4 in. long on 6 in. center fillet welds. It is a part of the

radiation monitoring system and its function is to control and monitor

various areas and process radiation monitors. Its qualification includes

seismic loads.

28

This unit is qualified based on tests performed by Wyle Laboratorieson another (0373-0501) unit. The details of the qualification tests are inthe Wyle Laboratory report: Seismic Testin of One Control Room Cabinet,No. 58696, dated December 8, 1981. There are two. other related repoAs.The first is: uglification Test Re ort For St. Lucie Class 1E E ui ment,

'o.

E-255-1063 dated February 10, 1982 by Gen'eral Atomics and the second:

ualification Summar for Shearon Harris Class lE E ui ment,

No. E"255"1123 of March 1983 by GA Technologies.

The tests performed by the Wyle Laboratories were on a similar cabinet(model No. 0373-0501) which is in the St. Lucie plant. Model

No. 0352-0501, 'at Shearon Harris, is very similar to the previous one as

pointed out in the GA Technologies report. The specimen for the Wyle

Laboratories test was welded to the test fixture with 1/4 inch fillet weldon front and back sides'esonance search in each of the three orthogonalaxis with 0.2 g magnitude, sine sweep with a sweep rate 'of one

octave/minute from 1 to 33 Hz indicated the following frequencies:

s/s f/b

9.5 Hz 14 Hz 32 Hz

Fol.lowing this, qualification tests with independent biaxial, random

input were performed. The input levels at 33 Hz were (at 2 and 3 percentdamping for OBE and SSE respectively):

s/s f/b

OBE

'SE2.9 g

3.2 g

2.5 g

2.3 g

5.0 g

2.7 g

The corresponding required g.-levels were:

s/s f/b

OBE

SSE

0.35 g

0.56 g

0.29 g

0.48 g

0.4 g

0.65 g

29

~ g

TRS were generated in each case. A comparison of TRS and RRS establishedthe structural adequacy of the cabinet.

Based upon the'bservation of the field installation, review of thequalification reports, and the applicant's responses to our questions, thecontrol room cabinet is adequately qualified for Shearon Harris plantpending the resolution of the following issues.

1. The tests established the structural adequacy of 'the cabinet butnot'the internals. Their qualification was in progress. The»

satisfactory completion of that program should be confirmed.

2. The field inspection revealed the generic question of inadequateclearance with respect to several cabinets. However, there is an

ongoing program.to analyze and correct the situation. A

satisfactory completion of this program is to be confirmed.

3. The generic question of evaluation of life-span for nonmetallicparts should be resolved.

3.10 Emer enc Screen Wash Pum s and Motor BOP 10

The two emergency screens wash pumps (MPL No. 1A-SA and SB) were

supplied by Crane Deming Pump Co. with model No. 3065. They were purchasedto specification No. CAR-SH-Mii Rev. 5. They are .270 gpm capacityhorizontal pumps driven by Reliance 15 hp electric motors. 'he pump and

motor assemblies are skid mounted and located at elevation 261 ft of theemergency service water intake structure. The skids are bolted down withfour 1 inch diameter embedment bolts. These pumps provide wash water forthe intake structure screens.

I

The pumps and motors were qualified by analysis. The motor supportbolts, pump, and support frame were analyzed by McDonald EngineeringAnalysis Co. and documented by report No. ME-626, dated November 1, 1984.

A. three dimensional computer model of the pump assembly was used for theanalysis using the computer code ICES-STRUDL. The natural frequencies of

30

the pump assembly were determined to be in the rigid range. The lowestnatural frequency was 36.9 Hz side-to-side. A static analysis was

performed with a SSE acceleration of 1.0 g in each direction with nozzle

loading. The highest stressed component was determined to be the frame

adaptor bolts with a calculated stress of 23,734 psi compared to an

allowable stress of 30,800'psi. The relative displacement between the pump

impeller and casing was calculated to be .00342 inches compared to a

clearance of .015 inches.

A qualification analysis of the pump motor was performed by RelianceElectric Motor Co. documented by report No. 796-A-85, dated September 28,1979. This analysis wa's performed using static methods and an in house

computer code No. 706. The relative deflection between the pump stator and

rotor was calculated to be .0005 inches compared to a clearance of.0052 inches. The loading used in the calculation was based on preliminaryspectra ZPA which was approximately half of the final value. Thereforeusing the proper loading the relative deflection would be approximately.001 inches still only one fifth the allowable value.

Based on our inspection of the field installation, review of thequalification documents, and the applicant's responses to questions, theemergency screen wash pumps are adequately qualified for the prescribedloads,

3. 11 30-inch Butterfl Valve BOP 12

The 30-inch butterfly valve (ID No. 3SW-B106SB-1-09519, Model

No. 30-150-8229 MT MOD: B) was only briefly looked into due to lack oftime. The review established that a complete qualification documentation

package was in place but did not establish,the merit of the qualificationof the unit.

3. 12 H dramotor Valve 0 erator BOP-2A

The hydramotor valve operator, supplied by ITT General Controls (model

No, NH-91-Reverse) is located in the auxiliary building at the 305 ft

31

elevation. The safety function of the valve is to modulate flow forcooling of the service air handling unit.

The hydramotor valve operator was qualified by test in Myle'-.Laboratory

report 58072, Seismic Testin of Milliam H dramotor Actuator Part No.

NH-91 Reverse Serial No. 7545B 135481-01-001 for ITT General Controls,dated June 8, 1976. The operator was mounted vertically in the tests. The

operator was bolted to the test table. A threaded rod was welded to the. table and was connected to the operator coupling 'to simulate connection tothe valve stem. Biaxial testing (one horizontal axis and the verticalaxis) was performed in two different horizontal orientations 90 degrees

apart., Operability of the specimen was monitored during the testing.Independent random motion from 1.25 to 35 Hz was applied to the specimen.

Each axis had a 3 g zero period acceleration for SSE. The Shearon Harrisrequired accelerations for line mounted equipment is 3 g horizontal and 2 g

vertical. The TRS exceeded 3 g at all frequencies above 1.5 Hz. Thereforethe TRS enveloped the RRS. One SSE test and 5 OBE tests were performed.

The OBE tests were run at one-half of the SSE test level; i.e., 1.5 g zero

period acceleration. No anomalies occurred during testing.

Other testing of the operator was performed with the operator mounted

horizontally as described in ITT General Controls report 721.77.095,Addendum 5, Summar of NH90 Series Actuator Su lemental Generic

ualification Testin to Class 1E Re uirements Outside Containment. No

test anomalies were reported during testing.

Thermal aging was performed and a 20,000 hour qualified life was

identified in ITT General Controls report 721.77.095 Addendum 2,Certification of NH90 Actuators for 50 C 122 F Ambient Tem erature and

20 000 Hours Usa e at 6N'ated Load, dated May 16, 1978.

Based on the observation of the field installation, review of the

qualification document; and the applicant's response to questions, the

hydra motor valve operator is adequately qualified for the prescribed loads.

32

4. FINDINGS AND CONCLUSION

The review of the Shearon Harris, Unit+ will be completed when the

following open items are closed.

4.1 Generic Issues

4.1.1

During the field observation of the four-bay two-train solid stateprotection system train A (NSSS-3) it appeared that the clearance between

this unit and an adjacent one was not adequate. On inquiry, it was furtherlearned that this problem may be associated with many cabinets. However,

the applicant indicated that he was already aware of the situation and a

program was already in motion to analyze and correct the situation where

'required. The NRC should be informed when the program is completed.

4.1.2

The evaluation of the life-span of the nonmetallic parts has not been

performed. They should be performed and'RC informed of the completion.

4.2 E ui ment S ecific Issues

4.2.1

The qualification review of the control room cabinet (BOP-9) indicatesthat only the cabinet is qualified. as of now. However, the structuraladequacy as well as operability of the internals have not been established.

The qualification of the internal should be completed and NRC informed

of the satisfactory completion.

33

4.3 Conclusion

Based upon our review, we conclude that, pending resolution of allopen items, an appropriate qualification program has been, defined and

implemented for the seismic category I mechanical and electrical equipment

which will provide reasonable assurance that such equipment will functionproperly during and after the excitation due to vibratory forces imposed by

safe shutdown earthquake in combination with operating loads.

34

r$ '4 ~

J. Adams.J. T. AdamsK. D. BedfordGoutam BagchiBrad BondPete BradyT. L. BridgesGuy CampbellDon CasadoLee, CerraD. M. CrewsJan DudiakRandall FairK. M. FitzgeraldJ. B. GoreD. 0. Greenwood'. F. GuerinE. GurunB. LE HarrisK. G.

Hate'.

HeffnerC. S. HinnatP..HowardMark KomenicClarke KidoJ. KleinTony LentyCharles LeuteL. I. Lof1 in'im LombardoH. L. MaglebyGeorge F. MaxwellDavid C. McCarthyMark McDanielJohn J. McInerneyC. L. McKenzieJ. F. NevillDragos A. NuteJim OjalaBill PahashJames Parello

'Bob PountyJoe RuggieroDon RyanPedro SalasZ. T. ShiJag N. SinghDi'ck Stephens

LIST OF ATTENDEES

W Nuclear SafetyHPES StressCP&L HPESUSNRC

WestinghouseCP&L HPESEG&G Idaho, Inc.CP8L Maint.CP&LEbasco

~CP&L HPESWestinghouseCP&L T. S.CP&L HPEST&B EDRCP&L HPESW Nuclear SafetyEbasco EM

EG&G Idaho, Inc.CP&L QACP8L Maint.CP&L StartupCP&LWestinghouseEG&G Idaho, Inc.Ebasco"HVACCP&L HPOSEbasco CivilCP&L HPESUSNRCEG4G Idaho, Inc.USNRC SRICP&L NELDCP&L HPESW Nuclear SafetyCP&L QA/QC (OPS)CP&L HPESEbasco Civil/SAGCP&LEbasco'SCWestinghouseCP&L HPESEbasco Proj. Eng.CP&L HPESCP8L LicensingEbasco Civil/SAGEG8G Idaho, Inc.CP&L RAT

35

Matt SterrettHoward M. StrombergMax F. Thompson, Jr.J. N. UnderwoodR. Brian Van MetreE. J. WagnerH. L. WilliamfPeter YandoRon Zola

CP&L HPESEG&G Idaho, Inc.CP&L HPEMSCP&L HPESCP&L T.S.CP&L HPESCP&L HPESCP&L HPESCP&L TS,

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