UNJ.TS: ··2.its entirety the Revision 2 IST Program. - 2. Basis of Inservice Testing Program 2.1....

... : ~ ~ ·'' . ;_ ~;- .... . -:·· ....

UNJ.TS: ··2. ;:& . 3 . ' . . :·::···· .. ·. :.-:··. . : .

::·~,·

.... ·····;'.- ., ·.·

.:·.:·: ·. :.:(· . :=~.!, -~<~;;~·~·~· ·:··.) .. ·~. <

. t·

•. ·,i . ~. • • ··,··, ........ ·:.:· : ·. ; ;

.. ''· · .. ·

FOR ASME CLASS: .( .. 2~.--3' &. sAt=ety '~RE~:iTEO ~ ,;~ i

. ·-~~ ~ ' \.: ··.• : ~:· . ... ., :.lj~{:_ :, .:i:.· :.: :.··

PUMPS' AND':\IALVES ., . ,·

':.·· . :>: .. .. · ..

,t''-

INCLUDING AUGMENTED NRC.tES'TING .·

''•.;,\'.~~\~-"-. ·,. : .:>~:r.~-'.R'EVlis:ro i\i.~~.: < .. --.~-? _'· :·-:;;.."~:~ :·--:·.-:: .. ~;(\T~:~-;~:-.:g~~~;;q;~t.;~;~*J{~J,j~F~~:~(.'~:~; . "· · .. :.· ..

, \ ~ . ';~Rf3 ,S'~~ ~~:I[~~' · ,,, · ·JULY.·1;.·1 198:9····:>:;) · .- - · ... ·.·,-.,_ .. ;;::~ .. ;)··:· .. -. .· ... .- ..... :·· ·:·····l_ .. \!:~.-:_.:-.::··:~··-:~ 1·.:.-~~/{~S~ :;:-~, · · ·.:·:·"' .·:.- ... ~·-: .. '.~··

.' ~ ·· .. , .. "{.·: ·• '

: .. -'·.

li. · •..

~< .. '.~· ·. '

: ····.:.· .'· .'

.'·.. . ~ ··~ '

..... -:·~..: -,. . . ~ ~.: . . ~·

.· ... .. ·~- ·:r

COMMoN'wEAL'rH Eb1§6~i6~·~J~y't<},:·,'1,;''.,::;'._;/ ' . .. •

• TAB

1

2

3

4

5

6

6

7

8

• 9

-10

10

11

12

13

• 1305a/l

IST PROGRAM INDEX

INDEX Page 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

DRESDEN NUCLEAR STATION UNITS 2 & 3

NRC SUBMITTAL

DESCRIPTION

IST Program INDEX

IST Program Description

List of IST Systems and P&IDs

Intentionally Left Blank

!ST Listing - Data Format Legend

Listing of IST Pumps (by Equipment Part Number - EPN)

ASME .Class 1, 2 ·and 3 Pumps

Augmented IST of Pumps

Dresden Additional Information/Methodology for. Pumps

Dresden Pump Relief Requests

·Listing of !ST Valves (by Equipment Part Number - EPN)

ASME Class 1, 2 and 3 Valves

Augmented !ST of Valves

Dresden Additional Information/Methodology for Valves .

,Dresden Valve Relief Requests

I I

•

' •

• L_

IST Program Description Page 1 of 5 Dresden IST Program Rev. 3 July 1, 1989

DESCRIPTION

1. Introduction

1.1. This Inservice Testing (IST) Program doc1.Jment, Revision 3 dated July 1, 1989 has been prepared to describe the IST Program requirements for the 2nd Ten Year Inspection Interval (from March 1, 1982 to February 2~, .1992) of Dresden Nuclear Station Units 2 and 3. Numerous "iteiiis, ma'difications, and corrections have been made since the Revision 2 IST Program dated April 15, 1988. The Revision 3 IST Program replaces. in its entirety the Revision 2 IST Program. -

2. Basis of Inservice Testing Program

2.1. This program of inservice testing details the pumps and valves that are tested during the 2nd Ten Year Inspection Interval of March 1, 1982 to February 28, 1992 of plant operation in accordance with Dresden Nuclear Station Technical Specification Section, 3.6.F. and the American Society of Mechanical Engineers (ASME) B_oiler and. Pressure Vessel Code, Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components", 1977 Edition through Summer 1979 Addenda, except where specific written relief from testing, determined to be impractical, has been granted by the NRC pursuant to 10 CFR 50.55a (g)(6)(i).

2.2. When a specific ASME Code testing requirement has been determined to be impractical during actual inservice testing,_ relief requests will be submitted for approval to the NRC. Subsequently, all approved relief requests will be_ inCluded in the Dresden Nuclear Stations Inservice Testing Program.

2.3. The cormnercial service dates for Dresden 2 and 3 are June 9, 1972 and November_ 16, 1971, respectively. The NRC has granted permission for establishment of November 1, 1978 as the cormnon implementation for ISI/IST for both units 1. The November 1, 1978 implementation date began the 3rd Inspection Period of t~e 1st Inspection Interval.

2.4. The Second Inspection Interval for both units is from March 1, 1982 through February 2B, 1992.

l1etter from V. Stello,_ NRC, to C. Reed, CECo, dated May 5, 1978 •

1305a/2

•

•

•

IST Program Description Page.2 of 5 Dresden IST Program Rev. 3 July 1, 1989

2.5. Augmented Inservice Testing (AIST) is performed on pumps and valves which the NRC has requested. Specifically, this includes any additional testing parameters, increased test frequency, or additional pumps and valves to be tested. These AIST requirements are in addition to the ASME Code requirements.

3. System Classification

3.1. Dresden Units 2 and 3 were built prior to the establishment of ASME Class 1, 2, or 3 components, NRC Regulatory Guide 1.26 and ASME Section XI. The construction permits for Dresden Unit 2 and 3 are January 10, 1966 and October 14, 1966 respectively. At that time, the ASME Boiler and Pressure Vessel Code covered nuclear vessels only. Piping, pumps, and valves were built primarily to the rules of USAS B31.l.O, Power Piping.

3.2. The system classifications for the Inservice Inspection and Testing Programs are based on the requirements set forth in 10 CFR SO and Regulatory Guide 1.26 and were developed for the sole purpose of assigning the appropriate Inservice Inspection and Testing requirements.

3.3. All the applicable Piping and Instrumentation Diagrams (P&ID) are listed in the IST Program~ Among their other functions, these drawings depict the hydraulic circuit and the location and type of instrumentation •

4. Pump Reference Values

4.1. Pump Reference Values.are those values as established during the first series of inservice testing of pumps under the IST Program. When a reference value or set of values may ·have been affected by pump replacement, repair, or routine servicing of the pump, a new reference value or set of values shall be determined, or the previous value(s) reconfirmed by an inservice test, prior to or within 96 hours after return of the pump to normal service.

4.2. If it is necessary or desirable for some reason other than that stated above to establish an additional set of reference values, the reasons for so doing shall be documented and approved by Dresden management prior to implementation. The new reference values will comply with Dresden Station's Technical Specification requirements. Such documentation shall include an analysis to demonstrate that the condition does not impair pump operability and t_hat the pump will still fulfill its function .

1305a/3

•

•

•

IST Program Description Page 3 of 5 Dresden IST Program Rev. 3 July 1, 1989

5. Valve Timing

5.1. Valves that require valve timing and do not have operational time limits as specified by Technical Specifications, FSAR or the manufacturer, maximum limiting stroke times will be calculated in accordance with the instructions in DAP 11-21, Dresden Administrative Procedure for Pumps and Valves. These limits are based on reference stroke times determined from the average of three stroke times measured when the valves are known to be in good condition.

5.2. These valve timing limits shall then be added to their respective surveillance procedure's data sheet for future use.

5.3. Measurement of valve stroke times is from the initiation of switch movement to the previously illuminated light going off. This is referred to as "switch-to-light" valve timing.

6. Personnel Qualifications

7.

6.1. Personnel performing the tests shall be those as designated by Dresden Nuclear Station.

6.2. Personnel assigned to interpret, evaluate, and review inservice test results shall be considered qualified when personnel have a working knowledge of ASME Section XI Subsections IWP and IWV, applicable standards, specifications, and station surveillance procedures •

Test Schedule

7.1. The Dresden Operating Surveillance procedures are scheduled by the computer and the Dresden Surveillance Engineer. The computer works on a month of 31 days and 92 days per quarter.

7.2 The pump and valve testing schedule are performed in accordance with ASME Section XI and DAP 11-2, Surveillance and Periodic Scheduling Program.

8. Test Records

8.1. Dresden Nuclear Station has developed and maintains a record system containing all information related to the inservice tests, including methods of tests, schedules, results, corrective action required and taken, and qualifications of personnel. Dresden Nuclear Station shall assure that the "Quality Assurance Records" and other records as required by applicable codes, are retained and available for use as needed •

1305a/4

•

• ...

•

!ST Program Description Pagi 4 of 5 Dresden !ST Program Rev. 3 July 1, 1989

8.2. The Record Of Tests are the completed surveillance procedures •

8.3. Periodically, a Swnmary Report is prepared to describe the current status of the !ST Program including a summary of discrepancies and corrective actions performed. The Summary Report should be prepared at least quarterly.

9. Contents of Inservice Testing Program - NRC Submittal

9.1. TAB 1 - IST PROGRAM INDEX - Organizational format for reference, retrieval and revision status.

9.2. TAB 2 - IST PROGRAM DESCRIPTION - The rsr Program Description provides details of applicable ASME Section XI Code year and Addenda, Basis of the IST program, classification of components, pwnp reference values, valve timing, personnel qualifications, test methods, test schedule, and test records.

9.3. TAB 3 - LIST OF IST SYSTEMS AND P&IDS - This is a listing of all applicable systems and P&IDS that have pwnps and valves which require testing under this program.

9. 4. =TAB~-4~~INTENT===I=O=!N=ALL=Y=-=LE=FT~B=LANK==

9.5. TAB 5 IST LISTING - DATA FORMAT LEGEND - This provides an explanation of the data fields and abbreviations used in the !ST listing •

9.6. TAB 6 AND 7 - LISTING OF IST PUMPS - This is a list of all the pwnps that have been determined to require inservice testing. This includes all applicable ASME Class 1, 2, 3 and safety related pwnps, and any Augmented NRC testing of pwnps.

9.7.· TAB 8 - DRESDEN ADDITIONAL INFORMATION/METHODOLOGY - PUMPS -This section contains Dresden Additional Information and Methodology (DAIM) relating to aspects of the IST Program that may be necessary to provide a better understanding of the implementation of the IST ASME Section XI requirements. Included here is a cross reference to previously submitted relief requests for pwnps.

9.8. TAB 9 - RELIEF REOUESTS - PUMPS - This section contains those requests for relief from the inservice testing requirements of ASME Section XI, when such requirements have been determined to be impractical •

1305a/5

•

•

•

!ST Program Description Pag~ 5 of 5 !ST Dresden Program Rev. 3 July 1, 1989

9.9. TAB 10 AND 11 - LISTING OF IST VALVES - This is a list of all the valves that have been determined to require inservice testing. This includes all applicable ASME Class 1, 2, 3 and safety related valves, and any Augmented NRC testing of valves.

9 .10. TAB 12 - DRESDEN ADDITIONAL INFORMATION/METHODOLOGY -VALVES - This section contains Dresden Additional Information and Methodology (DAIM) relating to aspects of the !ST Program that may be necessary to provide a better understanding of the implementation of the IST ASME Section XI requirements. Included here is a cross reference to previously submitted relief requests for valves.

9.11. TAB 13 - RELIEF REQUESTS - VALVES - This section contains requests for relief from the inservice testing requirements of ASME Section XI, when such requirements have been determined to be impractical •

1305a/6

•

•

•

Unit 2 Drawing

M-12, Sh.

M-12, Sh.

M-14

M-20

M-22

M-25

M-26, Sh.

M-26, Sh.

M-27

M-28

M-29, Sh.

M-29, Sh.

M-30

M-31

M-32

M-33

M-34

M-35, Sh.

M-37, Sh.

M-38

M-39

M-40

1305a/7

1

2

1

2

1

2

1

2

P&ID LIST .Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

DRESDEN INSERVICE TESTING P&ID LISTING

Unit 2 Revision

NN

xx

KK

KK

BA

BE

AB

HH

wx

JJ

AT

p

WW

AE

AF

HH

AR

BM

QQ

NN

BC

WW

Unit 3 Drawing

M-345, Sh.

M-345, Sh.

M-347

M-353

M-355

M-356

M-35 7, Sh.

M-357, Sh.

M-358

M-359

M-360, Sh.

M-360, Sh.

M-361, Sh.

M-362

M-363

M-364

M-365

M-366

M-367, Sh.

M-368

M-369

M-370

1

2

1

2

1

2

1

2

Unit 3 Revision

AE

NN

AF

AC

NB

AN

AN

AE

AS

AF

UC

L

AG

T

w

AA

AAJ

AD

AC

z

VE

MP

Title

Main Steam

Main Steam

Reactor Feedwater

Reactor Building Cooling Water

Service Water

Pressure Suppression

Nuclear Boiler & Reactor Recirculation

Nuclear Boiler & Reactor

Recirculation

Core Spray

Isolation Condenser

L.P. Coolant Injection

L.P. Coolant Injection

Reactor Water Clean-up

Fuel Pool Cooling

Shutdown Reactor Cooling

Standby Liquid Control

Control Rod Drive Hydraulic

Well Water

Instrument Air Piping

Service Air Piping

Reactor Building Equipment Drains

Turbine Building Equipment Drains

•

•

-·

Unit 2 Drawing

M-41, Sh.

M-43, Sh.

M-49

M-51

M-173

M-269

M-273

M-706, Sh.·

M-707, Sh.

2

1

M-1234, Sh.

M-1235

M-3121

1305a/8

1

1

1

P&ID LIST ·Page 2 of 2 Dresden !ST Program Rev. 3 July 1, 1989

DRESDEN INSERVICE TESTING P&ID LISTING

Unit 2 Revision

E

BD

pp.

AH

v

L

p

R

N

6

4

2

Unit 3 Drawing

M-41, Sh.

M-371, _Sh.

M-49

M-374

M-173

M-529

M-273

M-706, Sh.

M-707, Sh.

2

M-1239, Sh.

M-1240

M-3121

1

2

2

1

Unit 3 Revision ~~~~~T=i~t=l~e~~~~~~~

E Turbine & Diesel Oil Piping

HH Offgas Piping

pp Standby Gas Treatment

AP H.P. Coolant Injection

v Corrosion Test & Diesel Start-up Air Piping

K Reactor Building Ventilation

p Control Room Office & Drywell Conditioning

N Containment Atmosphere Monitor

AC Atmospheric Containment Atmosphere Dilution

High Radiation Sampling System

High Radiation Sampling

6 High Radiation Sampling

4 High Radiation Sampling

2 Control Room HVAC

• FIELD

PUMP EPN

DESCRIPTION

CLS

PID

CORD

SPEED

• INLET PRESS

DIFF PRESS

FLOW RATE

VIBS

BEAR TEMP

TEST SCHED

REMARKS

• 1305a/9

Pump Format Legend Page 1 of 1 Dresden IST Program, Rev. 3 July 1, 1989

PUMP FORMAT LEGEND

DESCRIPTION

Pump equipment part number as used on the P&ID. To differentiate between units, the pumpcEPN is prefixed with "2-" or "3-" for units 2 and 3 respectively and with "2/3-" for a pump which is conunon to both units.

Pump word description and name.

1 ASME Section III Code Class 1. 2 ASME Section III Code Class 2. 3 ASME Section III Code Class 3. SR Non ASME Code Class 1, 2 or 3, but is

Safety-related. NSR Non ASME Code Class 1, 2 or 3, and Non

Safety-related.

Piping and Instrumentation Drawing (P&ID) Number. All drawing numbers are prefixed with "M". Sheet numbers follow the drawing number.

Pump location on the P&ID.

Speed of pump to be measured. N/A - Not applicable for pumps that- are either synchronous or- induction motor driven.

Inlet pressure of pump to be measured.

Differential pressure of pump to be measured.

Flow rate of pump to be measured.

Vibration amplitude and velocity of pump to be measured.

Bearing temperature of pump to be measured.

Testing interval of pumps.

Any additional pump description, conunents or DAIM No.

A relief request number is listed in the respective pump parameter field, when a specific ASME Code requirement is determined to be impractical. Relief request numbers are prefixed with "PR" indicating pump relief requests .

• FIELD

VALVE EPN

SIZE

PID

CORD

CLS

CAT

• VALVE TYPE

ACT TYPE

NOR POS

• 1305a/10

Valve Format Legend Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

VALVE FORMAT LEGEND

DESCRIPTION

Valve equipment part number as used on the P&ID and in the IST Program. To differentiate between units, the valve EPN is prefixed with "2-" or "3-'' for units 2 and 3 respectively and with "2/3- "for a valve which is common to both units.

Nominal size of valve in inches.

Piping and Instrumentation Drawing (P&ID) Number. All drawing numbers are prefixed with "M". Sheet numbers follow the drawing number.

Valve location on the P&ID.

1 2 3 SR

NSR

A B c D

BTF CK ERV FCV GA GL RPD RV SCK SV XFC TWV

AO EXP MAN

ASME Section III Code ASME ·section III Code ASME Section III Code Non ASME Code Class Safety-Related. Non ASME Code Class Safety-related.

ASME Valve Category ASME Valve Category ASME Valve Category ASME Valve Category

Butterfly Check Electromatic Relief Flow Control Valve Gate Globe Rupture Diaphragm Relief Stop Check Safety Excess Flow Check Three Way Valve

Air Operated Explosive Actuated Manual

1,

1,

A. B. c. D.

Class 1. Class 2. Class 3.

2, or 3, but is

2 or 3, and Non

MO Motor Operated SA Self Actuated SO Solenoid Operated

0

c

Valve is normally open during power operations (>1% power with mode switch in run) Valve is normally closed during power operations (>1% power with mode switch in run)

• FIELD

STR DIR

A/P

TEST

• TEST SCHED

REL REQ

REMARKS

• 1305a/11

Valve Format Legend Page 2 of 2 Dresden !ST Program Rev. 3 July 1, 1989

VALVE FORMAT LEGEND

DESCRIPTION

0 c

O/C

A

p

AT

BT

Valve stroke exercise is to the Open position Valve stroke exercise is to the Closed position Valve stroke exercise is to both the Open and to the Closed positions

Active valve. This valve is required to change its position to accomplish its safety-related function. Passive valve. This valve is not required to change its position to accomplish its safety-related function.

Valve seat leakage tested per Appendix J of 10 CFR 50 and Dresden Technical Specification Sections 3.7 and 4.7 (Containment Systems). Full stroke exercise which includes measurement of stroke times.

CT-0 Check valve exercise open CT-C Check valve exercise closed RT Safety valve and relief valve test per ASME

IWV-3510. DT FST PIT

OP cs RR

SAM SY

Fire explosive charge. Fail-safe test. Position indication test.

Tested Quarterly during normal operation. Tested during Cold Shutdown. Reactor refueling. For PIT, AT and DT tests, test frequency shall be at least once every 2 years. Sampling Plan Technique 5 Year Interval

A relief request nwnber is listed when a specific ASME Code requirement is determined to be impractical. Relief request numbers are prefixed with "VR" indicating a Valve relief request.

General valve description, comments or DAIM No. as necessary .

•

•

•

SORTED BY: EPH

PlJHP EPH

2-2382

2-3993

213-3993

2A-1182

2A-14e1

211-15&1-44

2A-15G2

28-lt&2

2B-1481

28-1591-44

2B-t5G2

2C-!59t-44

DESCRIPTION

2 HPCI

2 DIESEL COOi.it«;

213 DIESEL COOLING

2A-SBlC

211 CORE SPRAY

2A ccsw

2A LPCI

28-SBLC

2B CORE SPRAY

28 ccsw

28 LPCI

2C CCSW

IST PROGRAM FOR PUHPS DRESDEN UHITS 2 & 3

NRC SUBffITTAL

1e:36 WEDHESDM, ..Ill. Y s , t 98~

PAGE: 1 INLET DIFF FLOW BEAR TEST

CLS PID COOR SPEED PRESS PRESS RATE VIBS TEHP SCHED REMARJ(S

2 51 A5 YES YES YES YES YES PR-2 PR-3

3 22 819 HIA YES YES PR-5 PR-1 PR-2 PR-3

3 355 A19 ff/A YES YES PR-5 PR-1 PR-2 PR-3

2 33 D7 NIA YES YES YES PR-1 PR-2 PR-3

2 27 D9 NIA YES YES YES PR-1 · PR-2 PR-3

3 29 DIG NIA YES YES YES . PR-t PR-2 PR-3

2 29 F7 NIA YES YES YES PR-I PR-2 PR-3

2 33 E7 NIA YES YES YES PR-f PR-2 ·PR-3

2 27 E7 NIA YES YES YES PR-I PR-2. PR-3

3 29 Cl& NIA YES YES YES PR-I PR-2 PR-3

2 29 E7 NIA YES YES YES PR-I PR-2 PR-3

3 29 Bl& NIA YES YES YES PR-1 · PR-2 PR-3

•

•

•

SORTED BY: EPH

PUttP EPN

2C-15G2

2D-15G1-44

2D-15&2

3-2392

3-3993

3A-t192

3A-t591-44

3tH592

3B-i1&2

3B-1461

3B-1591-44

DESCRIPTIOH

2C LPCI

2D ccsw

2D LPCI

3 HPCI

3 DIESEL COOLING

3A SBLC

3A CORE SPRAY

3A ccsw

3A LPCI

3B SBLC

3B CORE SPRAY

38 ccsu

IST PROGRAtt FOR PUllPS DRESDEN UNITS 2 ~ 3

HRC SUBHITTAL

1e:36 llEDHESDA Y, Jll.Y s , 1989

PA~: 2 INLET DIFF FLOW BEAR TEST

CLS PID COOR SPEED PRESS PRESS RATE VIBS TEHP SCHED REMARKS

2 29 E3 NIA YES YES YES PR-1 PR-2 PR-3

3 29 A19 NIA YES YES YES PR-1 PR-2 PR-3

2 29 F3 NIA YES YES YES PR-I PR-2 _ PR-3

2 374 A5 YES YES YES YES YES PR-2 PR-3

3 355 B18 NIA YES YES YES PR-1 PR-2 PR-3

2 364 D7 NIA YES YES YES PR-1 PR-2 PR-3

2 358 E7 NIA YES YES YES PR-t PIM PR-3

3 369 AtO NIA YES YES YES PR-I PR-2 PR-3

2 368 E3 NIA YES YES YES PR-1 PR-2 PR-3

2 364 E7 -NIA YES YES YES PR-1 -PR-2 PR-3

2 358 E9 NIA YES YES YES PR-t PR-2 PR-:"3

3 369 AIO NIA YES YES YES PR-1 PR-2 PR-3

•

•

•

SORTED BY: EPH

. PUttP EPN

3B-1592

3C-1501-44

3C-f 5e2

31>-1501-44

3D-t592

DESCRIPTIOH

JB LPCI

3C LPCI

JD CCSW

3D LPCI

IST PROGRAM FOR PUKPS DRESDEN ~ITS 2 ~ 3

NRC SUBMITTAL

1e:36 WEDHESDA r, JUL v s , 198

PAGE: 3 INLET DIFF FLIHI BEAR TEST

CLS PID COOR SPEED PRESS PRESS RATE VIBS TEMP SCHED REMARKS

2 369 F3 NIA YES YES YES PR-1 PR-2 PR-3

3 36G Cl& NIA YES YES YES PR-1 PR-2 PR-3

2 36& E7 NIA YES YES YES PR-1 PR-2 PR-3

3 36& DI& NIA YES YES YES PR-I PR-2 PR-3

2 36& F7 N/A YES YES YES PR-1 PR-2 PR-3

•

•

•

SORTED BY: EPM

PUMP EPH

2-f9e2-A

2-1962-B

2-5263

2!3-5293

3-1902--A

3-19&2-B

3-52&3

DESt:IUPTIOH

2A FUEL POOL COOLING

2B FUEL POOL COOL IHb

2 DIESEL OIL TRANSFER

2/3 DIESEL OIL TRANSFER

3A FUEL POOL COOLING

3B Ftn POOi.. COOLIMG

3 DIESEL OIL TRAHSFER

IST PROGRAM FOR PUltPS DRESl)EN UHITS 2 ' 3

NRC SUBltITTAl

1 e : 5e llEDHESDA Y, Jt.u s , 1 m

PAbf · I 1Nl£T DIFF FLO\! BEAR TEST

CLS PID COOR SPEED PRESS PRESS RATE VIBS TEMP SCHED REMARKS

~ 31 2£ NIA PR-7 PR-7 YES YES PR-2 PR-3

NSR 31 2f N/A PR-7 PR-7 YES YES PR-2 PIH

SR 41 £6 H/A PR-4 PR-4 PR-4 PR-1 PR-2 PR-3

SR 41 D2 N/A PR-4 PR-4 PR-4 PR-I PR-2 PR-3

NSR 362 2E NIA PR-7 PR-7 YES YES PR-2 PR-3

NSR 362 2f NIA PR-7 PR-7 YES YES PR-2 PR-3

SR 41 B6 NIA PR-4 PR-4 PR-4 PR-t PR-2 PR-3

•

•

•

IST PROGRAM REV 3 DAIM

DESIGNATION

DAIM PUMP INDEX PAGE 1 OF 1 DRESDEN IST PROGRAM REV 3

July 1, 1989

DRESDEN ADDITIONAL INFORMATION/METHODOLOGY INDEX

DESCRIPTION

========================================================================== DA IM-Pl ESTABLISHING ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES

DAIM-P2 DELETED

DAIM-P3 DELETED

DAIM-P4 PUMP INSTRUMENTATION

DAIM-P5 OBSERVING OIL LEVELS ON PUMPS

1305a/12

•

•

•

DAIM-Pl Page 1 of 1 Dresden !ST Program Rev. 3 July 1, 1989

ESTABLISHIN~ ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES DAIM-Pl

1. Description

1.1. This provides additional information/methodology when establishing allowable ranges of inservice test quantities in accordance with ASME Section XI IWP-3210, Allowable Ranges of Inservice Test Quantities.

2. Discussion

2.1. In observing pump !ST data, it is the Station's experience that the ASME Section XI test parameters are subject to a number of conditions that produce data scatter. Data scatter is the apparent mix of data which does not clearly indicate a trend, either increasing or decreasing.

2.2. Specifically, the Flow and Differential Pressure data scatter may exceed the 2% High Value Alert Range or the 3% High Value Required Action Range of ASME Section XI Table IWP-3100-2.

2.3. The Station has investigated probable causes as to the conditions which would produce test results which exceed these upper ASME IST limits and reveals a situation where the complete pump performance was actually better than its established !ST reference values would indicate. A major contributor to data scatter and spurious readings is the cumulative effect of instrument fluctuations and allowable instrument accuracy range(s).

1305a/13

2.3.1. In observing the instrument used to conduct !ST testing, the Station has discovered that instrument fluctuations and allowable instruments accuracy range of ten times are responsible_ for such variations in the measured quantities. The Station has concluded from the pump test data, that these instrument conditions may often times produce quantities which exceed the ASME Section XI Table IWP-3100-2 Upper Limits, when in fact no deterioration in the pump performance can be found and the pump produces acceptable test parameters on subsequent tests without any adjustment (repair or replacement) to the pump.

2.3.2. Past pump test data will be evaluated for each individual pump in the IST program and where appropriate will be assigned new allowable ranges which will be based on a reasonable deviation from the normal data scatter experienced •

•

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DAIM-P4 Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-P4

1. Description

1.1. ASME Section XI Article IWP-4000 Methods of Measurement.

1.2. This DAIM provides additional information regarding Dresden's implementat_ion of the Methods of Measurements of ASME Section XI Article IWP-4000.

2. Discussion

2.1. Instrument accuracy for Pressure, Differential Pressure, and -Flow Rate type instruments are ± 2% of full scale. For temperature and vibration amplitude, the instrument accuracy is ± 5% of full scale.

2.2. The full-scale range of each instrument shall be three times the reference value or less.

2.3. Dresden is actively reviewing the instrumentation that is used to provide measurement of the various pump performance parameters (flow, temperature, vibration amplitude and differential pressure) as referenced in TABLE IWP-3100-1, Inservice Test Quantities. This review consists primarily of:

2.3.1. Verification of calibration (2% or 5% accuracy range); 2.3.2. Verification that full-scale range is within 3 times the

reference value or less; 2.3.3. Instrument location, including pressure tap construction

are being reyiewed and modified, as necessary, to properly meet ASME requirements and provide meaningful !ST methods of measurements.

3. Instrument Location

3.1. Instrument location, including pressure tap construction are being reviewed and modified, as necessary, to properly meet ASME requirements and provide meaningful !ST methods of measurements. Pressure taps are verified that they are located in a section of the flow path that is expected to have reasonably stable flow as close as practical to the pump. Any line valves between inlet and the discharge pressure taps shall be in the open position during the inservice test .

1305a/14

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DAIM-P4 Pa.ge 2 of 2 Dresden IST Program Rev. 3 July 1, 1989

4. Portable Flow Meter

4.1. Dresden will use a portable ultrasonic flow meter which meets or exceeds the ASME accuracy range of IWP-4110 Quality. This meter will allow for verification of current flow meter readings and where current instrumentation is not within the calibration range, it will provide an alternative way to get flow readings without delaying the inservice test. Additionally, the flow meter may be used to verify exercising certain valves where flow, pressure or other positive means of verification is not available.

5. Vibration Readings

5.1. Vibration readings are currently being taken in both mils displacement and velocity using the Technology for Energy Corporation's (TEC) SMART Meter. This equipment, using computer technology, automatically scales to no greater than 3 times the reading to maintain accuracy.

6. Instrument Tolerances

6.1. The effects of tolerance upon specified limits are two foldl. They may allow pump operation outside the specified range without operator knowledge. Or the effects of tolerance may require corrective action to be taken when, in fact, the pump is operating in an acceptable range •

6.2. When the Code tolerance is specified as "of full scale", it means that the percent tolerance at the full-scale point is converted into units (PSI) and is applied a't any point on the scale. The following example is based on one variable, the outlet pressure.

EXAMPLE: 1000 PSI gauge ± 2% tolerance 1000 PSI x 0.02 =

Instrument 20 PSI

Acceptable reading ± 20 PSI anywhere on the scale

Effects at 1/3 scale;

1/3 x 1000 = 333 PSI (reference value) + 20 PSI (tolerance)

353 PSI (High side of ref. value)

353/333 = 1.06 or 6% high reading

6.3. Referencing the Example above, based on a gauge which is 3 times the reference value, the instrument tolerance at the reference value is 6% •

lT.F. Hoyle, Effects of Tolerance On The Results of Section XI Pump Testing, February 11, 1980. 1305a/15

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1. Description

DAIM-PS Page 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

OBSERVING OIL LEVEL ON PUMPS DAIM-P5

1.1. This provides additional information/methodology about observing oil levels as required by ASME Section XI, Table IWP-3100-1.

2. Discussion

2.1. Oil level is observed and verified adequate for all pumps in the IST program which have oil lubricated bearings.

2.2. The Standby Liquid Control, Fuel Pool Cooling, Diesel Oil Transfer and High Pressure Coolant Injection Pumps are the only pumps in the IST program which have oil lubricated bearings.

2.3. The remaining pumps in.the IST program are water lubricated •

1305a/16

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!ST PROGRAM REV 3

REL. REQ DESIGNATION

PUMP RELIEF REQUEST INDEX P~GE 1 OF 1 DRESDEN IST PROGRAM REV 3

July 1, 1989.

DRESDEN PUMP RELIEF REQUEST INDEX

IST PROGRAM REV 2

REL. REQ DESIGNATION DESCRIPTION

----------------------------------------------------------------------------------------------------------------------------------------------------PR-1 PR-Al

PR-2 PR-A2

PR-3 PR-A3

PR-4 PR-P4

PR-5 PR-P5

PR-6 NIA

PR-7 NIA

1305all7

PUMP VIBRATION MEASUREMENT RELIEF FROM MILS DISPLACEMENT TO VELOCITY

PUMP BEARING TEMPERATURE MEASUREMENTS RELIEF TO PERFORM VIBRATION MEASUREMENTS

PUMP INSERVICE TESTING MONTHLY RELIEF TO PERFORM INSERVICE TESTING QUARTERLY

DIESEL OIL TRANSFER PUMP RELIEF FROM INLET PRESSURE AND FLOW RATE MEASUREMENTS

DIESEL GENERATOR COOLING WATER PUMP RELIEF FROM FLOW MEASUREMENT

SBLC PUMP RELIEF FROM RECORDING SUCTION PRESSURE

HPCI PUMP, RELIEF FROM OM-6 VIBRATION LIMITS

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RELIEF REQUEST NO. PR-1

1. Description

PR-1 Page 1 of 2 Dresden !ST Prog;am Rev. 3 July 1, 1989

1.1. Relief from Code pwnp vibration measurement of mils displacement to velocity.

2. AFFECTED CQMPONENT(S)

2.1. Component description:

2.1.1. All pwnps in the program.

3. ASME SECTION XI (S79) TEST REQUIREMENT(S)

3.1. IWP-4500 Vibration

4 •. BASIS FOR RELIEF

4.1. The ASME Code requires measurement of displacement vibration amplitude in mils, thousandths of an inch, every inservice test and bearing temperatures once per year. A far more· informative reading is obtained using vibration velocity equipment because it accounts for both displacement and range of frequency.

4.2. The alternative testing described herein for pump vibration monitoring was developed using ANSI/ASME OM~6 (Draft 11) as a guideline. Pwnp vibration measurements will be obtained and recorded in velocity (inches per second) and are broadband (unfiltered) peak readings. All monitored locations are clearly marked to identify the specific point at which the transducer is to be pla.ced while taking vibration measurements using portable equipment. The readout system and transducers used to take vibration measurements are capable of frequency response in the range of one-third minimum pump speed to at least one-thousand hertz, and they have a minimum accuracy over that range of ± 5%, with the exception of the Standby Liquid Control pumps.

4.2.l The SBLC pumps operate at 250 rpm. The low frequency response range requirement of ASME (1/2 minimum pump shaf~ rotational speed) for these pumps is 2.1 Hz. The current vibration measurement system used at Dresden is the Technology for Energy Corporation's (TEC) SMART Meter. The frequency range of this vibration measuring system (includes the SMART meter, cable and probe) is 2 to lOK Hz. When applying the OM-6 Draft 11 frequency response range criteria (1/3 minimum pump shaft rotational speed), the low frequency response range requirement becomes l.4Hz. Dresden knows of no available equipment which has this low range ability (limited by probe performance) •

1305a/18

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PR-1 Page 2 of 2 Dresden IST Program Rev. 3 July 1, 1989

4.3. Dresden Station proposes an alternate program which is believed to be more comprehensive than that required by ASME Section XI. This program consists of performing the required vibration readings in velocity rather than mils of displacement. The technique of velocity measurement is an industry accepted method which is much more meaningful and sensitive to small changes that are indicative of developing mechanical problems.

4.4. Velocity measurements detect not only high amplitude vibrations that indicate major mechanical problems but also the equally harmful low amplitude - high frequency due to misalignment, imbalance, or bearing wear that usually go undetected by simple displacement measurements.

4.5. All centrifugal pumps in the IST Program will have vibration taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing. Measurement will also be taken in the axial direction on all bearing housings when accessible. Reciprocating pumps will have vibration measurements taken approximately perpendicular to the crankshaft and the line of plunger travel, including the axial direction when accessible on each pump bearing housing.

5 • ALTERNATIVE TEST

5.1. Pump vibration measurements will be taken in vibration velocity (inches/second). The limit for vibration readings will not exceed ANSI/ASME OM-6 (Draft 11) with the exception of the HPCI pumps. The following vibration limits are applicable for all pumps at Dresden Units 2 and 3 with the exception of the HPCI pumps. The vibration limits for the HPCI pumps are specified in Relief Request PR-7.

TABLE PR-1

RANGES OF VIBRATIONS

ALERT RANGE PUMP TYPE LOW HIGH REQUIRED ACTION RANGE

Centrifugal >2.5Vref 6Vref >6Vref

But not >0.325 in/sec But not >0.70 in/sec

Reciprocating >2.5Vref 6Vref

NOTE:

1305a/19

Vref is the reference velocity in inches per second.

Any vibration measurement value below the low alert range is acceptable.

All of Dresden's Centrifugal pumps in the IST Program operate at a speed of greater than 600 rpm.

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1. Description


1.1. Relief from Code pump bearing temperature measurements.

2. AFFECTED COMPONENT(S)


2.1.1. All pumps in the program.

3. ASME SECTION XI (S79) TEST REOUIREMENT(S)

3.1. TABLE IWP-3100-1 Inservice Test Quantities, Bearing Temperature, Tb.

3.2. IWP-3300 Scope of Tests, Bearing temperatures shall be measured during at least one inservice test each year.

4. BASIS FOR RELIEF

4.1. Bearing temperature measurements will not provide significant additional information regarding bearing condition than that already obtained by measuring vibration. Measurement of vibration provides more concise and consistent information with respect to pump and bearing condition. The usage of vibration measurements can provide information as to a change in the balance of rotating parts, misalignment of bearings, worn bearings, changes in internal hydraulic forces and general pump. integrity prior to the condition degrading to the point where the component is jeopardized. Bearing temperature does not always predict such problems.

4.2. An increase in bearing temperature most often does not occur until the bearing has deteriorated to a point where additional pump damage may occur. Bearing temperatures are also affected by the temperatures of the medium being pumped, which could yield misleading results. Vibration readings are not affected by the temperature of the medium being pumped, thus the readings are more consistent.

5 . ALTERNATIVE TEST

5.1. Pump vibration measurements will be taken quarterly •

1305a/20

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1. Description

PR-3 PaEte 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

1.1. Relief from Code pump testing monthly to testing quarterly.



2.1.1. All pumps in the program.

3. ASME SECTION XI (S79) TEST REQUIREMENT{fil

3.1. IWP-3400 Frequency of Inservice Tests

4. BASIS FOR RELIEF

4.1. Changes in hydraulic and mechanical pump parameters will not significantly change over the period of one month because the pumps are primarily run only for operability and remain in a standby mode of operation. Quarterly measurement of these parameters is more than adequate in determining pump degradation.·


5.1. Pump parameters will be measured quarterly •

1305a/21

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1. Description

PR-4 Pagi 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

1.1. Relief from Code method of measurements for pump inlet pressure.

2. AFFECTED CQMPONKNT(S)


Unit-Pump No. Size CLS P&ID/CORD Function

2-5203 1.5" SR 41-2/E6 Diesel Oil Fuel Transfer Pump 2/3-5203 1. 5" " 41-2/D2 " 3-5203 1. 5" " 41-2/B6 "


3.1. IWP-4200 Pressure Measurement

4. BASIS FOR RELIEF

4.1. The Diesel Oil Transfer pumps do not have gauges installed to directly measure suction pressure required by ASME XI.

4.2. Relief is requested from the requirement of measuring pump inlet pressure during pump tests. These pumps are utilized in transferring fuel oil from the diesel generator fuel oil storage tank to the diesel fuel oil day tank. The configuration of the piping is such that the the pump is located above the storage tank. The pump is a positive d1splacement gear type pump not requiring a positive suction head for proper operation. Since this pump is a positive displacement type, the discharge pressure is independent of the suction pressure and, ther~fore, inlet pressure data is not important in evaluating pump performance.

5 . . ALTERNATIVE TEST

5.1. Pump discharge pressure will be set and flow will be measured.

5.2. Vibrations measurements will be recorded in accordance with PR-1 •

1305a/22

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1. Description

PR-5 Page 1 of 2 Dresden rsr Program Rev. 3 July 1, 1989

1.1. Relief from Code method of measurements for pump flow.



Unit-Pump No. Size CLS P&ID/CORD Function

2-3903 8" 2 22/AlO Diesel Generator Cooling Water Pump

2/3-3903 8" 2 355/AB "

3 .... 3903 8" 2 355/AlO II


3.1. IWP-4200 Pressure Measurement

3.2. IWP-4600 Flow Measurement

4. BASIS FOR RELIEF

4.1. The Diesel Generator Cooling Water pump flow instrument is located after the heat exchanger and approximately 400 feet from the pump discharge. This arrangement has led to inaccurate and unstable readings such that relevant inservice testing and trending cannot be performed.

4.2. Dresden has established modification packages nos. Ml2-2-87-54, Ml2-3-87-54, and Ml2-2/3-8-7-21 for pumps 2-3903, 3-3903 and 2/3-3903 respectively. These modifications relocate the flow gauges to a proper location in their respective hydraulic circuits .

1305a/23

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PR-5 Page 2 of 2 Dresden IST Prog~am Rev. 3 July 1, 1989

5.1. Dresden will perform inservice testing and will set differential pressure, measure vibration and observe flow. No trending of flow readings will be made; however, determination of flow for the Diesel Generator Cooling Water pump will be performed by verification of proper cooling of the Diesel Generator. Proper cooling is determined by monitoring the inlet and outlet temperature and pressure of the diesel generator cooling water, verifying they are within the allowable ranges as specified in monthly surveillance p~ocedure DOS 6600-1.

5.2. Upon successful completion of the modifications, flow measµrements will be performed and trended in accordance with ASME Section XI. At that time, this relief request will be deleted .

1305a/24

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PR-6 Paie 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

1 . Description

2.

3.

4.

1.1. Relief is requested from measuring suction pressure on the Standby Liquid Control (SBLC) pumps.

AFFECTED CQMPONENT(S)

P·ump EPN Size CLS P&ID/CORD Function

2A-1102 1. 5" 2 33/D7 Standby Liquid Control Pump

2B-1102 1.5" 2 33/E7 Standby Liquid Control Pump

3A-1102 1. 5" 2 364/D? Standby Liquid Control Pump

3B-l102 1. 5" 2 364/E? Standby Liquid Control Pump

ASME SECTION XI (S79) TEST REQUIR.EMENT(S)

3 .1. Table IWP-3100-1, Inservice Test Quantities, Inlet Pressure, Pi.

3.2. IWP-3110, Reference Values

3.3. IWP-3300, Scope of Tests

BASIS FOR RELIEF

4.1. In the test mode, the SBLC pumps pump water from a test tank through a closed loop back to the test tank. The level of the test tank is verified prior to each test. The tank is less than 5 feet high and therefore the maximum pressure developed by this head is less than 2 psig. The SBLC pumps take their suction from the bottom of .the tank and therefore the suction pressure cannot exceed 2 psig.

4.2. The discharge pressure for the test is set at 1275 psig. The discharge pressure gauge reads in 10 psig increments. Two psig is not readable on this gauge and therefore the suction pressure is insignificant in this case.

4.3. Also, since the reference suction pressure is approximately 1.3 psi, an extremely accurate and sensitive pressure gauge is needed to meet the code requirements of having the full scale reading of the gauge be less than three times the reference value. This type of gauge becomes unreadable due to the reciprocating action of the positive displacement SBLC pumps .

1305a/25

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PR-6 Paige 2 of 2 Dresden IST Program Rev. 3 July 1, 1989

4.4. Since the tank level is verified prior to testing, the only way to lose suction pressure would be either if the suction line became plugged or if there was a line break in the test piping. In either case the 1275 psig discharge pressure would not be achieved and the test would be terminated and the pump declared inoperable.

4.5. Because of the reasons stated above, the requirements to record suction pressures for these pumps are not practical.


5.1. The level of the test tank will be monitored prior to each inservice test and the discharge pressure will be set at 1275 psig •

1305a/26

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1. Description

PR-7 Paie 1 of 2 Dresden !ST Program Rev. 3 July 1, 1989

1.1. Relief from ANSI/ASME OM-6 (Draft 11) velocity vibration acceptable ranges.


Pump EPN Size CLS P&ID/CORD Function

2-2302 14" 2 51/A5 High Pressure Coolant Injection

3-2302 14" 2 374/A5 High Pressure Coolant Injection

3. ASME SECTION XI (579) TEST REQUIRF.l1ENT(S)

3.1. IWP-4500 Vibration

4. BASIS FOR RELIEF

4.1. During both Unit 2 and Unit 3 outages for 1988, the HPCI pump impellers were replaced with a newly designed impeller. This new impeller has cut the vibration levels in half on both the HPCI main and booster pumps.

4.2. Even though the overall vibration levels are much lower, in some cases the readings exceed the acceptable ranges established by Relief Request PR-1 and therefore ANSI/ASME OM-6.

4.3. The actual reference values and limits are documented in DAP 11-21 Form b, Technical Review of Pump Performance Parameters.

5. ALTERNATIVE TEST

5.1. In reference to the letter dated September 1, 1988, "Safety Evaluation by the Off ice of Nuclear Reactor Regulation Supporting !ST Program Relief Requests, Commonwealth Edison Company, Dresden Nuclear Power Station, Unit Nos. 2 and 3, Docket Nos. 50-237 and 50-249", Section 1.2., Relief Request PR-lA. Inservice Test Procedure, Temperature Measurement, this relief request is being submitted to establish velocity alert and action limits based on the actual pump vibration readings specific to these pumps.

5.2. The new vibration limits, though higher than those placed on the other pumps in the !ST program, are modeled similar to the other limits in the program and are indicative of HPCI pump degradation. The vibration limits for each HPCI pump are listed below •

1305a/27

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Alert Range Low

Unit 2 HPCI

Main Pump Horizontal >l .5Vref to

Main Pump Vertical >l.5Vref to

Booster Pump Horizontal >l.5Vref to

Booster Pump Vertical >l.5Vref to

Unit 3 HPCI

Main Pump Horizontal >1.5Vref to

Main Pump Vertical >l.5Vref to

Booster Pump Horizontal >l.5Vref to

Booster Pump Vertical >l.5Vref to


Required Action Range High

2Vref >2Vref

2Vref >2Vref

2Vref >2Vref

2Vref >2Vref

2Vref >2Vref

2.SVref >2.5Vref

2.SVref >2.SVref

2.SVref >2.SVref

NOTES: Vref is the reference velocity in inches per second.

Any vibration measurement below the alert range is acceptable .

1305a/28

IST PROGRAH FOR VALVES DRESDEN UHITS 2 & 3

NRC: SUBKITTAL

16:32 WEDHESDAY, JULY 5, 1~

• SORTED BY: VALVE EPH PAGE: 1

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VALVE ACT NOR STR TEST REL EPH SIZE PID CORD C:LS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

2-&292-4A

2-e2e2-4B

2-6292-5A

2-&292-SB

2-62e2-7A

2-&262-78

2-e2e2-9A

2-G2&2-9B

2-6263-tA

2-&263-18

2-&263-IC:

28 26-2 5C: t B GA KO 0 0 P H/A

28 26-2 2C t B GA HO 0 0 P NIA

28 26-2 6D 1 ·B GA ltO 0 C A BT CS PIT RR

28 26-2 3C t B GA KO 0 C A BT CS PIT RR

4 26-2 6D t B GA HO C C P NIA

4 26-2 3C t B GA tlO C C P H/A

2 26-2 58 t B GA tlO O/C C A BT OP PIT RR

2 26-2 48 . 1 B GA tlD O/C C A BT OP PIT RR '

26 12-t 4E 1 A Gl AO 0 c A AT RR BT OP FST cs PIT RR

2(l 12-1 4D 1 A GL AO 0 c A AT RR BT OP FST cs PIT RR

20 12-1 4C I A GL AO 0 c A AT RR BT OP FST cs PIT RR

DAIIM5

DAilt-V5

VR-6 DAilt-VI DAIH-V24



TEST: AT-SEAT LEAKAGE TEST; BT-FULL STRIJl(E EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORl1AL OPERATION; CS-COLD SHUTDOWH; RR-REACTOR REFUELING; SAlt-SIVtPLING Pl.AH TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

IST PRO&RAtt FOR VALVES 1&:32 WEDHESDAY, JULY 5, 198' DRESDEN UNITS 2 & 3

NRC SUBHITTAL

• SORTED BY: VALVE EPff PAGE: 2

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHARKS

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2-&2&3-1D 26 12-1 4B I A Gl AO 0 c A AT RR VR-6 DAIH-VI BT OP DAIH-V24 FST cs PIT RR

2-G293-2A 2& 12-2 7F I A Gl AO 0 c A AT RR VR-6 DAIIH1 BT OP DAIH-V24 FST cs PIT RR

2-9293-28 2& 12-2 7E 1 A Gl AO 0 c A AT RR VR-6 DAIK-V1 BT OP DAIH-V24 FST cs PIT RR

2-t293-2C 29 12-2 7D 1 A Gl AO 0 c A AT RR VR-6 DAIK-V1 BT OP DAIH-V24 FST cs PIT RR

2-t293-2D 29 12-2 7C 1 A Gl AO 0 c A AT RR VR-6 DAIK-V1 BT OP DAIH-V24 FST cs

• PIT RR 2-&2&3-3A 6 12-1 7F 1 BC TRV AO/SA C 0 A BT RR VR-3

RT RR VR-4 PIT RR

2-9293-3B 6 12-1 7E 1 BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

2-&2&3-3C 6 12-1 7C 1 BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

2-t2&3-3D 6 12-1 7B t . BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

2-92&3-3E 6 12-1 6E I BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

2-0293-4A 6 12-1 SE I c SY SA c 0 A RT RR VR-2

• . -···-TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

·TEST SCHED: OP-HORHAL OPERATION; CS-COLD SHUTDOWH; RR-REACTOR REFUELING; SAK-SAHPLIHG PLAH TECHNIQUE; 5Y-OHCE EVERY 5 YEARS.

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SORTED BY: VALVE EPN

IST PROGRAM FOR VALVES DRESDEN UNITS 2 & 3

Nll.C SUBltITTAL

VALVE ACT NOR STR TEST RR EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P·TEST SCHED REQ REltARKS

2-92&3-4B 6 f2-1 BE f C SV SA C 0 A RT RR VR-2

2-&2&3-4C 6 f 2-1 BD f C SV SA C 0 A RT RR · VR-2

2-8293-4]) 6 12-t SD 1 C SV SA C 0 A RT RR VR-2

2-&2&3-4E 6 12-1 SC f C SV SA C 0 A RT RR VR-2

2-92&3-4F 6 12-f 8C 1 C SV SA C 0 A RT RR VR-2

2-&293-4G 6 f2-f 88 f C SY SA C 0 A RT RR VR-2

2-92&3-4H 6 12-f SB 1 C SY SA C 0 A RT RR VR-2

2-92&5-2-4 2.5 26-f 6E f A GA HO c O/C A AT RR VR-6 DAIH-VI BT OP PIT RR

2-92&5-27 2.5 26-1 5E 1 AC CK SA c O/C A AT RR VR-6 CT-0 RR VR-f7 CT-C RR

2-9229-1 2 12-f 4E 1 A &l. MO 0 c A AT RR VR-6 DAIH-Vf BT OP PIT RR

2-&22&-17A 9.5 12-2 BE f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

1&:32 WEDNESDAY, JULY 5, 198S

TEST: AT-SEAT LEAKAGE TEST; BT-FULL !TRoKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RRIEF VALVE TEST; DI-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORHAl OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAttPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

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IST PROGRAM FOR VALVES 19:32 WEDHESDAY, JULY 5, 1~ DRESDEN ~ITS 2 & J

NRC SUBMITTAL

SORTED BY: VALVE EPH PAGE: 4

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REltltRKS

----------------------------------------------------------------------------------------------------------------------------------

2-e22e-17B e.5 12-2 SD I AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

'2-&22G-l 7C e.5 12-2 8C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-em-111> e.s · 12-2 SB t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-G22t-t8A 8.5 12-2 8E t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6229-tSB &.5 t2-2 SD t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9228-ISC e.5 12-2 8C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9229-lSD e.s t2-2 SB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&22&-19A &.5 26-2 5B t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&22&-19B &.5 26-2 3B t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&22&-2 2 12-2 7E 1 A GI. l10 0 c A AT RR VR-6 DAI It-Vt BT OP PIT RR

2-G22&-2&A e.s 26-2 SB t AC XFC SA 0 c A AT RR YR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VAL.VE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORHAL OPERATION; CS-COlD SHUTDOWN; RR-REACTOR REFUELIN'; 5Alt-SAl1PLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

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IST PROGRAlt FOR VALVES 16:32 WEDHESDAY, JULY 5, 1~ DRESDEN UNITS 2 & 3

NRC SUBHITTAL

SORTED BY: VALVE EPH PA&E: 5

VALVE ACT HOR STR TEST REL EPH SIZE PID CCJRJ) CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHARKS

----------------------------------------------------------------------------~----,-------------------------------------------------

2-e22e-2&B e.s 26-2 3B 1 AC XFC SA 0 c A AT RR CT-C RR

2-9228-21A 9.S 26-2 BD 1 AC XFC SA 0 c A AT RR CT-C RR

2-i22&-21B e.s 26-2 1D 1 AC XFC SA 0 c A AT RR CT-C RR

" 2-922e-22A 9.S 26-2 BD 1 AC XFC SA 0 c A AT RR

CT-C RR

2-G220-22B 9.S 26-2 1D 1 AC XFC SA 0 c A AT RR CT-C RR

2-9228-44 .75 26-2 2E 1 A bl AO 0 c A AT RR BT OP FST OP PIT RR

2-$22&-45 • 75 26-2 tE 1 A bl AO 0 c A AT RR BT OP FST OP PIT RR

2-9229-S1 e.s 26-t SE t B GL AO c c p NIA

2-9228-S2 e.s 26-t SE 1 B GL AO 0 0 p NIA

2-922&-54 8.S 26-t SE t AC XFC SA 0 C A AT RR CT-C RR

2-9228-SBA 18 14 4£ 1 AC CK SA 0 C A AT RR CT-C RR

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

VR-6

VR-6

VR-6 VR-24

VR-6 VR-21

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-D-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DI-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORl'IAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAlt-SiWLIH& PLAN TECHHIQUE; SY-ONCE EVERY S YEARS.

•

•

•

IST PROGRAM FOR VALVES DRESDEN ~ITS 2 ~ 3

HRC SUBHITTAL

10:32 WEDNESDAY, JULY 5, 1~

SORTED BY: VALVE EPH

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

2-0220-588 19 14

2-&22e-59 18 14

2-e22e-62A 18 14

2-622&-62B 18 14

2-622&-67A e.s 26-2

2-&22e-67B e.5 26-2

2-0229-67C e.5 26-2

2-6229-670 e.5 26-2

2-622&-67E e.5 26-2

2-622&-67F e.5 26-2

2-6229-67G 0.5 26-2

4F 1 AC CK SA 0 C A AT RR CT-C RR

2F 2 C CX SA 0 C A CT-C RR

JE 1 AC CK SA 0 c A AT RR CT-C RR

3f I AC CK SA 0 c A AT RR CT-C RR

5F 1 AC XFC SA 0 c A AT RR CT-C RR



SF 1 AC XFC SA 0 c A AT RR CT-C RR

3f 1 AC XFC SA 0 c A AT RR CT-C RR


3F 1 AC XFC SA 0 c A AT ·RR CT-C RR

VR-6 VR-21

VR-20

VR-6 VR-21

VR-6 VR-21

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

VR-6 VR-24

YR-6 VR-24

VR-6 VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-Fllll STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 6

TEST SCHED: OP-NORHAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAHPLIHG Pl.AH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAH FOR VALVES f6:32 WEDHESDAY, JULY 5, f9S~ DRESDEN UNITS 2 & 3

NRC SUBHITTAL

SORTED BY: VALVE EPH PA~: 7

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl!ARKS

------------------------------~---------~-----------------------------------------------------------------------------------------

2-e22e-67H e.s 26-2 3F 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-G262-25A e.s 26-2 7B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-0262-25B e.s 26-2 2B t AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-i262-26A e.s 26-2 7B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-6262-268 e.5 26-2. 2B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-9263-2-11 e.s 26-1 SE 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-9263-2-tJA e.s 26-1 5D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-i26J-2-13B e.s 26-1 3D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-&26J-2-15A e.s 26-1 SD 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-0263-2-158 e.s 26-1 3D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-926J-2-17A e.5 26-1 SD f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FUll StltiJKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VAL.VE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE-TEST; PIT-POSITION INDICATOR CHECK.

'TEST SOIED: OP-HORltAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAtlPLIHG Pl.AH TECHNIQUE; SY-ma: EVERY s YEARS.

' i

IST PROGRAM FOR VALVES DRESDEN UHITS 2 ~ 3

NRC SUBKITTAL

19:32 WEDHESDAY, JULY 5, 198<

• SORTED BY: VAL VE EPH PAt;E: 8

•

•

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

2-9263-2-17B 6.5 26-t 3D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-t9A e.s 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-198 9.S 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-2&A e.s 26-t SB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&263-2-2eB e.s 26-1 SB 1- AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-2&c e.s 26-1 JB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-2eD &.5 26-1 3B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-23A e.s 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-23B G.S 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-23C 9.S 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-6263-2-23» e.s 26-1 3C 1 AC XFC SA ·O c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAtt-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY S YEARS.

•

•

•

IST PROGRAM FOR VALVES 1&:32 llEDHESDAY I JULY 5, 1981

DRESD£N UNITS 2 & J NRC SUBKITTAL

StlRTED BY: VALVE EPtf PAGE: 9

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHE:D REQ REMARKS

----------------------------------------------------------------------------------------------------------------------------------

2-9263-2-25 e.5 26-1 5B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9263-2-27 e.5 26-t 5B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9263-2-ltB e.5 26-1 5C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-G263-2-3tC e.5 26-t 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&263-2-311) e.5 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-G263-2-3tE e.5 26-1 5C 1 AC XFc' SA 0 c A AT RR VR-6 CT-C RR VR-24

2-8263-2-3tG e.5 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&263-2-3tff e.5 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-G263-2-31J e.s 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

.2-&263-2-3tK e.5 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-0263-2-JtK &.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST;· BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORKAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAtlPLIHG PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES t8:32 WEDHESDAY, JULY 5, 1909 DRESDEN UHITS 2 & 3

NRC SUBHITTAL

SORTED BY: VALVE EPH PAGE: te

VALVE ACT HOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

----------------------------------------------------------------------------------------------------------------------------------\

2-6263-2-JtH e.5 26-1 3C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9263-2-31P 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&263-2-31R 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-&263-2-31T 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-e263-2-3tU 9.5 26-f 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-e263-2-31V 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-9263-2-JHI 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24


2-e263-42A e.5 26-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-e263-42B 9.5 26-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-8361-95 4 34 2D 1 AC CK SA c c p AT RR VR-6

TEST: AT-SEAT LEAKAGE TEST; BT-FULL SfROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-:-POSITION INDICATOR CJfECI(.

TEST SCHED: OP-NORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAtt-SAHPLING PLAH TECHNIQUE; 5Y-OHCE EVERY 5 YEARS~

•

•

•


NRC SUBIUTTAL

H): 32 WEDNESDAY I JUL y s I 198


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHARKS

2-G3e1-98 4 34 2D f AC CK SA C C P AT RR VR-6

2-G392-157A 34 2F 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-&Je2-1m 34 5f 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-G3&2-f 58A 34 2F 2 A GA AO 0 c A AT RR . VR-6 BT OP FST OP PIT RR

2-&3&2-158B 34 5f 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-GJ&2-160A 34 IF 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-&3&2-fb&B 34 6f 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-G3&2-16fA 34 IF 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP

<. PIT RR 2-&3&2-1618 34 6F 2 A GA AO 0 c A AT RR VR-6

BT OP FST OP PIT RR

2-9305-114 e.5 34 9D 2 c CK SA c 0 A CT-0 OP YR-I

2-G3&5-ff5 e.5 34 eE 1 C CK SA 0 C A CT-C CS DAIIH4

TEST: AT-SEAT LEAKAGE TEST; BT-fllll MRBKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 11

TEST SCHED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAtlPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.


NRC SUBMITTAL

1G:32 WEDHESDAY, JULY 5, 1~


•

•

VALVE ACT MOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED . REQ REMARKS

-----~----------------------------------------------------------------------------------------------------------------------------

2-eJGS-129 e.5 34 GD f B GA SO C C P NIA

2-93G5-f2f 8.5 34 &D 1 B GA SO C C P HIA

2-eJGS-t22 e.5 34 &D f B GA SO C C P H/A

2-e3es-t23 e.5 34 9D f B GA SO C C P NIA

2-&JGS-126 e.5 34 8E f B GA AO c 0 A BT OP VR-t FST OP

2-9365-f 27 e.5 34 9D f B GA AO c 0 A BT OP VR-t FST OP

2-93G5-f 38 e.s 34 ec f c CK SA 0 c A CT-C OP

2-9399-544 34 D2 B GA SO C C P NIA

2-t&eHA f6 32 9B t A GA HO c c A AT RR VR-6 DAI1t-V2 BT cs PIT RR

2-tOOf-tB t6 32 9E t A GA HO c c A AT RR VR-6 DAitt-V2 BT cs PIT RR

2-f00f-2A t4 32 BA f A GA HO c c A AT RR VR-6 DAilt-V2 BT cs PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STRDKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECk VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

·TEST SCHED: OP-NORMAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; 5Y-OM:E EVERY 5 YEARS.

•

•

•

IST PROGRAK FOR VALVES 1e:32 WEDNESDAY, JULYS, 198~

DRESDEN ~ITS 2 & 3 NRC SUBHITTAL

SORTED BY: VALVE EPff PAGE: 13

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ RE HARKS

----------------------------------------------------------------------------------------------------------------------------------

2-1001-2B 14 32 ac 1 A GA ti) c c A AT RR VR-6 DAIK-V2 BT cs PIT RR

2-tee1-2c 14 32 8F t A &A MO c c A AT RR VR-6 DAll1-V2 BT cs PIT RR

2-1001-SA 14 32 1E 1 A &A KO c c A AT RR VR-6 DAil'l-V2 BT cs PIT RR

2-1&et-5B 14 32 2E 1 A &A HO c c A AT RR VR-6 DAil'l-V2 BT cs PIT RR

2-fl6H5 1.5 33 3C 1 AC CK SA c O/C A AT RR YR-6 CT-0 RR YR-12 CT-C RR

2-1101-16 1.5 33 4C 1 AC CK SA c O/C A AT RR VR-6 CT-0 RR VR-12 CT-C RR

2-1161-43A 1.5 33 6D 2 c CK SA c 0 A CT-0 OP

2-1101-43B 1.5 33 6E 2 C CK SA C 0 A CT-0 OP

2-1105A 9.5 33 4C 2 C RY SA C 0 A RT SY

2-11e5e e.s 33 4D 2 C RY SA C 0 A RT SY

2-110611 LS 33 4C 2 D &A EXP C 0 A DT SAl1

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION .IMI>ICATOR CHECX.

TEST .SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAKPLING PLAN TECHNIQUE; 5Y-OHC£ EVERY 5 YEARS.

•

•

•

IST PROGRAH FOR VALVES DRESDEN UHITS 2 & 3

NRC SUBIUTTAL

1&:32 WEDNESDAY, JULY 5, 198~

SORTED BY: VALVE EPN PAbE: 14


----------------------------------------------------------------------------------------------------------------------------------

2-11&6B 1.5 33 4C 2 D liA EXP C 0 A DT SAH

2-1201-1 8 3& 3A 1 A GA KO 0 c A AT RR VR-6 DAIK-V1 BT OP PIT RR

2-t20HA 2 30 3A 1 A &L HO O/C C A AT RR VR-6 DAIK-VI BT OP PIT RR

2-1201-158 8 30 SA 2 c CK SA 0 c A CT-C OP

2-1201-2 8 30 3A 1 A GA HO 0 c A AT RR VR-6 DAI!t-V1 BT OP PIT RR

2-1201-3 8 3& 4A 1 A GA ltO c c A AT . RR VR-6 DAIK-Vt BT OP

~ PIT RR

2-13&1-t · . 14 28 9C 1 A GA KO 0 c A AT RR VR-6 DAIK-V1 BT OP PIT RR

2-1301-1& 4 28 3C 3 B GA KO c 0 A BT OP PIT RR

2-1301-11 4 28 JC 3 c CK SA c 0 A CT-0 SAM VR-11

2-13&1-17 .75 28 2A 2 A GL AO 0 c A AT RR VR-6 DAilt-V1 BT OP PIT RR FST OP

2-1391-2 14 28 &B 1 A GA HO 0 c A AT RR VR-6 DAIK-V1 BT OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-D-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORltAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRA!t FOR VALVES 1e:32 WEDHESDAY , JULY s , 199'7 DRESDEN UHITS 2 & 3

NRC SUBHITTAL


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

----------------------------------------------------------------------------------------------------------------------------------

2-13e1-2e .75 28

2-1391-23 &.5 28

2-1381-24 e.5 28

2-1391-29 &.5 28

2-1391-3 12 28

2-1361-38 0.5 28

2-1391-36 4 28

·2-13&1-4 12 28

2-14&2-13A L5 27

2-1462-13B 1.5 27

2-14e2-24A 1e 21

3A 2 A GL AO 0 c A AT RR BT OP PIT RR FST OP

ec 1 AC XFC SA 0 c A AT RR CT-C RR

ec 1 AC XFC SA 0 c A AT RR CT-C RR

SE 1 AC XFC SA 0 c A AT RR CT-C RR

7E 1 A GA HO c O/C A AT RR BT OP PIT RR

SE 1 AC XFC SA 0 c A AT RR CT-C RR

5D 3 c CK SA c O/C A CT-0 SAM CT-C SAM

SE 1 A &A tlO 0 c A AT RR BT OP PIT RR

ec 2 c SCK SA c 0 A CT-0 OP

7D 2 C SCK SA C 0 A CT~O OP

2B 2 A GA HO 0 O/C A AT RR BT OP PIT RR

VR-6 DAI!t-V1

VR-6 VR-24

YR-6 VR-24

VR-6 VR-24

VR-6 l>ADt-V1

YR-6

VR-11

VR-6 l>AIH-VI

VR-6 DAIH-VI

TEST: AT-SEAT LEAKAGE TEST; BT-flll..L STROKE EXERCISE; CT-D-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAMPl.IN& PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 16: 32 WEDHESDAY I JUL y 5 I 19B' DRESDEN UNITS 2 ~ 3

HRC SUBMITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMRKS

-----------------------------------------------------------------------------~----------------------------------------------------

2-1462-248 19 27 58 2 A GA llO 0 O/C A AT RR VR-6 DAIH-VI BT OP PIT RR

2-f4&2-25A te 27 2C f A GA ttO c O/C A AT RR VR-6 DAilt-V2 BT OP DllIH-Vf PIT RR

2-1492-258 I& 27 SC 1 A GA tlO c O/C A . AT RR VR-6 Mllt-V2 BT OP DllIH-V1 PIT RR

2-14G2-28A 2 27 6D 2 c RV SA c 0 A RT SY

2-1462-28B 2 27 9B 2 C RV SA C 0 A RT SY

2-14e2-3A 16 27 7F 2 A GA tlO 0 c A AT RR VR-6 l>Ailf-V1 BT OP PIT RR

2-1492-38 16 27 SF 2 A GA tlO 0 c A AT RR VR-6 l>AIK-Vf BT OP PIT RR

2-1402-31A 0.5 27 3D 1 AC XFC SA o c A AT RR VR-6 CT-C RR VR-24

2-14$2-318 &.5 27 4D 1 AC XFC SA o c A AT RR VR-6 CT-C RR VR-24

2-l.W2-34A .75 27 SD 2 c CK SA 0 c A CT-C SAl1 VR-13

2-1~2-348 .75 27 6D 2 C CK SA 0 C A CT-C SAii VR-13

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAtl-SAtlPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•


NRC SUBMITTAL

10: 32 llEDHESDAY I JULY 5 I 199'


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl!ARKS

2-1482-36A .75 27 8E 2 C SCK SA 0 C A CT-C OP

2-14&2-368 .75 27 6£ 2 C SCK SA 0 C A CT-C OP

2-1482-38A 1.5 27 SB 2 B Gil lfO 0 O/C A BT OP DAiii-Vt PIT RR

2-1492-3SB 1.5 27 7C 2 B GA KO 0 O/C A BT OP DAitl-Vt ,. PIT RR

2-14e2'.'"4A s 27 SB 2 A GL lfO c c A AT RR VR-6 DAitl-Vt BT OP PIT RR

2-1462-4B 8 27 SB 2 A GL lfO c c A AT RR VR-6 DAIK-Vt BT OP PIT RR

2-14&2-BA 12 27 BC 2 c SCK SA c 0 A CT-0 OP

2-1482-BB 12 27 78 2 C SCI< SA C 0 A CT-0 OP

2-14&2-9A 1e 27 3C 1 AC CK SA c O/C A AT RR VR-6 DAIK-Vte CT-0 CS CT-C RR

2-1492-9B t& 27 4C 1 AC CK SA c O/C A AT RR VR-6 DAIK-VIG CT-0 CS CT-C RR

2-15eHA 19 29-2 3B 3 c CK SA c 0 A CT-0 OP

TEST: AT-SEAT LEAKAG~ TEST; BT-FULL -STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: f7

· TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES DRESDEH UNITS 2 & 3

NRC SUBltITTAl

1&:32 WEDNESDAY, JULY 5, 198\



2-1591-IB 10 29-2 3C 3 C CK SA C 0 A CT-0 OP

2-1561-IC 1& 29-2 3E 3 C CK SA C 0 A CT-0 OP

2-1591-ID 1& 29-2 3f 3 C CK SA C 0 A CT-0 OP

2-150HIA iB 29-1 9E 2 B GA KO 0 O/C A BT OP DAIH-VI PIT RR

2-i50H1B 18 29-1 2D 2 B GA KO 0 D/C A BT OP DAIH-V1 PIT RR

2-156H3A 3 29-1 7C 2 B GA KO 0 DIC A BT OP DAIH-V1 PIT RR

2-1501-138 3 29-1 2C 2 B GA KO 0 O/C A BT OP DAIH-Vt PIT RR

2-1501-17A 2 29-1 8C 2 c RY SA c 0 A RT 5Y

2-1501-178 2 29-1 2C 2 C RY SA C 0 A RT 5Y

2-t5GHBA 6 29-1 89 2 A Gt. tlO c O/C A AT RR VR-6 DAilt-Vt BT OP PIT RR

2-15t>H8B 6 29-1 29 2 A &L tlO c O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR

TEST: AT-SEAT LEAKA&E TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION.INDICATOR CHECK.

PAQ:: 18

TEST SCHED: OP-NORltAL OPERATIOH; CS-COLD SHUTJ){)WN; RR-REACTOR REFUELING; SAlt-SAl'IP\.ING PLAN TECHHIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM·FOR VALVES 16:32 WE~SDAY, JULY 5, 198~ DRESDEN ~ITS 2 & 3

NRC SUBHITTAL

SORTED BY: VALVE EPN PAGE: 19


----------------------------------------------------------------------------------------------------------------------------------

2-1591-2GA 14 29-1 7B 2 A GA l'IO c O/C A AT RR VR-6 DAill-V1 BT OP PIT RR

2-t5e1-20B 14 29-1 2B 2 A GA KO c O/C A AT RR VR-6 DAIH-Vt BT OP PIT RR

2-156t-2tA 18 29-t BA 2 B GA KO 0 O/C A BT OP DAiii-Vt PIT RR

2-1591-218 ts 29-t 2A 2 B GA KO 0 O/C A BT OP DAIH-Vt PIT RR

2-15G1-22A 18 29-1 78 t A GA ttO c O/C A AT RR VR-6 DAilt-V2 BT OP DAil1-V1 PIT RR

2-15Gt-22B IB 29-1 3B 1 A GA tlO c O/C A AT RR VR-6 DAIM-V2 BT OP DAil1-V1 PIT RR

2-15Gl-25A 14 29-1 58 1 AC CK SA c O/C A AT RR VR-6 DAIM-V2 CT-0 CS DAil1-V1G CT-C CS PIT RR

2-1591-258 14 29-t 48 1 AC CK SA c O/C A AT RR VR-6 DAIM-V2 CT-0 CS DAIH-Vt& CT-C CS PIT RR

2:-1™-27A 16 29-t 6A 2 A GA KO c O/C A AT RR VR-6 DAIH-VI BT OP PIT RR

2-15&1-27B 16 29-t 6A 2 A GA HO c O/C A AT RR VR-6 DAIH-Vt BT OP PIT RR

2-t5et-28A 16 29-1 3A 2 A GA KO c O/C A AT RR VR-6 DAIH-V1 BT OP PIT RR


TEST SCHED: OP-NORMAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELINb; SAlt-SAl'!PLIHG PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtt FOR VALVES 18:32 WEDHESDAY, JULY 5, f9S9 DRESDEN UHITS 2 & 3

NRC SUBMITTAL


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCffED REQ REMARKS

----------------------------------------------------------------------------------------------------------------------------------

2-159f-28B 16 29-1 3A 2 A GA HO c O/C A AT RR VR-6 DAIH-Vf BT OP PIT RR

2-15&1-32A IB 29-f BD 2 B GA· HO 0 c A BT cs DAIM-V25 PIT RR

2-15et-32B 18 29-1 2D 2 B GA HO 0 - c A BT cs DAIK-V25 PIT RR

2-f 5e1-38A 14 29-t SB 2 A GL HO c O/C A AT RR VR-6 DAIH-VI BT OP PIT RR

2-1581-388 14 29-1 3B 2 A GL HO c O/C A AT RR VR-6 DAIK-Vt BT OP PIT RR

2-15&t-5A 14 29-1 5E 2 A GA t10 0 c A AT RR VR-6 DAIK-VI BT OP PIT RR

2-1591-58 14 29-t 5F 2 A GA HO 0 c A AT RR VR-6 DAIK-Vt BT OP PIT RR

2-t5Gl-5C 14 29-1 4E 2 A GA t10 0 c A AT RR VR-6 DAIK-VI BT OP PIT RR

2-f5ef-5D 14 29-1 4F 2 A GA "° 0 c A AT RR VR-6 DAIK-VI BT OP PIT RR

2-1se1-63A 12 29-t 7E 2 c CK SA c O/C A CT-0 OP CT-C OP

2-15et-63B f 2 29-t 7F 2 c CK SA c O/C A CT-0 OP CT-C OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SA!t-SAtfl.IHG Pl.AH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

••

••

IST PROGRAM FOR VALVES DRESDEN UNITS 2 ~ 3

NRC SUBKITT Al

16:32 WEDHESDAY, JULY 5, 198<


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR AIP TEST SCHED REQ REl1ARKS

2-15&f-63C 12 29-1 2E 2 C CK SA C DIC A CT-0 OP CT-C OP

2-15&t-63D 12 29-f 2F 2 C CK SA C DIC A CT-0 OP CT-C OP

2-f50f-65A 2 29-f 7F 2 C CK SA C 0 A CT-0 OP

2-150t-65B 2 29-t 7E 2 C CK SA C 0 A CT-0 OP

2-f5Gf-65C 2 29-f 2E 2 C CK SA C 0 A CT-0 OP

2-f50f-65D 2 29-f 2F 2 C CK SA C 0 A CT-0 OP

2-150f-66A 2 29-f Sf 2 C SCK SA 0 C A CT-C OP

2-f5&f-66B 2 29-f 2F 2 C SCK SA 0 C A CT-C OP

2-f 58f-67A 2 29-1 BF 2 C CK SA 0 C A CT-C SAM YR-f4

2-f501-67B 2 29-f 2F 2 C CK SA 0 C A CT-C SAM VR-14

2-!599-13A 2 29-f 6E 2 C RY SA C 0 A RT SY

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEff, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INl>ICATOR CHECK.

PAGE: 2f

TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SllH-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

IST PROGRAM FOR VALVES DRESDEN UMITS 2 & 3

HRC SUBKITTAL

10:32 WEDNESDAY I JULY 5, 1981

• SORTED BY: VALVE EPN PAGE: 22

•

•


2-f599-f3B 2 29-1 6£ 2 C RV SA C 0 A RT SY

2-f S99-t3C 2 . 29-f 4E 2 C RV SA C 0 A RT SY

2-f599-13D 2 29-1 4E 2 C RV SA C 0 A RT 5Y

2-2eeHe5 3 39 6F 2 A GA AO c O/C A AT RR BT OP PIT RR FST OP

2-2&&1-3 3 39 4E 2 A GA AO O/C O/C A AT RR BT OP PIT RR FST OP

2-2ee1-s 3 39 4E 2 A GA AO O/C C A AT RR BT OP PIT RR FST OP

2-2l9He 12 SI 4E 2 B Gl HO c c A BT OP PIT RR

2-23&H4 4 51 6C 2 B GL "° c O/C A BT OP PIT RR

2-2391-29 16 51 2E 2 c CK SA c 0 A CT-0 OP

2-23&1-23 1 .5 51 4A 2 C RV SA C 0 A RT 5Y

2-2301-26 • 7S 51 OC t AC XFC SA 0 C A AT RR CT-C RR

VR-6

VR-6

VR-6

VR-6 VR-24

DAilt-VI

DAilt-VI

DAIH-VI


'TEST SCH£D: OP-NORMAL OPERATiotl; CS-COLD SHUTDOWH; RR-REACTOR REFUELING; SAH-SAKPLINli Pl.AH TECHHIQUE; SY-ONCE EVERY S YEARS.

,.

•

•

--

IST PROGRAM FOR VALVES 16:32 WEDHESDAY; JULY 5, 198< DRESDEN lltITS 2 & J

HRC SUBtllTTAL

SORTED BY: VALVE EPff PAbE: 23

VALVE ACT HOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

----------------------------------------------------------------------------------------------------------------------------------

2-2301-27 .75 51 &D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-23&1-28 5t BB 2 B GL AO c 0 A BT OP l>Ail1-V1 PIT RR FST OP

2-23&1-29 5t 9B 2 B GL AO 0 c A BT OP DAitl-Vt PIT RR FST OP

2-23&1-3 IG 5t 9A 2 B GA MO c 0 A BT OP DAIK-Vt PIT RR

2-23&1-lt 51 9A 2 B GL AO c 0 A BT OP PIT RR FST OP

2-2301-32 51 78. 2 B GL so c O/C A BT OP PIT RR FST OP

2-23&t-34 2 51 BD 2 AC CK SA c O/C A AT RR YR-6 DAil1-Vll .CT-0 OP CT-C CS

2-2391-35 16 5t 2E 2 A GA HO c O/C A AT RR VR-6 DAIK-Vt BT OP PIT RR

2-23&t-36 16 5t 9E 2 A GA HO c O/C A AT RR VR-6 l>AIK-Vt BT OP PIT RR

2-23&1-39 16 51 8E 2 c CK SA c O/C A CT-0 SM! VR-t5 CT-C SAM·

2-23&1-4 19 51 9C 1 A GA HO 0 c A AT RR VR-6 DAIK-V1 BT OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STR6KE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORl1AL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

'··

•

•

IST PROGRAM FOR VALVES DRESDEN UHITS 2 & 3

NRC SUBMITTAL

19:32 WEDNESDAY, JULY 5, 198'


VALVE ACT NOR STR TEST REL EPN SIZE . PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

----------------------------------------------------------------------------------------------------------------------------------

2-2391-4& 4 51 . C7 3 AC CK SA C 0 A CT-0 OP

2-2391-45 24 St SB 2 AC CK SA c O/C A AT RR YR-6 DAil1-V1 I CT-0 OP CT-C CS

2-2381-48 4 51 4B 2 B GA HO c 0 A BT OP PIT RR

2-2361-49 4 51 4D 2 B GA HO 0 c A BT OP PIT RR

2-2381-5 19 51 eB I A &A KO 0 C . A AT RR VR-6 DAIH-VI BT OP PIT RR

2-2361-SeA 4 51 4C 2 c CK SA c 0 A CT-0 OP

2-2391-51 4 51 4C 2 c CK SA 0 c A CT-0 OP

2-2381-53 4 51 3C 2 C RY SA C 0 A RT 5Y

2-2391-6 16 51 2F 2 B &A MO O C A BT OP DAIK-VI PIT RR

2-2391-68 . 16 51 7A 2 C RPD SA C 0 A NIA DAIH-V3

2-2381-69 16 51 7A 2 C RPD SA C 0 A N/A DAIH-V3

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VAL.VE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SNl-SAtlPLING Pl.AH TECHNIQUE; 5Y-ONC£ E_VERY 5 YEARS.

••

•

•

IST PROGRAM FOR VALVES 10:32 WEDHESDAY, JULY 5, 1981

DRESDEN UNITS 2 ~ 3 NRC SUBHITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHAAKS

----------------------------------------------------------------------------------------------------------------------------------

2-2301-7 14 51 6E 2 c CK SA c O/C A CT-0 RR VR-22 CT-C RR

2-2301-71 2 51 SD 2 AC SCI( SA c O/C A AT RR YR-6 DAI11-Vt1 CT-0 OP CT-C CS

2-23&1-74 t2 5t SC 2 AC SCK SA c O/C A AT RR YR-6 DAiii-Vt 1 CT-0 OP CT-C CS

2-23&1-75 4 51 4B 2 c CK SA c O/C A CT-& OP CT-C OP

2-23&1-76 2 51 4C 2 c CK SA c O/C A CT-0 OP CT-C OP

2-2361-8 14 51 6E 2 B GA l10 c O/C A BT OP DAHi-Vt PIT RR

2-2301-9 14 51 SE 2 B GA t1f) 0 0 A BT OP PIT RR

2-2354-500 .75 51 6E 2 c CK SA 0 c A CT-C SAM YR-18

2-2354-561 • 75 51 6E 2 C SCIC SA 0 C A CT-C OP

2-2499-lA 0.5 796-1 6D 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2499-18 e.s 106-1 2D 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST;. BT-FULL STROKE EXERCISE; CT-0-CllECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAl1PLING PLAN TECHHIQUE; SY-ONCE EYERY 5 YEARS.

IST PROGRAH FOR VALVES 1&:32 llEDHESDAY, JULY 5, 1984i DRESDEN UHITS 2 ~ 3

NRC SUBKITTAL ". SORTED BY: VALVE EPff PAGE: 26

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST sa!ED REQ REMRKS

----------------------------------------------------------------------------------------------------------------------------------

2-2499-2A e.5 1e6-1 6D 2 A GA 50 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2499-2B 9.5 7&6-t JD 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2499-28A e.5 796-t 7C 2 AC CIC SA 0 c A AT RR VR-6 DAIK-YIB CT-C CS CT-0 OP

2-2499-288 &.5 796-1 2C 2 AC Ck SA n c A AT RR VR-6 DAIK-YtB CT-C CS CT-0 OP

ll

2-2499-3A 6.5 796-t 7B 2 A GA 50 c O/C A AT RR VR-6 BT OP PIT RR

• FST OP 2-2499-38 e.5 796-t 2B 2 A GA 50 c O/C A AT RR VR-6

BT OP PIT RR FST OP

2-2499-4A e.s 7e6-t 6B 2 A GA 50 c O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2499-4B &.5 706-t 3B 2 A GA so c O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2599-f A 1.5 7e7' SC 2 B GL AO c O/C A BT OP DAilt-Vt PIT RR FST OP

2-2599-tB 1.5 767 tC 2 B GL AO c O/C A BT OP PIT RR FST OP

2-2599-2A 767 5C 2 A Gl AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

• TEST: AT-SEAT LEAKAGE TEST; BT-FULL STR()l(E EXERCISE; CT-Cl-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORl'IAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAHPLING Pl.AN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

IST PROGRAM FOR VALVES 1G:32 WEDHESDAY, JULY 5, 190' DRESDEN UNITS 2 ~ 3

NRC SUBHITTAL

·'· SORTED BY: VALVE EPH PAGE: 27


----------------------------------------------------------------------------------------------------------------------------------

2-2599-28 787 4C 2 A Gl AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2599-22 t .s 797 611 2 c CK SA c O/C A CT-0 OP DAI1t-Yt3 CT-C CS

2-2599-23A 797 6C 2 AC CK SA c O/C A AT RR VR-6 DAIH-Vt9 CT-0 OP CT-C CS

2-2599-238 797 3C 2 AC CK SA c O/C A AT RR VR-6 DAIH-Vt9 CT-0 OP CT-C CS

2-2599-24A 797 6C 2 AC CK . SA c O/C A AT RR VR-6 DAIH-Yt9 CT-0 OP CT-C CS

• 2-2599-248 797 3C 2 AC CK SA c O/C A AT RR VR-6 DAIH-Yt9 CT-0 OP CT-C CS

2-2599-26A e.5 797 4D 2 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

2-2599-268 0.5 7&7 3D 2 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

2-2599-JA 707 6C 2 A Gt AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2599-38 797 3C 2 A Gt. AO c O/C A AT RR VR-6 BT OP PIT RR

· FST OP 2-2599-4A e.5 101 3F 2 A GL AO c O/C A AT RR VR-6

BT OP PIT RR FST OP

• TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

·TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAit-SAMPLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

••

•

•

IST PROGRAl1 FOR VALVES 19:32 WEDNESDAY, JIJLY 5, 198< DRESDEN ~ITS 2 & 3

NRC SUBHITTAL


VAL.VE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

--------~-------------------------------------------------------------------------------------------------------------------------

2-2599-4B e.s 797 3E 2 A GL AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

2-2599-5A e.5 7&7 5F 2 B ·GL AO c O/C A BT OP PIT RR FST OP

2-2599-58 e.5 7&7 5£ 2 B GL AO c O/C A BT OP PIT RR FST OP

2-3792 6 2& 38 2 A GA HO 0 c A AT RR DAitt-V23 BT cs PIT RR

2-3763 6 29 18 2 A GA HO 0 c A AT RR DAIH-V23 BT cs PIT RR

2-37e6 6 2e 1B 2 A GA l10 0 c A AT RR VR-6 DAIK-V23 BT cs PIT RR

2-393&-5et 8 22 GB 3 c CK SA c 0 A CT-0 OP

2-3999-252 4 22 7B 3 C CK SA 0 C A CT-C OP

2-3999-253 4 22 SB 3 C CK SA C 0 A CT-0 OP

2-3999-336 29-2 4C 3 C CK SA 0 C A CT-C OP

2-3999-338 29-2 . 4E 3 C CK SA 0 C A CT-C OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VAL.VE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION.INDICATOR CHECK.

TEST SCHED: OP-HORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; 5Y-OHCE EVERY 5 YEARS.

J IST PROGRAM FOR VALVES

DRESDEN UNITS 2 & 3 MRC SUBMITTAL


• SORTED BY: VALVE EPH PAbE: '29

VALVE ACT HOR. STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

2-4167-5$1 4 28 5C 3 C CK SA C 0 A CT-0 ~ VR-11

2-4899-72 39 6E 2 C RV SA C 0 A RT SY

2-4899-77 39 5E 3 C RV SA C 0 A RT SY

2-4899-78 39 5E 2 C RV SA C 0 A RT SY

2-4899-79 39 6E 3 C RV SA C 0 A RT 5Y

• 2/3-3899-2&6 2.5 3121 2B 3 C CK SA C 0 A CT-0 OP

•

2/3-393&-591 8 355 SA 3 C CK SA C 0 A CT-0 OP

2/3-3999-336 3 3121 2B 3 C CK SA C 0 A CT-0 OP

2/3-5741-962 2.5 3121 3B 3 B GL AO O/C 0 A BT OP FST OP

2/3-5741-35 2.5 3121 D7 3 B GL AO c 0 A BT OP FST OP

2/3-5741-48A 2.5 3f 2f 2A 3 B GA AO O/C 0 A BT OP FST OP


TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOllH; RR-REACTOR REFUELING; SAll-SA11PLIHG Pl.AH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

IST PROGRAi'f FOR VALVES DRESDEN UHITS 2 & 3

HRC SUBKITTAL

19:32 WEDHESDAY, JULY 5, 1995

• SORTED BY: VALVE EPH PA~: 3e

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE. POS DIR A/P TEST SCHED REQ REl'IARKS

2/3-574f-48B 3 3t2f 2B 3 B GA AO O/C C A BT OP FST OP

3-&262-4A 28 357-2 6D 1 B GA HO 0 0 P NIA

3-&2e2-4B 28 357-2 2C 1 B GA HO 0 0 P N/A

3-&2e2-5A 28 357-2 6D f B GA HO 0 c A BT cs I DAilt-V5 PIT RR

3-9292-SB 28 357-2 3C 1 B GA l10 0 c A BT cs DAI1t-V5 PIT RR

• 3-&2Q3-fA 2e 345-t 4E f A Gt AO 0 c A AT RR VR-6 DAilt-Vt BT OP DAilt-V24 FST cs PIT RR

3-6283-18 28 345-1 4D t A Gt AO 0 c A AT RR VR-6 DAI It-Vt BT OP DAIK-V24 f ST cs PIT RR

3-92&3-tC 2e 345-t 4C I A Gt AO 0 c A AT RR VR-6 DAilt-Vt BT OP DAitt-V24 f ST CS PIT RR

3-6283-t]) 29 345-1 4B t A Gt AO 0 c A AT RR VR-6 DAIIHI BT OP DAIK-V24 f ST CS PIT RR

3-92&3-2A 2e 345-2 7f t A Gt AO 0 c A AT RR VR-6 DAilt-Vt BT OP DAIK-V24 FST CS PIT RR.

3-6293-28 2e 345-2 7E t A Gt AO 0 c A AT RR VR-6 DAilt-VI BT OP DAIK-V24 FST CS PIT RR

• TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CHI-CHECK VALVE EXERCISE OPElf, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

TEST SCHED: OP-HORttAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAtl-SAl'IPLIHG PLAH TECHNIQUE; SY-ONCE EVERY 5 .YEARS.

•

•

•

IST PROGRAM FOR VALVES 19:32 WEDHESDAY, JULYS, t~ DRESDEN UHITS 2 & 3

NRC SUBMITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ RE11MKS

--------------------------------------------------------------------------------------------------------------~--------------~----

3-92$3-2C 29 345-2 7D 1 A Gl AO 0 c A AT RR VR-6 DAil1-V1 BT OP DAIIH24 FST cs PIT RR

3-92&3-2D 2e 345-2 7C 1 A Gl AO 0 c A AT RR VR-6 DAilf-V1 BT OP DAIH-V24 FST cs PIT RR

3-i283-3A 6 345-t 7F 1 BC TRV AO/SA C 0 A BT RR · VR-3 RT RR VR-4 PIT RR

3-6293-JB 6 345-1 7E 1 BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

3-i283-3C 6 345-1 7C t BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

3-92&3-3D 6 345-t 7B 1 . BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

3-6293-JE 6 345-t 6E t BC ERV so c 0 A BT RR VR-3 RT RR VR-4 PIT RR

3-G293-4A 6 345-t 8E t c SY SA c 0 A RT RR VR-2

3-9293-4B 6 345-t 8E 1 C SV SA C 0 A RT RR VR-2

3-G2e3-4C 6 345-1 BD 1 C SY SA C 0 A RT RR VR-2

3-&2e3-4D 6 345-t SD 1 C SV SA C 0 A RT RR VR-2

TEST: AT-SEAT LEAKAGE TEST; BT-FUU STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HDRltAL OPERATIOH; CS-COLD SHUTOOVN; RR-REACTOR REFUELING; SM-SAMPLING PLAN TECHHIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtt FOR VALVES DRESDEN UNITS 2 & 3

NRC SUBMITTAL



VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYP£ POS DIR A/P TEST SCHED REQ REMARKS

3-G2$3-4E 6 345-f 8C 1 C SV SA C 0 A RT RR VR-2

3-9203-4F 6 345-1 BC f C SV SA C 0 A RT RR VR-2

3-G2$3-4G 6 345-f SB f C SV SA C 0 A RT RR VR-2

3-$203-4H 6 345-f 88 f C SV SA C 0 A RT RR VR-2

3-0205-2-4 2.5 357-f 6E 1 A GA "° c O/C A AT RR VR-6 DAitf-Vf BT OP PIT RR

3-0265-27 2.5 357-f 5E f AC CK SA c O/C A AT RR VR-6 CT-0 RR VR-17 CT-C RR

3-0220-f 2 345-f 4E f A GL KO 0 c A AT RR VR-6 DAil1-Vf BT OP PIT RR

3-9229-HA &.5 345-2 SE f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&226-f 7B e.5 345-2 BD 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

I

3-022!H7C 0.5 345-2 SC f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&22&-f7D 0.5 345-2 SB f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST;· BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VAL.VE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 32

'TEST SCH£»: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAtlPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 10:32 WEDHESDAY, JULY 5, 198' DRESDEN UNITS 2 & 3

HRC SIJBHITTAL



----------------------------------------------------------------------------------------------------------------------------------

3-0WHBA e.s 345-2 BE 1 AC Xf C SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&220-1BB e.s 345-2 SD 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-G22e-18C 0.5 345-2 SC 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-922e-1SD e.s 345-2 SB 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-G22e-19A 0.5 357-2 5B 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-022e-19B 0.5 357-2 3B AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-0229-2 2 345-2 7E 1 A Gt. HO 0 c A AT RR VR-6 DAilf-Vt BT OP PIT RR

3-0220-29A e.5 357-2 SB 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-0220-298 0.5 357-2 3B 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-em-21A &.5 357-2 SD 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&229-21B 0.5 357-2 1D 1 AC xrc SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL S'fR6KE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtl FOR VALVES 10:32 llEDHESDAY, JULY 5, 1985 DRESDEN l»fITS 2 & 3

HRC SUBMITTAL



----------------------------------------~---------------------------------------------------------------------------------~-------

3-G22G-22A e.s 357-2 SD t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-622&-22B &.5 357-2 tD t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9229-44 .75· 357-2 2E 1, A Gt AO 0 c A AT RR YR-6 BT OP FST OP PIT RR

3-622&-45 .75 357-2 IE 1 A Gl AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

3-9229-51 e.s 357-1 5E t B GL AO c c p NIA

3-9229-54 e.5 357-1 5E t AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-0226-SSA 18 347 4£ 1 AC CK SA 0 c A AT RR VR-6 CT-C RR VR-21

3-622&-588 18 347 4f 1 AC CK SA 0 c A AT RR YR-6 CT-C RR VR-21

Hl220-59 18 347 2F 2 c CK SA 0 c A CT-C RR VR-2G

3-622&-62A 18 347 3E 1 AC CK SA . 0 C A AT RR VR-6 CT-C RR VR-21

3-&22&-62B 18 347 3f I AC CK SA 0 C A AT RR VR-6 CT-C RR VR-21

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORHAL OPERATIOH; CS-COLD SHUTDOWH; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 19:32 WEDHESDAY, JULY 5, DRESDEN llffITS 2 & 3

MRC SUBHITTAL



----------------------------------------------------------------------------------------------------------------------------------

3-9229-67A e.s 357-2 5F f AC XFC Sii 0 c A AT RR VR-6 CT-C RR VR-24

3-6228-67B e.s 357-2 5F 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-922e-67C e.s 357-2 5F 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-822&-67D 9.5 357-2 SF 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-822&-67E 9.5 357-2 3F t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-8229-67F 9.5 357-2 3F 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-9229-67G 9.5 357-2 3F t AC XFC SA 0 c A . AT RR YR-6 CT-C RR VR-24

3-9229-67H 9.5 357-2 3F 1 AC XFC SA 0 c A AT RR YR-6 CT-C RR VR-24

3-&262-25A 9.5 357-2 7B AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9262-258 9.5 357-2 2B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&262-26A 9.5 357-2 78 t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPlOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORKAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAl'l-SAffPLING Pl.AH TECHHIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•


NRC SUBHITTAL

10:32 WEDHESDAY, JULY 5, 199'

SORTED BY: VALVE EPff

VALVE ACT NOR STR TEST Ra EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHE:D REQ REl'IARKS

J-9262-268 e.5 357-2 2B f AC Xf C SA 0 c A AT RR VR-6 CT-C RR VR-24

J-G263-2-f1 e.5 357-1 SE 1 AC Xf C SA 0 c A AT RR VR-6 CT-C RR VR-24

J-G263-2-13A &.5 357-1 5D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-G26J-2-t3B &.5 357-1 JD 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

H>26J-2-15A &.5 357-1 5D t AC Xf C SA 0 c A AT RR VR-6 CT-C RR VR-24

J-&263-2-158 &.5 357-1 JD 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-&26J-2-17A &.5 357-1 5D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-&263-2-17B &.5 J57-t 3D t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-626J-2-19A e.5 357-t 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-G263-2-t9B e.5 357-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

J-9263-2-2&1\ e.5 351-1 SB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKA&E TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 36

TEST SCHEI>: OP-HOIUIAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAii-SAMPLING PLAN TECHNIQUE; 5Y-OhtE EVERY 5 YEARS.

•

•

•

"IST PROGRMI FOR VALVES DRESDEN UHITS 2 & 3

NRC SUBttITTAL




3-G263-2-29B e.5 351-1 5B f AC lxrc SA 0 c A AT RR VR-6 CT-C RR VR-24

3-G263-2-20C e.5 357-f JB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-2-2&D e.5 351-1 JB 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-2-23A e.5 357-1 5C 1 AC XFC . SA 0 c A AT RR VR-6 CT-C RR VR-24

3-G263-2-2JB e.5 357-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-2-23C e.5 357-1 3C 1 AC XFC SA 0 c A AT RR . VR-6 CT-C RR VR-24

3-G263-2-2JD e.5 351-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-0263-2-25 e.5 357-f 5B 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-0263-2-27 e.s 357-f 58 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-G263-2-31B e.5 357-1 5C 1 AC XFC SA 0 c A AT "RR VR-6 CT-C RR VR-24

3-0263-2-JtC e.s 357-t 5C f AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 37

TEST SCHED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAM-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

--~-------- -----

•

•

•

IST PROGRA" FOR VALVES DRESDEN UHITS 2 ~ 3

HRC SUBHITTAL

16:32 WEDHESDAY, JULY 5, 198'



3-0263-2-31D e.s 357-1 SC 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-31E e.s 357-1 5C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-2-31G e.s 357-1 SC 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-31H e.5 351-1 SC 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-G263-2-31J e.5 357-1 SC 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-31K e.s 357-1 SC 1 AC XFC SA 0 c A AT RR VR-6 cT-c RR VR-24

3-&263-2-31H &.5 357-1 3C 1 AC XFC SA 0 c A AT RR VR-6 cT-c RR VR-24

3-&263-2-31H fl.S 357-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-31P e.s 3S7-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-31R e.s 3S7-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-fl26J-2-3H e.s 357-1 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION. INDICATOR CHECK.

PA&E: 38

TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

IST PROGRAM FOR VALVES DRESDEN ~ITS 2 ~ 3

HRC SUBttITTAL


• SORTED BY: VALVE EPN PAGE: 39

•

•


----------------------------------------------------------------------------------------------------------------------------------

3-9263-2-3tU 9.5 357-t 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-2-3f V e.5 351-1 3C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-&263-2-3f W e.5 357-t 3C 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24


3-9263-42A e.5 357-1 5C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-42B e.5 357-1 3C t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-9263-52 e.5 351-1 5E 1 B GL AO 0 0 p N/A

3-93e2-156A 365 5F 2 A f;A AO 0 c A AT · RR VR-6 BT OP FST OP PIT RR

3-&392-156B f 365 2F 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

3-93e2-157A 365 2F 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

3-0362-1578 365 5F 2 A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: DP-HORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAff-SAtlPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

IST PROGIWI FllRVALVES DRESDEN UNITS 2 & J

HRC SUBHl TT Al

16:32 WEDNESDAY, JULY 5, 1985

• SORTED BY: VALVE EPff PAGE: 49

•

•

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHARKS

3-G382-158A 3 365 2F 2 . C RV SA C D A RT 5Y

3-&362-158B 3 365 5F 2 C RV SA C D A RT 5Y

3-9392-168A 365 ff 2 A GA AO D c A AT RR VR-6 BT OP FST OP PIT RR

3-8382-168B 365 bf 2 A GA AO 0 c A AT RR VR-6 BT OP FST DP PIT RR

3-93&2-161A 365 ff 2 A GA AO D c A AT RR VR-6 BT DP FST DP PIT RR

3-&Je2-16tB 365 6F 2 A GA AO 0 c A AT RR VR-6 BT DP FST OP PIT RR

3-e3G5-114 e.5 365 9D 2 c CK SA c D A CT-0 DP VR-1

3-8385-U5 0.5 365 eE t C CK SA 0 C A CT-C CS DAIH-V4

3-8305-120 &.5 365 GD 1 B GA SO C C P NIA

3-9385-121 8.5 365 GD 1 B GA SO C C · P It/A

·3-&305-122 &.5 365 OD t B GA SO C C P NIA

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLIHG PLAH TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•


IST PROGRAM FOR VALVES DRESDEN UNITS 2 & J

NllC SUBHITTAI..

VAL VE ACT . NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REHARKS

3-9395-123 &.5 365 &D 1 B GA SO C C P H/A

3-9395-126 9.5 365 GE 1 B GA AO C 0 A BT OP VR-1 FST OP

3-&3e5-t27 e.5 365 9D t B GA AO c 0 A BT OP VR-1 FST OP

3-&395-t38 9.5 365 ec 1 c CK SA 0 c A CT-C OP

3-te&HA 16 363 9B 1 A GA liO c c p AT RR VR-6 DAIIH2 BT cs PIT RR

3-tOOHB 16 363 9E t A GA ti{) c c p AT RR YR-6 DAIH-V2 BT cs PIT RR

3-100t-2A 14 363 8A t A GA ti{) c c p AT RR YR-6 DAitt-V2 BT cs PIT RR

3-1091-28 14 363 BC t A GA ti{) c c p AT RR YR-6 DAitl-Y2 BT cs PIT RR

3-1001-2C 14 363 SF t A GA HO c c p AT RR VR-6 DAitl-Y2 BT cs PIT RR

3-1001-5A 14 363 IE t A GA ltO c c p AT RR YR-6 DAilt-V2 BT cs PIT RR

3-1001-58 14 363 2E t A GA HO c c p AT RR YR-6 DAitl-Y2 BT cs PIT RR

10:32 WE:DNESDAY, JULY 5, !98'

PAGE: 41

TEST: AT-SEAT LEAKAGE TESTi BT-FULL STROl(E EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION IHDICATOR CHECK.

TEST SCHED: OP-NORHAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUEL!~; SAff-SAt1PLING PL.AH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAH FOR VALVES DRESDEN UHITS 2 ~ 3

NRC SUBHITTAL



VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE . POS DIR A/P TEST SCHED REQ REMARKS

3-119H5 1.5 364 3C t AC CK SA c O/C A AT RR VR-6 CT-0 RR VR-12 CT-C RR

3-1191-16 t.5 364 4C 1 AC CK SA c O/C A AT RR VR-6 CT-0 RR VR-12 CT-C RR

3-11&1-43A I .5 364 6D 2 c CK SA c 0 A CT-0 OP

3-11&t-43B 1.5 364 6E 2 C CK SA C O A CT-0 OP

3-11e5A e.s 364 4C 2 c RV SA ' c a A RT 5Y

3-t195B e.5 364 4D 2 C RV SA C 0 A RT SY

3-1196A t.5 364 4C 2 D GA EXP C 0 A DT SAl1

3-t !e6B t.5 364 4C 2 D GA EXP C 0 A DT SAM

3-12&1-t 8 361 3A 1 A GA MO 0 c A AT RR VR-6 DAIK-Vl BT OP PIT RR

3-1291-tA 2 361 JA t A GL HO O/C C A AT RR VR-6 DAitl-Vl BT OP PIT RR

3-12&1-158 8 361 SA 2 c CK SA 0 c A CT-C OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-c:HECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIV£ VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK •

PAGE: 42

. TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAHPLINb PLAN TECHNIQUE; 5Y-OHCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 19:32 WEDNESDAY, JULY 5, 1985 DRESDEN UHITS 2 & 3

NRC SUBKITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl1ARKS

----------------------------------------------------------------------------------------------------------------------------------

3-12e1-2 8 361 3A 1 A &A lfO 0 c A AT RR VR-6 DAUH1 BT OP PIT RR

3-12e1-3 8 361 4A 1 A &A lfO c c A AT RR VR-6 DAilt-VI BT OP PIT RR

3-1391-t 14 359 9C I A GA llO 0 c A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-1301-1& 4 359 3C 3 B GA MO c 0 A BT OP DAilt-Vt PIT RR

3-13&HI 4 359 3C 3· c CK SA c 0 A CT-0 SAK VR-11

3-1391-17 .75 359 2A 2 A &l AO 0 c A AT RR VR-6 DAUt-VI BT OP PIT RR FST OP

3-1391-2 14 359 9B t A GA HO 0 c A AT RR VR-6 DAI It-Vt BT OP PIT RR

3-1391-29 .75 359 3A 2 A &l AO 0 c A AT RR VR-6 DAilt-Vt BT OP PIT RR FST OP

3-1301-23 0.5 359 ec t AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-1391-24 9.5 359 9C AC XFC SA 0 c A AT RR YR-6 CT-C RR VR-24

3-1391-29 9.5 359 BE I AC XFC SA. 0 c A AT RR YR-6 CT-C RR VR-24

TEST: AT-SEAT LEAKA&E TESTi BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION.INDICATOR CHECK.

TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•


HRC SUBMITTAL

le: 32 WEDNESDAY I JUL y 5 I 198'


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

----------------------------------------------------------------------------------------------------------------------------------

3-fJOf-3

3-1361-30

:H301-36

3-IJet-4

·J-t4&2-13A

f2 359 7E 1 A GA KO C O/C A AT RR BT OP PIT RR

0.5 359 SE f AC XFC SA 0 C A AT RR CT-C RR

4 359 5D 3 c CK SA c O/C A CT-0 SAM CT-C SAM

12 359 SE 1 A GA KO 0 c A AT RR BT OP PIT RR

1.5 358 ec 2 c SCK SA c 0 A CT-0 OP

3-14&2-13B t.5 358 7D 2 C SCI< SA C 0 A CT-0 OP

3-14&2-24A 19 358 28 2 A GA HO 0 O/C A AT RR BT OP PIT RR

3-1462-248 H> 358 58 2 A GA HO 0 O/C A AT RR BT OP PIT RR

3-f492-25A 10 358 2C 1 A GA HO c O/C A AT RR BT OP PIT RR

3-f462-25B 19 358 5C 1 A GA HO c O/C A AT RR BT OP PIT RR

3-t402-28A 2 358 6D 2 c RV SA c 0 A RT 5Y

VR-6 DAilt-Vf

VR-6 VR-24

VR-11

VR-6

VR-6

VR-6

VR-6

VR-6

DAilf-V1

DAIK-VI

DAIK-VI

DAIK-Vt DAitt-V2

DAIK-VI DAitt-V2

TEST: AT-SEAT LEAKAGE TESTi BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORttAL OPERATION; CS-COLD SHUTDOtlN; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.


NRC SUBMITTAL



•

•

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED. REQ REllARKS

3-t482-28B 2 358 9B 2 C RV SA C 0 A RT 5Y

3-t4&2-3A 16 358 7f 2 A &A lfO 0 c A AT RR VR-6 DAiii-Vt BT OP PIT RR

3-14&2-3B 16 358 5f 2 A &A lfO 0 c A AT RR VR-6 DAIH-V1 BT OP PIT RR

3-14G2-31A 0.5 358 3D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-14&2-31B e.5 358 4D 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-t492-34A .75 358 91) 2 c CK SA 0 c A CT-C SAit VR-13

3.:.14&2-34B • 75 358 6D 2 c CK SA 0 c A CT-C ~ VR13

3-14e2-36A .75 358 SE 2 C SCK SA 0 C A CT-COP

3-14&2-36B .75 358 6E 2 C SCK SA 0 C A CT-COP

3-1492-38A 1.5 358 SB 2 B &A KO 0 O/C A BT OP DAIH-V1 PIT RR

3-1402-388 1.5 358 7C 2 B &A KO 0 O/C A BT OP DAIH-Vt PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT~ULL STROKE EXERCISE; CT-G-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORl'IAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAM-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.


HRC SUBIUTTAL

f9:32 WEDNESDAY' JULY 5 I 't9S<

• SORTE]) BY: VALVE EPH PAGE: 46

•

•

VALVE ACT NOR STR TEST REL EPN SIZE PID CORJ> CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

3-14&2-4A B 358 BB 2 A GL HO c c A AT RR VR-6 DAitl-Vf BT OP PIT RR

3-14&2-4B B 358 88 2 A GL HO c c A AT RR VR-6 DAIH-VI BT OP PIT RR

3-14$2-SA f 2 358 8C 2 c SCK SA c 0 A CT-0 OP

3-14&2-BB 12 358 7B 2 C SCK SA C 0 A CT-0 OP

3-14e2-9A 1e 358 3C 1 AC CK SA c O/C A AT RR VR-6 DAIH-Vf G CT-0 CS CT-C RR

3-1492-98 te 358 4C 1 AC CK SA c O/C A AT RR VR-6 DAIH-VIG . CT-0 CS

CT-C RR

3-1499-34A • 75 358 D9 2 c CK SA 0 c A CT-0 OP

3-15GHA 19 369-2 38 3 C CK SA C 0 A CT-0 OP

3-1591-18 19 36&-2 3C 3 C CK · SA C 0 A CT-0 OP

3-15GHC 19 369-2 3E 3 C CK SA C 0 A CT-0 OP

3-1561-tD I& 36&-2 3F 3 C CK SA C 0 A CT-0 OP

TEST: AT-SEAT LEAKAGE TEST; BT-FIJLL STROKE EXERCISE; CT-0-0IECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; · RT-RELIEF VALVE TEST; DJ-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH lff])ICllTOR CHECX.

TEST SCHED: OP-NORllAL OPERATIOHi CS-COlD SHUTDOllH; RR-REACTOR REFUELING; SAH-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

• SORTED BY: VALVE EPN

IST PROGRAM FOR VALVES Df!ESDEH UHITS 2 & 3

NRC SUBltITTAL

VALVE ACT HOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR AJP TEST SCHED REQ REHARKS

3-1591-11A 18 369-1 9E 2 B GA HO 0 O/C A BT OP DAIIH1 PIT RR

3-15eHtB 18 369-1 2D 2 B GA HO 0 O/C A BT OP DAIK-Vt PIT RR

3-15&H3A 3 36&-1 2C 2 B GA HO 0 O/C A BT OP DAIK-Vl PIT RR

3-1591-13A<RV> 2 369-1 4F 2 c RY SA c 0 A RT 5Y

3-1591-138 3 369-1 7C 2 B GA HO 0 O/C A BT OP DAilt-V1 PIT RR


PAGE: 47

• J-1591-13B<RV> 2 369-1 4E 2 C RY SA C 0 A RT 5Y

•

J-1591-13CCRV> 2 36&-1 6E 2 C RV SA C 0 A RT 5Y

J-1591-17A 2 366-1 BC 2 C RV SA C 0 A RT SY

3-1591-178 2 369-1 2C 2 C RV SA C 0 A RT 5Y

3-15eH8A 6 369-1 SB 2 A GL HO c O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR

:H59HBB 6 369-1 2B 2 A bl KO c O/C A AT RR VR-6 DAIK-VI BT OP PIT RR

TEST: AT-SEAT LEAXA&E TEST; BT-Flll.L STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-DIECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

TEST st:HED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAltPLING PLAH TECHHIQUE; 5Y-OHCE EVERY 5 YEARS.

•

•

•

IST PROGRAlt FOR VALVES 19:32 W~DHESDAY, JULY 5, 19lri . DRESDEN ~ITS 2 & 3

NRC SUBHITT AL



----------------------------------------------------------------------------------------------------------------------------------

3-15G1-2eA 14 368-1 78 2 A GA HO c O/C A AT RR VR-6 DAIH-V1 BT OP PIT RR

3-1501-26B 14 366-1 2B 2 A GA HO c O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR

3-1501-2tA 18 368-1 SA 2 B GA HO 0 O/C A BT OP DAIK-VI PIT RR

·3-1se1-21B 18 36&-1 2A 2 B GA HO 0 ·o;c A BT OP DAIK-VI PIT RR

3-15Gl-22A 18 366-t 3A 1 A GA HO c O/C A AT RR VR-6 DAIK-VI BT OP DAilf-V2 PIT RR

3-15e1-22B 18 369-t 7A I A GA HO c O/C A AT RR VR-6 DAIK-Vt BT OP DAIH-V2 PIT RR

3-t501-25A 14 360-1 5B I AC CK SA c O/C A AT RR VR-6 DAIH-VI& CT-0 CS DAIK-V2 CT-C CS PIT RR

3-1501-25B 14 360-1 4B I AC CK SA c O/C A AT RR VR-6 DAIH-VIO CT-0 CS DAIK-V2 CT-C CS PIT RR

3-15&1-27A 16 36&-1 6A 2 A GA tlO c O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR

3-15&1-27B 16 36&-1 6A 2 A GA HO c O/C A AT RR VR-6 DAIH-VI BT OP -PIT RR

3-1591-28A 16 360-t 3A 2 A GA HO c O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST;_ PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORHAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAtfl.ING PLAN TECHNIQUE; SY-OHCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 10:32 WEDHESDAY, JULY 5, 198' DRESDEN ~ITS 2 ~ 3

HRC SUBHITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

-------------------------------------------------------------------------------------------------------------~--------------------

3-159f-28B 16 369-1 3A 2 A GA KO c O/C A AT RR VR-6 DAiii-Vi BT OP PIT RR

3-15ef-32A ts 36&-1 SD 2 B GA HO 0 c A BT cs DAilt-V25 PIT RR

3-15G1-32B 18 36&-f 2D 2 B GA tlO 0 c A BT cs DAilt-V25 PIT RR

3-15&f-38A 14 369-1 SB 2 A &L HO c O/C A AT RR VR-6 DAilt-Vt BT OP PIT RR

3-1501-381 14 36&-t 3B 2 A &L HO c O/C A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-tsot-SA 14 36&-1 5E 2 A GA lfO 0 c A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-15ef-5B 14 36&-1 5F 2 A GA lfO 0 c A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-15et-5C 14 360-t 4E 2 A GA lfO 0 c A AT RR VR-6 DAI It-Vt BT OP PIT RR

3-1501-SD 14 360-t 4F 2 A GA lfO 0 c A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-15&t-63A t2 36&-1 7E 2 c CK SA c O/C A CT-0 OP CT-C OP

3-1591-63B t2 36&-I 7F 2 c CK SA c O/P A CT-0 OP CT-C OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUEL!"'; SAlt-SAltPLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•


NRC SUB111TTAL


stlRTED BY: VALVE EPH

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REKARKS

3-1501-63C 12 360-1 2E 2 C CK SA C O/C A CT-0 OP CT-C OP

3-1591-63» 12 360-1 2F 2 ·c CK SA C 0 A CT-0 OP CT-C OP

3-15&1-65A 2 360-1 7F 2 C CK SA C 0 A CT-0 OP

3-1501-658 2 36&-t 7E 2 C CK SA C 0 A CT-0 OP

3-t5et-65C 2 360-1 2E 2 C CK SA C 0 A CT-0 OP

3-t501-65D 2 36G-t 2F 2 C CK SA C 0 A CT-0 OP

3-t5&1-66A 2 36&-t SF 2 C SCK SA 0 C A CT-C OP

3-1501 -668 2 36&-1 2f 2 C SCK SA 0 C A CT-C OP

3-t5&1-67A 2 360-t 8F 2 C CK SA 0 C A CT-C SAK VR-tt

3-1501-678 2 36&-t 2F 2 C CK SA 0 C A CT-C SM VR-11

3-15&t-85D(RY> 2 Jbe-1 F6 2 C RY SA C 0 A RT SY .

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-0IECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION IHDICATOR CHECK •

PAGE: 50

TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAKPLING PLAH TECHNIQUE; 5Y-OHCE EVERY 5 YEARS.

•

•

•

IST PROGRAlt FOR VALVES 1 & : 32 WEDNESDAY I JUL y 5 I 198' DRESDEN UNITS 2 & 3

NRC SUBltITTAL

SORTED BY: VALVE EPH PA&E: 51


---------------------------------------------------------------~------------------------------------------------------------------

3-200H&5 3 369 6f 2 A GA AO c O/C A AT RR VR-6 DAill-V1 BT OP PIT RR FST OP

3-2901-3 3 369 4E 2 A GA AO O/C O/C A AT RR VR-6 DAIK-V1 BT OP PIT RR FST OP

3-2001-5 3 369 4E 2 A GA AO O/C C A AT RR VR-6 DAIK-V1 BT OP PIT RR FST OP

3-239H9 12 374 4E 2 B Gl KO c c A BT OP DAIK-V1 PIT RR

3-23&t-14 4 374 6C 2 B GL l'K> c O/C A BT OP DAIK-V1 PIT RR

3-2391-29 16 374 2E 2 c CK SA c 0 A CT-0 OP

3-23&1-23 1.5 374 4A 2 c RV SA c 0 A RT SY

3-2391-26 .75 374 ec · 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-2391-27 .75 374 GD 1 AC XFC SA 0 c A AT RR VR-6 CT-C RR YR-24

3-2391-28 374 SB 2 B GL AO c 0 A BT OP DAIK-V1 PIT RR FST OP

3-2391-29 374 9B 2 B GL AO 0 c A BT OP DAIK-V1 PIT RR FST OP


TEST SCHED: OP-HORKAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAPl-SAl'IPLING Pt.AH TECHHIQUE; 5Y-O~ EVERY 5 YEARS.

•

•

••

IST PROGRAl'I FOR VALVES 16:32 WEDHESDAY, JULY 5, 19Slt DRESDEN UHITS 2 L 3

NRC SUBtfITTAL


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REi'IARKS

----------------------------------------------------------------------------------------------------------------------------------

3-2361-3

3-23&1-3t

3-2391-32

3-23&1-34

3-23&1-35

3-23&1-36

3-2301;:;39

3-2381-4

3-2381-49

3-23&1-45

3-2381-48

1G 374 9A 2 B GA HO c 0 A BT OP PIT RR

374 9A 2 B GL AO c D A BT OP PIT RR FST OP

374 78 2 B Gt. so c O/C A BT OP PIT RR FST OP

2 374 SD 2 AC CK SA 0 O/C A AT RR CT-0 OP CT-C CS

16 374 2E 2 A GA HO c D/C A AT RR BT OP PIT RR

16 374 9E 2 A GA HO c O/C A AT RR BT OP PIT RR

16 374 BE 2 c CK SA c O/C A CT-0 SM! CT-C SAM

1e 374 9C t A GA HO 0 c A AT RR BT OP PIT RR

4 374 C7 3 AC CK SA c 0 A CT-0 OP

24 374 88 2 AC CK SA C O/C A AT RR CT-0 OP CT-C CS

4 374 48 2 B GA KO 0 0 A BT OP PIT RR

DAilt-V1

DAilt-YI 1

VR-6 DAIK-Vt

VR-6 DAIK-VI

VRl5

VR-6 DAIK-VI.

VR-6 DAIH-VI I

DAIK-VI


TEST SCKED: OP-HORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAttPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

• i L__

IST PROGRAM FOR VALVES DRESDEN IJHITS 2 & 3

NRC SUBMITTAL

16:32 WEDHESDAY, JULY 5, 191ri


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REffMKS

3-239f-49

3-2Jet-S

4 374 4D 2 B GA HO C C A BT OP PIT RR

f& 374 OB t A GA KO 0 C A AT RR BT OP PIT RR

3-2Jef-50A 4 374 4C 2 C CK SA C 0 . A CT-0 OP

3-239f-Sf 4 374 4C 2 C CK SA 0 C A CT-C OP

3-23&1-S3 4 374 3C 2 C RV SA C 0 A RT SY

3-23&f-6 f 6 374 2f 2 B GA KO 0 C A BT OP PIT RR

. 3-239f-68 16 374 7A 2 C RPD SA C 0 A NIA

3-2361-69 f6 374 7A 2 C RPD SA C 0 A N/A

3-2301-7 14 374 6E 2 c CK SA c O/C A CT-0 RR CT-C RR

3-23&f-71 2 374 SD 2 AC SCK SA c O/C A AT RR CT-0 OP CT-C CS

3-2391-74 12 374 BC 2 AC CK SA c O/C A AT RR CT-0 OP CT-C CS

DA lit-Vt

VR-6 DAIK-Vt

DAitt-Yf

DAitl-Y3

DAilt-V3

VR-22

YR-6 DAilt-V1 I

VR-6 DAill-Vf 1

TEST: AT-SEAT LEAKAGE TEST; BT-flll..L STROKE EXERCISE; CT-ll-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECl(.

PAGE: 53

TEST SCHED: OP-NORMAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAlt-SAflPLIHG PLAN TECHNIQUE; SY-ONCE EVERY S YEARS.

•

•

•

IST PROGRAl'I FOR VALVES DRESDEN UNITS 2 & 3

HRC SUBHITTAL

19:32 WEDHESDAY, JULY 5, 1984J


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE - TYPE POS DIR A/P TEST SCHED REQ REl'IARKS

----------------------------------------------~-----------------------------------------------------------------------------------

3-2361-75 4 '374 4B 2. C CK SA C O/C A CT-0 OP CT-C OP

3-2391-76 2 374 4C 2 C CK ·SA C O/C A CT-0 OP CT-C OP

3-2391-8 t4 374 6E 2 B GA l'IO C O/C A BT OP DAIIHf PIT RR

3-2391-9 t4 374 5E 2 B GA KO 0 0 A BT OP DAIH-Vf PIT RR

3-2354-5&& .75 374 6E 2 C CK SA 0 C A CT-C RR VR-tB

J-23~-set • 75 374 6E 2 C SCK SA 0 C A CT-C OP

3-2399-« • 75 374 D4 2 C RY SA C 0 A RT SY

3-2499-tA 9.5 106-2 6D 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2499-tB e.5 106-2 2D 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2499-2A e.s 7&6-2 6D 2 A GA so 0 O/C A AT RR VR-6 BT OP PIT RR FST OP .

3-2499-28 9.5 786-2 JD 2 A GA so 0 O/C A AT RR YR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CHl-OIECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HOIUIAL OPERATION; CS-COLD SHUTOOUH; RR-REACTOR REFUELI~; SAll-SmLING PLAN TECHNIQUE; 5Y-Otft:E EVERY 5 YEARS.

1 I

I

•

•

•

IST PROGRAtl FOR VALVES 16:32 WEDHESDAY, JULY 5, 1989 DRESDEN ~ITS 2 & 3

NRC SUBHITTAL

SORTED BY: VALVE EPft PAGE: 55

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl'IARKS

----------------------------------------------------------------------------------------------------------------------------------

3-2499-28A e.5 786-2 7C 2 AC CK SA 0 c A AT RR VR-6 DAIH-VIS CT-0 OP CT-C CS

3-2499-28B &.5 706-2 2C 2 AC CK SA 0 c A AT RR VR-6 DAlli-VfB CT-0 OP CT-C CS

3-2499-3A e.5 706-2 7B 2 A GA so c O/C A AT RR VR-6 BT OP PIT RR FST OP.

3-2499-JB e.s 706-2 2B 2 A GA so c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2499-4A e.5 106-2 6B 2. A GA so c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2499-4B &.5 706-2 3B 2 A GA so c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-IA 1.5 787-2 SC 2 B GL AO c D/C A BT OP PIT RR FST OP

3-2599-IB 1.5 787-2 IC 2 B GL AO c D/C A BT OP PIT RR FST OP

3-259'-2A 787-2 5C 2 A GL AD c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-2B 787-2 4C 2 A GL AD c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-22 1.5 7&7-2 6A 2 c CK SA c O/C A CT-0 OP DAIIHl3 CT-C CS

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-ll-CHECK VALVE EXERCISE OPEH, CT-C-CffECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL Qp.ERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAtlPLING PLAN TECHNIQUE; 5Y-DNCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 10:32 WEDHESDAY, JULY 5, 1989 DRESDEN ~ITS 2 l 3

NRC SUBIHTTAL

SORTED BY: VALVE EPH PAGE: SO


----------------------------------------------------------------------------------------------------------------------------------

3-2599-23A 797-2 6C 2 AC CK SA c O/C A AT RR VR-6 DAilt-V19 CT-0 OP CT-C CS

3-2599-238 7&7-2 3C 2 AC CK SA c O/C A AT RR YR-6 DAIH-V19 CT-0 OP CT-C CS

3-2599-24A 797-2 6C 2 AC CK SA c O/C A AT RR VR-6 DAIH-V19 CT-0 OP CT-C CS

3-2599-248 7&7-2 3C 2 AC CK SA c O/C A AT RR VR-6 DAIH-V19 CT-0 OP CT-C CS

3-2599-26A e.5 797-2 4D 2 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-2599-268 e.5 707-2 3D 2 AC XFC SA 0 c A AT RR VR-6 CT-C RR VR-24

3-2599-JA 797-2 6C 2 A GL AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-JB 797-2 JC 2 A GL AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-4A e.5 707-1 3F 2 A GL AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-48 &.5 767-2 3E 2 A GL AO c O/C A AT RR VR-6 BT OP PIT RR FST OP

3-2599-5A 0.5 707-2 SF 2 B GL AO c O/C A BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-FUl..L STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORKAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELINI;; SAM-SAJ'IPLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRA.11 FOR VALVES te:32 WEDHESDAY, JULY s, t98< DRESDEN ~ITS 2 & 3

NRC SUBMITTAL


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl!ARKS

----------------------------------------------------------------------------------------------------------------------------------

3-2599-SB e.5 767-2 5E 2 B Gt. AO c O/C A BT OP PIT RR FST OP

3-37G2 6 353 3B 2 A GA HO 0 c A AT RR VR-6 DAIK-V23 BT cs PIT RR

3-3793 6 353 1B 2 A GA HO 0 c A AT RR VR-6 DAIK-V23 BT cs PIT RR

3-3706 6 353 1B 2 A GA KO 0 c A AT RR VR-6 DAIK-V23 BT cs PIT RR

3-39Je-se1 s 355 GB 3 c CK SA c 0 A CT-0 OP

3-3999-252 4 355 7B 3 C CK SA 0 C A CT-C OP

3-3999-253 4 355 SB 3 C CK SA C 0 A CT-0 OP

3-3999-336 360-2 4C 3 C CK SA 0 C A CT-C OP

3-3999-33S 366-2 4E 3 C CK SA 0 C A CT-C OP

3-41e1-se·t 4 359 SC 3 C CK SA C 0 A CT-0 SAH VR-lt

3-4899-84 369 SE 3 C RV SA C 0 A RT SY

TEST: AT-SEAT LEAKM;E TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEH, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-fAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAl'IPLING PLAN TECHHIQUE; SY-OHCE EVERY 5 YEARS.

•

•

•


NRC SUBMITTAL

19:32 WEDNESDAY I JULY 5, 198~

SORTED BY: VALVE EPtt

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SOU REQ REllMKS

3-4899-89 369 BE 2 C RV SA C 0 A RT 5Y

3-4899-98 369 7E 2 C RY SA C 0 A RT SY

3-4899-99 369 7E 3 C RV SA C 0 A RT SY


PAGE: 58

TEST SCHED: OP-HORl!AL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAlt-SAtfl.IN& PLAN TECHHIQUE; 5Y-ONCE EVERY S YEARS.

•

•

•

IST PROGRAH FOR VALVES 19:46 WEDHESDAY, JULY 5, 198~ DRESDEN ~ITS 2 & J

NRC SUBKITTAL

SORTED BY: VALVE EPH PAbE: 1

VALVE ACT NOR STR TEST REL EPff SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl'IARKS

----------------------------------------------~-----------------------------------------------------------------------------------

BACK DRAFT DHP 24 49 9A SR C CK SA c O/C-A CT-0 OP CT-C OP

BACX DRAFT MP 24 49 9C SR c CK SA c O/C A CT-0 OP CT-C OP

2-922e-1e5A 8 25 5E SR c CK SA c O/C A CT-0 RR VR-16 DAilt-V16 v

CT-C RR

2-9229-1958 8 25 5E SR c CK SA c O/C A CT-0 RR. VR-16 DAilt-V16 CT-C RR

2-e22e-1esc 8 25 5E SR c CK SA c O/C A CT-0 RR VR-16 DAilt-V16 CT-C RR

2-922&-1&5D 8 25 5E SR c CK SA c O/C ~ CT-0 RR VR-16 DAI1t-V16 CT-C RR

2-e22e-rn5E 8 25 5E SR C CK SA c O/C A CT-0 RR VR-16 DAilt-V16 CT-C RR

2-9229-84A &.5 12-t JF SR c CK SA 0 c A CT-C RR YR-23

2-022&-84B 9.5 12-1 3F SR C CK SA 0 C A CT-C RR VR-23

2-922&-84C &.5 12-1 JF SR C CK SA 0 C A CT-C RR YR-23

2-e22&-84D e.s 12-1 3F SR c CK SA 0 c A CT-C RR VR-23

TEST: AT-SEAT LEAKAGE TEST; BT-FULL SiR!IKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEH, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOff INDICATOR CHECK •

TEST SCHED: OP-HORltAL DPERATIOH; CS-COLD SHUT10VN; RR-REACTOR REFUELING; SAlt-SAtfiING Pl.AH TECHNIQUE; SY-Ot«:E EVERY 5 YEARS.

••

•

•


10: 46 llEDHESDAY I JUL y 5' 198'

. HRC SUBMITTAL


VAL VE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

2-e22e-SSA e.5 12-2 7F SR c CK SA 0 c A CT-C RR VR-23

2-G22&-85B e.s 12-2 7F SR c CK SA 0 c A CT-C RR VR-23

2-e22e-ssc e.s f2-2 7F SR c CK SA 0 c A CT-C RR VR-23

2-&22&-SSD &.5 f2-2 7F SR C CK SA 0 C A CT-C RR VR-23

2-&3&2-t66A 34 F2 SR C CK SA C 0 A CT-0 OP

2-&3&2-1668 34 F6 SR C CK SA C 0 A CT-0 OP

2-&3&2-19A G.5 34 7ESRBTWYSO OCABTCS VR-9

2-G392-19B &.5 34 7E SR B TWV· SO 0 C A BT . CS YR-9

2-e3&2-2&A e.s 34 SESRBTWYSO OCABTCS VR-9

2-&392-2GB G.5 34 BESRBTWVSO OCABTCS YR-9

2-e3&5-ff7 e.s 34 9DSRBTWVSO OCABTRR YR-f

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CHI-CHECK VALVE EXERCISE OPEN, CT-C-CHECX VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 2

TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAtlPLING Pl.AH TECHNIQUE; SY-ONCE EYERY 5 YEARS.

•

•

•


NRC SUBMITTAL

16:46 llEDHESDAY, JULY 5, 1989


VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

2-63$5-118 9.5 34 9D SR B TllV SO 0 C A BT RR VR-1

2-0399-524A 34 SD SR B TWV SO 0 C A BT RR VR-8

2-9399-5248 34 SD SR 8 TWV SO 0 C A BT RR VR-8

2-6399-525 34 SD SR B CK SA C 0 A CT-0 OP

2-:9399-548A 34 9CSRBGA SO COA8TRR VR-8

2-0399-5488 34 9CSRBGA SO COABTRR VR-8

2-&399-549A BESRBGA SO COABTRR VR-:8

2-6399-5498 34 BESRBGA SO COABTRR VR-8

2-9733-A 0.5 37-2 1F SR A BAL so c c A AT RR VR-6 BT OP PIT RR

2-0733-B e.s 37-2 1F SR A BAL so c c A AT RR VR-0 BT . OP PIT RR

2-6733-C e.s 37-2 1F SR A BAL so c c A AT RR VR-6 BT OP PIT RR

TEST: AT-SEAT LEAl(AGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 3

TEST SCHED: OP-NORl!Al OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAM-SAtlPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•



NRC SUBMITTAL

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE ·TYPE POS DIR AIP TEST SCHED REQ REllARKS

2-6733-D e.5 37-2 1F SR A BAL so c c A AT RR VR-6 BT Of' PIT RR

2-G733-E e.5 37-2 IF SR A BAL so c c A AT RR VR-6 BT OP PIT RR

2-9736-t e.5 37-2 IF SR D GA EXP 0 c A DT RR

2-9736-2 &.5 37-2 IF SR D GA EXP 0 C A DT RR

2-G736-3 9.5 37-2 IF SR D GA EXP 0 C A DT RR

2-9736-4 &.5 37-2 1F SR D GA EXP 0 C A DT RR

2-9736-5 9_.5 37-2 IF SR D GA EXP 0 C A DT RR

2-t59H9A 6 29-f 7B SR A GA KO c O/C A AT RR VR-6 DAIH-V1 BT OP PIT RR

2-159H9B 6 29-1 2B SR A GA HO c O/C A AT RR VR-6 DAIK-VI BT OP PIT RR

2-1599-61 3 29-1 4D SR A GA AO c c A AT RR VR-6 DAil1-VI BT OP PIT RR FST OP

2-1599-62 3 29-1 4D SR A GA AO c c A AT RR VR-6 DAIK-VI BT OP PIT RR FST OP

1e:46 WEDNESDAY, JULY 5, 198~

PA~: 4

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT--0-CHECK VALVE EXERCISE OPEN, CT-C-CH£CK VALVE EXERCISE CLOSED; · RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-MORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAl!-SAKPLING PLAN TECHNIQUE; SY-ONCE. EVERY 5 YEARS.

•

•

••

IST PROGRAM FOR VALVES 1e:46 WEDNESDAY, JULY s, t 9a· DRESDEN UHITS 2 & J

NRC SUBMITTAL

SORTED BY: VALVE EPH PAi;E: 5


----------------------------------------------------------------------------------------------------------------------------------

2-16&1-2GA 2G 25 SD SR A BTF AO c O/C A AT RR VR-6 DAHi-Vi BT OP FST OP PIT RR

2-tbe1-29B 29 25 SE SR A BTF AO c O/C A AT RR VR-6 DAIH-V1 BT OP FST OP PIT RR

2-1691-21 18 25 6C SR A BTF AO c c A AT RR VR-6 DAIIHI BT OP FST OP PIT RR

2-1661-22 18 25 6C SR A BTF AO c c A AT R~ VR-6 DAIH-V1 BT OP FST OP PIT RR

2-16&1-23 18 25 3B SR A BTF AO c c A AT RR VR-6 DAIH-VI BT OP FST OP PIT RR

2-16&1-24 18 25 2B SR A BTF AO c c A AT RR VR-6 DAIH-VI BT OP FST OP PIT RR

2-16&1-JIA 29 25 9D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-1691-318 . 20 25 9E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16&1-J2A 18 25 JD SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16&1-328 18 25 JD SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-1691-32C 18 25 JD SR AC CK SA c O/C A AT RR YR-6 CT-0 OP CT-C OP


TEST SCHED: OP-NORMAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAl1PLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

IST PROGRAM FOR VALVES 16:46 llEDHESDAY, JULY 5, 1989 DRESDEN UHITS 2 & J

NRC SUBHlTTAL

• SORTED BY: VAL YE EPM PAGE: 6

VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl1AAKS

----------------------------------------------------------------------------------------------~-----------------------------------

2-16e1-J2D rn 25 JE SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16et-32E 18 25 3E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16e1-J2F 18 25 3E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16&1-JJA 1a 25 7D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16e1-33B ta 25 7D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

• 2-1691-JJC 1a 25 7D SR AC CK SA' c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-t691-33D ta 25 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-16e1-33E 18 25 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-f6e1-33F 1a 25 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

2-t691-55 4 25 6B SR A BTF AO 0 c A AT RR YR-6 BT OP FST OP PIT RR

2-1691-56 t8 25 61) SR A BTF AO 0 c A AT RR VR-6 DAili-Vf BT OP FST OP PIT RR

• TEST: AT-SEAT LEAKAGE TEST; [IT-FULL STROi<E EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DI-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORllAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAtlPl.ING PLAH TECHHIQUE; SY-ONCE EVERY 5 YEARS.

L_

•

•

•

IST PROGRAM FOR VALVES 19:46 llEDHESDAY, JULY 5, 1989 DRESDEN UHITS 2 & 3

NRC SUBHITTAL


VALVE f¥:T NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllMKS

----------------------------------------------------------------------------------------------------------------------------------

2-f6ef-57 t.5 25 BD SR A GL HO 0 c A AT RR VR-6 DAilt-Vf BT OP PIT RR

2-16$1-58 1.5 25 7D SR A GL AO c c A AT RR VR-6 BT OP FST OP PIT RR

2-1601-59 t.5 25 61) SR A GL AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-169f-6e 18 25 2E SR A BTF AO c c A AT RR VR-6 DAIK-V1 BT OP FST OP PIT RR

2-1691-61 2 25 2E SR A GA AO c .O/C A AT, RR VR-6 Miit-Vt BT OP FST OP PIT RR

2-1601-62 2 25 3B SR A GL AO c O/C A AT RR VR-6 BT OP FST OP PIT RR

2-1601-63 6 25 2A SR A BTF AO c O/C A AT RR VR-6 DAI It-Vt BT OP FST OP PIT RR

2-1699-591\ • 75 25 2F SR A GL ltAH 0 0 p AT RR VR-6

2-1699-598 .75 25 6F . SR A GL ttAH 0 0 P AT RR VR-6

2-1699-65A .75 25 2E SR A GL tlM 0 D · P AT RR VR-6

2-1699-65B .75 25 9E SR A GL HAN 0 0 P AT RR VR-6

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CHI-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INJ)ICATOR CHECK.

TEST SCHED: OP-HORltAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAM-SAtlPLIN& PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES DRESDEN UHITS 2 & J

HRC SUBHITTAL

16:46 llEDHESDAY, JULY 5, 1~


VALVE ACT - NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

2-199t-27A 6 31 JE NSR C CK SA O/C 0 A CT-0 OP CT-C OP

2-1991-278 6 31 JE NSR C CK SA O/C 0 A CT-0 OP CT-C OP

2-1991-4& 6 31 6E NSR B GA Atl C 0 A BT OP

2-2e&t-te6 3 39 7F SR A GA AO O/C C A AT RR VR-6 DAUi-Vt BT OP PIT RR FST OP

2-2001-6 3 39 JE SR A GA AO O/C C A AT RR VR-6 DAilt-V1 BT OP PIT RR FST OP

2-23&1-64 51 5A SR B GL Atl 0 c A BT OP PIT RR FST OP

·2-2361-65 51 6A SR B GL Ao 0 c A BT OP PIT RR FST OP

2-2399-761\ 51 SD SR C CK SA c O/C A CT-0 SAH VR-19 CT-C SAH

2-2399-768 51 SD SR C CK SA c O/C A CT-0 SAH VR-19 CT-C SAH

2-2399-77A 51 BD SR C CK SA c O/C A CT-0 SAH VR-19 CT-C SAH

2-2399-778 51 SD SR c CK SA c O/C A CT-0 SAH VR-19 CT-C SAH

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF Vft.VE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAGE: 8

TEST SCHED: OP-HORltAL OPERATION; CS-COl.D SHUTDOWN; RR-REACTOR REFUELIN&; SAll-SMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAll FOR VALVES DRESDEN UNITS 2 & 3

NRC SUBKITTAL

19:46 WEDNESDAY, JULY 5, 199c

SORTED BY: VALVE EPH PAliE: 9


-----------------------------------------------------------------------------------------------------------------~----------------

2-2541-61 f .25 797 6A SR C CK SA C 0 A CT-0 OP

2-2599-8 e.s 7&7 A8 SR c CK SA c 0 A CT-0 OP

2-4te2 4 28 SC NSR B GA HO c 0 A BT OP PIT RR

2-4699-311A e.s 173 4F SR c CK SA c O/C A CT-0 OP CT-C OP

2-4699-3118 e.s 173 6F SR C CK SA c O/C A CT-0 OP CT-C OP

2-4699-312 1.S 173 SD SR c CK. SA c O/C A CT-0 OP CT-C OP

2-4699-313A &.S 173 3D SR c RV SA c 0 A RT SY

2-4699-3138 9.S 173 SD SR C RV SA C 0 A RT SY

2-4699-314A &.S 173 4D SR C RV SA C 0 A RT SY

2-4699-3148 9.S 173 6D SR C RV SA C 0 A RT SY

2-4720 37-2 7C SR A GA AO 0 C A AT RR BT OP FST OP PIT RR

VR-6

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT--0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE ClOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAH-SAtlPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PR(){;RAlt FOR VALVES 19:46 WEDNESDAY, JULY 5, 198~

DRESDEN UNITS 2 l 3 NRC SUBMITTAL

SORTED BY: VALVE EPM PAbE: 19

VALVE ACT HOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

----------------------------------------------------------------------------------------------------------------------------------

2-4721 37-2 7C SR A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

2-4722 37-2 2E SR A GL AO 0 c A AT RR VR-6 DAIK-V13 BT cs FST cs PIT RR

2-4799-511 e.s 37-2 5F SR A GA so 0 C . A AT RR VR-6 BT OP

2-4799-514 e.5 37-2 4F SR AC CK SA 0 c A AT RR VR-6 DAIK-V21 CT-C CS

2-4799-567 .25 37-2 SB SR c CK SA 0 c A CT-C OP

2-4799-569 .25 37-2 SB SR C CK SA 0 C A CT-C OP


2-5261 2.9 41-2 5E SR C RV SA C 0 A RT 5Y

2-5292-A-50& LS 41-2 5E SR C CK SA. C 0 A CT-0 OP

2-5262-8-506 1.5 41-2 5E SR C· CK SA C 0 A CT-0 OP

2-5425 1.5 43-1 SB SR C RV SA C 0 A RT SY

TEST: AT-SEAT LEAKAGE TESTi BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAMPLING PLAH TECHNIQUE; 5Y-OHCE EVERY 5 YEARS.

•

•

•

!ST PROGRAM FOR VALVES DRESDEN UNITS 2 & 3

NRC SUBl'IITTAL


SORTED BY: VALVE EPN PAhE: it


2-5741A 48 269 IA SR B BTF AO 0 c A BT (fl

FST OP - PIT RR

2-57418 48 269 IA SR B BTF AO 0 c A BT OP FST OP PIT RR

2-5742A 48 269 OB SR B BTF AO 0 c A BT OP FST OP PIT RR

2-5742B 48 269 OB SR B BTF AO 0 c A BT OP FST OP PIT RR

2-6999-193 .375 173 &A SR B GA so c 0 A BT OP

2-6999-104 .375 173 &A SR C CK SA c 0 A CT-0 OP

2-75&3 18 49 2B SR B BTF tlO 0 D/C A BT DP PIT RR

2-BS&HA e.5 25 2E SR A CV AD 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-BS&HB &.5 25 2E SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-85&1-3A e.5 25 4D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-85&1-3B &.5 25 4D SR A FCV AO o c A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECl( VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORMAL DPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELINb; SAtl-SAMPLIHG PLAN TECHHIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtl FOR VALVES DRESDEN UHITS 2 & 3

HRC SUBl1ITTAL




2-8581-SA e.s 2s 3D SR A FCV AO 0 c A AT RR VR-6 BT Of> PIT RR FST OP

2-8581-SB &.5 25 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-8526 .75 25 SD SR C RY SA c 0 A RT SY

2-8941-799 9.5 1234-t 5E SR B GA AO c 0 A BT OP FST Of> PIT RR

2-8941-716 e;s 1234-1 5D SR B GA AO c 0 A BT Of> FST OP PIT RR

2-92&5A &.5 25 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-92G5B &.5 25 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-9286A e.s 25 4D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-92668 9.5 25 4D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-9287A e.5 25 6D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

2-92978 e.5 25 6D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECIC VALVE EXERCISE OPEN, CT-C-CHECIC VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORltAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAtlPLIN& PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAK FOR VALVES DRESDEN UNITS 2 & J

NRC SUBKITTAL

18:46 WEDNESDAY, JULY 5, 1989,


VALVE ACT HOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCflED REQ REKARKS


2-92GBD e.s 25 6D SR A FCV AO 0 c A AT RR VR-6 BT DP PIT RR FST OP

2/3-4699-3ttA e.s t73 4F SR C CK SA c O/C A CT-0 OP CT-C OP

2/3-4699-3ttD e.5 173 6F SR C CK SA c O/C A CT-0 OP CT-C OP

2/J-4699-312 t .5 t73 5D SR C CK. SA c O/C A CT-0 OP CT-C OP

213-4699-3tJA e.5 113 JD SR C RY SA c 0 A RT SY

21J-4699-3tJB e.5 113 5D SR C RV SA c 0 A RT 5Y

2/3-4699-314A &.5 173 4D SR C RY SA C 0 A RT 5Y

213-4699-3148 e.5 173 6D SR C RV SA C 0 A RT 5Y

213-5281 2.9 41-2 ID SR C RY SA C 0 A RT 5Y

2/3-52&2-A-588 I .5 41-2 1D SR c CK SA c 0 A CT-0 OP

TEST: AT-SEAT LEAKM;E TEST; BT-Fllll STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECX VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PA&E: 13

TEST SCHED: OP-NORltAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFU£LIN&; SAll-SAl'IPLIN& PLAH TECHNIQUE; SY-0~ EVERY 5 YEARS.

•

-·

•

IST PROGRAlt FOR VALVES DRESDEN llff ITS 2 ~ 3

NRC SUBHITTAL




----------------------------------------------------------------------------------------------------------------------------------

2/3-5292-B-596 1.5 41-2 1D SR C CK SA C 0 A CT-0 OP.

213-5741-55 10 3121 5C SR B BTF AO 0 c A BT OP FST OP PIT RR

2/3-5741-56 10 3121 5C SR B BTF AO 0 c A BT OP FST OP PIT RR

2/3-5741-57 16 3121 6B SR B BTF · · AO 0 c A BT OP FST OP PIT RR

2/3-5741-58 19 3121 7C SR B BTF AO c 0 A BT OP FST OP PIT RR

213-6999-163 .375 173 9A SR B GA so c 0 A BT OP

2/3-6999-164 .375 173 eA SR c CK SA c 0 A CT-0 OP

2/3-7595A 24 49 3A SR B BTF KO c 0 A BT OP PIT RR

2/3-75958 24 49 3A SR B BTF KO c 0 A BT OP PIT RR

2/3-7597A 24 49 9C SR B BTF KO c 0 A BT OP PIT RR

2/3-75078 24 49 9A SR B BTF KO c 0 A BT OP PIT RR


TEST SCHED: OP-HORHAL OPERATION; CS-COLD SHUTOOllN; RR-REACTOR REFUELING; SAll-SAHPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtl FOR VALVES DRESDEN ~ITS 2 ~ 3

NRC SUBMITTAL



VALVE ACT · NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

2/3-75t&A 24 49 9C SR B BTF KO 0 0 P NIA

213-7519[1 24 49 9A SR B BTF HO 0 0 P N/A

3-G220-195A 8 356 5E SR C CK SA c O/C A CT-0 RR VR-16 DAIIH16 CT-C RR

3-&22&-t95B a 356 5E SR C CK SA c O/C A CT-0 RR YR-16 DAIIM16 CT-C RR

3-922e-t95C 8 356 SE SR C CK SA c O/C A CT-0 RR VR-16 DAIK-V16 CT-C RR

3-G226-1&5D 8 356 5E SR C CK SA c O/C A CT-0 RR VR-16 DAIK-V16 CT-C RR

3-&229-1G5E a 356 5E SR C CK SA c O/C A CT-0 RR VR-16 DAIK-V16 CT-C RR

3-0229-B3A 0.5 345-2 7F SR C CK SA 0 c A CT-C RR VR-23

3-9226-838 0.5 345-2 7F SR C CK SA 0 C A CT-C RR YR-23

3-G220-83C 6.5 345-2 7F SR C CK SA 0 C A CT-C RR VR-23

3-G226-83D 9.5 345-2 7F SR C CK SA 0 C A CT-C RR YR-23

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CH£CK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

PAt;E: 15

TEST SCHE:D: OP-NORl'!AL OPERATION; CS-COLD SHUT»OWN; RR-REACTOR REFUELING; SAK-SAMPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•


HRC SUBMITTAL

10:46 llEDHESDAY, JULY 5, i9S~


VIII.VE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

----------------------------------------------------------------------------------------------------------------------------------

3-6229-84A 9.5 345-1 3F SR C CK SA 0 C A CT-C RR VR-23

3-0226-84B e.5 345-1 3F SR C CK SA 0 C A CT-C RR VR-23

3-622&-84C 6.5 345-1 3F SR C CK SA 0 C A CT-C RR VR-23

3-022&-B4D 0.5 345-1 3F SR C CK SA 0 C A CT-C RR VR-23

3-6302-16/JA 365 F2 SR C CK SA C 0 A CT-0 OP

3-6302-16/iB 365 F6 SR C CK SA C 0 A CT-0 OP

3-0302-19A 9.5 365 7E SR B TIIV SO 0 C A BT CS VR-9

3-6302-198 e.5 365 7E SR B TWV so 0 c A BT cs YR-9

3-6302-26A 6.5 365 SE SR B TWV SO 0 C A BT CS VR-9

3-6302-268 6.5 365 SE SR B TWV SO 0 C A BT CS YR-9

3-6305-117 e.5 365 eD SR B TWV so 0 c A BT RR VR-1

TEST: AT-SEAT LEAKAGE TEST; BT-FULL stRIJKE EXERCISE; CT-o-cliECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION IHDICATOR CHECK.

TEST SCHEJ): OP-HORKAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SA!f-SAflPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAtl FOR VALVES DRESDEN UNITS 2 & J

NRC SUBHITTAL

1G:46 llEDHESDAY, JULY 5, 198,



3-G3&5-tt8 G.5 365 GD SR B TWV SO 0 C A BT RR VR-t

3-8399-524A 365 8D SR B TWV SO 0 C A BT RR VR-B

3-&399-524B 365 SD SR B TWY SO 0 C A BT RR VR-8

3-&399-525 365 SD SR B CX SA C 0 A CT-0 OP

3-&399-548A 365 9CSRBGA SO COABTRR VR-8

3-&399-5488 365 9C SR B GA SO C 0 A BT RR VR-8

3-G399-549A 365 BE SR B GI\ SO C 0 A BT RR VR-8

3-&399-5498 365 BESRBGA SO COABTRR VR-8

3-&733-A e.s 367-2 tF SR A BAL so c c A AT RR VR-6 BT OP PIT RR

3-&733-B G.5 367-2 tF SR A BAL so c c A AT RR - VJt-6 BT OP PIT RR

3-9733-C e.5 367-2 tF SR A BAL so c c A AT RR VR-6 BT OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT--O-OIECX VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR.CHECK.

PA~: 17

TEST SCHED: OP-HORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELIN'; SAK-SAffPLitlli PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRA!t FOR VALVES DRESDEN UHITS 2 l 3

HRC SUBHITTAL

16:46 llEDHESDAY, JULY 5, t98

SORTED BY: VALVE EPH PA~: 18


3-9733-D 9.5 367-2 1F SR A BAL so c c A AT RR VR-6 BT OP PIT RR

3-9733-E 9.5 367-2 IF SR A BAL so c c A AT RR VR-6 BT OP PIT RR

3-&736-1 9.5 367-2 1F SR D GA EXP 0 c A DT RR

3-&736-2 6.5 367-2 tF SR D GA EXP 0 C A DT RR

3".'9736-3 9.5 367-2 1F SR D GA EXP 0 C A DT RR

3-9736-4 6.5 367-2 1F SR D GA EXP 0 C A DT RR

3-&736-5 0.5 367-2 1F SR D GA 'EXP 0 C A DT RR

3-156H9A 6 369-1 7B SR A GA HO c O/C A AT RR VR-6 BAIK-VI BT OP PIT RR

3-15&H9B 6 369-1 2B SR A GA HO c O/C A AT RR VR-6 DAIK-Vt BT OP PIT RR

3-1599-61 3 366-1 4D SR A GA AO c c A AT RR VR-6 DAIK-V1 BT OP PIT RR FST OP

3-1599-62 3 366-1 4D SR A GA AO c c A AT RR VR-6 DAIK-VI BT OP PIT RR FST OP

TEST: AT-SEAT LEMAGE TEST; BT-FULL STROtcE EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

TEST SCHED: OP-HORltAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAMPLING PLAN TECHHIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRA" FOR VALVES 10:46 llEDHESDAY, JULY 5, 1~ DRESDEN ~ITS 2 ~ J

NRC SUBMITTAL



----------------------------------------------------------------------------------------------------------------------------------

3-16e1-29A 29 356 SD SR A BTF AO c O/C A AT RR VR-6 DAI"-'11 BT OP FST OP PIT RR

J-t6e1-2&B 2e 356 8£ SR A BTF AO c O/C A AT RR VR-6 DAIH-V1 BT OP FST OP PIT RR

3-1661-21 18 356 6C SR A BTF AO c c A AT RR VR-6 DAIH-V1 BT OP FST OP PIT RR

3-t6et-22 18 356 6C SR A BTF AO c c A AT RR VR-6 DAIH-V1 BT OP FST OP PIT RR

3-1601-23 18 356 3B SR A BTF AO c c A AT RR VR-6 DAIH-Vt BT OP FST OP PIT RR

3-16&1-24 ts 356 2B SR A BTF AO c c A AT RR VR-6 . DAIH-Vt BT OP FST OP PIT RR

3-t6el-3tA 26 356 9D SR AC CK SA c O/C A AT RR VR-6 . CT-0 OP

CT-C OP

3-t6et-31B 29 356 9E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-t6e1-32A 18 356 3D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP cT-c op

3-1691-328 18 356 3D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-16G1-32C 18 356 3D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP


TEST SCHED: OP-NORMAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAl'lf'l.ING Pl.AH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

IST PROGRAtt FOR VALVES 16:40 llEDHESDAY, JULYS, 1989 DRESDEN UNITS 2 & 3

NRC SUBl1ITTAL

• SORTED BY: VALVE EPH PA&E: 20

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REl!MKS

----------------------------------------------------------------------------------------------------------------------------------

3-1&W1-32D 18 356 3E SR AC Ck SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-16e1-32E 18 356 3E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-16el-32f 18 356 3E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-1&Wt-33A 18 356 7D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-t&W.1-339 18 356 7D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

• J-t6et-33C 18 356 7D SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-t6G1-33D 18 356 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-1&Wt-33E 18 356 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-1691-33F 18 356 7E SR AC CK SA c O/C A AT RR VR-6 CT-0 OP CT-C OP

3-1691-55 4 356 69 SR A BTF AO 0 c A AT RR VR-6 DAIK-VI BT OP FST OP PIT RR .

3-1691-56 18 356 6D SR A BTF AO 0 c A AT RR VR-6 DAIK-VI BT OP FST OP PIT RR

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED;

• RT-RELIEF VALVE TEST; DT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NflRKAl OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAK-SAtlPLIN& PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PRDGRAtf FOR VALVES 1e:46 WEDNESDAY, JULY 5, 198~

DRESDEN UHITS 2 ~ 3 HRC SUBMITTAL

SORTED BY: VALVE EPtf PAGE: 21

VALVE ACT NOR STR TEST REL EPH SIZE Piii CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REllARKS

----------------------------------------------------------------------------------------------------------------------------------

3-1~1-57 1.5 356 SD SR A GL KO D c A AT RR VR-6 DAIH-V1 BT OP PIT RR

3-1~1-58 t.5 356 7D SR A GL AO c c A AT RR VR-6 DAIH-VI BT DP FST OP PIT RR

3-1681-59 1.5 356 6)) SR A GI. AO D c ft AT RR VR-6 BT OP FST OP PIT RR

3-1691-be. 18 356 2E SR A BTF AO c c A AT RR VR-6 DAIH-Vt BT DP FST OP PIT RR

3-16$1-61 2 :m 2E SR A GA AO c O/C A AT RR VR-6 DAIH-V1 BT OP FST OP PIT RR

3-16$1-62 2 356 38 SR A GI. AO c O/C A AT RR VR-6 BT OP FST OP PIT RR

3-1681-63 6 356 2A SR A BTF AO c O/C A AT RR VR-6 DAIH-V1 BT DP FST OP PIT RR

3-1699-63/t .75 356 9E SR A GL lfAff 0 0 p AT RR VR-6

3-1699-638 .75 356 2E SR A GL HAH 0 0 P AT RR VR-6

3-1699-85A • 75 356 7F SR A GL KAH 0 D P AT RR VR-6

3-1699-96 • 75 356 2F SR A GL HAH 0 D P . AT RR VR-6


TEST SCHED: OP-HORHAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAlt-SAt!Pl.IN& PLAN TECHHIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•


HRC SUBMITTAL

10:46 WEDNESDAY, JULY 5, 198(


VALVE ACT HOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

3-190t-27A 6 362 3E NSR C CK SA O/C 0 A CT-0 OP CT-C OP

3-19ef-27B 6 362 3F NSR C CK SA O/C 0 A CT-0 OP CT-C OP

3-1991-46 6 362 6E NSR B GA AO C 0 A BT OP

3-2&eH&6 3 369 7f SR A GA AO O/C C A AT RR VR-6 DAIK-V1 BT OP PIT RR FST OP

3-2001-6 3 369 3E SR A GA AO O/C C A AT RR VR-6 DAIK-V1 BT OP PIT RR FST OP

3-2301-64 374 SA SR B GL AO 0 c A BT OP FST OP PIT RR

3-2301-6S 374 6A SR B GL AO 0 c A BT OP FST OP PIT RR

3-2399-76A 374 SD SR C CK SA c O/C A CT-0 SAM VR-19 CT-C SAM

3-2399-768 374 SD SR C CK SA c O/C A CT-0 SAM VR-19 CT-C SAit

3-2399-77A 374 SD SR C CK SA c O/C A CT-0 SAM VR-19 CT-C SAtf

I.

3-2399-778 374 SD SR C CK SA c O/C A CT-0 SAM VR-19 CT-C SAM

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITIOH INDICATOR CHECK.

PA&E: 22

TEST SCHED: OP-NORi'IAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELINb; SAK-SAi'IPLING PLAN TECHNIQUE; SY-ONCE EVERY S YEARS.

•

•

•


NRC SUBHITTAL




---------------------~------------------------------------------------------------------------------------------------------------

3-2541-01 1.25 787-2 6A SR C CK SA C 0 A CT-0 OP

3-2599-B 8.5 797-2 AB SR C CK SA C 0 A CT-0 OP

3-4162 4 359 5C NSR B GA JtO c 0 A BT OP PIT RR

3-4699-311A 6.5 173 4F SR C CK SA c O/C A CT-0 OP CT-C OP

3-4699-31tB 6.5 173 6F SR C CK SA c O/C A CT-0 OP CT-C OP

3:-4699-312 1.5 173 5D SR C CK SA c O/C A CT-0 OP CT-C OP

3-4699-313A . e.5 173 3D SR C RY SA c 0 A RT SY

3-4699-313B e.5 173 5D SR C RV SA C 0 A RT 5Y

3-4699-314A e.5 173 4D SR C · RY SA C 0 A RT 5Y

3-4699-314B e.5 173 6D SR C RV SA C 0 A RT 5Y

3-4729 367-2 7C SR A GA AO 0 C A AT RR BT OP FST OP PIT RR

VR-6 DAIK-VI


TEST SCHED: OP-HOR/tAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAll-SAtlPLING PLAN TECHNIQUE; 5Y-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAlt FOR VALVES DRESl>EN ~ITS 2 & 3

HRC SUBMITTAL

19: 46 WEMESD~ y I JUL y 5 I 198'

SORTED BY: VALVE EPH PA(;[: 24


----------------------------------------------------------------------------------------------------------------------------------

3-4721 367-2 7C SR A GA AO 0 c A AT RR VR-6 BT OP FST OP PIT RR

3-4722 367-2 2E SR A GL AO 0 c A AT RR VR-6 DAilt-Vt3 BT cs FST cs PIT RR

3-4799-511 e.5 367-2 5F SR A GA so 0 c A, AT RR VR-6 BT OP

3-4799-514 9.5 367-2 4F SR AC CK SA 0 C A AT RR VR-6 DAIH-V21 CT-C CS




3-5291-RV 2.& 41-2 5B SR C RV SA C 0 A RT 5Y

3-52&1-SO t.5 41-2 5C SR B GA SO C O/C A BT OP

3-5292 1.5 41-2 7D SR B GA SO C C A BT OP

3-5292-A-599 1.5 41-2 5B SR C CK SA C 0 A CT-0 OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-O~CJIECK VALVE EXERCISE.OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-P3SITIOH INDICATOR CHECK.

TEST SCHED: OP-HORKA!. OPERATION; CS-COLD SHUTOOWN; RR-REACTOR REFUELING; SAH-SAKPLING PLAN TECHHIQUE; 5Y-OHCE EVERY 5 YEARS.

•

•

•


NRC SUBMITTAL

f&: 46 WEDNESDAY I JULY s I 1985

SORTED BY: VALVE EPM PAGE: 25

VALVE !)CT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMARKS

----------------------------------------------------------------------------------------------------------------------------------

3-5292-B-599 f.5 41-2 SB SR C CK SA C 0 A CT-0 OP

3-5203 1.5 41-2 SD SR B GA SO C C A BT OP

3-5425 48 371-1 BB SR C RV SA C 0 A RT 5Y

3-5741A 48 529 1A SR B BTF AO 0 c A BT OP PIT RR FST OP

3-5741B 48 529 1A SR B BTF AO 0 c A BT OP PIT RR FST OP

3-5742A . 48 529 &B SR B BTF AO 0 c A BT OP PIT RR FST OP

3-5742B 48 529 98 SR B BTF AO 0 c A BT OP PIT RR FST OP

3-6999-103 .375 173 &A SR B GA so c 0 A BT OP

3-6999-104 .375 173 GA SR C CK SA C 0 A CT-0 OP

3-7593 18 49 2A SR B BTF tlO 0 O/C A BT OP PIT RR

3-8501-IA 9.5 356 2E SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST1 BT-FULL STR(Jl(E EXERCISE; CT-0-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSE]); RT-RELIEF VALVE TEST; BT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PiT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORffAL OPERATION; CS-COLD SHUTDOWN; RR-REACTOR REFUELING; SAff-SAttPLINli PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 1&:46 WEDNESDAY I JULY 5, 198 DRESDEN UHITS 2 & 3

HRC SUBHITTAL


VALVE ACT NOR STR TEST REL EPN SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED REQ REMRKS

----------------------------------------------------------------------------------------------------------------------------------

3-8501-fB e.5 356 2E SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-8501-3A &.5 356 4D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-85&1-3B &.5 356 4D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-8561-SA e.5 356 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-8561-SB e.5 356 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-8526 .75 356 BD SR c RY SA c 0 A RT SY

3-8941-1&1 &.5 t24e 6C SR B GA AO c c p N/A

3-8941-709 e.s 1239-1 5E SR B GA AO c 0 A BT OP FST OP PIT RR

3-8941-719 9.5 1239-1 5)) SR B GA AO c 0 A BT {)p FST OP PIT RR

3-9295A 9.5 356 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP.

3-9295B 9.5 356 3D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-flll..L STROKE EXERCISE; CT-o-cHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; OT-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORKAL OPERATION; CS-COLD SHUTDOllH; RR-REACTOR REFUELING; SAfl-SAi'IPLING PLAN TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM FOR VALVES 1&:46 WEDNESDAY, JULY 5, 1981

DRESDEN ~ITS 2 & 3 HRC SUBHITTAL

SORTED BY: VALVE EPH PAQ:: 27

VALVE ACT NOR STR TEST REL EPH SIZE PID CORD CLS CAT TYPE TYPE POS DIR A/P TEST SCHED · REQ REi'IARKS

-------------------------------------------------------------------------------------------------------------~--------------------

3-9206A e.s 356 4D SR A FCV AO 0 . c A AT RR VR-6 BT OP PIT RR FST OP

3-9~6B e.s 356 4D SR A FCV AO 0 c A Al RR VR-6 BT OP PIT RR FST OP


3-92978 9.5 356 6D SR A FCV AO 0 c A AT RR Vlt-6 BT OP PIT RR FST OP

3-92eSA e.5 356 6D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

3-92&8B e.s 356 6D SR A FCV AO 0 c A AT RR VR-6 BT OP PIT RR FST OP

TEST: AT-SEAT LEAKAGE TEST; BT-FULL STROKE EXERCISE; CT-0-CHECK VALVE EXERCISE OPEN, CT-C-CHECK VALVE EXERCISE CLOSED; RT-RELIEF VALVE TEST; DI-EXPLOSIVE VALVE TEST; FST-FAIL SAFE TEST; PIT-POSITION INDICATOR CHECK.

TEST SCHED: OP-NORllAL OPERATIOH; CS-COLD SHUTDOWN; RR-REACTOR REFUEL!!&; SAlt-SA'IPLING PLAH TECHNIQUE; SY-ONCE EVERY 5 YEARS.

•

•

•

IST PROGRAM REV 3 DAIM

DESIGNATION

DAIM-Vl

DAIM-V2 DAIM-V3 DAIM-V4

DA IM-VS

DAIM-:V6 DAIM-V7 DAIM-V8 DAIM-V9 DAIM-VlO

DAIM-Vll

DAIM:....v12 DAIM-V13

DAIM-V14 DAIM-VlS DAIM-Vl6

DAIM-Vl7 DAIM-V18

DAIM-Vl9

DAIM-V20 DAIM-V21

DAIM-V22 DAIM-V23

DAIM-V24

DAIM-V25

130Sa/29

DAIM VALVE INDEX P~GE 1 OF 1 DRESDEN IST PROGRAM REV 3

July 1, 1989

DRESDEN ADDITIONAL INFORMATION/METHODOLOGY INDEX

IST PROGRAM REV. 2 DAIM

DESIGNATION

DAIM-Vl

DAIM-V2 DAIM-V3 DAIM-V4

DA IM-VS

DAIM-V6 DAIM-V7 DA IM-VB DAIM-V9 DAIM-VlO

DAIM-Vll

DAIM-Vl2 DAIM-V13

DAIM-V14 DAIM-VlS DAIM-V16

DAIM-V17 DAIM-V18

DAIM-Vl9

DAIM-V20 DAIM-V21

DAIM-V22 DAIM-V23

DAIM-V24

NIA

DESCRIPTION

VALVE TIMING FOR STROKE TIMES GREATER THAN 2 SECONDS LIST OF PRESSURE ISOLATION VALVES RUPTURE DISK TESTS CRD CHARGING WATER ACCUMULATOR CHECK VALVES, EXERCISE DURING COLD SHUTDOWNS RECIRC PUMP DISCHARGE VALVE, EXERCISE DURING COLD SHUTDOWNS DELETED - SEE RELIEF REQUEST VR-16 DELETED - SEE RELIEF REQUEST VR-17 DELETED DELETED - SEE RELIEF REQUEST VR-20 CS, LPCI & HPCI CHECK VALVES, EXERCISE DURING COLD SHUTDOWN HPCI ISOLATION CHECK, EXERCISE DURING LEAK TEST DELETED - SEE RELIEF REQUEST VR-21 INSTRUMENT AIR ISOLATION, EXERCISE DURING COLD SHUTDOWN DELETED - SEE RELIEF REQUEST VR-15 DELETED - SEE RELIEF REQUEST VR-24 MS ELECTROMATIC AND TARGET ROCK VALVES, EXERCISE DURING COLD SHUTDOWNS, _SEE ALSO RELIEF REQUEST VR-16 · DELETED - SEE RELIEF REQUEST VR-23 CAM ISOLATION VALVES, EXERCISE DURING COLD SHUTDOWNS ACAD PRIMARY CONTAINMENT ISOLATION VALVES, EXERCISE DURING COLD SHUTDOWNS DELETED TIP CONTAINMENT ISOLATION VALVES, EXERCISE DURING COLD SHUTDOWNS CHECK VALVE DISASSEMBLY PROGRAM RBCCW CONTAINMENT ISOLATION VALVES, EXERCISE DURING COLD SHUTDOWN

. MAIN STEAM ISOLATION VALVES, EXERCISE DURING COLD SHUTDOWN LPCI CROSS-TIE VALVES, EXERCISE DURING COLD SHUTDOWNS

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•

•

DAIM-Vl Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-Vl

1. Description

Valve timing.alert ranges for valves with stroke times greater than 2 seconds.

2. Discussion

2.1. Most air operated (AO) and motor operated (MO) valves have maximum stroke times that are much longer than actual stroke times. For example, M0-1301-3, Isolation Condenser Condensate Return Isolation Valve, has a maximum acceptable stroke time of 30 seconds but typically strokes in about 2 seconds. Stroke times could increase moderately (less than 50%) over successive tests and not trigger any closer observations, thus not allowing detection and corrective action. Degradation in such valves could then be severe before corrective actions would be takenl.

2.2. Errors have occurred with analyzing stroke times. Some valves with stroke times that have increased by over 50% from previous tests have not been placed in the Alert Range for closer observation and to allow detection and corrective action should further degradation occur. Providing a known Alert Range and Maximum Stroke Time, will eliminate these errors.

3. Alternative Valve Timing

3.1. In accordance with ASME Section XI IWA-2240, Dresden Nuclear Station has determined an alternative test method which is equivalent or superior to those of ASME Section XI, IWV-3413(c). Specifically, the test method provides for alternative valve timing, Reference Values, Alert Stroke Time and Maximum Stroke Time for the valves tested in the IST Program. A summary of the determination of these timed action ,, ranges are provided below.

3.2. Valves that require timing have their reference values established after the first normally scheduled inservice testing of these valves. These valve timing Reference Values shall then be added to their respective surveill~nce procedure's data sheet for use.

linstitute of Nuclear Power 0.E>erations' (INPO) July 1987 Evaluation of Dresden Station. Page 37; Finding (TS.2-1) .

1305a/30

•

•

•

DAIM-Vl P~ge 2 of 2 Dresden IST Program Rev. 3 July 1, 1989

3.2.1. Stroke time Reference Values are established during the first normally scheduled inservice test'ing of the specific valve. These reference values are used to determine the alert stroke time limits.

3.2.2. Maximum Stroke Times for the valves tested in the IST Program are determined by the Technical Specifications. If Maximum Stroke Times are not included in the Technical Specifications, then the FSAR and valve manufacturer will be researched to establish the maximum stroke time. If maximum stroke times are unavailable in these documents, then a calculation will be performed for the establishment of the maximum stroke time. The details of this calculation are specified in the administrative procedure controlling the IST Program, Dresden Administrative Procedure (DAP) 11-21, Inservice Testing Program for Pumps and Valves.

3.2.3. The Alert Stroke Time limit for each valve is determined as follows:

3.2.3.1. For valves with a reference value stroke time from 2 to 10 seconds, the Alert Stroke Time limit is equal to 1.5 times the reference value. If the Alert Stroke Time limit calculated this way exceeds the Maximum Stroke Time, then the Alert Stroke Time is equal to 1.2 times the reference value •

3.2.3.2. For valves with a reference value stroke time greater than 10 seconds, the Alert Stroke Time limit is equal to 1.25 times the reference value. If the Alert Stroke Time limit calculated this way exceeds the Maximum Stroke Time, then the Alert Stroke Time is equal to 1.15 times the reference value.

NOTE: In no case will the Alert Stroke Time Limit exceed the Maximum Stroke Time Limit.

4. Valve Stroke Ti.me Measurement

4.1. Measurement of valve stroke times is from the initiation of switch movement to the previously illuminated light going off. This is referred to as "switch-to-light' valve timing .

1305a/31

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DAIM-V2 Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-V2

1. Description

1.1. This DAIM addresses and identifies Pressure Isolation Valves (PIVs). PIVs are defined for each interface as any two valves in series within the reactor coolant pressure boundary which separates the high pressure reactor coolant system (RCS) from an atta_ched low pressure or low temperature system. These valves are normally closed during power operation.

1. 2. All the PIVs are Category A Valves in the IST Program and receive Appendix J type leak tests.


IST Valve EPN Size CAT Class

2-1402-9A 1011 AC 2-1402-9B 1011 AC 2-1402-25A 10 11 A· 2-1402-25B 1011 A 2-1501-25A 1411 AC 2-1501-25B 1411 AC 2-1501-22A 18 11 A 2-1501-22B 18 11 A 2-1001-lA 16 11 A 2-1001-lB 16 11 A 2:.::100l-2A 1411 A 2-1001-2B 1411 A 2-1001-2C 1411 A 2-1001-SA 1411 A 2-1001-SB 1411 A 3-1402-9A 1011 AC 3-1402-9B 10 11 AC 3-1402-25A 1011 A 3-1402-25B 1011 A 3-1501-25A 1411 AC 3-1501-25B 1411 AC 3-1501-22A 18 11 A .1-1501-22B 1811 A

_ 3-1001-lA 16" A 3-1001-lff 16 11 A 3-1001-2A 1411 A 3-1001-2B 1411 A 3-1001-2C 1411 A 3-1001-SA 1411 A 3-1001-SB 1411 A

1305a/32

1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 l 1 1 1 1 1 1

P&ID/CORD Function

27/3C Core Spray Inboard Check· 27/4C II

27/2C Core Spray Outboard Injection 27/5C II

29-1/SB LPCI Loop I Injection Check 29-l/4B LPCI Loop II Injection Check 29-l/7B LPCI Injection Isolation 29-l/3B II

. 32/9B SDC Inlet Isolation 32/9E II

32/8A SDC Pump Suction Isolation 32/BC II

. 32/BF II

32/lE SDC Outlet Isolation 32/2E II

-358/3C Core Spray Inboard Check 358/4C II

358/2C Core Spray Outboard Injection 358/SC II

360-1/SB Loop I Injection Check Valve 360-l/4B Loop II Injection Check-Valve 360-l/3A Injection Isolation 360-1/?A II

363/9B Inlet Isolation 363/9E II

363/8A Pump Suction Isolation 363/8C II

. 363/BF II

363/lE Outlet Isolation 363/2E II

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•

2. Discussion


2.1. All valves listed in Section 1.3 are also primary containment isolation (PCI) valves that are tested in accordance with 10 CFR 50 Appendix J, Dresden Technical Staff Surveillance Procedure DTS-1600-1, Local Leak Rate Testing of Primary Containment Isolation Valves. These PCI valves are tested using DTS 1600-1 and DTS 1600-9 every refueling outage (or at least once every two years) and after valve maintenance .

1305a/33

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1. Description

2.

1.1. Rupture Disk Tests.


IST Valve EPN Size CAT Class P&ID/CORD Function

2-2301-68 16" c 2 51/7A HPCI Turbine Exhaust 2-2301-69 16" c 2 51/7A " 3-2301-68 16" c 2 374/7A II

3-2301-69 16 11 c 2 374/7A II

Discussion

2.1. These Rupture Disks are of a non-testable design and provide a vent path on high exhaust pressure from the High Pressure Coolant Injection turbine.

2.2. ASME Section XI IWV-3620 Rupture Disk Tests, requires only rupture disks of testable design shall be tested. Because these rupture disks are of a non-testable design, no testing is required .

1305a/34

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1. Description.

2.

1.1. ASME Section XI IWV-3522, Exercising Procedure, states in part "Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns."

1.2. This DAIM provides documentation for exercising the listed components during Cold Shutdown.



2-0305-115 • 5" c 1 34/0E CRD Accumulator Backf low to Charging Water Line

3-0305-115 . 5" c 1 365/0E II

Discussion

2.1. In order to verify closure of these valves, the control rod drive pump would need to be secured. In doing this, the seal purge water flow to the recirculation pump seals and cooling water to the control rod drive seals would be stopped and possible damage to these seals could result •

Check

2.2. Therefore, these valves will be exercised during Cold Shutdown outages when the charging water header can be depressurized. Monitoring individual accumulator pressure and alarms will be performed to verify that the check valves have closed on reversed flow .

1305a/35

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DAIM-VS Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-VS

1. Description

2.


1.2. This DAIM provides documentation for exercising the listed components during cold shutdown.



2-0202-SA 28" B 1 26-2/6D Recirc Pump Discharge Valve 2-0202-SB 28" B 1 26-2/3C II

3-0202-SA 28" B 1 357-2/6D II

3-0202-SB 28" B 1 357-2/3D II

Di§cussion

2.1. For Unit 2, the discharge valves cannot be full stroke tested during reactor operation because it would require a load drop (of approximately 400 megawatts) to a minimum recirculation pump speed of 28%. This is deemed impractical.

2.2. For Unit 3, the discharge valves cannot be full stroke tested during reactor operation because it would require a load drop to a minimum recirculation pump speed of 28% and insertion of control rods to achieve less than 80% Flow Control Line. The closure logic for these valves would result in the recirculation pump trip and would place the plant in an unwanted system/power transient, as well as in Technical Specifications LCO.

2.3. The potential of operating in the prohibited region of the power flow map [above 80% Flow Control Line (FCL), below 39% core flow] exists when one (1) recirculation pump is shut down. The low flow/high power region of the operating map typically exhibits less margin to stability than other regions. Instabilities result in LPRM and APRM Oscillations significantly greater than normal noise levels.

2.3.1 Reference Procedure DOP 202-10, Recirculation System Shutdown of One Pump

1305a/36

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ADDITIONAL INFORMATION/METHODOLOGY DAIM-VS

2.4. To place the plant in this potential condition is deemed not practical. ·

2.5. Therefore, these valves will be full stroke tested during cold shutdown conditions .

1305a/37

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DAIM-VlO Page 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODQLOGY DAIM-VlO

1. Description

2 .

1.1. ASME Section XI IWV-3412, Exercising Procedure, states in part "Valves that cannot be exercised during plant operation shall be specifically identified by· the Owner and shall be full-stroke exercised during cold shutdowns."




2-1402-9A 10" AC 1 27/3C Core Spray injection check 2-1402-9B 10" AC 1 27/4C " 3-1402-9A 10" AC 1 358/3C Core Spray injection check 3-1402-9B 10" AC 1 358/4C " 2-1501-25A 14" AC 1 29-1/SB LPCI injection check 2-1501-25B 14" AC 1 29-l/4B " 3-1501-25A 14" AC 1 360-l/4B LPCI injection check 3-1501-25B 14" AC 1 360-l/4B "

Dis~ussiQn

2.1. During normal plant operation, the high differential pressure across the seats of the CS and LPCI valves prohibits the stroking of these valves. Additionally, for CS and LPCI valves, the reactor pressure is too high for the system and injection into the reactor is not possible.

2.2. Therefore, these valves will be exercised during cold shutdown .

1305a/38

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DAIM-Vll Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-Vll

1 . Description

2.


1. 2. This DAIM provides documentation for exercising the listed components during cold shutdown.

1. 3. Component description:

!ST Valve EPN Size CAT Class P&ID/CORD Function

2-2301-34 2" AC 2 51/8D HPCI Exhaust Drain to Torus 3-2301-34 2" AC 2 374/8D II

2-2301-45 24" AC 2 51/8B HPCI Exhaust to Torus 3-2301-45 24" AC 2 374/8B II

2-2301-71 2" AC 2 51/8D HPCI Steam Exhaust Stop Check to Torus

3-2301-71 2" AC 2 374/8D HPCI Steam Exhaust Stop Check to Torus

2-2301-74 12" AC 2 51/8C HPCI Steam Exhaust to Torus Check

3-2301-74 12" AC 2 374/8C HPCI Steam Exhaust to Torus Check

Di§cussiQn

2.1. These valves have a safety function in the open direction for proper operation of the HPCI system and they also have a safety function in the closed direction for primary containment isolation.

2.2. These valves are considered to be open as demonstrated during HPCI surveillance tests. To verify closure, as is required for containment isolation, these valves will be tested during the leakage test requirements of Category A testing.

2.3. These valves are leak rate tested per Appendix J requirements every reactor refueling outage •

1305a/39

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DAIM-Vll Page 2 of 2 Dresden IST Program Rev. 3 July 1, 1989

2.4. Verification that these valves are closed is not readily possible during normal operation. These valves open when operating the HPCI Turbine. Verification of closure would require manual exercising of the stop checks which would require securing the HPCI Turbine. This is not considered to be a safe practice and would require Dresden to enter a Limiting Condition of Operation with the HPCI system inoperable.

2.5. Therefore, these valves will be exercised during cold shutdown .

1305a/40

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DAIM-Vl3 Page 1 of 1 Dresden IST Program Rev. 3 July 1, 1989


1 . Description

2 .

1.1. ASME Section XI IWV-3412, Exercising Procedure, states in part "Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be full-stroke exercised during cold·shutdowns."

1.2. ASME Section XI IWV-3415, Fail-Safe Valves, states in part "When. practical, valves with fail-safe actuators shall be tested by observing the opertion of the valves upon loss of actuator power. If these valves cannot be tested once every 3 months, they shall be tested during each cold shutdown;"

1.3. This DAIM provides documentation for exercising and fail-safe ·testing the listed components during Cold Shutdown.


IST Valve EPN Size CAT Class P&ID/CORP Function

2-4722 l" A SR 37-2/2E Instrument Air Containment Isolation (drywell pneumatic)

3-4722 l" A SR 367-2/7C II

Dis~YJZSiQn

2.1. The 2(3)-4722 valves provide the containment isolation function for the instrument air system which supplies various fail-safe valves, including the Main Steam Isola~ion Valves (MSIV's). Exercising and fail-safe testing of the 2(3)-4722 valves during reactor operation could cause the instrument air system to bleed down should the 2(3~-4722 fail closed. Without air to hold open the MSIV's, the MSIV's would be exercised to their fail-safe position (closed). Closure of the MSIV's during reactor operation would cause transient conditions which would result in a reactor scram and loss of the reactor's primary heat sink.

2.2. Therefore, these valves will be exercised and fail-safe tested during cold shutdown periods .

1305a/41

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1.

2.

DAIM-Vl6 hge 1 of 1 Dresden IST Program Rev. 3 July 1, 1989


Description





2-0220-105A 8" c SR 25/5E Main Steam Relief Valve Discharge Piping Vacuum Breaker Check Valves

2-0220-105B 8" c SR 25/5E II

2-0220-105C 8 II c SR 25/5E II

2-0220-105D 8 II c SR 25/5E II

2-0220-105E 8" c SR 25/5E II

3-0220-105A 8" c SR 356/5E II

3-0220-105B 8" c SR 356/5E II

3-0220-105C 8" c SR 356/5E " 3-0220-lOSD 8" c SR 356/5E II

3-0220-105E 811 c SR 356/5E II

Discussion

2.1. These valves provide vacuum relief on the main steam electromatic and target rock relief valve piping to the torus. They are normally closed and are required to open on vacuum when steam, which has been blown down to the torus, is condensing.

2.2. To exercise these valves would require reducing reactor power, de-inerting and entering the Drywell and manually exercising the valves. The minimal dose rate in the drywell would be 200 millirem per hour. This test is impractical to perform during normal operation.

2.3. Therefore, these valves will be exercised during cold shutdowns when the drywell is de-inerted.

2.4. Also see Relief Request VR-16 .

1305a/42

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DAIM-Vl8 Page 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHQDQLOGY DAIM-V18

1 . Description ·

1.1. ASME Section XI IWV-3522, Exercising Procedure, states in part "Valves that cannot be exercised during plant operation shall. be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns."

1.2. This DAIM provides documentation for exercising the listed components during cold shutdowns.

1.3. Component descriptio?:


2-2499-28A 0.5" AC 2 706-l/7C Containment Air Monitor System Containment Isolation

2-2499-28B 0.5" AC 2 706-l/2C II

3-2499-28A 0.5 11 AC 2 706-2/7C " 3-2499-28B 0.5" AC 2 706-2/7C II

2. Discussion

2.1. ~hese valves are normally open and are required to close for containment isolation, additionally they are required to be open for proper operation of the containment atmosphere monitor system. To verify closure would require securing the system, and disconnecting the line and air back pressurizing. This would violate primary containment during operation. Verification of closure is performed during cold shutdown leak testing.

2.2. Therefore, these valves will be exercised during cold shutdowns •

1305a/43

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DAIM-Vl9 Page 1 of l Dresden IST Program Rev. 3 July 1, 1989

ADDITIONAL INFORMATION/METHODOLOGY DAIM-Vl9

1. Description


1. 2. This DAIM provides documentation for exercising the listed components during cold shutdowns.



2-2599-23A 1 AC 2 707-l/6C Primary Containment Isolation Valve

2-2599-23B 1 AC 2 707-l/3C 2-2599-24A 1 AC 2 707-l/6C 2-2599-24B 1 AC 2 707-l/3C 3-2599-23A 1 AC 2 707-2/6C 3-2599-23B 1 AC 2 707-2/3C 3-2599-24A 1 AC 2 707-2/6C 3-2599-24B 1 AC 2 707-2/3C

2. Discussion

2.1. These valves are normally closed and are required to close for containment isolation, additionally they are required to open for proper operation of the atmospheric containment atmosphere dilution system. These valves are exercised open every quarter; however, to verify closure would require securing the Atmospheric Containment Atmosphere Dilution system, disconnecting the piping and air back pressurizing. This testing is impractical to perform during power operation due to the amount of piping needed to be disconnected and the time constraints of performing the test.

2.2. Therefore, these valves will be verified closed during cold shutdowns and verified open quarterly .

1305a/44

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DAIM-V21 Page 1 of l Dresden IST Program Rev. 3 July 1, 1989


1. Description





2-4799-514 0. 5" AC SR 37-2/4F TIP Nitrogen Purge Containment Isolation

3-4799-514 0.5" AC SR 367-2/4F II

2. Discussion

2.1. These valves are normally open and are required to close for containment isolation. These check valves are required to be open during operation to maintain a constant nitrogen purge. Exercising of these valves requires disconnecting the line downstream of the valves and applying external pressure to back seat the valves. To secure the TIP system during operation in order to exercise these valves is not considered practical, and would result in violating primary containment.

2.2. Therefore, these valves will be exercised during cold shutdowns when the drywell is de-inerted .

1305a/45

DAIM-V22 Page 1 of 3 . Dresden IST Program Rev. 3 July 1, 1989


• 1. Description

1.1. This information is intended to provide information/documentation for the disassembly and inspection of Category C check valves for which relief has been requested from ASME Section XI, IWV-3522.

1.2 Specific valve relief requests have been submitted for the valves listed in Section 1.3.

1. 3. Component Description

' RELIEF REQUEST

VALVE EPN SIZE P&ID COOR CL CAT TYPE NO. GROUP FUNCTION

2-1402-34A 0.75 27 8D 2 c CK VR-13 1 . CS KEEP FILL CHECK 2-1402-34B 0. 7S 27 6D 2 c CK VR-13 1 CS KEEP FILL CHECK 2-lSOl-67A 2.0 29-1 BF 2 c CK VR-14 2 LPCI KEEP FILL CHECK 2-1S01-67B 2.0 29-1 2F 2 c CK VR-14 2 LPCI KEEP FILL CHECK 2-2301-39 16.0 Sl 9E 2 c CK VR-lS 3 HPCI TORUS SUCTION CHK 2-23S4-SOO 0.7S Sl 6E 2 c CK VR-18 4 HPCI KEEP FILL 2-2399-76A 1.0 Sl SD SR c CK VR-19 s HPCI TURB EXH VAC BRK 2-2399-76B 1.0 51 SD SR c CK VR-19 5 HPCI TURB EXH VAC BRK 2-2399-77A 1.0 Sl SD SR c CK VR-19 5 HPCI TURB EXH VAC BRK

• 2-2399-77B 1.0 51 SD SR c CK VR-19 s HPCI TURB EXH VAC BRK 2-1301-11 4.0 28 3C 3 c CK VR-11 .6 ISO CONDENSER MAKEUP 2-1301-36 4.0 28 SD 3 c CK VR-11 6 ISO CONDENSER MAKEUP 2-4107-SOl 4.0 28 SC 3 c CK VR-11 6 ISO CONDENSER MAKEUP 3-1402-34A 0.7S 3S8 SD 2 c CK VR-13 7 CS KEEP FILL CHECK 3-1402-34B 0.7S 358 6D 2 c - CK VR-13 7 CS KEEP FILL CHECK 3-1S01-67A 2.0 360-1 BF 2 c CK VR-14 8 LPCI KEEP FILL CHECK 3-1S01-67B 2.0 360-1 2F 2 c CK VR-14 8 LPCI KEEP FILL CHECK 3-2301-39 16.0 374 BE 2 c CK VR-lS 9 HPCI TORUS SUCTION CHK 3-23S4-SOO 0. 75 374 7C 2 c CK VR-18 10 HPCI KEEP FILL 3-2399-76A 1.0 374 8D SR c CK VR-19 11 HPCI TURB EXH VAC BRK 3-2399-76B 1.0 374 8D SR c CK VR-19 11 HPCI TURB EXH VAC BRK 3-2399-77A 1.0 374 SD SR c CK VR-19 11 HPCI TURB EXH VAC BRK 3-2399-77B 1.0 374 SD SR c CK VR-19 11 HPCI TURB EXH VAC BRK 3-1301-11 4.0 359 3C 3 c CK VR-11 12 ISO CONDENSER MAKEUP 3-1301-36 4.0 3S9 SD 3 c CK VR-11 12 ISO CONDENSER MAKEUP 3-4107-SOl 4.0 359 SC 3 c CK VR-11 12 ISO CONDENSER MAKEUP

• 1305a/46

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2. Discussion


2.1 Check Valve Exercising

2.1.1

2.1.2

ASME Section XI provides an exercise procedure for Category C valves. When direct or indirect methods of exercising check valves are not available or when it is impractical to exercise a valve using system flow, the check valve will be disassembled and inspected using a sampling technique.

For check valves which cannot be verified operable by standard ASME test procedures, Dresden station will prove operability by disassembly/inspection.

2.2 Test Frequency

2.2.1 Check valves will be disassembled and inspected on a refueling outage basis only.

2.3 Sampling Technique

2.3.1

2.3.2

2.3.3

The sampling technique utilized by Dresden requires that one valve from each valve Unit Grouping be disassembled and inspected each reactor refueling outage. More than one valve may be disassembled and inspected each refueling outage depending on outage duration .

A different valve in each valve Group will be disassembled and inspected at subsequent refueling outages.

All valves in each valve Group will be disassembled and inspected once before any one valve is disassembled and inspected twice. The scheduling will continue for subsequent inspections.

2.4 Check Valve Groupings

2.4.1

1305a/47

Valve Groups are defined as each valve in a group having .the following identical characteristics:

a. Unit b. Manufacturer c. Size d. Model number e. material of construction f. Service conditions (i.e. process fluid, temperature,

pressure, flow, etc.)

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2:5 Disassembly/Inspection (Exercising)

1305a/48

2.5.l Upon valve disassembly, a visual inspection of the valve internals is performed to ensure that all parts are intact and structurally sound (no loose or corroded parts).

2.5.2 During the visual inspection, the valve disk is manually exercised to ensure the valve is capable of full-stroking.

2.6 Corrective Actions

2.6.l

2.6.2

If the disassembled valve's full stroke capability is in question, the remaining valves in that group will be disassembled, inspected and ful'l-stroke exercised during the same refueling outage.

If any valve fails to exhibit full stroke capability, the valve shall be repaired or replaced in accordance with the corrective actions of IWV-3427(a) •

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ADDITIONAL INFORMATION/METHODQLOGY DAIM-V23

1. Description

2 .


1.2. This DAIM provides documentation for exercising the listed components during Cold Shutdown.



2-3702 6 A 2 20/3B Reactor Building Containment Isolation

2-3703 6 A 2 20/lB II

2-3706 6 A 2 20/lB II

3-3702 6 A 2 353/3B II

3-3703 6 A 2 353/lB II

3-3706 6 A 2 353/lB II

DiscussiQn

2.1. These valves are normally open and are required to close for containment isolation. They provide primary containment isolation for the reactor building cooling water system. To exercise these valves to the closed position would require both recirculation pumps to be out of service because the recirculation pumps require seal purge for operation. This action is considered impractical during normal operation.

2.2. These valves will be exercised during Cold Shutdown •

1305a/49

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ADDITIONAL INFORMATION/METHQDQLOGY DAIM-V24

1 . Description

1.1. ASME Section XI IWV-3415, Fail-Safe Valves, states in part "When practical, valves with fail-safe actuators shall be tested by observing the opertion of the valves upon loss of actuator power. If these valves cannot be tested once every 3 months, they shall be tested during each cold shutdown:"

1.2. This DAIM provides documentation for fail-safe testing the listed components during Cold Shutdown.



2-0203-lA 20" A 1 12-l/4E Main Steam Isolation Valves 2-0203-lB 20" A 1 12-l/4D 2-0203-lC 20" A 1 12-l/4C 2-0203-lD 20" A 1 12-l/4B 2-0203-2A 20" A 1 12-2/7F 2-0203-2B 20" A 1 12-2/7E . ) 2-0203-2C 20" A 1 12-2/7D

· 2-0203-2D 20" A 1 12-2/7C 3-0203-lA 20" A 1 345-l/4E 3-0203-lB 20" A 1 345-l/4D 3-0203-lC 20" A 1 345-l/4C 3-0203-lD 20" A 1 345-l/4B 3-0203-2A 20" A 1 345-2/7F 3-0203-2B 20" A 1 345-2/]E 3-0203-2C 20" A 1 345-2/7D 3-0203-2D 20" A 1 345-2/]C

2. Discussion

2.1. These valves are normally open and are required to close for containment isolation. They provide primary containment isolation for the main steam system. ·These valves are air operated open and air to close with spring assist. To completely fail-safe exercise these valves to the closed position, the air lines to the valves must be disconnected. Thus, with the loss of air, the fail-safe mechanism (springs) would be demonstrated. The resultant exercising of the MSIV's could place the plant in an unsafe mode of operation causing transient conditions which would result in a reactor scram.

2.2. These valves will be exercised during Cold Shutdown •

1305a/50

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ADDITIONAL INFORMATION/METHODQLOGY DAIM-V25

1. Description

2.

1.1. ASME Section XI IWV-3412, Exercising Procedure, states in part "Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be fullstroke exercised during cold shutdowns."




2-1501-32A 18" B 2 29-1/SD LPCI Cross-tie 2-1501-32B 18" B 2 29-l/2D LPCI Cross-tie 3-1501-32A 18" B 2 360-1/8D LPCI Cross-tie 3-1501-32B 18" B 2 360-l/2D LPCI Cross-tie

Dis!;us§ion

2.1. These cross-tie valves are normally open to allow all four of the LPCI pumps to inject through one set of injection valves. This prevents pump damage as well as allowing all four pumps to inject.

2.2. Since these valves do not auto-open on a LPCI initiation, closing any of the cross-tie valves will render both LPCI Loop A and Loop B inoperable. This is not considered to be a safe practice and would require Dresden to enter a Limiting Condition of Operation with the LPCI system inoperable.

2.3. These valves will be exercised during cold shutdown •

1305a/51

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IST PROGRAM REV 3

REL. REQ. DESIGNATION

VR-1 VR-2 VR-3

VR-4

VR-5 VR-6

VR-7 VR-8

VR-9

VR-10

VR-11

VR-12 VR-13

VR-14

VR-15 VR-16

VR-17

VR-18

VR-19

VR-20

VR-21

VR-22 VR-23

VR-24

1305a/52

RELIEF REQUEST INDEX PAGE 1 OF 1 DRESDEN !ST PROGRAM REV 3

July 1, 1989

DRESDEN VALVES RELIEF REQUEST INDEX

IST PROGRAM REV. 2

REL. REQ. DESIGNATION DESCRIPTION

VR-Al VR-A2 VR-A3

VR-A4

VR-P5 VR-A6

VR-P7 VR-PS

VR-P9

CRD SCRAM VALVES - RELIEF ON TIMING SAFETY VALVES - RELIEF FROM ADDITIONAL TESTS TARGET ROCK AND RELIEF VALVES, EXERCISE ONCE PER CYCLE AND RELIEF ON TIMING TARGET ROCK AND RELIEF VALVES, RELIEF FROM PRESSURE SETPOINT RELIEF FROM VALVE TIMING TOLERANCE OF S79 USE W81 PC ISOLATION VALVES, LEAK TESTED PER 10CFR50 APPENDIX J DELETED CRD ARI/A1WS AIR HEADER BLEED VALVES, RELIEF FROM VALVE TIMING CRD BACKUP SCRAM AND SCRAM DUMP VALVES, RELIEF FROM VALVE TIMING

VR-PlO TARGET ROCK SAFETY-RELIEF VALVES, RELIEF FROM AS-FOUND TESTING

N/A ISOLATION CONDENSER MAKEUP CHECK VALVES, DISASSEMBLY/INSPECTION

NIA SBLC CHECK VALVES, RELIEF FROM TESTING FREQUENCY N/A CORE SPRAY KEEP: FILL CHECK VALVES,

DISASSEMBLY/INSPECTION N/A LPCI KEEP FILL CHECK VALVES,

DISASSEMBLY/INSPECTION N/A HPCI SUCTION CHECK VALVES, DISASSEMBLY/INSPECTION N/A MAIN STEAM VACUUM BREAKER CHECK VALVES, RELIEF

FROM TORQUE MEASUREMENT N/A HEAD SPRAY CHECK VALVES, RELIEF FROM TESTING

FREQUENCY NIA HPCI KEEP FILL CHECK VALVES,

DISASSEMBLY/INSPECTION N/A HPCI TURBINE EXHAUST VAC BREAKER CHECKS,

DISASSEMBLY/INSPECTION N/A FEEDWATER CHECK VALVE (220-59), RELIEF FROM

FREQUENCY NIA FEEDWATER CHECK VALVES (220-58&62), RELIEF FROM

FREQUENCY N/A HPCI INJECTION CHECK VALVE, RELIEF FROM FREQUENCY NIA MSIV AIR ACCUMULATOR CHECK VALVES, RELIEF FROM

FREQUENCY NIA EXCESS FLOW CHECK VALVES, RELIEF FROM FREQUENCY

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VR-1 Page 1 of 2 Dresden IST Program Rev. 3 July 1, 1989

RELIEF REQUEST NO. VR-1

1. Description

1.1. Relief from Code timing and information on valve exercising frequency in accordance with Technical Specification frequency.


2.1 Component description:


2-0305-126 . 5" B 1 34/0D CRD Scram Inlet Valve 2-0305-127 • 5 II B 1 34/9D CRD Scram Outlet Valve 2-0305-114 • 5 II c 2 34/9D CRD Scram Outlet Check 3-0305-126 • 5" B 1 365/0E CRD Scram Inlet Valve 3-0305-127 • 5 II B 1 365/90 CRO Scram Outlet Valve 3-0305-114 . 5" c 2 365/90 CRD Scram Outlet Check

There are 177 of each of the valve numbers listed. One for each of the CRD Hydraulic Control Units (HCU).

IST Valve EPN Size CAT Class P&ID/CORO Function

2-0305-117 • 5" B SR 34/100 CRO Scram Pilot Valve 2-0305-118 . 5" B SR 34/100 II

3-0305-117 . 5" B SR 365/100 " 3-0305-118 . 5" B SR 365/100 "

3. ASME SECTION XI (S79) TEST REQUIREMENTS(S)

3.1. IWV-3411 Test Frequency

3.2. IWV-3413 Power Operated Valves

3.3. IWV-3522 Exercising Procedure

4. BASIS FOR RELIEF

4.1. To exercise these valves requires scramming the individual CRD's.

4.2. The proper operation of each of the valves is demonstrated by the Technical Specification required scram testing. To exercise these valves more than the current Technical Specification requirements is not practical .

1305a/53

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4.3. These valves are exercised and each individual control rod drive scram insertion is timed and must meet specific time increments as stated in the Technical Specifications. This individual rod timing ensures that the valves function properly.


5.1. Individual scram insertion times and subsequent valve exercising will be performed per the Technical Specification requirements. The required frequency is as follows:_

1305a/54

5.1.1. After each refueling outage, prior to operation greater than 30 percent of rated thermal power, all control rods shall be subject to scram-time tests from the fully withdrawn position with reactor pressure above 800 psig; and

5.1.2. At 16-week intervals, 50% of the control rod drives shall be tested so that every 32 weeks, all the control rods · shall have been tested .

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1. Description

1.1. Relief from Code Safety Valve test sample expansion.


3.

4.


2-0203-4A 6 II c 1 12-1/SE Main Steam Safety Valve 2-0203-4B 6 II c 1 12-1/SE 2-0203-4C 6 II c 1 12-1/SD 2-0203-4D 6 II c 1 12-1/SD 2-0203-4E 6 II c 1 12-1/SC 2-0203-4F 6 II c 1 12-1/SC 2-0203-4G 6 II c 1 12-1/SB 2-0203-4H 6 II c 1 12-1/SB 3-0203-4A 6 II c 1 345-1/SE 3-0203-4B 6 II c 1 345-1/SE 3-0203-4C 6 II c 1 345-1/SD 3-0203-4D 6 II c 1 345-1/SD 3-0203-4E 6 II c 1 345-1/SC 3-0203-4F 6 II c 1 345-1/SC 3-0203-4G 6 II c 1 345-1/SB I

3-0203-4H 6 II c 1 345-1/SB II

ASME Section XI (S79) Test Reguirement(s)


3.2. IWV-3513 Additional Tests

B~sis FQr R~lief

4.1. Dresden Technical Specification Surveillance Requirement 4.6.E. provides that a minimum of ~ of all safety valves shall be bench checked or replaced with a bench checked valve each refueling outage. ASME requires that N/60 x Total No. of safety relief valves be tested, where N is the number of months between outages.

4.1.1. Dresden's existing program replaces ~of 8 valves or 4 valves per outage per unit. Every other outage or every 36 months, all of the valves will have been tested or replaced with cleaned, rebuilt valves, which have verified set points •

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4.1.2. ASME Section XI requires that 18/60 X 8 or 2.4 valves be tested per outage per unit. All valves will have been tested at least once every 60 months.

4.1.3. ASME Section XI requires a sample expansion testing program of an additional 2.4 valves (in Dresden's case) when any valve in a system fails to function properly during a regular test.

4.2. Dresden Station has reviewed the ASME Section XI IST sample expansion requirements and believes that the frequency of removal and maintenance of these valves on an accelerated basis provide adequate assurance that these valves will perform safely and reliably.


5.1. Dresden Station will remove and replace with rebuilt safety valves every refueling outage, % of the total number of Main Stearn safety valves. This means that all Main Stearn safety valves will be replaced with rebuilt safety valves every other refueling outage or approximately every 36 months. Therefore, should any of the 4 removed valves fail as-found testing, no sample expansion will be performed .

1305a/56

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VR-3 Pege 1 of 2 Dresden IST Program Rev. 3 July 1, 1989


1. Description

1.1. Relief from Code timing and information on valve exercising during Cold Shutdown.

2. AFFECTED·CQMPONENT(S)

3.

4.


2-0203-3A 6" BC 1 12-l/7F Main Steam Target Rock ADS 2-0203-3B 6" BC 1 12-l/7E Main Steam Electromatic

Relief ADS 2-0203-3C 6" BC 1 12-l/7C " 2-0203-3D 6" BC 1 12-l/7B " 2-0203-3E 6" BC 1 12-l/6E " 3-0203-3A 6" BC 1 345-l/7F Main Steam Target Rock ADS 3-0203-3B 6" BC 1 345-l/7E Main Steam Electromatic

Relief ADS 3-0203-3C 6" BC 1 345-l/7C " 3-0203-3D 6" BC 1 345-l/7B II

3-0203-3E 6" BC 1 345-l/6E II

ASME Section XI (S79) Test Requirement(s)

3 .1. IWV-3411 Test Frequency



Basis For Relief

4.1. Valve Timing

4.1.1. Relief is requested for the timing requirement for these valves. These valves provide steam blowdown (relief) to the torus which is initiated either automatically or manually by the use of a key operated switch. Because of the ability to be manually operated, they are categorized as both "B" and "C" valves .

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VR-3 P~ge 2 of 2 Dresden !ST Program Rev. 3 July 1, 1989

4.1.2. These valves are exercised once each operating cycle with the reactor at pressure. Each valve is manually opened and is verified open by a compensating turbine bypass valve or control valve closure. Consistent timing of this event for the purpose of determining the operational readiness of these valves is not considered practical.

4.2. Valve Exercising

4.2.1. The relief valve discharges at one location in the torus and should the valve remain open for longer than five minutes, there is a concern that the extended blowdown at a given point could overheat the water locally, resulting in the release of free steam. This can create localized problems with the interior coating.

4.2.2. Manually exercising these valves requires steam pressure behind the disk before cycling and thus must be performed with the reactor at pressure. Thus, the plant must be in an operating or startup condition with the required steam pressure in the main steam lines.

4.2.3. Additionally, under IST Category C safety valve and relief valve tests, all these valves are rebuilt every other outage or approximately 36 months. Dresden Station believes the combination of rebuilding (once every 36 months) and insitu exercising (once each operating cycle) adequately verifies the valves operational readiness.

5. Alternative Test

5.1. These valves will be full stroke exercised without timing at least once per operating cycle in accordance with Technical Specification 4.5.D.l.b.

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VR-4 P~ge 1 of 2 Dresden IST Program Rev. 3 July 1, 1989


1. Description

1.1. Relief from Code relief valve.set points.


3.

4.


IST Valve EPN Size CAT Class P&ID/CORD

2-0203-3A 6" 2-0203-3B 6"

2-0203-3C 6" 2-0203-3D 6" 2-0203-3E 6" 3-0203-3A 6" 3-0203-3B 6"

3-0203-3C 6" 3-0203-3D. 6" 3-0203-3E 6"

BC BC

BC BC BC BC BC

BC BC BC

1 1

1 1 1 1 1

1 1 1.

12-l/7F 12-l/7E

12-l/7C 12-l/7B 12-:l/6E 345-l/7F 345-l/7E

345-l/7C 345-l/7B 345-l/6E

ASME Sg~tion XI (572} Te5t Reguirement(&}

3 .1. IWV-3512 Test Procedure

Basi6 For Religf

Function

Main Steam Target Rock ADS Main Steam Electromatic Relief ADS " " " Main Steam Target Rock ADS Main Steam Electromatic Relief ADS " " II

4.1. The electromatic relief valves and the relief function of the target rock valve are operated by actuation of a pilot solenoid valve which opens the main valve by creating differential pressure across the main disk. The pilot valve is actuated from an electric signal from either a control switch, the auto-depressurization logic, or a pressure switch that senses reactor system pressure.

4.2. The requirement of IWV-3512 to check relief and safety valve setpoints in accordance with ASME PTC-25.3-1976 is.not applicable in this case because the set points are established by calibrating the pressure.switch which senses system pressure. Therefore, relief is requested from compliance with this requirement.

4.3. The pressure setpoint of these valves is set by calibrating the pressure switch rather than testing the complete valve assembly. The combination of the pressure switch calibration and the exercisirtg test for operability (BT) satisfies the intent of paragraph IWV-3512 .

1305a/59

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5. Alternative Test


5.1. The pressure switch for each of these valves will be calibrated to verify the correct setpoint and the exercise test in accordance with Technical Specification 4.5.D.l.b. will verify operability of the valve •

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1. Description


1.1. Valve Timing Tolerances for Valves with Maximum Allowable Stroke Times of 10 seconds and less.

2. Affected Component(s)

2.1. All Valve timing for power operated valves.

3. ASME Section XI (S79) Test Requirement(s)


(b) The stroke time of all power-operated valves shall be measured to the nearest second or 10% of the maximum allowable stroke time, whichever is less, whenever such a valve is full-stroke tested.

4. Basis For Relief

4.1. The NRC has evaluated and found acceptable later editions and addenda of ASME Section XI which provide a more practical approach to valve timing tolerances. Specifically, the same paragraph in the ASME Section XI 1980 Edition with Winter 1981 Addenda states:

IWV-3413 Power Operated Valves

(b) The stroke time of all power operated valves shall be measured to the nearest second, for stroke times 10 sec or less, or 10% of the specified limiting stroke time for full-stroke times longer than 10 sec whenever such a valve is full-stroke tested.

4.2. To record stroke times to the nearest 10% of the maximum stroke time does not measurably increase the assurance of the ability of valves to perform their intended function, but does increase the administration burden and probability for recording errors.

5. Alternative Test

5.1. The stroke time of all power operated valves shall be measured to the nearest second, for stroke times 10 sec or less, or 10% of the specified limiting stroke time for full-stroke times longer than 10 sec, whenever such a valve is full-stroke tested .

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1. Description

VR-6 Paoge 1 of 1 Dresden IST Program Rev. 3 July 1, 1989

1.1. Relief from ASME Code leak test requirements to do tests in accordance with 10CFR50 Appendix J, Type C, Local Leak Rate Testing.



2.1.1. All Category A and AC, Primary Containment Isolation valves.

3. ASME SECTION XI ($79) TEST REQUIRFMENT(S)

3.1. IWV-3426 Analysis of Leakage Rates

3.2. IWV-3427(b) Corrective Actions

4. BASIS FOR RELIEF

4.1. Primary containment Category A isolation valves will be seat leak tested in accordance with the requirements of Technical Specification Sections 3.7 and 4.7 and 10 CFR 50 Appendix J.

4.2. Failure to meet the maximum allowable leakage rates as defined by the Technical Specifications shall require compliance with ASME Section XI, IWV 3427(a).

4.3. Data trending, as required by IWV-3427(b) for valves 6 in. and larger, does not provide meaningful information that would justify the burden of taking corrective action. With the increased frequency, constraints would be placed upon the plant requiring extended shutdowns. Therefore, corrective action per IWV-3427(b) will not be used.

5. ALTERNATIVE TEST

5.1. Perform seat leakage testing in accordance with the requirements of 10 CFR 50 Appendix J, or as amended by Technical Specifications.

5.2. The seat leakage results of the primary containment isolation valves will be analyzed in accordance with 10 CFR 50 Appendix J, and Technical Specification Section 3.7 and 4.7.

5.3. Containment isolation valves will be repaired or replaced as required when the leakage rate exceeds the maximum allowable as stated in the Dresden Nuclear Station Technical Specifications or IWV-3427 (a) .

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VR-8 Pcrge 1 of 2 Dresden !ST Program Rev. 3 July 1, 1989


1. Description

1.1. Relief from Code valve timing.


3.

4.



2-0399-524A 111 A SR 34/8D CRD-ARI/ATWS Air Header Bleed Valve

2-0399-524B 111 A SR 34/8D 2-0399-548A 111 A SR 34/9C 2-0399-548B 1" A SR 34/9C 2-0399-549A 111 A SR 34/8E 2-0399-549B 111 A SR 34/8E 3-0399-524A 111 A SR 365/SD 3-0399-"-524B 111 A SR 365/SD 3-0399-548A 111 A SR 365/9C " 3-0399-548B 111 A SR 365/9C II

3-0399-549A · 111 A SR 365/SE II

3-0399-548B l" A SR 365/BE II

ASME SECTION XI (S79) TEST REQUIREMENT(S)

3.L IWV-3413 Power Operated Valves


BA5I5 FOR RELIEF

4.1. These Valves are part of the alternate rod insertion/ anticipated transient without scram (ARI/ATWS) system. These solenoid operated valves provide an alternate method of relieving the CRD scram air header of air pressure so as to provide CRD insertion.

4.2. Exercising these valves results in the insertion of all the control rod drives. This is not considered practical during normal operation.

4.3. These 1/2" valves operate too rapidly and there is no position indication for any practical timing measurements. Their operational readiness and safety-related function are verified during Reactor Refueling. AdditiOnal testing for valve timing is considered impractical .

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5.1. These valves will be exercised, without timing, and verify proper operation and venting during Cold Shutdown .

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1. Description

1.1. Relief from Code valve timing.




2-0302:...19A 0. 511 A SR 34/7E CRD Backup Scram Valve 2-0302-19B 0. 5" A SR 34/7E II

2-0302-20A 0. 5" A SR 34/SE CRD Scram Dump Valve 2-0302-20B 0.5" A SR 34/SE II

3-0302-19A 0.5 11 A SR 365/7E CRD Backup Scram Valve 3-0302-19B 0.5" A SR 365/7E II

3-0302-20A 0. 5" A SR 365/SE CRD Scram Dump Valve ::'.:~,·~ . 3-0302-20B 0.5" A SR 365/SE II




4. BASIS FOR RELIEF

4.1. Exercising these valves results in the insertion of all the control rod drives. This is not considered practical during normal operation.

4.2. These 1/211 valves operate too rapidly and there is no position indication for any practical timing measurements. Their operational readiness and safety-related function are verified during Cold Shutdown. Additional testing for valve timing is considered impractical.


5.1. These valves will be exercised, without timing, and verify proper venting during Cold Shutdown .

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1 . Description

1.1. Relief from Code safety valve and relief valve testing in the as-found condition.



Valve EPN

2-0203-3A 3-0203-3A

IST Size CAT Class

6" BC 1 6" BC 1

P&ID/CQ~D"-___.F~un.......,,c~t=i=o=n.__~~~~~~~~

12-1/?F 345-1/?F

Main Steam Target Rock ADS II


3.1. IWV-3512 Test Procedure

4. BASIS FOR RELIEF

4.1. There is one main steam Target Rock Safety-relief.valve on each unit. These valves have their pilot assembly replaced w,ith a rebuilt and tested assembly every Reactor Refueling outage. The main valve body is replaced every other Reactor Refueling outage.

4.2. To perform as-fotmd testing of the one valve when the pilot assembly is being replaced with a rebuilt and tested assembly is impractical.


5.1. Therefore, these valves will have their pilot assembly replaced with a rebuilt and tested assembly every Reactor Refueling outage and the main valve body will be replaced every other Reactor Refueling outage .

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1. Description

1.1 Relief is requested from full and partial stroke exercising isolation condenser make up check valves quarterly.

2. Affected Components

2.1 Component description:

VALVE EPN SIZE CAT CLASS P&ID/CQRD FUNCTION

2-1301-11 4.0" c 3 M-28/3C Isocondenser makeup 2-1301-36 4.0" c 3 M-28/5D Cond trnfr makeup 2-4107-501 4.0" c 3 M-28/5C Diesel fire makeup 3-1301-11 4.0" c 3 M-359/3C Isocondenser makeup 3-1301-36 4.0" c 3 M-359/5D Cond trnfr makeup 3-4107-501 4.0" c 3 M-359/5C Diesel fire makeup

3. ASME Section XI (579) Test Requirements

3.1. AWV-3521 Test Frequency


4. Basis for Relief

4.1. To properly exercise these valves requires running the Diesel Fire pump and discharging the water to the shell side of the isolation condenser.

4.2. During normal operation, the isolation condenser shellside contains approximately 22,000 gallons of clean demineralized water. By conducting the required flow test to verify valve operability with the Diesel Fire pump, untreated service water would be introduced to the isolation condenser shell at a rate of 3000 gallons per minute.

4.3. The isolation condenser tubes are the primary boundary between the reactor vessel water and outside secondary containment. Service·water contains chlorides, sulfates and minerals which would deposit on the tubes and cause pitting and eventual tube failure. ·

4.4. To drain, clean and refill the isolation condenser with clean demineralized water every 3 months after verifying valve operability by flow testing is not possible since the isolation condenser is required for normal reactor operations and the time to drain and fill the condenser may possibly exceed the Limiting Condition for Operation.

5. Alternative Test

5.1. The valves listed in section 2.1 will be disassembled and inspected to verify valve operability in accordance with the sampling technique discussed ~n DAIM-V22.

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1. Description

1.1. Relief is requested from partial and full stroke exercising the Standby Liquid Control (SBLC) check valves during quarterly or cold shutdown periods.



VALVE EPN SIZE CAT CLASS P&ID/CORD FUNCTION

2-1101-15 1. 5" AC 1 33/3C SBLC Injection Check Valve 2-1101-16 1.5" AC 1 33/3C SBLC Injection Check Valve 3-1101-15 1. 5" AC 1 364/3C SBLC Injection Check Valve 3-1101-16 1. 5" AC 1 364/3C SBLC Injection Check Valve

3. ASME Section XI (S79) Test Requirements



4. Basis for Relief

4.1. Exercising these valves requires firing the squib valves and injecting demineralized water into the reacto·r vessel .

4.2. Injecting ambient water into the reactor vessel during operations is undesirable because the SBLC system would be inoperative during this test due to the isolation of the sodium pentaborate solution (neutron poison). In addition to SBLC being inoperative and plac~ng the plant in a seven day Technical Specifications Limiting Condition of Operation (LCO), injecting cold water into the reactor would eventually fatigue and crack the injection nozzles due to the induced thermal shock. In addition to the nozzle cracking.concerns, a cold water transient in the vessel would cause a reactor trip.

4.3. Because sodium pentaborate is a neutron poison, it is imperative that there be a physical separation between the poison and the primary system. To attempt a full flow test during a cold shutdown period would require a thorough system flushing and either removal or firing of one explosive valve. This work is beyond the scope of a normal cold shutdown period.

5. Alternative Test

5.1 These valves will be exercised during reactor refueling outages. This will be done in conjunction with the firing of one explosive squib valve and injecting demineralized water into the reactor vessel at rated system flow. These valves are also leak tested during react~r refueling outages .

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VR-13 Page 1 of l Dresden IST Program Rev. 3 July 1, 1989


1. Description

2.

1.1. Relief is requested from full stroke exercising closed the Core Spray keep fill check valves quarterly or during cold shutdown periods.

Affected Components



2-1402-34A 0.75" c 2 M-27/8D Core Spray Keep Fill 2-1402-34B 0.75" c 2 M-27/6D Core Spray Keep Fill 3-1402-34A 0.75" c 2 M-358/8D Core Spray Keep Fill 3-1402-34B 0. 75" c 2 M-358/6D Core Spray Keep Fill




4. Basis for Relief

4.1. Exercising closed the core spray keep fill check valves ·quarterly is not possible since the downstream valve (1402-36) is also a check valve (two check valves in series) and can not be back pressurized during normal core spray pump testing.

4.2. Valves 2(3)-1402-34A and B can not be verified closed independently of the 2(3)-1402-36A and B by any direct or indirect method during normal operations or cold shutdown periods because test connections between the valves do not exist.

4.3. Valves 2(3)-1402-36A and B are verified closed each quarter by closing the valve handwheels.

5. Alternative Test

5.1 The valves listed in section 2.1 will be disassembled and inspected on a refueling outage basis to verify valve operability in accordance with the sampling technique discussed in DAIM-V22 .

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VR-14 P~ge 1 of 1 Dresden !ST Program Rev. 3 July 1, 1989


1. Description

2.

1.1. Relief is requested from full stroke exercising the Low Pressure Coolant Injection (LPCI) keep fill check valves quarterly or during cold shutdown periods.

Affected Components


VALVE EPN SIZE CAT CLASS P&IP{CJ)_RD FUNQTION

2-1501-67A 2.0" c 2 M-29-1/BF LPCI Keep Fill 2-1501-67B 2.0" c 2 M-29-l/2F LPCI Keep Fill 3-1501-67A 2.0" c 2 M-360-1/SF LPCI Keep Fill 3-1402-67B 2.0" c 2 M-360-l/2F LPCI Keep Fill




4. Basis for Relief

4.1. Exercising closed the LPCI keep fill check valves quarterly is not possible since the downstream valve (1501-66) is also a check valve (two check valves in series) and can not be back pressurized during normal LPCI pump testing.



S. Alternative Test

5.1 The valves listed in section 2.1 will be disassembled and inspected on a refueling outage basis to verify valve operability in accordance with the sampling technique discussed in DAIM-V22 .

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1. Description

1.1. Relief is requested from full stroke exercising closed the High Pressure Coolant Injection (HPCI) pump suction check valve quarterly or during cold shutdown periods.

2. Affected CQIQponents


VALVE EPN

2-2301-39 3-2301-39

SIZE CAT CLASS

16.0" c 2 16.0" c 2

'

P&ID/CORD

M-51/BE M-374/8E

3. ASME Section XI (S79) Test Requirements



4. Basis for Relief

FUNCTION

HPCI Torus Suction HPCI Torus Suction

4.1. To full stroke exercise this valve open requires a flow test using suppression pool (torus) water as the HPCI pump suction .

4.2. The normal test flow path uses the condensate storage tank (CST) as the pump suction rather than the torus. The torus is not used as the HPCI pump suction for testing because the system test loop is not designed to recirculate water from the torus to the torus.

4.3. The only flow path available to verify full flow valve operability would involve pumping torus water to the condensate storage tank. Since torus water is untreated, low quality water and the condensate storage tank water is demineralized, the tank would have to be drained (approximately 100,000 gallons), flushed and refilled to restore water chemistry back to specifications after each test. This testing would be extremely burdensome because of the time involved in draining and refilling the CST and processing the large amount of waste water would be generated.

5. Alternative Test

5.1 The valves listed in section 2.1 will be disassembled and inspected on a refueling outage basis to verify valve operability. The disassembly and inspection will be performed in accordance with the sampling technique discussed in the IST Program submittal.

5.2. The valves_in section 2.1 will also be partial stroked exercised in conjunction with the HPCI pump operability test each quarter.

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1. Description



1.1. Relief is requested from measuring the force or torque required to exercise the Main Steam vacuum breaker check valves.

4.1. These valves provide vacuum relief on the main steam electromatic and target rock relief valve piping to the torus. They are normally closed and are required to open when steam is blown down to the torus. The steam condenses and creates a vacuum.

4.2. The requirements of rwv~3522 to measure the force or torque used by a mechanical exerciser to move the disk is not applicable in this case because the valve does not have a manual exerciser and can only be exercised by reaching into the valve and pushing the disk off the seat. These valves are designed to open on a differential pressure of less than 1 psid and therefore manually exercising the disk requires only slight hand pressure. Obtaining and adapting a device to measure the force exerted on the disk while exercising it is impractical.

5. Alternative Test

5.1. These valves will be manually full stroke exercised during each cold shutdown when the drywell is de-inerted.

5.2. Addition~l!y, since the valve internals are visible without disassemably, the valve disk, seat, pin and spring will be visually inspected during the stroke test.

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VR-17 P~e 1 of 1 Dresden !ST Program Rev. 3 July 1, 1989


1 . Description

1.1. Relief is requested from partial and full stroke exercising the inboard isolation reactor head spray check valves quarterly or cold shutdown periods.



VALVE EPN SIZE CAT CLASS P&ID/CORD

2-205-27 2.5" AC 1 26-1/SE

3-205-27 2.5" AC 1 357-l/5E

3. ASME Section XI (S79) Test Req_uirements

3.1. AWV-3412 Exercising Procedure

4. Basis for Relief

FUNCTION

Inboard isolation function for the reactor head spray line

II

4.1. These valves are normally closed during both reactor operation and extended shutdown periods. The designated safety position of these valves is closed; however, reactor head spray could be used for injecting into the vessel. Credit for this feature is not taken.

4.2. To exercise these valves during operations or cold shutdowns would require injecting approximately 70°F water into the reactor. Injecting cold water into the reactor could cause cracks in the reactor vessel due to thermal shock.

5. Alternative Test

5.1. These valves will be exercised and leak tested during reactor refueling .

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1 . Description

2.

1.1. Relief is requested from full stroke exercising closed the High Pressure Coolant Injection (HPCI) keep fill check valves quarterly or during cold shutdown periods.

AFFECTED CQMPONENT(S)


VALVE EPN SIZE CAT CLASS

2-2354-500 0.75" c 2 3-2354-500 0.75" c 2

P&ID/CORD

M-51/7C M-374/7C

FUNCTION

HPCI Keep Fill HPCI Keep Fill

3. ASME SECTION XI (S79) TEST REQUIRmENT(S)



4. BASIS FOR RELIEF

4.1. Exercising closed the HPCI keep fill check valves quarterly is not possible since the downstream valve (2354-501) is also a check valve (two check valves in series) and can not be back pressurized during normal HPCI pump testing.



5. ALTERNATIVE TEST

5.1. The valves listed in section 2.1 will be disassembled and inspected on a refueling outage basis to verify valve operability in accordance with the sampling technique discussed in DAIM-V22 .

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1. Description

2.

4.

1.1. Relief is requested from partial and full stroke exercising the High Pressure Coolant Injection (HPCI) turbine exhaust vacuum breakers.

AFFECTED COMPONENT(S)



2-2399-76A 1.0" c SR M-51/8C HPCI Vac Breaker 2-2399-76B 1.0" c SR M-51/SD HPCI Vac Breaker 2-2399-77A 1.0" c SR M-51/BD HPCI Vac Breaker 2-2399-77B 1.0" c SR M-51/BD HPCI Vac Breaker 3-2399-76A 1.0" c SR M-374/BC HPCI Vac Breaker 3-2399-76B 1.0" c SR M-374/BD HPCI Vac Breaker 3-2399-77A 1.0" c SR M-374/BD HPCI vaC: Breaker 3-2399-77B. 1.0" c SR M-374/BD · HPCI Vac Breaker

3. ASME SECTION XI (579) TEST REQUIREMENT(S)



BASIS FQR RELIEF

4.1. To full stroke exercise· these valves open/closed requires entering the torus and disassembling and manually exercising the valves to verify operability.

4.2. This testing is impractical during power operations since these valves are located inside the torus and are inaccessible because the torus is inerted and at a negative pressure.

4.3. To perform a full stroke exercise of these valves during cold shutdowns is extremely burdensome because entering the torus requires removal of the 4.0 ft. diameter manway cover. Once the cover is replaced after testing, a local leak rat~ test must then be performed to verify the primary containment boundary. This added maintenance and testing burden would invariably delay unit startup.


5.1. The valves listed in section 2.1 will be disassembled and inspected to verify valve operability in accordance with the sampling technique discussed in the IST Program submittal .

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1. Description

1.1. Relief is requested from full stroke exercising the feedwater check valves quarterly or during cold shutdown periods.



VALVE EPN SIZE CAT CLASS P&ID/CORD

2-0220-59 18" C 2 14/2F

3-0220-59 18" C 2 357-l/5E

3. ASME Section XI (S79) Test Reqyirements

3.1. AWV-3412 Exercising Procedure

4. Basis for Relief

FUNCTION

Backflow check into feedwater during HPCI injection

"

4.1. To verify full stroke exercising of these valves closed requires back pressurizing the valves ~hen the feedwater system is not required .

4.2. Since feedwater is required for operations, these valves cannot be tested quarterly.

4.3. During cold shutdowns, the condensate/feedwater system is required to be operable in order to maintain reactor water inventory. The normal make-up path to the reactor during cold shutdowns is through the 2·(3)-0220-59 check valve and therefore it cannot be isolated for testing.

5. Alternative Test

5.1. These check valves will be full stroke exercised during reactor refueling outages when the feedwater system is not required to be operable •

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VR-21 Page 1 of l Dresden IST Program Rev. 3 July 1, 1989


1. Description

1.1. Relief is requested from verifying closed the inboard and outboard Feedwat°er check valves quarterly or during cold shutdowns.


2.1 .. Component description:


2-0220-58A 18.0" AC 1 M-:14/4E Inboard FW Check 2-0220-58B 18.0" AC 1 M-14/4F Inboard FW Check 2-0220-62A 18.0" AC 1 M-14/3E Outboard FW Check 2-0220-62B 18.0" AC 1 M-14/3F Outboard FW Check 3-0220-58A 18.0" AC 1 M-347/4E Inboard FW Check 3-0220-58B 18.0" AC 1 M-347/4F Inboard FW Check 3-0220-62A 18.0" AC 1 M-347/3E Outboard FW Check 3-0220-62B 18.0" AC 1 M-347/3F Outboard FW Check

. 3.· ASME SECTION XI (S79) TEST REQUIR.EMENT(S)



4. BASIS FOR RELIEF

4.1. These valves are normally open and cannot be exercised closed during normal operation because the feedwater system is required to be operable to maintain reactor coolant inventory.

4.2~ To .exercise these' valves closed during coid shutdowns would require isolating the feedwater system, deinerting the drywell and backpressurizing the check valves individually to verify closure.

4.3. This testing is impractical to perform during cold shutdowns due to the Reactor Water Cleanup path and Feedwater being required (means of maintaining reactor coolant inventory) during cold shutdowns. Additionally, approximately 2,200 gallons of feedwater would need to be drained from the feedwater system headers prior to performing the necessary backflow test. This added operational and testing burden would invariably delay unit restart.

5. ALTERNATIVE TEST

5.1. The valves listed in section 2.1 will be exercised closed each reactor refueling •

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1. Description

1.1. Relief is requested from full and partial stroke exercising the High Pressure Coolant Injection (HPCI) valves quarterly or during cold shutdowns.



VALVE EPN

2-2301-7 3-2301-7

SIZE CAT CLASS

14.0" c 2 14.0" c 2

P&ID/CORD

M-51/6E M-374/6E

FUNCTION

HPCI Injection Check HPCI Injection Check

3. ASME SECTION XI (579) TEST REOUIRF.MENT(S)



4. BASIS FOR RELIEF

4.1. The HPCI check valves have both an open and closed safety function. These valves are required to be closed during normal power operation to prevent flow diversion of reactor coolant (feedwater). These valves are also required to open upon a HPCI initiation to provide the injection path for HPCI.

4.2. To full stroke exercise these valves open quarterly or during cold shutdowns requires injecting approximately 5,000 gpm of condensate storage tank water at 70°F into the reactor vessel at 540°F. This type of test is impractical because repeating this test will eventually fatigue and crack the injection nozzles due to the induced thermal shock. In addition to the nozzle cracking concerns, a cold water transient in the vessel will cause a reactor trip.

4.3. A reverse flow test (back pressurizing) is required to verify the closed position of the HPCI injection check valves.

4.4. To accurately perform a reverse flow test on these valves during normal power operation (quarterly) requires entering the x-area, mounting a temporary gauge and monitoring the pressure upstream of the injection valve. This test is impractical because of the extremely high dose rates in the area coupled with the amount of time necessary to determine valve operability .

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VR-22 Paige 2 of 2 Dresden IST Program Rev. 3 July 1, 1989


The average dose rate in the X-area during normal reactor operation is approximately 1500 millirem per hour. Two technicians will be required to perform the test. The test will take approximately 30 minutes baring any operational problems (i.e. the possibility of the motor operated valve being stuck open due to the 1000 psi reactor pressure). The estimated dose to perform this test each quarter of 1.5 ManRem is considered extremely impractical.

To verify closure of the HPCI injection check valve during cold shutdown periods requires isolating the Feedwater and Reactor Water Cleanup systems, draining and venting the respective test volume and leak rate testing the HPCI injection valve. This test is impractical to conduct during cold shutdown because Reactor Water Cleanup flow path and Feedwater being required (means of maintaining reactor coolant inventory) during cold shutdown. Additionally, the added operational and testing burden would delay unit restart.


5.1. The valves listed in section 2.1 will be full stroke exercised open and closed each reactor refueling. Additionally, these -valves will be partial stroke exercised open during cold shutdowns .

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1. Description

1.1. Relief is requested from exercising the Main Steam Isolation Valve (MSIV) Accumulator check valves quarterly or during cold shutdowns.

2. AFFECTED CQMPQNENT(S)

2.1. , Component description:


2-0220-84A 2-0220-84B 2-0220-84C 2-0220-84D 2-0220-85A 2-0220-85B 2-0220-85C 2-0220-85D

. 3-0220-83A 3-0220-83B 3-0220-83C

. 3-0220-83D 3-0220-84A 3-0220-84B 3-0220-84C 3-0220-84D

0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5" 0.5"

c c c c c c c c c c c c c c c c

SR SR SR SR SR SR. SR SR SR SR SR SR SR SR SR SR

M-12-l/3F MSIV Accumulator Check M-12-l/3F MSIV Accumulator Check M-12-l/3F MSIV Accumulator Check M-12-l/3F MSIV Accumulator· Check M-12-2/3F MSIV Accumulator Check M-12-2/7F MSIV Accumulator Check M-12-2/3F MSIV Accumulator Check M-12-2/7F MSIV Accumulator Check M-345-2/7F MSIV Accumulator Check M-345-2/7F MSIV Accumulator Check M-345-2/7F MSIV Accumulator Check M-345-2/7F . MSIV A~cumulator Check M-345-l/3F MSIV Accumulator Check. M-345-l/3F MSIV Accumulator Check M-345-l/3F MSIV Accumulator Check M-345-l/3F MSIV AccUlllulator Check

3 • ASME SECTION XI (S79) TEST REOUIREMEN'T(S)

3.1~ IWV-3521 Test Frequency


4. BASI_S FOR RELIEF

4.1. The MSIV accumulator check valves are normally open and are required to close upon loss of the pneumatic system •.

4.2. The only practical method of exercising these_ valves closed is by backpressurizing the check valve and verifying the valve closed by observing no significant loss of pressure (leak rate test) .

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VR-23 Pase 2 of 2 Dresden !ST Program Rev. 3 July 1, 1989


4.3. ·Verifying closure of these valves during power operation or cold shutdown requires deinerting and entering the drywell and X-area to perform the appropriate leak rate tests. The average dose rates for these areas is 1500 millirem per hour during normal operation and 300 millirem per hour during cold shutdown periods. These dose rates are considered to be extremely high. Additionally, to perform the necessary leak test, an extensive amount of accumulator piping must be disassembled to isolate the check valves. This extensive.maintenance will delay unit startup if the unit is in cold shutdown. This test is impractical to perform during normal operation or cold shutdown due to the dose considerations and the burden of disassembling the MSIV accumulator piping.

· 5. ALTERNATIVE TEST •.

5.1. · The valves listed in section 2.1 will be exercised open and closed each reactor refueling •

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1. Description

1.1. Relief is requested from partial and full stroke exercising of all excess flow check valves during quarterly or cold shutdown periods.



All excess flow check valves as listed in the IST Program. Excess flow check valves are denoted as XFC in the Valve Type column and have VR-24 listed in the Relief Request .column.




4. BASIS FOR RELIEF

4.1. These are reactor process instrument line excess flow check valves that are tested in accordance with Technical Specification 4.7.D.l.B. requirements which consist of a leakage test conducted every reactor refueling outage. The testing involves uncoupling the ins_trument lines and verifying_ that each valve strokes to the closed position_. The test also verifies that the valve limits flow to an acceptable level. These excess flow check valves are designed to automatically close in the event ofa down stream line rupture. Valving operations and instrument line disconnections during the pe~formance of the inservice testing can result in an emergency core cooling system initiation or other automatic actuations during the time the vessel is pressurized. This would result in uncontrolled rapid pressure transients in the reactor vessel and/or other undesirable consequences. The optimum time for the inservice testing of these valves is during reactor refueling.


5.1. The valves will be exercised during reactor refueling in accordance with Technical Specification 4. 7 .D.1.B.

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UNJ.TS: ··2.its entirety the Revision 2 IST Program. - 2. Basis of Inservice Testing Program 2.1....

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