ML18142B975

R. E. Ginna - 10/31/1977 Response to Request for Additional Information Inservice Pump and Valve Testing Program

ML18142B975
Person / Time
Site:	Ginna
Issue date:	10/31/1977
From:	Amish K Rochester Gas & Electric Corp
To:	Schwencer A Office of Nuclear Reactor Regulation
References
Download: ML18142B975 (46)

Text

DISTRIBUTION,AZTM ISSUANC OPERATXiVG LICENSE

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C NRQ DISTR I8UTION FQR PART SD DOCKET MATERIAL OOCKET NUMEER Flt E BUMSER i TO:

Mr. A+ Schwencer FROM:

Rochester Gas

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Rochester, New York K

Wo Amish CATE OF OOCUMENT 10/31/77 OAT'E RECEIy'EO 11/3/77 Ig( =TTER QORIQINAl SCOPY QNOTORIZEO UNCLASSIPIEO PROP INPUT PORM NUMBER OF COPIES RECEIyEO

,'ESCRIPTICN I

I ENCLOSURE Attach, A:

Response

to NRC questions re, proposed Inservice Inspection-Pump and Valve Testing Programe

~ ~

I Attache B:

Revised program, Appendix C, Revision 2, of the Quality Assurance Manual entitled "Ginna Statj.on Inservice Pump 5 Valve Testing Program for the Sept, 1,

1977 through May 31, 1979'eriod"

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V ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER, N.Y. 74649 KEITH W. AMISH EXECUTIVE VICE PRCSIOCNT October 31, 1977 TCLCPHONC ARCA COOK Tla 546-2700 Director of Nuclear Reactor Regulation Attention:

Mr. A Schwencer, Chief Operating Reactors Branch Nl U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Xnservice Pump and Valve Testing Progra R. E. Ginna Nuclear Power Plant, Unit 1 Docket No. 50-244

~CELIAC CqCLm>On.

Io

~lhQISS IVIII

<<5<h NO'Its $77~

Gentlemen:

This letter is in response to questions from members of your staff on our proposed Xnservice Pump and Valve Testing Program as submitted by our letter of August 4, 1977.

Our responses to the questions are presented in Attachment A to this letter.

A revised program, Appendix C, Revision 2, of the Ginna Station Quality Assurance Manual entitled "Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 through May 31, 1979 Period" is presented in Attachment B for your information.

Forty (40) copies of this letter and the Attachments are provided for your use.

Very truly yours,

(

K. W. Amish Attachments

>>30701~2'

jrf' V

ATTACHMENT A RESPONSES TO NRC QUESTIONS Provide a listing of all Category E Valves and clarification of how operational checks are performed and the records kept on each valve's movement and position?

Category E Valves are now included in the program Table 4.12 with paragraph 4.6 describing the program for Locked Valve Control.

Provide a definition of a time period when the plant is at cold shutdown when in most cases it would be impossible to implement the cold shutdown valve test schedule?

The testing of valves required at cold shutdown or refueling outages will normally take four (4) days to complete.

When cold shutdowns, are of a shorter duration (2-3 days),

test.

personnel shall attempt to test as many valves as possible without holding up the startup of the unit with testing:

beginning no longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the plant reaches cold shutdown (as defined in Technical Specification 1.2).

For very short'cold shutdowns

((48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />), it would be impossible to mobilize test personnel to implement the testing program under the required procedural controls, therefore no valves would be tested.

It is possible that, during a four (4) day cold shutdown, the work load on test personnel may pre-clude their completion of all the required valve test, prior to startup.

Valve testing during cold shutdowns shall not be more frequent than one test per quarter for each valve in the test program.

Explain why valves which cannot be fully stroked are not being partially stroked to provide valve excercise?

Valves that cannot be fully opened to meet. the excercising requirements of Section XI, Article IWV cannot be partially stroked because the operating circuits logic are designed so that when a open-close signal is received the valve must complete a full stroke before the relays are released to pro-vide stroke in the other direction.

Explain why relief valves

744, 758A,

758B, and 818 are not in the valve testing program when valves 755A and 755B which are in the same portion of the component cooling system are included?

After a review of the piping system relief valves

744, 758A, 758B and 818 have been added to the Inservice Testing Program for Category C Valves.

Explain why the Service Water Pump Discharge Check Valves

4601, 4602,

4603, and 4604 are not in the testing program?

Valve 4601,

4602, 4603 and 4604 have been added to C In-service Testing Program for Category C Valves.

Provide clarification as to why valves 1813A and 1813B were taken out of the Inservice Testing Program with the issuance of Revision 1 to the program?

Valves 1813A and 1813B provide a flow path from the containment Sump B to the reactor coolant drain tank pumps.

This could provide an alternate path for supplying water to the reactor vessel for long term cooling following a loss of coolant acc-ident.

However, no credit was taken for this path in the safety analyses.

Thus, it is not necessary to test these valves.

Explain why the relief valves associated with the service water system are not included in the Inservice Testing Program for Category C Valves?

The service water system is a 150 psi system by design, but operated between 70 and 85 psi.

Because of this, there is not a requirement for the service water system relief valves to function when the service water system is operating.

How-ever, if the Component Cooling Heat Exchangers were left in service with the service water supply isolated there could be an overpressurization due to heat, build up and the resultant thermal expansion of the water.

Therefore, Relief Valves

4653, 4654 and 4657 have been added to the Inservice Testing Program for Category C Valves.

Are there any valves that provide separation between high pressure and low pressure portions of systems where a specific maximum amount of leakage has been established?

A review of the valves in systems which separate high pressure from low pressure portions of the system revealed that these valves are required to open to fulfilltheir safety function and seat leakage in the closed position is inconsequential for fulfillment of their function.

There is not a specific maximum amount of leakage requirement for these valves because each system is provided with overpressurization protection in the form of safety relief valves.

Leakage through these valves would be monitored by standard operating instrumentation such as pressure

gauges, level indicators, and through the Reactor Coolant System Inventory Control System.

If seat leakage

occurs, Technical Specification 3.1.5 establishes maximum allowable leakage rate from the primary coolant system.

QUALITY AS CE MANUAL SECT. NO.

EFFECTIVE DATE R EV.

PAGE 49 OOA 1

DF ROCHESTER GAS

& ELECTRIC CORPORATXON GINNA STATION PREPARED BY:

October 31, 1977 SIGNATURE DATE TITLE Appendix C

Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period REVIEWED BY APPROVEO BY:

/up Pro ram Table of Contents

==

Introduction:==

Discussion Definitions:

Program:

PVT 1.0 Scope and Responsibility PVT 2.0 Code Edition and Testing Xnterval PVT 3.0 Inservice Pump Testing Program PVT 4.0 Inservice Valve Testing Program PVT 5.0 Records

QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDXX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE 40 QOC October 31, 1977 PAGE OF Introduction This appendix to the Quality Assurance Manual defines the Inservice Pump and Valve Testing Program for the twenty month period starting September 1, 1977 through April 30, 1979.

Included in this program are the Quality Groups A, B and C Pumps which are provided with an emergency power source and those Quality Groups A, B and C Valves which are required to shut down the reactor or to mitigate the consequences of an accident and maintain the reactor in a safe shutdown condition.

This program has been developed as required by Section 50.55(a) (g) of 10CFR50 following the guidance of the ASME Boiler and Pressure Vessel Code Section XI "Rules for Inservice Xnspection of Nuclear Power Plant Components,"

(hereafter referred to as the "Code" ) excluding the controls of the Authorized Inspector, Enforcement Authority, Report-ing Systems and N-Stamp Symbol.

The inservice testing pro-gram shall be controlled by the Ginna Station Quality Assur-ance Program for Station Operation.

Quality Groups A, B and C components correspond to those defined in NRC Regula-,

tory Guide 1.26.

Further addenda and editions of Section XI of the Code shall be used for clarification of test requirements and performance.

The Inservice Pump and Valve Testing Program does not affect the pump and valve surveillance program required by Technical Specifications.

Technical Specification re-quirements shall continue to be implemented at the required frequency.

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Xnservice Pump and Valve Testing Program for the September 1, 1977 Through May 31, 1979 Period DATE 40iOOC 32 ctober 31, 1977 PAGE Definitions AFP AOV APV

'BA Code CC CK CS CSP CV C/R ECCS FCV GA GDT HCV HX LCV

'NDAFP NOV MV PCV PIV PRT PVT Q

R RCDT RCP RCV RHR RNW RV RWST RX S/G SI SXV SW TDAFP TK VC VCT VH Auxiliary Feedwater Pumps Air Operated Valve Air Operated Piston Valve Boric Acid American Society of Mechanical Engineers Boiler and Pressure Vessel Code Component Cooling Check Containment Spray Containment Spray Pump Check Valve Cold Shutdown or Refueling Emergency Core Cooling System Flow Control Valve Gas Analyzer Gas Decay Tank Hand Control Valve Heat Exchanger Level Control Valve Notor Driven Auxiliary Feedwater Pump Motor Operated Valve Manual Valve Pressure Control Valve Primary Xsolation Valve I

Pressurizer Relief Tank Pump and Valve Testing Quarterly Refueling Outage Reactor Coolant Drain Tank Reactor Coolant Pump Radiation Control Valve Residual Heat Removal Reactor Makeup Water Relicf Valve Refueling Water Storage Tank Reactor Vessel Steam Generator Safety Injection Secondary Isolation Valve Service Water Turbine Driven Auxiliary Feed Pump Tank Volume Control Volume Control Tank Vent. Header

QUALITYASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE 40 OOC 4

32 October 31, 1977 PAGE Pum and Valve Testin Pro ram PVT l. 0 Sco e and Res onsibilit 1.2 The inservice testing program defines the testing pro-gram for Quality Groups A, B and C Pumps and Valves in accordance with the requirements of Articles IWP and IWV of Section XI of the Code.

The results of these tests are to assure the operational readi-ness of pumps and valves.

It is the responsibility of the Ginna Station Test and Results Engineer to implement this test pro-gram and develop inservice test procedures which will outline the specific test. for each pump and valve included in the program.

1.3 After preventative or corrective maintenance the affected pumps or valves shall be tested to reestablish any reference values and assure operability.

PVT 2.0 Code Edition and Testin Interval 2.1 The Inservice Pump and Valve Testing Program for the twenty (20) month period starting September 1,

1977 through April 30, 1979 was developed utilizing the 1974 Edition of Section XI of the Code through the Summer 1975 Addenda.

PVT 3.0 Inservice Pum Testin Pro ram 3.1 The Inservice Pump Testing Program was developed in accordance with the requirements of Article IWP of Section XI of the Code.

This program includes all Quality Group A, B and C pumps which are provided with an emergency power source and are required to safely shut down the reactor or to mitigate the consequences of an accident and maintain the reactor in a safe shutdown condition.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for.the Septeinber 1,

1977 Through Ma 31, 1979 Period DATE 40 OOC October 31, 1977 PAGE OF 32 3.2 The following pumps shall be tested in accordance with Article IWP of Section XI:

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

(k)

(1)

(m)

(n)

(o)

(p) lA Component Cooling 1B Component Cooling lA Safety Injection 1B Safety Injection 1C Safety Injection lA Residual Heat Removal 1B Residual Heat Removal lA Containment Spray 1B Containment Spray 1A Auxiliary Peed 1B Auxiliary Feed Turbine Driven Auxiliary Feed 1A Service Water 1B Service Water 1C Service Water 1D Service Water 3.3 Plow rates will not be accurate for the residual heat removal pumps because the bypass test loop can only pass 200 gpm.

This bypass test loop is a fixed resistance system; therefore, hydraulic resistance remains unchanged from test to test.

PVT 4.0 Inservice Valve Testin Pro ram 4.1 The Inservice Valve Testing Program was developed in accordance with the requirements of Article IWV of Section XI of the Code.

All those valves that are required to perform a safety function either to shut down the reactor or to mitigate the con-sequences of an accident and maintain the reactor, in a safe shutdown condition are included in the program.

QUALITYASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for 'the September 1,

1977 through May,31, 1979 Period DATE 4D QOC October 31, 1977 PAGE OF 6

=.32 4.2 The Inservice Valve Testing Program Requirements for Category A and B Valves are found in Tables PVT 4.8 and 4.9, respectively.

Category C Valves are broken down into two categories, Check Valves and Relief Valves, which are found in Tables PVT 4.10 and 4.11, respectively.

Category D Valves are not included in this testing program because there are none included in Ginna Station design.

Category E Valves are found in Table PVT 4.12.

4.3 Some exceptions and exemptions to the testing re-quirements of Article IWV have been taken based on operational interference, placing the plant in an unsafe condition and Technical Specification requirements.

All exceptions and exemptions are listed on the valve tables and explained in the referenced

notes, PVT 4.13.

4.4 The exercising program for Category A and B Valves, with the exception of check valves, shall require a complete stroking of each valve per the valve testing tables.

All check valves, including Category C Valves, shall be exercised to the posi-tion required to fulfilltheir function.

These functional tests shallt be verified by the operation of, the required system.

4.5 Category A and B valves operation shall be timed each time they are stroked utilizing switch initiation and the position indicators, which are accessible during plant operation.

During each refueling outage a visual verification shall be made to confirm direct correspondence between valve operators and the position indicators.

4.6 In accordance with paragraph IWV-3700 of Section XI of the Code, Category E Valves are controlled in accordance with Ginna Station Administration proced-ure A-52.2 Control of Locked Valve Operation.

This procedure requires all operations of locked valves to be recorded in the "Locked Valve Operations Log" or as required by certain operational procedures which also record any locked valve operations.

t,

QUALITYASSURANCE MANUAL G INNA STATION APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 through May 31, 1979 Period DATE 49 99C October 31, 1977 PAGE 7'"

32 4

~ 7 The testing of valves required at cold shutdown or refueling outages will normally take four (4) days to complete.

When cold shutdowns are of a shorter duration (2-3 days), test personnel shall attempt to test as many valves as possible without holding up the startup of the unit with testing beginning no longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the plant reaches cold shutdown (as defined in Technical Specification 1.2).

For very short cold shutdowns

(<48 hours), it woul'd be impossible to mobilize test personnel to implement the testing program under the required procedural controls, therefore no valves would be tested.

It is possible that, during a four (4) day cold shut-down, the work load on test personnel may preclude their completion of all the required valve tests prior to startup.

Valve testing during cold shut-downs shall not be more frequent than one test per quarter for each valve in the test program.

4.8 Valve I 304A 304B 313 370B 371 383B Category A Valves T~e CV 1-A RCP Seal Injection Check CV 1-B RCP Seal Injection Check MOV Seal Water Return Isolation CV Charging Line Isolation Valve AOV Letdown Isolation CV Alternate Charging Line Check Note

~ Test 1

Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Frece C/R R

C/R R

C/R R

C/R R

C/R R

C/R R

508 AOV RMW to Containment Vessel

.Stop Stroke Q

Leak R

529 CV RMW to PRT 528 CV N2 Supply to PRT Stroke Leak Stroke Leak Q

R Q

R

QUALITYASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE October 31, 1977 PAGE 8

OF 32 Valve N

~Te Descri tion Not,e

Test, Fleece 539 743 745 750A AOV PRT Stop Valve Analyzer CV CC From Excess to Gas Letdown HX.

CV CK CC t.o A RCP AOV CC Return From Excess Let-down HX.

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke C/R Leak R

750B 759A 759B 813 814 846 862A 862B 870A 870B CV CK CC to B RCP MOV Containment Stop CC From Loop A RCP MOV Containment Stop CC From Loop B RCP MOV Supply CC to RX Support Cooling MOV Return CC to RX Support.

Cooling AOV N2 Supply to Accumulators CV 1-A CSP Disch Check CV 1-B CSP Disch Check CV 1-A to 1-C SI Pump Disch Check CV 1-B to 1-C SI Pump Disch Check Stroke C/R Leak R

Stroke C/R Leak R

Stroke C/R Leak R

Stroke C/R Leak R

Stroke C/R

-Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

QUALITY. ASSURANCE MANUAL GINNA STATION TITlE APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period OATE 49 OOC October 31, 1977 PAGE 9

oF Valve N

~Tpe 879 MV SI Test Line Isolation Note Test Frece Stroke Leak R

889A 889B 966A 966B 966C CV 1-A SI Pump Disch Check CV 1-B SI Pump Dis ch Check t

AOV Pressurizer Steam Space VC AOV Pressurizer Liquid Space VC Isolation Valve AOV Loop A and B Hot Leg VC Isolation Valve Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

1003A LCV 1-A RCDT Pump Suction 1003B LCV 1-B RCDT Pump Suction I

Stroke Q

Leak R

Stroke Q

Leak R

1713 CV N2 to RCDT CV Stroke Q

Leak R

1721 1723 1728 1786 AOV Suction line to RCDT AOV A Containment Sump Disch Stop Valve to Waste Holdup Tank AOV A Containment Sump Disch Stop Valve to Waste Holdup Tank AOV SIV RCDT to VH Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

~I QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE 40 90C October 31, 1977 PAGE 10 32 Valve N

T~pe Descri tion Note Test Freer 1787 AOV PIV RCDT to VH Stroke Leak Q

R 1789 5869 5870 5878 5879 AOV ISO Valve Outlet RCDT to GA APV Containment Purge Supply Isolation APV Containment Purge Supply Isolation APV Containment Purge Exhaust Isolation APV Containment Purge Exhaust Isolation Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q

R Q

R Q

R

4.9 Category B Valves Valve N

ape Descri tion Frey 014 017 081 082 083 RCV Aux Building GDT Release RCV Comp Cool Surge TK Vent Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

084 085 086 APV APV APV Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Stroke Q

Stroke Q

Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Cinna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through Ma 31 1979 Period DATE October 31, 1977 PAGE 11 OF 32 112B LCV Valve N

T~e Emergency Makeup RWST to Charging Pump Note Test Fleece Stroke Q

112C 427 624 625 626 HCV 1-A R HR HX Outlet RHR Loop Return LCV VCT Outlet AOV Letdown From Loop B

HCV, 1-B R HR HX Outlet Stroke Stroke Stroke Q

Stroke 3

Stroke C/R 700 701 MOV MOV Suction Stop From Loop A to RHR Pumps Suction Stop From Loop B to RHR Pumps 8

Stroke C/R 8

Stroke C/R 704A 704B 720 MOV MOV Suction 1-B RHR Pump Motor Operation Pump Disch to RHR Pumps MOV Suction 1-A RHR Pump Stroke Q

Stroke Q

8 Stroke C/R 721 MOV Motor Op 10" Disch to B Loop From RHR Pumps 8

Stroke C/R 738A 738B 825A 825B MOV CC to 1-A RHR HX YiOV CC to 1-B RHR HX YiOV SI Pump Suction From RWST MOV SI Pump Suction From RWST Stroke Q

Stroke Q

9 Stroke C/R 9

Stroke C/R 826A MOV SI Pump Suction From BA Tank Stroke Q

QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through Ma 31, 1979 Period OATE October 31, 1977 PAGE 12 32 Valve I ~Te Descri tion Note Test Freer 826B 826C MOV MOV SI Pump Suction From BA Tank SI Pump Suction From BA Tank Stroke Q

Stroke Q

826D 836A 836B MOV HCV HCV SI Pump Suction From BA Tank Spray Additive Tank Dis-charge Spray Additive Tank Dis-charge Stroke Q

Stroke Q

Stroke Q

850A 850B 851A 851B 852A 852B 856 NOV Sump B to RHR Pumps NOV Sump B to RHR Pumps MOV In Sump B to RHR Pumps MOV MOV In Sump B to RHR Pumps

,RHR Pump to RX Vessel MOV RHR Pumps to RX Vessel MOV RWST to RHR Pumps Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

9 Stroke C/R 857A 857B 857C 860A 860B MOV MOV NOV MOV MOV Isolate gl RHR HX Prom CS and SI Pumps Isolate I2 RHR HX From CS and SI Pumps Isolate el RHR HX Prom CS and SI Pumps Parallel Discharge MOV From 1-A CSP Parallel Discharge MOV From 1-A CSP Stroke Q

Stroke Q

Stroke Q

Stroke Q

St,roke Q

QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 through May 31, 1979 Period OATE October 31 1977 PAGE 13 32 Valve 0

T~e Note Test Freer 860C 860D 871A 871B 875A 875B 876A 876B 896A 896B 1815A 1815B 3504 3505 MOV Parallel Discharge MOV From 1-B CSP MOV Parallel Discharge MOV From 1-B CSP MOV 1-A to 1-C SI Pump Discharge MOV 1-B to 1-C SI Pump Discharge MOV Parallel MOV From CS Pumps to Charcoal Filter Deluge MOV Parallel MOV From CS Pumps to Charcoal Filter Deluge MOV Parallel MOV From CS Pumps to Charcoal Filter Deluge MOV Parallel MOV From CS Pumps to Charcoal Filter Deluge MOV RWST to CS and SI Ppmps MOV RWST to CS and SI Pumps MOV C-SI Pump Suction From RWST MOV C-SI Pump Suction From RWST MOV Main Steam to AFP From 1-B S/G Remote Valve MOV Main Steam to AFP From 1-A S/G Remote Valve Stroke Q

Stroke Q

Stroke Stroke Stroke Q

Stroke Stroke Stroke Stroke Q

Stroke Stroke 9

Stroke C/R 9

Stroke C/R Stroke Q

QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period OATE 49 90c October 31, 1977 PAGE 14 oF 32 valve N

3652 3996 4000A 4000B 4007'008 4013 4027 4028 4098 4291 4297 4298 4304

~Te Descri tion AOV AFW Reg. Discharge Valve to 1-A S/G AOV Aux.

FW Reg. Valve Dis-charge to 1-B S/G AOV 1-A MDAFP Recirculation Cont. Valve MV Main Steam Throttle Valve to TDAFP MOV TDAFP Discharge Valve MOV Cross Over Valve For MDAFP MOV Cross Over Valve For MDAFP MOV 1-A MDAFP Discharge Valve MOV 1-B MDAFP Discharge Valve MOV TDAFP Service Water Supply Isolation Valve MOV 1-A MDAFP Service Water Isolation Valve MOV 1-B MDAFP Service Water Isolation Valve MV Service Water Supply Iso-lation to TDAFP AOV TDAFP Recir. Line Note Test Frece Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

4310 4561 AOV 1-B MDAFP Recirculation Containment. Valve AOV Containment Vent Recirc.

Fans Discharge Flow Con-trol Valve Stroke Q

Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION..

TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September.'.1, 1977 Through May 31, 1979 Period DATE 40 OOC October 31, 1977 PAGE 15 32 Valve N

~T)e 4562 4609 4613 4614 4615 4616 4663 4664 4670 4733 4734 AOV MOV MOV

'MOV MOV MOV MOV MOV MOV MOV MOV Containment Vent Recirc.

Fans Discharge Flow Con-trol Bypass Valve 1-Al Intake Screen Wash Isolation Valve 1-B2 Turbine Building SW Isolation Valve 1-Al Turbine Building SW Isolation Valve 1-Bl Aux. Building SW Isolation Valve 1-Al Aux. Building SW Xsolation Valve to CC HX Air Condition Chillers SW Xsolation Valve 1-Al Turbine Building SW'so-lation Valve 1-A2 Turbine Building SW Supply Isolation Valve 1-Bl Air Cond. Chillers SW Xsolation Valve 1-A2 Aux. Build.

SW Isolation Valve 1-B2 Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

4735 4780 5171 MOV MOV MOV Aux. Build.

SW Isolation Valve 1-A2 Condenser Circulation Pump Seal Xsolation Valve Turbine Build. Fire Water Loop Supply Isolation Valve Stroke Q

Stroke Q

Stroke Q

QUALITYASSURANCE MANUAL GINNA STATION TITLE:

APPBND1 Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period OATE 49iOOC October 31, 1977 PAGE 16 32 Valve N

~Te 5871 APV Containment Post Accident Filter Damper Note Test.

F~re Stroke Q

5872 5873 5874 5875 5876 APV Containment Post, Accident Filter Damper APV Containment Post.

Accident'ilter Damper APV Containment Post Accident Filter Damper APV Containment Post Accident Filter Damper APV Containment Post Accident Filter Damper 4.10 Category C Check Valves Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

Valve I

~TEIe 710A CV Check Discharge 1-A RHR Pump r~

Stroke Q

710B 723A 723B 842A 842B CV CV CV CV Check Discharge 1-B RHR Pump Discharge Check Valve 1-A CC Pump Discharge Check Valve 1-B CC Pump First Check Valve in Loop A Accumulator Dump Line First Check Valve in Loop B Accumulator Dump Line

= Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

QUALITY ASS U RANC E MANUAL GINNA STATION TITI.E:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE 40 OOC 17 OF October 31, 1977 PAGE Valve N

~Te Descri tion Note Test Frece 847A 847B CV CV A-CSP From Spray Additive Tank to Eductor B-CSP From Spray Additive Tank to Eductor Stroke St.roke 853A 853B 854 866A CV Core Deluge Check CV Core Deluge Check

'CV CV RWST to RHR Pump Check CS Pump 1 A to Charcoal Filter Deluge 10 Stroke C/R 10 Stroke C/R ll Stroke C/R 12 866B 867A 867B 878G 878J CV CV CV CV CV CS Pump 1-B to Charcoal Filter Deluge Accumulator Dump and SI to Cold Leg Loop B Accumulator Dump and SI to Cold Leg Loop AI 1-A SI Pump to Cold Leg Loop B After MOV 878B 1-B SI Pump to Cold Leg Loop A After MOV 878D 13 Stroke C/R 13 Stroke C/R 13 Stroke C/R 13 Stroke C/R 1812A CV 1-A RCDT Pump to 1-B RHR HX Stroke Q

1812B CV 1B RCDT Pump to 1A RHR HX Stroke 3516 CV 1B S/G Main Steam Swing Check Stop Valve 14 Stroke Start-up 3517 3998 CV CV lA S/G Main Steam Swing Check Stop Valve AFP Discharge Check Valve 14 Stroke Stroke Start-up

I 1

QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE 49 OOC 18 32 October 31, 1977 PAGE Valve N

~Tpe 4000C CV Descri tion lA MDAFP Discharge Check Valve Downstream MOV-4007 Note Test F~re Stroke Q

4003 CV 4000D CV 1B MDAFP Discharge Check Valve Downstream MOV-4008 TDAFP to S/G lA Check Valve Stroke Q

Stroke Q

4004 CV TDAFP to S/G 1B Check Valve

Stroke Q

4009

'V lA MDAFP to S/G lA Check Valve Stroke Q

4010 CV 1B MDAFP to S/G 1B Check Valve Stroke Q

4014 4016 4017 4023 4601 CV TDAFP Condensate Suction Check Valve CV 1B MDAFP Suction Check CV lA NDAFP Suction Check Valve CV TDAFP Recirculation Check Valve CV lA Service Water Pump Discharge Check Stroke Q

Stroke Q

Stroke Q

Stroke Q

Stroke Q

4602 4603 CV CV 1B Service Water Pump Discharge Check 1C Service Water Pump Discharge Check Stroke Q

Stroke Q

4604 5133 CV 1D Service Water Pump Discharge Check CV Diesel Pump Disch. Check Valve Stroke Q

Stroke Q

5136 CV Motor Pump Discharge C.V.

Stroke Q

QUALIT'( ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1, 1977 Through May 31, 1979 Period DATE October 31, 1977 PAGE 19 32 4.11 Category C Relief Valve 203 RV Valve I ape Descri tion Letdown High Pressure Safety Relief Note Test Frece 15 209 434 435 732 I

744 755A RV RV RV RV RV RV Letdown Low Pressure Safety Relief Pressurizer Relief Pressurizer Relief CC Surge Tank Relief CC From Excess Letdown Heat Exchanger CC From A RCP Thermal Barrier Relief 15 15 15 15 15 15 755B 758A 758B RV RV RV CC From B RCP Thermal Thermal Barrier Relief CC From A-RCP Oil Coolers 15 15 CC From B-RCP Oil Coolers 15 818 861 RV RV CC From Reactor Support 15 Coolers 1-B CS Pump Suction Relief 15 887 1817 3508 RV RV RV On SI Test Line Inside Containment Alternate Suction From RHR Pump to C SI Pump 1-B S/G PRV 15 15 15 3509 RV 1-A S/G PRV 15 3510 RV 1-B S/G PRV 15

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QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inseryice Pump and'Valve Testing Program for the September 1,

1977 thorough May 31, 1979 Pere.od DATE loiOOC 20 32 October 31, 1977 PAGE alve 4

T~e Note Test Frece 3511 3512 3513 3514 3515 4653 4654 4657 5134 5135 RV 1-A S/G PRV RV

. 1-A S/G PRV RV 1-A S/G PRV RV 1-B S/G PRV RV 1-A S/G PRV RV Service Water Relief RV Service Water Relief RV Service Water Relief RV Diesel Pump Disch R.V.

RV Motor Pump Disch R.V.

4.12 Category E Locked Valves 15 15 15 15 15 15 15 15 15 15 311B MV 329 MV Valve I T~e Excess Letdown to Seal Water Return lA Boric Acid Pump Recir-culation Valve Normal Position Open Open 336 337 344 369 384B 543 544 703 MV MV MV MV MV MV MV lA Boric Acid Transfer Pump Suction Flush 1B Boric Acid Transfer Pump Suction Flush 1B Boric Acid Pump Recir-culation Valve Letdown Line Sample and Return Charging Line Outlet Letdown Stop Valve Excess Letdown Stop RHR Out RHR HX's to Letdown Closed Closed Open Closed Open Open Open Open

QUALITYASSURANCE MANUAL GINNA STATION TITI.E APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE October 31, 1977 PAGE 21 32 Valve N

~Te Descri tion Normal Position 705C MV Valve 850A Pressure Relief Bonnet Vent Open 705D 707A 707B 708A 708B 709A 709B 709C 709D 714 715 716 717 728 MV Valve 850B Pressure Relief Bonnet Vent MV CC to lA Residual Heat Pump MV CC to lB Residual Heat Pump

'MV CC From lA Residual Heat Pump MV CC From 1B Residual Heat Pump MV Discharge Stop lA RHR Pump MV Discharge Stop 1B RHR Pump MV RHR Pump Discharge Cross Tie MV RHR Pump Discharge Cross Tie MV RHR to lA RHR HX MV RHR Out 1B RHR HX MV RHR to 1B RHR HX MV RHR Out lA RHR HX MV CC HX Surge Line Stop Open Open Open Open Open Open Open Closed Closed Open Open Open Open Open 764C MV Combined CC Return From SI Pumps Throttled 764D 769 777A 777B MV Combined CC Return From Con-tainment. Spray Pumps MV Combined Stop CC From RHR Pumps MV CC to 1A Containment Spray Pump MV CC From 1A Containment Spray Pump Throttled Throttled Open Open

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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE October 31 1977 PAGE 22 32 Valve N

~Te 777C MV CC From 1B Containment Spray Pump Normal Position Open 777D MV CC From 1B Containment Spray Pump Open 777E 777F 777G 777H 777J 777K 777L 777M 777N 777P 777R 777S

'MV CC From 1C SI Pump MV CC To 1C SX Pump MV CC To 1B SI Pump MV CC From 1B SX Pump MV CC To lA SI Pump MV MV CC From lA SX Pump CC To 1C SI Pump CC From 1C SI Pump CC From 1B SI Pump MV CC To 1B SI Pump CC From 1A SX Pump MV CC To lA SI Pump Open Open Open Open Open Open Open Open Open Open Open Open 788A 803 804 822B 831A 831B MV MV MV MV MV MV Make up Water Valve to SFP SFP Filter Discharge to RUST SFP HX By-pass From SFP Filter RHR Pump Recirculation Spray Additive Tank From CS Pump Suction Spray Additive Tank From CS Pump Suction Closed Closed Throttled Open Open Open

QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for'the September 1,

1977 Through Ma 31 1979 Period 23 32 DATE October 31, 1977 PAGE 841 852A 852B 856 858A 858B 859A 859B Descri tion MV Suction Valve to CS Pump 1B Normal Position

'pen Closed Closed Open Open Open MV Test Line Valve From CS Pump lA Test Line Valve From CS Pump 1B Closed Closed MOV Accumulator Discharge Loop B MOV Core Deluge MOV Core Deluge MOV RWST To RHR Pumps MV Suction Valve to CS Pump lA 864A 864B MV MV Test Connection on Discharge Line of CS Pump lA Test Connection on Discharge Line of CS Pump 1B Closed Closed 865 86 8A 868B MV Discharge Valve From CS Pump lA Discharge Valve From CS Pump 1B MOV Accumulator Discharge Loop A Open Open Open 873A 873B 873C 873D MV MV MV MV Spray Additive Tank from CS Pumps Open Spray Additive Tank from CS Pumps Open Spray Additive Tank from CS Pumps Closed Spray Additive Tank from CS Pumps Closed 878A 878B 878C MOV SI to Loop B Hot Leg MOV SI to Loop B Cold Leg MOV SI to Loop A Hot Leg Closed Open Closed

C

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for 'the September 1,

1977 through May 31, 1979 Period DATE October 31, 1977 PAGE 24 32 Valve 0

T~e Descri tion Normal Position 878D 879 880B 880C 881A 881B 881C 881D 888A 888B 890A 890B MOV SI to Loop A Cold Leg MV SI Test Line MV Loop B Accumulator Test Line MV Loop A Accumulator Test Line MV Spray Additive Tank Drain MV Spray Additive Tank Outlet MV Spray Additive Eductor Outlet MV Spray Additive Eductor Outlet MV 1A SI Pump Discharge MV 1B SI Pump Discharge MV Suction For SI Pump 1A MV Suction For SI Pump 1B I

Open Closed Open Open Closed Open Open Open Open Open Open Open 1076A 1076B 1080A 1084A 1084B MV A Hydrogen Recombiner Pilot Line Closed MV B Hydrogen Recombiner Pilot Line Closed MV Hydrogen Recombiner Oxygen Makeup Closed MV A Hydrogen Recombiner Main Burner Closed MV B Hydrogen Recombiner Main Burner Closed 1554 1556 MV D Recirculation Fan Air Sample MV D Recirculation Fan AIr Sample Closed Closed

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QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inseryice Pump and Valve Testa.ng Porgram for the September 1,

1977 through May 31, 1979 Period DATE 49iOOC October 31, 1977 PAGE 25 32 Valve 0

T~e 1557 1559 1560 A Recirculation Fan Air Sample A Recirculation Fan Air Sample A and D Recirculation Fans Air Sample Return Normal Position Closed Closed Closed 1562 1563 1565 1566 1568 1569 1571 1572 MV MV MV MV MV A and D Recirculation Fans Air Sample Return B Recirculation Fan Air Sample B Recirculation Fan Air Sample B Recirculation Fan Air Sample Return B Recirculation Fan Air Sample Return C Recirculation Fan Air Sample C Recirculation Fan Air Sample C Recirculation Fan Air Sample Return Closed Closed Closed Closed Closed Closed Closed Closed 1574 MV C Recirculation Fair Air Sample Return Closed 1722 MV Refueling Canal Drain to RCDT Pump Closed 1820A MV Shutoff Valve for A SI Pump Test Line 1820B MV Shutoff Valve for C SI Pump Test Line 1820C MV Shutoff Valve for B SI Pump Test Line Open Open Open

QUALITYASSURANCE MANUAL GINNA STATION TITLE

'PPENDIX C Ginna Station Inservice Pump and Valves-Testing Program for the September 1,

1977 through May 31, 1979 Period DATE 49 DOC 26 32 ctober 31 1977 PAGE Valve 5

T~e 3528 MV Descri tion Main Steam to Auxiliary Feedwater Pump Normal Position Open 4015 4018 4019 4070 TDAFP Suction Isolation MV 'BMDAFP Suction Isolation lAMDAFP Suction Isolation Condensate Storage Tank 1B Xsolation Valve Open Open Open Open

'071 Condensate Storage Tank 1A Isolation Valve Open 4072 4073 MV 1B Condencate Storage Tank Drain Closed 1A Condensate Storage Tank Drain Closed 4074 4075 4080 4081 4082 MV MV AFP Recirculation to 1B Conden-sate Storage AFP Recirculation to lA Conden-sate Storage TDAFP Discharge Orfice Xsolation lA MDAFP Discharge Orfice Isolation 1B MDAFP Discharge Orfice Isolation Open Open Open Open Open 4098 MV Service Water Isolation to TDAFP

'pen 4344 MV Service Water Isolation to MDAFP Closed

I

QUALlTY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inseryice Pump and Valves Testing Program for the September 1,

1977 through May 31, 1979 Period 49 QOC DATE October 31, 1977 PAGE 27 '"

32 Valve 0 T~e 4 345 MV 4738 MV 4739 MV 4789 MV 4790 MV 4791 MV 4791A MV Descri tion Service Water to lA MDAFP A Service Water Loop to CC B Service Water Loop to CC SI Pump Bearing Oil Cooler Isolation SI Pump Bearing Oil Cooler Isolation 1A SI Pump Bearing Oil Cooler Inlet 1A SI Pump Bearing Oil Cooler Outlet Normal Position Closed Open Open Open Open Open Open 4794 MV 4794A MV 4795 MV 4795A MV 5022 MV 5024 MV 5931 MV 5932 MV 5935 MV lB SI Pump Bearing Oil Cooler Inlet 1B SI Pump Bearing Oil Cooler Outlet 1C SI Pump Bearing Oil Cooler Inlet 1C SI Pump Bearing Oil Cooler Outlet DI Water Supply DI Water Supply 1A Diesel Generator Cooling Water 1B Diesel Generator Cooling Water lA Diesel Generator Cooling Water Open Open Open Open Closed Closed Open Open Open

QUALITY ASS U RANC E MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1, 1977 Through May 31, 1979 Period DATE 49 OOC 28 32 October 31, 1977 PAGE Valve N ~Te Descri tion Normal Position 5936 MV 5947 MV 1B Diesel Generator Cooling Water 1A Diesel Generator Air Receiver Outlet Open Open 5947A MV 5948 MV lA Diesel Generator Air Receiver Outlet 1B Diesel Generatory. Air Receiver Outlet Open Open 5948A MV 5973 MV 1B Diesel Generator Air Receiver Outlet 1A Diesel Generator Isolation Valve Open Open 5974 MV 5977C MV 5977D MV 1B Diesel Generator Isolation Valve lA Diesel Generator Day Tank lA Diesel-Generator Drain to Reservoir Open Closed Closed 5978C MV 5978D MV 1B Diesel Generator Day Tank lB Diesel Generator Drain to Reservoir Closed Closed 7140 MV Guard Valve Upstream Secondary Isolation Valve Closed 7141 MV Secondary Isolation Valve Outside Containment Closed 7227 MV 744 8 MV Primary Isolation Valve Inside Containment Isolation Valve to Pressure Indicators Closed Closed

QUALITY ASS U RANCE MANUAL G INNA STATION TITLE:

APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1, 1977 Through Ma 31 1979 Period DATE 40iOOC October 31, 1977 PAGE OF

~ 29 Valve 5

~Te 7452 MV Isolation Valve for Local Pressure Indicators Normal Position Closed 7456 MV Isolation Valve for Local Pressure Indicators Closed 4.13 Inservice Valve Testing Notes Note 1Valves

304A, 304B and 3

3 cannot be stroked during normal plant operation on a quarterly basis because they would interrupt coolant flow'to the reactor coolant pump seals.

These valves will be stroked at cold shutdowns or re-fueling outages Note 2 Note 3 Valve 370B cannot be stroked during normal plant operation on a quarterly basis because this test would 'interrupt charging pump flow. 'This valve will be stroked at cold shutdowns or refueling outages.

Valves 371 and 427 cannot be stroked dur-ing normal plant operation on a quarterly basis because this test would interrupt the letdown (CVCS) system.

These valves will be stroked at cold shutdowns or refueling outages.

Note 4Valve 383B cannot be stroked during normal plant operation on a quarterly basis b'ecause this test would result in substantial radiation exposure to test personnel.

A recent survey in the area of the test connection indicated a

neutron field of 500 mr/hr and a gamma field of 250 mr/hr.

This valve will be stroked at cold shutdowns or refueling outages.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,

1977 Through Ma 31, 1979 Period DATE 49 OOC 30 OF 32 October 31, 1977 PAGE Note 5

Valves

750A, 750B, 759A and 759B cannot be stroked during normal plant operation on a quarterly basis because this test would require the reactor coolant pumps to be shut down to eliminate the flow through these checks and MOVs These valves will be stroked at cold shutdowns or refueling outages.

Note 6 Note 7

Valves 813 and 814 cannot be stroked dur-ing normal plant operation on a quarterly basis because this test would remove the coolant to the reactor vessel supports and cavity wall.

These valves will be stroked at cold shutdowns or refueling outages Valve 879 is a manual valve in the safety injection test line and is kept locked shut.

This valve is not required to change position to perform a safety func-tion.

The only requirement. is that leak-age through valve 879 be acceptably low.

Therefore, the quarterly stroke test has been deleted.

This valve will be leak tested at refueling outages Note 8

Valves 700 and 721 cannot be stroked dur-ing normal plant operation on a quarterly basis because there is an interlock sys-tem which prevents these valves from opening when the primary system is at operating pressure.

Valves 700, 701, 720 and 721 separate a high pressure system from a low pressure system.

These valves will be stroked at cold shutdowns or refueling outages

QUALITYASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,

1977 Through May 31, 1979 Period DATE October 31, 1977 PAGE 31 32 Note 9

Note 10-Valves 825A, 825B,

856, 896A, and 896B should not be stroked during normal opera-tion on a quarterly basis because this would cause a temporary loss of system function of the ECCS.

These valves pro-vide the suction from the refueling water storage tank to the safety injection and residual heat removal pumps.

These valves will be stroked at cold shutdowns or re-.

fueling outages.

Valves 853A and 853B cannot be stroked dur-ing normal. plant operation on a quarterly basis because this test would pressurize the RHR system to the primary system opera-tion pressure.

These valves will be stroked at cold shutdowns or refueling outages.

Note Note 12-Valve 854 cannot be stroked during normal plant operation on a quarterly basis be-cause there is not a way to establish a

flow through this valve when the primary system is at pressure and the RHR system is not operating.

This valve will be stroked at c'old shutdowns or refueling outages Valves 866A and 866B cannot be stroked at any time because they are part of the con-tainment spray system, which when pressurized, sprays borated water and/or sodium hydroxide solution throughout con-tainment.

Such a condition would be in-tolerable for future plant operation.

An air test could be performed by supplying a large volume of air to the spray ring header which hopefully would be able to lift the check valve flapper.

At this time there is not any instrumentation to verify check valve operability, even if an air test would lift the flapper.

Therefore, this valve will not be tested until a proper modification may be made in the future.

c.

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4 QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1, 1977 Through May 31, 1979 Period DATE 49 OOC October 31, 1977 PAGE 32 32 Note 13-Valves 867A, 867B,

878G, and 878J cannot be stroked during normal operation on a quarterly basis because this test cannot be done when the primary system is at operating pressure.

This test may only be done when the plant is in a cold shutdown condition with a partially full primary system in order to prevent an overpressurization.

Note 14-Valves 3516 and 3517 cannot be stroked during normal plant operation in a quarterly basis because they are the main steam swing check stop valves.

These, valves are stroked during each plant startup.

Note 15-Category C Relief Valves shall be tested in accordance with the extent and frequency requirements of Paragraph IWV-3510 of Article XWV of Section XX of the Code.

PVT 5.0 Records 5.1 Records for the Xnservice Pump Testing Program shall be developed and maintained in accordance with Article XWP-6000 of Section XX of the Code.

5.2 Records for the Xnservice Valve Testing Program shall be developed and maintained in accordance with Article IWV-6000 of Section XI of the Code.

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