Text

Rev 6 to QA Manual,App C Re Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1989
	ML17254A423
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Site:	Ginna
Issue date:	01/10/1985
From:	Anderson C; ROCHESTER GAS & ELECTRIC CORP.
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	NUDOCS 8507090141
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QUALITY ASSURANCE MANUAL GINNA STATION ROCHESTER GAS

& ELECTRIC CORPORATIO

REY,

~RiR A PACK 1DP 4

EPPECTIYK DATE(January 10, 1985 5ICHATVRK DATE TITI.Ec Appendix C - Ginna Station Inservice Pump and Valve Testing Program for the January 1,

1981 through December 31, 1989 Period PREPARED EYE REVIEW APPRDYED SYc Q P. CM~~ //I/g5

~/i/~

Pr ram Table of Contents

==

Introduction:==

Definitions:

Program:

Discussion PVT l.0 Scope and Responsibility PVT 2.0 Code Edition and Testing Interval PVT 3.0 Inservice Pump Testing Program PVT 4.0 Inservice Valve Testing Program PVT 5.0 Records 8507090141 850703 PDR ADOCK 05000244 PDR"

a QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve, Testing Program DATE1/10/85 PAGE 2

OF 40 Introduction This appendix to the Quality Assurance Manual defines the Inservice Pump and Valve Testing Program for the ten year period starting January 1,

1981 through December 31, 1989.

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 50.55a(g) of 10CFR50 following the guidance of the ASME Boiler and Pressure Vessel Code Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components,"'hereafter referred to as the "Code" ) excluding the'controls of the Authorized Inspector, Enforcement'Authority, Reporting Systems and N-Stamp Symbol.

The inservice testing program shall be controlled by the Ginna Station Quality Assurance Program for Station Operation.

Quality Groups A,

B and C components correspond to those defined in NRC Regulatory 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 substantially augments but does not affect the pump and valve surveillance program required by Technical Specifications.

Technical Specification requirements associated with pump and valve surveillance, shall continue to be implemented as specified.

~

rg 0

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 3

pp 40 Definitions AFP AOV APV BA Code CC CS CSP CV C/R ECCS FCV GA GDT HCV HX LCV M

MAFP MOV MV PCV PORV PRT PRV PVT Q

R RCDT RCP RCV RHR RV RWST

~ RX S/G SAFWP SI SOV SW gz.neers Pump Auxiliary Feedwater Pump Air Operated Valve-Air Operated Piston Valve Boric Acid American Society of Mechanical En Boiler and Pressure Vessel Code Component Cooling Containment Spray Containment Spray Pump Check Valve Cold Shutdown and Refueling Emergency Core Cooling System Flow Control Valve Gas Analyzer Gas Decay Tank Hand Control Valve Heat Exchanger Level Control Valve Monthly Motor Driven Auxiliary Feedwater Motor Operated Valve Manual Valve Pressure Control Valve Power Operated Relief Valve Pressurizer Relief Tank Pressure Relief Valve Pump and Valve Testing Quarterly Refueling Outage Reactor Coolant Drain Tank Reactor Coolant. Pump Radiation Control Valve Residual 'Heat Removal Reactor Makeup Water Relief Valve Refueling Water Storage Tank Reactor Vessel Steam, Generator Standby Auxiliary Feedwater Pump Safety Injection Solenoid Operated Valve Service Water

QUALITY ASSURANCE MANUAL GINNA STATION TITLEi APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE-4 PP 40 Definitions TAFP VC VCT VH Turbine Driven Auxiliary Feedwater Pump Volume Control Volume Control Tank Vent Header CAT A VALVE - Valves for which seat leakage is limited to a specific maximum amount in the closed position of fullfillmentof their function.

CAT B VALVE Valves for which seat leakage in the closed position is inconsequential for fullfillment of their function.

CAT C VALVE Valves which are self-actuating in response to some characteristic, such as pressure (relief valves) or flow direction (check valves).

QUALITY ASSURANCE MANUAL

'GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE1/10/85 PAGE 5

40 OF Pum and Valve Testin Pro ram PVT 1.0'co e and Res onsibilit 1.2 The inservice testing program defines the testing program 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 readiness of pumps and valves.

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

1.3 When a valve, pump or its control system has been replaced or repaired or has undergone maintenance that could affect its performance, and prior to the time it is returned to service, it shall be tested as necessary to demonstrate that the per-formance parameters which could have been affected by the replacement, repair, or maintenance are within acceptable limits.

PVT 2. 0 Code Edition and Testin Interval 2.1 The Inservice Pump and Valve Testing Program for the ten (10) year period starting January 1,

1981 through December 31, 1989 was developed utilizing the 1977 Edition of Section XI of the Code through the Summer 1978 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 perform a specific function in shutting down a reactor or in mitigating the consequences of an accident and maintain the reactor in a safe shutdown condition.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 6

pp 40 3.2 The following pumps shall be tested in accordance with Article IWP of Section XI:

3.3 (a) lA Component Cooling (b) 1B Component Cooling (c) lA Safety Injection (d) 1B Safety Injection (e) 1C Safety =Injection (f) lA Residual Heat Removal (g) 1B Residual Heat Removal (h) 1A Containment Spray (i) 1B Containment Spray (j) 1A Motor Driven Auxiliary Feedwater (k) 1B Motor Driven Auxiliary Feedwater (1)

Turbine Driven Auxiliary Feedwater (m) lA Service Water (n) 1B Service Water (o) 1C Service Water (p) 1D Service Water (q) 1C Standby Auxiliary,Feedwater (r) 1D Standby Auxiliary Feedwater With one exception, test parameters that shall be measured or observed during inservice testing of each pump are those listed in Table IWP-3100-1 of Section XI and include inlet pressure, differential

pressure, flow rate, vibration amplitude, and proper lubricant level or pressure.

The exception is for the measurement of pump bearing temperatures and there are several reasons why this measurement is either undesirable or inconclusive.

Specifically, for the service water pumps, the bearings are submersed in up to forty feet. of water making bearing temperatures closely approximate the surrounding water terriperature and measurement of temperatures almost impossible.

For the auxiliary and standby auxiliary feedwater pumps the test conditions require the discharge. of ambient temperature water into the 400 degree F feedwater lines.

Since it can typically take in excess of an hour to stabilize bearing temperatures this causes an unnecessary, extended temperature trans-ient in the feedwater, line.

For the residual heat removal and safety injection pumps the system configurations do not allow testing the pumps at actual pump service conditions during plant operation.

Instead, the tests must be

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 DF 40 3.4 performed at an off-design flow condition which results in higher bearing temperatures than normal.

This is to be'xpected since higher than normal thrust loads are placed on the pump bearings during'his reduced flow test condition.

The extended time required for bearing temperatures to stabilize subjects the pump to lengthy periods of unnecessarily high loads.

The pump vendors do'ot consider the measurement of bearing temperature in this type of off-design condition to be a good indication of bearing conditions.

The vendors recommended bearing temperature limits are based on normal operating conditions and,do not apply to this type of testing.

In general, vibration

's considered to be. a better indication of bearing condition since a significant increase in bearing temperature will normally only occur if.bearing failure is imminent.

Finally, test conditions cannot be easily controlled to produce temperature repeatability since readings are subject to a large number of variables such as ambient air temperature, cooling water temperature (where applicable),

location of temperature probe attach-ment, temperature of the fluid pumped and quantity of the fluid pumped.

One or both residual heat removal pumps may be required to be operable, by the plant Technical Specifications, when the average reactor coolant temperature is between 350 degrees

.F.

and 200 degrees F. or the plant is at cold or refueling shutdown.

Typically, in this case, at least one residual heat removal pump will be in operation.

Testing will be performed in accordance with IMP-3400, which, includes operating the pump at reference conditions, if practicable, and providing a log which shows that the parameters monitored during normal plant operation were measured, recorded and analyzed.

The practicability of duplicating cold shutdown reference conditions may be impacted by refueling water level during refueling and inservice reactor inspections as well as decay heat removal rate.

The test freguency for the pumps shall be as follows:

a.

Component cooling water pumps shall be tested monthly.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 8

pp 40 b.

c ~

d.

Safety injection pumps shall be tested monthly except during cold or refueling shutdowns.

The pumps shall be tested prior to startup if the time since the last test exceeds one month.

C Residual heat removal pumps shall be tested monthly except during cold or refueling shutdown.

The pumps shall be tested prior to startup if the time since the last test exceeds one month.

When the reactor coolant system temperature is between 350'F and 200'F or the plant is at cold or refueling shutdown the plant Technical Specifications may require one or both residual heat removal pumps to be operable.

If this is the case, then the required pumps shall be tested monthly.

Containment spray pumps shall be tested monthly except during cold or refueling shutdown.

The pumps shall be tested prior to startup if the time since the last test exceeds one month.

e.

Motor driven auxiliary feedwater

pumps, turbine driven auxiliary feedwater

pump, and the standby auxiliary feedwater pumps shall be tested monthly except during cold or refueling shutdowns.

The pumps shall be tested prior to exceeding 5% power if the time since the last test exceeds one month.

Service water pumps shall be tested monthly.

Testing of a pump need not be performed if that pump is declared inoperable without the testing.

Consistent with plant Technical Specifications, specified intervals may be extended by 25% to accommodate normal test schedules.

DATE'UALITY ASSURANCE NANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 9

Dp 40 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 specific function either to shut down the reactor to the cold shut-down condition or in 'mitigating the consequences of an accident and maintain the reactor in a safe shutdown condition are included in the program.

4.2 4.3 The Inservice Valve Testing Program Requirements for Category A and B Valves are in Tables PVT 4.7 and 4.8, respectively.

Category C Valves are broken down into two categories, Check Valves and Relief Valves, which are in Tables PVT 4.9 and 4.10, respectively.

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

Some exceptions and exdmptions 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 4.12.

4.5 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.

Except where operational

'onstraints prevail and exceptions 'have been authorized all check valves, including Category C

Valves, shall be exercised to the position required to fulfilltheir function.

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

Valves which malfunction during stroking will not be considered inoperable as defined by Technical Specifications, when the malfunction does not prevent the valves from performing its safety function.

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.

Durin each

l

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program

,1/10/85 PAGE.

10 DP 40 4.6 refueling outage a visual verification shall be made to confirm direct correspondence between valve operators and the position indicators.

For a valve in a system declared inoperable or not required to be operable the exercising test schedule need not be followed.

Within 30 days prior to return of the system to operable status, the valves shall be exercised and the schedule resumed.

4.7 4.8 The testing of valves required at cold shutdown and 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 later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the plant reaches cold shutdown (as defined in Technical Specification l.2). For very short cold shutdowns (less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months '), 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 shut-down, the work load on test personnel may preclude their completion of all the required valve tests prior to startup.

Any testing not completed at one cold shutdown due to outage duration shall be performed during any subsequent cold shutdowns that may occur before the next refueling outage to meet the specified testing frequency.

Valve testing during cold shutdowns need not be more frequent than one test per quarter for each valve.

in the test program.

Category A Valves Valve 5

~Te Note Test

~Fre 204A 304A 304B MV Letdown to NRHX CV l-A RCP Seal Injection CV l-B RCP Seal Injection Stroke C/R Leak R

Stroke C/R Leak R

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/10/85 PAGE-ll pp 40 313 370B 37l 383B 508 528 529

'39 546 547 743 745 749A 749B 750A MOV Seal Water Return Isolation CV Charging Line Isolation AOV Letdown Isolation CV Alternate Charging Line AOV RMW, to Containment Vessel Stop CV N

Supply to PRT CV RMW to PRT

'OV PRT Stop Valve to Gas Analyzer MV PRT to Gas Analyzer MV Nitrogen to PRT CV CC From Excess Letdown HX.

AOV Return From Excess Let-down HX.

MOV CCW to A RCP MOV CCW to B RCP CV CC to A RCP Note 5

Test Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak

~Fre C/R R

C/R R

Q R

~

Q R

C/R R

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE-12 Pp 40 Valve 5

~Te 750B CV CC to B RCP 759A 759B MOV Containment Stop CC From Loop A RCP MOV Containment Stop CC From Loop B RCP Note Test Stroke Leak Stroke Leak Stroke Leak

~Fre C/R R

C/R R

8l3 814 820 842A 842B 846 853A 853B 862A MOV CC Supply to RX Support Coolers MOV CC Return to RX, Support Coolers MV Letdown to NRHX CV Loop A Accumulator Dump Line Check Valve CV Loop B Accumulator Dump Line Check Valve AOV N2 Supply to Accumulators CV Core Deluge Check CV Core Deluge Check CV l-A CSP Disch 28 28 10 10 10 10 Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak C/R R

C/R R

C/R C/R C/R C/R Q

R C/R C/R C/R C/R Q

R 862B CV l-B CSP Disch Stroke Q

Leak R

867A 867B CV Accumulator Dump and SI to Cold Leg Loop B CV Accumulator Dump and SI to Cold Leg Loop A 13 13 13 13 Stroke Leak Stroke Leak R

C/R R

C/R

QUALITY AS SURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program 4k'2 C 13 DF 40 DATE 1/10/85 PAGE Valve 0

~Te Descri tion Note Test Freq 870A CV 1-A to 1-C SI Pump Disch Stroke Q

Leak R

870B 877A 877B 878F 878G 878H 878J 879 889A 889B 921

- 922 923 924 CV High Safety Injection Loop B Hot Leg CV High Safety Injection Loop A Hot Leg CV High Safety Injection Loop B Hot Leg CV 1-A SI Pump to Cold Ieg Loop B CV High Safety Injection Loop A Hot. Leg CV 1-B SI Pump to Cold Leg Loop A MV SI Test Line Isolation CV l-A SI Pump Disch CV 1-B SI Pump Disch SOV Loop A Hydrogen Monitor Inlet SOV Loop A Hydrogen Monitor Outlet SOV Loop B Hydrogen Inlet I'OV Loop B Hydrogen Outlet Monitor II Monitor CV l-B to l-C SI Pump Disch 11 29 11 29ll 29 13 13 ll 29 13 13 Stroke Q

Leak R

Stroke Leak 40 Mo.

Stroke R

Leak C/R Stroke Leak 40 Mo.

Stroke R

Leak C/R Stroke Leak R

Stroke Q

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 TITLEc APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 14 DP 40 I

It 956D 956E 956F 966A MV Hot Zeg Loop Sample Containment Isolation MV PRZR Ziquid Space Sample Containment Isolation MV PRZR Steam Space Sample Containment Isolation AOV Pressurizer Steam Space Containment Isolation Note Test

~Fre Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

966B 966C 1003A 1003B 1076A IV-3A 1076B IV-3B 1080A IV-2A IV-2B AOV Pressurizer Liquid Space Containment Isolation AOV Loop A and B Hot Leg Containment Isolation LCV l-A RCDT Pump Suction LCV 1-B RCDT Pump Suction Oxygen Make Up to ment Isolation (A I

Oxygen Make Up to ment Isolation (B

Contain-11 Recombiner)

Contain-ll Recombiner)

MV Hydrogen to "A" Recombiner 11 Pilot Containment Isolation SOV Hydrogen to "A" Recombiner ll Pilot Containment Isolation MV Hydrogen to "B" Recombiner 11 Pilot Containment Isolation SOV Hydrogen to "B" Recombiner 11 Pilot Containment Isolation MV Oxygen Make Up to Contain-11 ment Isolation Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Z eak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Z eak Stroke Leak Q

R Q

R

QUALITY AS SURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 15 PP 40 Valve 5 1084A IV-5A 1084B IV-5B 1554 1556 1557 1559 1560 1562 1563 1565 1566 1568

~Te SOV SOV Descri tion Hydrogen to "A" Recombiner Main Burner Containment Isolation Hydrogen to "A" Recombiner Main Burner Containment Isolation Hydrogen to "B" Recombiner Main Burner Containment, Isolation Hydrogen to "B" Recombiner Main Burner Containment Isolation D Recirc.

Fan Air Sample Isolation D Recirc.

Fan Air Sample Isolation A Recirc.

Fan Air Sample Isolation A S D Return Line Isolation A & D Return Line Isolation B Recirc.

Fan Air Sample Isolation B Recirc.

Fan Air Sample Return Line Isolation B Recirc.

Fan Air Sample Return Line Isolation Note Test

~Fre 11 Stroke Leak R

11 Stroke Leak R

ll Stroke Leak R

11 Stroke Leak R

ll Stroke Leak R

11 Stroke Leak R

ll Stroke Leak R

11 Stroke Leak R

ll Stroke Leak R

0

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 16 DF 40 Valve 5

~Te 1569 C Recirc.

Fan Air Sample Isolation Note Test

~Fre Stroke Leak 1571 1572 1574 1596 1597 1598 1599 1655 1713 172l 1723 1728 1786 1787 C Recirc.

Fan Air Sample Isolation C Recirc.

Fan Air Sample Return Line Isolation C Recirc.

Fan Air Sample Return Line Isolation MV Radiation Monitor Supply AOV Radiation Monitor Supply AOV Radiation Monitor Exhaust AOV Radiation Monitor Exhaust MV RCDT to Gas Analyzer CV N2 to RCDT AOV Suction line to RCDT AOV A Containment Sump Disch to Waste Holdup Tank AOV A Containment Sump Disch to Waste Holdup Tank AOV RCDT to VH Isolation AOV RCDT to VH Isolation Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q

R=

Q R

'Q R

Q R

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE.

17 DP 40 Note 1819A MV Containment Pressure 21 Transmitter 945 Isolation Valve 0

~Te 1789 AOV RCDT to GA Containment Isolation Stroke Leak Stroke Leak Q

R C/R R'est Freq 1819B 1819C MV Containment Pressure 21 Transmitter 946 Isolation MV Containment Pressure 21 Transmitter 947 Isolation Stroke Leak Stroke Leak C/R R

C/R R

1819D MV Containment Pressure 21 Transmitter 948 Isolation Stroke C/R Leak R

1819E 1819F 1819G 460$

4602 4603 4604 5129 5392 5393 CV 1B Service Water Pump Discharge CV 1C Service Water Pump Discharge 31 31 31 31 CV 1D Service Water Pump 31 Discharge 31 MV Construction Fire Service ll Water Containment Isolation AOV Instrument Air to Contain-19 ment Isolation CV Instrument Air to Containment Isolation 19 MV Containment Pressure 21 Transmitter 949 Isolation MV Containment Pressure 21 Transmitter 950 Isolation MV Containment Pressure 21 Transmitter 944 Isolation CV 1A Service Water Pump 31 Discharge 31 Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak C/R R

C/R R

Q R

R R

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE

~

18 pF 40 Valve 0

~Te Note Test

~Fre 5701 5702 5733 5734 5735 5736 5737 MV A-S/G Blowdown Isolation MV B-S/G Blowdown Isolation MV A-S/G Sample Isolation MV B-S/G Sample Isolation AOV "A" S/G Blowdown Sample Isolation AOV "B" S/G Blowdown Sample Isolation AOV "B" S/G Blowdown Isolation Stroke Leak Q

R Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Leak R

5738 5869 5870 5878 5879 6151 6152 AOV "A" S/G Blowdown Isolation APV Containment Purge Supply Isolation APV Containment Purge Supply Isolation APV Containment Purge Exhaust Isolation APV Containment, Purge Exhaust Isolation MV Auxiliary Steam Supply to Containment MV Condensate Return from Containment 22 22 22.

22 Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Ieak Stroke Leak Stroke Ieak Q

R

,* See Note 22

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE.

oF 4o Valve 4

~Te

'6165 6175 7141 7226 7443 7444 MV Aux. Steam Supply to Containment MV Condensate Return from Containment Service. Air Isolation Outside Containment Service Air Isolation Inside Containment CV MOV Containment Air Test Supply MOV Containment Air Test Vent Note Test

~Fre 11 Stroke Leak R

11 Stroke Leak R

7445 7448 7452 7456 7970 7971 8418 MOV Containment Air Test Vent MV Isolation Valve from Containment to Local Pressure Indicator for Containment. Air Test MV Isolation Valve from Containment to Local Pressure Indicator for Containment Air Test MV Isolation Valve from Containment, to Local Pressure Indicator for Containment Air Test AOV Containment Depressuri-zation Valve AOV Containment Depressuri-zation Valve AOV Demin. Water to Contain-ment Isolation ll Stroke Leak R

ll Stroke Leak R

11 Stroke Leak R

.11 Stroke Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Leak R

QUALITY AS SURANCE MANUAL GINNA STATION APPENDIX C.

Pump and Valve Testing Program 1/10/85 PAGE.

20 pp 40 Valve 5

~Te Note Test

~Fre 8419 8623 9227 9229 4.9 CV Demin. Water to Contain-ment Isolation CV Nitrogen 'to Accumulators Isolation AOV Fire Service Water Containment Isolation CV Fire Service Water Containment Isolation Category B Valves Stroke Leak Stroke Leak Stroke Leak Stroke Leak R

Valve 4

~Te 014 017 RCV Component Cooling Surge Tank Vent RCV Aux Building GDT Release Note Test

~Fre Stroke Q

Stroke Q

081 082 083 084 085 086 112B APV LCV Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Emergency Makeup RWST to Charging Pump Stroke Q

Stroke Q

112C LCV VCT Outlet Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION l

APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE

~

21 DP 40 427 430 AOV PORV Valve 0

~Te Letdown From Loop B Pressurizer Power Operated Relief Note Test

~Fre 3

Stroke C/R 16 Stroke C/R 431C PORV Pressurizer Power Operated Relief 16 Stroke C/R 515 516 MOV MOV Pressurizer PORV Block Valve Pressurizer PORV Block Valve 23 23 Stroke Q

Stroke Q

590 591 592 593 624 625 626 700 MOV RHR Inlet Isolation From Loop A SOV Reactor Head Vent SOV Reactor Head Vent SOV Reactor Head Vent SOV Reactor Head Vent HCV l-B RHR HX Outlet HCV l-A RHR HX Outlet FCV RHR Loop Return Recirc.

32 26 26 Stroke R

Stroke C/R Stroke C/R Stroke Q

Stroke C/R 32 Stroke R

32 Stroke R

701 MOV RHR Inlet Isolation From Loop A 8

Stroke C/R 704A 704B 720 MOV RHR Return Isolation to Loop B MOV Suction l-A RHR Pump MOV Suction l-B RHR Pump 24 Stroke Q

24 Stroke Q

8

. Stroke C/R 721 MOV RHR Return Isolation to Loop' 8

Stroke C/R

DATE'UALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 22 DF 40 Note Test

~Fre 738A 738B 825A 825B'26A 826B 826C 826D 836A 836B MOV CC to l-A RHR HX MOV CC to l-B RHR HX MOV SI Pump Suction From RWST MOV SI Pump Suction From RWST MOV SI Pump Suction From BA Tank MOV SI Pump Suction From BA Tank MOV SI Pump Suction From BA Tank MOV SI Pump Suction From BA Tank HCV Spray Additive Tank Dis-charge HCV Spray Additive Tank Dis-charge Stroke Q

Stroke Q

9 Stroke C/R Stroke C/R 25 St roke Q

25 Stroke Q

17/24 Stroke Q

850A 850B 851A 851B 852A 852B 856 857A MOV Sump B to RHR Pumps MOV Sump B to RHR Pumps MOV Sump B to RHR Isolation MOV Sump B to RHR Isolation 24 Stroke Q

24 Stroke Q

Stroke Stroke Stroke C/R Stroke C/R Stroke C/R Stroke C/R 30 30 MOV RWST to RHR Pumps MOV lB RHR HX to CS and SI Pump Isolation 27 MOV RHR Pumps to Reactor Vessel 18 MOV RHR Pumps to Reactor Vessel 18

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing'Program 1/10/85 PAGE.

23 Dp 40 857B MOV Valve 5

~Te Descri tion lA RHR HX to CS and SI Pump Isolation Note Test

~Fre 27 Stroke C/R 857C 860A 860B 860C 860D 871A MOV lA RHR HX to CS and SI Pump Isolation MOV 1-A CSP Discharge MOV 1-A CSP Discharge MOV 1-B CSP Discharge MOV 1-B CSP Discharge MOV'-A to 1-C SI Pump Discharge 27 Stroke C/R 24 Stroke Q

24 Stroke Q

871B 875A 875B 876A 876B MOV MOV MOV MOV MOV 1-B to l-C SI Pump Discharge CS Pump Discharge to lA Charcoal Filter Deluge CS Pump Discharge to lA Charcoal Filter Deluge CS Pump Discharge to 1B Charcoal Filter Deluge CS Pump Discharge to 1B Charcoal Filter. Deluge 24 Stroke Q

Stroke Q

896A 896B 897 898 MOV RWST to CS and SI Pumps MOV RWST to CS and SI Pumps AOV SI Pump Recirc. to RWST AOV SI Pump Recirc. to RWST 9

" Stroke C/R 9

Stroke C/R 27 Stroke C/R 27 Stroke C/R 951 AOV Pressurizer Steam Space Sample 33 Stroke

DATE'UALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 24 PP 40 Valve C

~Te Note 953 AOV Pressurizer Liquid Space 33 Sample Test

~Fre Stroke 955 959 AOV "B" Loop Hot Leg Sample AOV RHR Loop Sample 20 Stroke Q

Stroke C/R 1811A 1811B 1815A 1815B 3504 3505 3652 3996 4000A 4000B 4007 4008 4013 4027 MV Reactor Coolant Drain Tank

- ll Isolation to RHR System MV Reactor Coolant Drain Tank ll Isolation to RHR System MOV C-SI Pump Suction From RWST 24 MOV C-SI Pump Suction From RWST 24 MOV Main Steam to TAFP From 1-B S/G MOV Main Steam to TAFP From 1-A S/G MV Main Steam Throttle Valve to TAFP MOV TAFP Discharge MOV Cross Over Valve For MAFP MOV Cross Over Valve For MAFP MOV 1-A MAFP Discharge MOV 1-B MAFP Discharge MOV TAFP Service Water Supply Isolation MOV 1-A MAFP Service Water Isolation Stroke Q

Stroke Q

Stroke M

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Pr'ogram DATE 1/10/85

PAGE, 25 pF 40 Valve 4

~Te 4028 MOV 1-B MAFP Service Water Isolation Note Test Free{

Stroke 4291 4297 4298 AOV TAFP Recir. Iine AOV TAFP Discharge to 1-A S/G AOV TAFP Discharge to 1-B S/G Stroke M

Stroke Stroke M

4304 4310 4561

'562 4609 4613 4614 AOV AOV AOV AOV MOV MOV MOV 1-A MAFP Recirculation Control 1-B MAFP Recirculation Control Containment Vent Recirc.

Fans Discharge Flow Con-trol Containment Vent Recirc.

Fans Discharge Flow Con-trol Bypass lAl Screen House SW Isolation 1B2 Turbine Building SW Isolation lAl Turbine Building SW Isolation Stroke Stroke M

Stroke Q

4615 MOV 1Bl Aux. Building SW Isolation

. Stroke Q

4616 4627 4628 MOV lAl Aux. Building,SW Isolation Service Water to A Fan Cooler Isolation Service Water to B Fan Cooler Isolation Stroke Q

Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 26 PP 40 Valve 0

~Te 4629 4630 Service Water from A Fan Cooler Isolation Service Water from B Fan Cooler Isolation Note Test Free[

Stroke Q

4635 4636 4641 4642 4643 4644 4663 4664 4670 4733 MOV MOV MOV MOV Reactor Compartment Cooling Unit A Inlet Isolation Reactor Compartment Cooling Unit A Outlet Isolation Service Water to C Fan Cooler Isolation Service Water to D Fan Cooler Isolation Service Water from C Fan Cooler Isolation Service Water from D Fan Cooler Isolation 1Al Air Cond. Chillers SW Isolation 1A2 Turbine Building SW Isolation 1B1 Turbine Building SW Isolation lA2 Air Cond. Chillers SW Isolation Stroke Q

Stroke Q

4734 4735 4757 MOV 1B2 Aux. Build.

SW Isolation MOV 1A2 Aux. Build.

SW Isolation Reactor Compartment Cooling Unit B Inlet Isolation Stroke Q

Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 27 DF 40 Valve 0

~Te 4758 Note Reactor Compartment Cooling Unit B Outlet Isolation

Test, Free[

Stroke Q

4780 517l 5871 5872 5873 5874 5875 5876 9629A 9629B MOV MOV APV MOV MOV lA2 Screen House SW Isolation Turbine Build. Fire Water Loop Supply Isolation Containment Post Accident Filter Damper Containment Post Accident, Filter Damper Containment Post Accident Filter Damper Containment"Post Accident Filter Damper Containment Post Accident Filter Damper Containment, Post Accident Filter Damper 1C'SAFP Service Water Isolation 1D SAFP Service Water Isolation Stroke Q

Stroke Q

9701A 9701B 9703A 9703B 9704A MOV MOV SAFP Cross Over l

1 1C SAFP Containment Isolation MOV 1C SAFP Discharge MOV 1D SAFP Discharge MOV SAFP Cross Over Stroke Q

Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 28 DP 40 Valve 5

~Te 9704B MOV 1D SAFP Containment Isolation Note Test.

~Fre Stroke Q

9710A 9710B AOV 1C SAFP Recirc. Control AOV 1D SAFP Recirc. Control Stroke Q

Stroke Q

4.10 Category C Check Valves Valve 5

~Te Note Test Freer 710A 710B 723A 723B 847A 847B 854 866A 866B 3516 3517 3998 4000C 4000D CV l-A RHR Pump Discharge CV l-B RHR Pump Discharge CV l-A CC Pump Discharge CV 1-B CC Pump Discharge CV A-CSP From Spray Additive Tank to Eductor CV B-CSP From Spray Additive Tank to Eductor CV.

RWST to RHR Pump Check CV CS Pump l-A to Charcoal Filter Deluge CV CS Pump 1-B to Charcoal Filter Deluge CV lB Main Steam Isolation CV lA Main Steam Isolation CV TAFP Discharge Check CV lA MAFP Discharge Check i

CV 1B MAFP Discharge Check Stroke Q

Stroke Q

12 Stroke C/R Stroke Q

Stroke R

Stroke M

QUALITY ASSURANCE MANUAI GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program 42 52C 29 DF

'40 DATE 1/10/85 PAGE Valve 0

~Te 4003 4004 4009 4010 4014 4016 40l7 4023 5133 5l36 9627A 9627B 9700A 9700B 9705A 9705B CV TAFP to S/G lA CV TAFP to S/G lB CV lA MAFP to S/G lA CV 1B MAFP to S/G lB CV TAFP Suction CV 1B MAFP Suction CV lA MAFP Suction CV TAFP Recirculation CV Diesel Fire Pump Disch.

CV Motor Fire Pump Discharge CV 1C SAFP SW Suction CV 1D SAFP SW Suction CV 1C SAFP Discharge CV 1D SAFP Discharge CV 1C SAFP to S/G lA CV 1D SAFP to S/G 1B 4.11 Category C Relief Valve Valve 5

~Te Note Test

~Fre Stroke M

Stroke M

Stroke Q

'Stroke Q

Stroke Q

Note Test

~Fre 203 209 434 RV Letdown High Pressure Safety Relief RV Letdown Low Pressure Safety Relief RV Pressurizer Safety Relief 15 15 15

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 30 PP 40 Valve 5

~Te Note Test

~Fre 435 732 RV Pressurizer Safety Relief 15 RV CC Surge Tank Relief 15 RV CC From Excess Letdown 15 Heat Exchanger 755A 755B RV RV CC From A RCP Thermal Barrier CC From B RCP Thermal Barrier 15 15 758A 758B RV CC From A-RCP Oil Coolers 15 RV CC From B-RCP Oil Coolers 15 818 RV CC From Reactor Support 15 Coolers 861 RV 1-B CS Pump Suction Relief 15 887 RV SI Test Line Relief Valve 15 Inside Containment 1817 RV Alternate -Suction From RHR Pump to C SI Pump 15 3508

-3509 RV 1-B S/G PRV RV 1-A S/G PRV 15 15 3510 3511 RV RV 1-B S/G PRV 1-A S/G PRV 15 15 3512 3513 3514 3515 RV 1-A S/G PRV RV 1-A S/G PRV RV 1-B S/G PRV RV 1-A S/G PRV 15 15 15

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE-31 pF 40 Valve 5

~Te Descri tion Note Test Free[

4653 4654 4657 RV Service Water Relief RV Service Water Relief RV Service Water Relief 15 15 5134 RV Diesel Fire Pump Disch Relief 15 5135 RV Motor Fire Pump Disch Relief 15 4.12 Inservice Valve Testing Notes Note 1 - Valves 304A, 304B and 313 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 and refuel-ing outages.

Note 2

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 and refueling outages.

Note 3 - Valves 204A, 371 and 427 cannot be stroked during normal plant operation on a

. quarterly basis because this test would interrupt the letdown (CVCS) system.

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

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

Surveys in the area of the test connection during plant operation indicate neutron fields of approximately 500 mr/hr and a

gamma fields of 250 mr/hr.

4 0

QUALITY ASSURANCE MANUAL GINNA STATION TITLEi APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE.

32 Pp 40 Note 5-Total whole body dosage to test personnel is estimated to be 375 mrem.

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

Valves 749A,

749B, 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 and refueling outages.

Note 6 Note 7 Valves 813 and 8l4 cannot be stroked during 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 and 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 passive valve will be only leak tested at refueling outages consistent with IWV-3700-1.

Note 8-Valves 700 and 721 'cannot be stroked during normal plant operation on a quarterly basis because there is an interlock system 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 and refueling outages.

V QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE.

33 DF 40 Note 9 Note 10-Note ll-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.'hese 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 and re-fueling outages.

Valves 853A and 853B cannot be stroked during normal plant operation on a quarterly basis because this test requires pressurizing the RHR system to the primary system operation pressure.

These valves will be stroked at refueling outages.

Leakage testing of check valves 853A and 853B shall be accomplished prior to criticality following (1) refueling, (2) cold shutdown, and (3) maintenance, repair or replacement work on the valves.

Leakage may be measured indirectly from the performance of pressure ind'icators, system volume measuurements or by direct measurement.

Minimum test differential'hall be, greater than 150 psid.

Technical Specification 4.3.3.4 defines the allowable leakage rates.

Valves 820,

877A, 877B,

878F, 878H,

1076A, 1076B 1080A~

1084Ag 1084B IV 3A IV 3B/

IV-5A, IV-5B, IV-2A, IV-2B, 1554,

1556, 1557,

1579, 1560,

1562, 1563,

1565, 1566,

1568, 1569,

1571,

~ 1572,

1574, 1811A,

1811B, 5129,

6151, 6152,

6155, 6175,

7141, 7226,

7443, 7444,

7445, 7448,

7452, 7456,

8418, 8419,

8623, 9227 and 9229 are con-sidered passive valves which are not required to change position to acccomplish their specific function.

Stroking these valves would serve no useful function and will therefore not be done as per IWV-3700-

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE-34 DF 40 Note l2-Valve 866A cannot be stroke tested during normal plant operation on a quarterly basis because this test would result in a sub-stantial radiation exposure to test per-sonnel.

Stroke testing at this location resulted in approximately 400 mrem whole body exposure to the test personnel.

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

Note 13-Valves 867A,

867B, 878G,

.and 878J cannot be stroked during normal operation on a quarterly basis or at cold shutdown condition when the primary system is full.

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

Leakage testing of check valves

867A, 867B, 878G and 878J shall be accomplished prior to criticality following (1) refueling, (2) cold shutdown, and (3) maintenance, repair or replacement work on the valves.

Leakage may be measured

'indirectly from the performance of pressure indicators, system volume measurements or by direct measurement.

Check valves 878G and 878J shall also be tested for leakage following each safety injection flow test.,

Minimum test differential shall be greater than 150 psid.

Technical Specification 4.3.3.4 defines the allowable leakage rates.

Note l4-Note l5-Valves 3516 and 3517 cannot be stroked during normal plant operation on a quar-terly basis because they are the main steam isolation valves.

These valves are stroked during each plant refueling.

Category C Relief Valves shall be tested in accordance with the extent and fre-quency requirements of Paragraph IWV-3510 of Article IWV of Section XI of the Code.

QUALITY" ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 1/10/85 35 PP 40 Note 16-Valves 430 and 431C are the power operated relief valves associated with the overpressurization system.

These valves shall. not be stroked quarterly as an unplanned pressure transient could result from a leaky block valve.

Operability of these valves shall be verified as follows:

(1)

Full stroke exercising during cool down prior to achieving water solid condition in the pressurizer and during cold shutdown prior to heat up ~

(2)

Stroke timing to be performed as a

minimum once each refueling cycle as a part of the channel calibration specified by Technical Specifications 4.16.1b.

(3)

Fail safe actuation testing is permitted by the code to be per-formed at each cold shutdown if valve cannot be tested during power operation.

(4)

Technical specification 4.16.1a and 4.16.1c delineate additional re-quirements for operability verifi-cation of the PORV actuation channel and valve position.

Note 17-Additional stroking will be consistent with: Technical Specifications.

Note 18-Valves 852A and 852B cannot be stroked during normal plant operation as these

valves, when cycled, could subject the Residual Heat Removal System to a pressure in excess of its design pressure.

These

=valves will be stroked at cold shutdowns and refueling outages.

Note 19-Stroking Valves 5392 and 5393 during operation and cold shutdown would inter-

'rupt instrument air to containment and

QUALITY

, ASSURANCE MANUAL GINNA STATION TITLEs APPENDIX C Pump and Valve Testing Program DATE'/10/85 PAGE.

36 PP 40 Note Note Note Note 20-21-22-23>>

be disruptive to air operated valves inside.

These valves will be stroked at refueling outages.

Valve 959 is normally closed. and in the containment isolating position during normal operation.

These valves will be stroked at cold shutdown and refueling outages.

Valves 1819A, B,

C, D, E, F and G cannot be stroked during normal plant operation as this test would interrupt containment pressure monitoring transmitters from performing their intended function.

These valves will be stroked at cold and refueling outages.

Category A valves

5869, 5870, 5878 and 5879 are normally closed and in the containment, isolating position during normal operation.

Leak tightness of these valves is reverified following reclosure after each use in accordance with, Section 4.4.2.4 of Technical Speci-fications.

The valves shall be stroked at least each, cold shutdown.

In addition, if the valves are opened for purging, they shall be stroked at least once each quarter during which they have been opened.

Valves 515 and 516 stroked quarterly except if already closed or during cold and refueling'hutdowns.

Note Not to be done during time that redundant valve is inoperable per Technical Speci-fication.

Note 25-As per Technical Specifications 3.3.1.2.f, no cycling shall be done if normally open valve in other flow path is inoperable in the open position.

TITLE:

DATE'2 SIC QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE 37 DF 40 Note 26-As per Technical Specifications 3.3.1.2.e, failure of valves 624 and 625 during quarterly stroking in the closed position can degrade LPSI system function.

How-

ever, these valves shall be stroked at cold shutdown and refueling outages.

Note 27-As per Technical Specifications 3.3.1.2.e, failure of valves

857A, 857B,

857C, 897 and 898 during quarterly stroking can degrade the injection phase of the SI pumps.

However, these valves shall be Note stroked at cold shutdown and refueling outages.

Check valves 842A and 842B (accumul'ator check valves) cannot and should not be exercised during plant operation.

28-Exercising of these valves requires the reactor coolant system pressure to be

. reduced to below accumulator pressure.

Therefore testing of these valves will be performed after refueling and cold shutdowns, and after maintenance, repair or replacement.

Full stroke testing, which involves discharge of the accumu-lator through the valve to a partially-filled reactor coolant system will not be utilized since this test mode is considered impractical'nd unsafe.

Valve operability from the normal closed position will be verified by partial stroking prior to leak testing with flow through the safety injection test line.

valve, pressuring the line downstream of the check valves and measuring the upstream

leakage, or (2) by measuring Leak testing will be performed to assure primary system integrity following each cold and refueling shutdown after achieving normal reactor coolant system pressure and prior to reactor criticality.

Testing will be performed by either (1) closing each accumulator motor operated discharge

J

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program 1/10/85 PAGE

~

38 DF 40 Note 29-accumulator in-leakage by pressurizing the line downstream of the 842 valves.

These valves are not event V-check valves.

Therefore, the test acceptance criterion shall be that of Technical Specification 3.1.5.

Valves 877A,

877B, 878F and 878H are currently not listed in our valve test

program, however, a pair of these valves in each hot leg high head safety injec-tion line (877A nd 878F in loop B hot leg and 877B and 878H in loop A hot leg) together form one of the two pressure boundaries. required to be tested by Technical Specification 4.3.3.3.

Because these valves are normally closed-and the piping contains motor operated valves (MOV's) which are also closed and deener-

gized, the check valves will not move with the possible exception of when the MOVs are required to be opened to test the check valves.

Thus, once tested the check valves will remain closed.

An NRC order dated April 20, 1981 established an appropriate test frequency for these valves to be once every 40 months or after each opening of the MOVs.

These valves are listed as passive valves in our valve testing program with testing required to meet Technical Specification 4.3.3.3.

Note 30-Note 31-Valves 851A and 851B are not qualified to operate in the post-accident containment environment and therefore not required to perform a post-accident function.

Since the valves are normally

open, and in their post-accident position, stroking of these valves will not be performed.

Valves 4601,

4602, 4603 and 4604 shall be leak tested each refueling outage using a back flow test method to determine

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 1/10/85 39 DF 40 Note Note 32>>

33-if back flow to the correspon'ding idle pump is minimal (i.e.

2 psid as monitored by pressure change in the discharge header between pump discharge isolated and unisolated).

Quarterly valve stroking shall be limited to verifying that a normally closed valve will open concurrent with the start of an idle pump.

An open check valve for a pump already in service will be deemed operable without having to stop and restart the pump since the open valve is considered to be performing its normal safety function.

Valves 590,

591, 592 and 593 shall not be stroked quarte'rly as an unplanned pressure transient could result from a leaky alternate isolation valve.

These valves will be stroked at refueling outages Sampling valves 951 and 953 need not be stroked as part of this program as they are not required to perform a safety function.

Although considered to be part of the react

'coolant system boundary, 10CFR50.55a(c)(2) specifies that components which are connect to the reactor coolant system and are part of the boundary as defined in 50.2(v) of this part need not meet the requirements of paragraph (c)(1) of this section, provided:

In the event of postulated failure of the component during normal reactor operation, the reactor can be shut down and cooled down in an orderly manner, assuming makeup is provided by the reactor coolant makeup system.

The valves are exercised during routine sampling operations.

PVT 5.0 5.1 Records I

Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article IWP-6000 of Section XI of the Code.

QUALITY ASSURANCE NANUAI GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE PAGE 42 5RC 1/10/85 40 pp 40 5.2 Records for the Inservice Valve Testing Program shall be developed and maintained in accordance with Article IWV-6000 of Section 'XI of the Code.

ML17254A423

Text

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