ML17254A743

Rev 7 to QA Manual,App C, Ginna Station Inservice Pump & Valve Testing Program for 810101-891231 Period.

ML17254A743
Person / Time
Site:	Ginna
Issue date:	01/24/1986
From:	Anderson C, Wilkins P ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17254A742	List: ML17254A741 ML17254A743
References
NUDOCS 8602050105
Download: ML17254A743 (55)

Text

RE Y. PAGE QUALITY ASSURANCE MANUAL OF GINNA STATION EFFECTIVE DATE:

ROCHESTER GAS & ELECTRIC CORPORATION January 30, 1986 SIGNATURE DATE TITLE: PREPARED BT: (, /7 L' [ /~/g Appendix C Ginna Station Inservice Pump and Valve Testing Program'or the January 1, 1981 through December 31, 1989 Period REVIEW APPROVED BY:

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Pro ram Table of Contents

==

Introduction:==

Discussion Definitions:

Program: 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 sa02OS0>0S aaozas PDR ADOCK 05000244 P PDR

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TITLKs DATE QUAI ITY 1/30/86 AS SURANCE APPENDIX C PAGE MANUAI Pump and Valve GINNA STATION Testing Program 2 DP 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 10CFRSO 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.

42i52 C TITLEs DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PACE MANUAI Pump and Valve GINNA STATION Testing Program 3 DP 40 Definitions AFP Auxiliary Feedwater Pump AOV Air Operated Valve APV Air Operated Piston Valve BA Boric Acid Code American Society of Mechanical Engineers Boiler and Pressure Vessel Code CC Component Cooling CS Containment Spray CSP Containment Spray Pump CV Check Valve C/R, Cold Shutdown and Refueling ECCS Emergency Core Cooling System FCV Flow Control Valve GA Gas Analyzer GDT Gas Decay Tank HCV Hand Control Valve HX Heat Exchanger LCV Level Control Valve M Monthly MAFP Motor Driven Auxiliary Feedwater Pump

'OV Motor Operated Valve Manual Valve PCV Pressure Control Valve PORV Power Operated Relief Valve PRT Pressurizer Relief Tank PRV Pressure Relief Valve PVT Pump and Valve Testing Q Quarterly R Refueling Outage RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump RCV Radiation Control Valve RHR Residual Heat Removal RMW Reactor Makeup Water RV Relief Valve RWST Refueling Water Storage Tank RX Reactor Vessel S/G Steam Generator SAFWP Standby Auxiliary Feedwater Pump SI Safety Injection SOV Solenoid Operated Valve SW Service Water

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42i5t C TITLE< DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 4 DF 40 Definitions TAFP Turbine Driven Auxiliary Feedwater Pump VC Volume Control VCT Volume Control Tank VH Vent Header CAT A VALVE Valves for which seat leakage is limited to a specific maximum amount in the closed position of fullfillment of'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).

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TITLEc DATE QUALITY 1/30/86 AS SURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 5 DF 40 Pum and Valve Testin Pro ram PVT 1.0 Sco e and Res onsibilit 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.

1.2 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.

TITLE< DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 6 OF 40 3.2 The following pumps shall be tested in accordance with Article IWP of Section XI:

(a) lA Component Cooling (b) lB Component Cooling (c) 1A Safety Injection (d) lB Safety 1njection (e) lC Safety Injection (f) lA Residual Heat Removal (g) 1B Residual Heat Removal (h) lA Containment Spray (i) 1B Containment Spray (j) lA Motor Driven Auxiliary Feedwater (k) lB Motor Driven Auxiliary Feedwater (1) Turbine Driven Auxiliary Feedwater (m) lA Service Water (n) lB Service Water (o) 1C Service Water (p) lD Service Water (q) 1C Standby Auxiliary Feedwater (r) 1D Standby Auxiliary Feedwater 3.3 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 temperature 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 lant o eration. Instead the tests must be

4i AC TITLE< DATE QUALITY l/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 7 OF 40 performed at an off-design flow condition which results in higher bearing temperatures than normal. This is to be expected since higher than normal thrust loads are placed on the pump bearings during this 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 not 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 is considered-to be a better indication of bearing condition since a significant increase in bearing temperature will normally only occur failure is imminent. Finally, test if bearing 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 IWP-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.

3.4 The test frequency for the pumps shall be as follows:

a. Component cooling water pumps shall be tested monthl

.I p QUALITY 1/30/86 ASSURANCE APPENDIX C PACE MANUAL Pump and Valve GINNA STATION Testing Program 8 DF 40

b. Safety injection pumps shall be tested monthly except during cold or refueling shutdowns. The pumps shall be tested prior to startup exceeds if the time since the last one month.

test 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.

d. Containment spray pumps shall be tested monthly except during cold or refueling shutdown. The pumps shall be tested prior to startup exceeds if the time since the last test 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 exceeds one month.

last test Service water pumps shall be tested monthly.

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

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

0 TITI.Ks DATE QUALITY 1/30/86 ASSURANCE APPENDIX C MANUAL Pump and Valve GINNA STATION Testing Program 9 DF 40 PVT 4.0 Inservice Valve Testin Pro ram II 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

-'f an accident and maintain the reactor in a safe shutdown condition are included in the program.

4.2 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.

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 4.12.

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. Except where operational constraints prevail and exceptions have been authorized all check valves, including Category C Valves, shall be exercised to the position required to fulfill

'ests shall their function. These functional 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.

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 durin lant o eration. Durin each

TITI.Ea DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 10 DP 40 refueling outage a visual verification shall be made to confirm direct correspondence between valve operators and the position indicators.

4.6 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 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 <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 (less than 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 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.

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4.8 Category A Valves Valve 5 ~Te Descri tion Note Test ~Fre 204A MV Letdown to NRHX Stroke C/R Leak R 304A CV 1-A RCP Seal Injection Stroke C/R Leak R 304B CV 1-B RCP Seal Injection Stroke C/R Leak R

TITL,Ka GATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 11 gf: 40 Valve 5 ~Te . Note Test ~Fre 313 MOV Seal Water Return Stroke C/R Isolation Leak R 370B CV Charging Line Isolation Stroke C/R Leak R 371 AOV Letdown Isolation Stroke C/R

.Leak R 383B CV Alternate Charging Iine Stroke C/R Leak R 508 AOV RMW to Containment Vessel Stroke Q Stop Leak R 528 CV N2 Supply to PRT Stroke Q Leak R 529 CV RMW to PRT Stroke Q Leak R 539 AOV PRT Stop Valve to Gas Stroke Q Analyzer Leak R 546 MV PRT to Gas Analyzer Stroke Q Leak R 547 MV Nitrogen to PRT Stroke Leak 743 CV CC From Excess Letdown HX. Stroke Q Leak R 745 AOV Return From Excess Let- Stroke Q down HX. Leak R 749A MOV CCW to A RCP Stroke C/R Leak R 749B MOV CCW to B RCP Stroke C/R Leak R 750A CV CC to A RCP Stroke C/R Leak R

TITLE) DATE QUALITY 1/30/86 ASSURANCE'ANUAL APPENDIX C PAGE Pump and Valve GINNA STATION Testing Program 12 DF 40 Valve 4 T~e Note Test ~Fre 750B CV CC to B RCP Stroke C/R Leak R 759A MOV Containment Stop CC From 5 Stroke C/R Loop A RCP 7 Leak R 759B MOV Containment Stop CC From Stroke C/R Ioop B RCP Leak R 813 MOV CC Supply to RX Support Stroke C/R Coolers Leak R 814 MOV CC Return to RX Support Stroke C/R Coolers Leak R 820 MV Letdown to NRHX Stroke Leak 842A CV Loop A Accumulator Dump 28 Stroke C/R Line Check Valve Leak C/R 842B CV Loop B Accumulator Dump 28 Stroke C/R Line Check Valve Leak C/R 846 AOV N2 Supply to Accumulators Stroke Q Leak R 853A CV Core Deluge Check 10 Stroke C/R 10 Leak C/R 853B CV Core Deluge Check 10 Stroke C/R 10 Leak C/R 862A CV 1-A CSP Disch Stroke Q Leak R 862B CV l-B CSP Disch Stroke Q Leak R 867A CV Accumulator Dump and SI 13 Stroke R to Cold Leg Loop B 13 Leak C/R 867B CV Accumulator Dump and SI 13 Stroke R.

to Cold Leg Loop A 13 Leak C/R

TITI.Ec DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 13 DP 40 Valve 0 ~Te Note Test Free{

870A CV 1-A to 1-C SI Pump Disch Stroke Q Leak R 870B CV l-B to 1-C SI Pump Disch Stroke Q Leak R 877A CV High Safety Injection 11 Stroke Loop B Hot Leg 29 Leak 40 Mo.

877B CV High Safety Injection 11 Stroke Loop A Hot Leg 29 Leak 40 Mo.

878F CV High Safety Injection ll- Stroke Loop B Hot Leg 29 Z,eak 40 Mo.

878G CV 1-A SI Pump to Cold Leg 13 Stroke R Loop B 13 Leak C/R 878H CV High Safety Injection 11 Stroke Loop A Hot Leg 29 Leak 40 Mo.

878J CV 1-B SI Pump to Cold Leg 13 Stroke R Zoop A 13 Leak C/R 879 MV SI Test Line Isolation Stroke Leak R 889A CV l-A SI Pump Disch Stroke Q Leak R 889B CV l-B SI Pump Disch Stroke Q Leak R 921 SOV Loop A Hydrogen Monitor Stroke Q Inlet Leak R 922 SOV Zoop A Hydrogen Monitor Stroke Q Outlet Zeak R 923 SOV Loop B Hydrogen Monitor Stroke Q Inlet Z,eak R 924 SOV Loop B Hydrogen Monitor Stroke Q Outlet Leak R

TITLE: DATE QUAZ ITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 14 DF 40 Valve 0 ~e Descri tion Note Test ~Fre 956D Hot Leg Loop Sample Stroke Q Containment Isolation Leak R 956E PRZR Liquid Space Sample Stroke Q Containment Isolation Leak R 956F PRZR Steam Space Sample Stroke Q Containment Isolation Leak R 966A AOV Pressurizer Steam Space Stroke Q Containment Isolation Leak R 966B AOV Pressurizer Liquid Space Stroke Q Containment Isolation Zeak R 966C AOV Loop A and B Hot Leg Stroke Q Containment Isolation Zeak R 1003A LCV l-A RCDT Pump Suction Stroke Q Leak R 1003B LCV l-B RCDT Pump Suction Stroke Q Zeak R 1076A MV Hydrogen to "A" Recombiner 11 Stroke Pilot Containment Isolation Leak IV-3A SOV Hydrogen to "A" Recombiner Pilot Containment Isolation ll Stroke Zeak 1076B MV Hydrogen to "B" Recombiner ll Stroke Pilot Containment Isolation Leak IV-3B SOV Hydrogen to "B" Recombiner ll Stroke Pilot Containment Isolation Leak 1080A MV Oxygen Make Up to Contain- ll Stroke ment, Isolation. Leak R IV-2A Oxygen Make Up to Contain- ll Stroke ment Isolation (A Recombiner) Leak IV-2B Oxygen Make Up to Contain- 11 Stroke ment, Isolation (B Recombiner) Leak

TITLE: DATE QUALITY 1/3 0/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 15 OF 40 Valve 5 ~e Note Test ~Fre 1084A MV Hydrogen to "A" Recombiner Stroke Main Burner Containment Leak Isolation IV-5A SOV Hydrogen to "A" Recombiner Stroke Main Burner Containment Leak Isolation 1084B MV Hydrogen to "B" Recombiner Stroke Main Burner Containment Leak Isolation IV-5B SOV Hydrogen to "B" Recombiner Stroke Main Burner Containment Leak Isolation 1554 MV D Recirc. Fan Air Sample Stroke Isolation Leak 1556 MV D Recirc. Fan Air Sample Stroke Isolation Leak 1557 MV A Recirc. Fan Air Sample Stroke Isolation Leak R 1559 MV A Recirc. Fan Air Sample Stroke Isolation Leak 1560 MV A S D Return Iine Stroke Isolation Leak 1562 MV A 6 D Return Line Stroke Isolation Leak 1563 MV B Recirc. Fan Air Sample Stroke Isolation Leak 1565 MV B Recirc. Fan Air Sample Stroke Isolation Leak 1566 MV B Recirc. Fan Air Sample Stroke Return Line Isolation Leak 1568 MV B Recirc. Fan Air Sample Stroke Return Line Isolation Leak

'J i2 QC TITLEi DATE QUALITY 1/30/86'6 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program DF 40 Valve 4 ~Te Note Test ~Fre 1569 C Recirc. Fan Air Sample Stroke Isolation Leak R 1571 C Recirc. Fan Air Sample Stroke Isolation Leak R 1572 C Recirc. Fan Air Sample Stroke Return Line Isolation Leak R 1574 C Recirc. Fan Air Sample Stroke Return Line Isolation Leak R 1596 MV Radiation Monitor Supply Stroke Q Leak R 1597 AOV Radiation Monitor Supply Stroke Q Leak R 1598 AOV Radiation Monitor Exhaust 'troke Q Leak R 1599 AOV Radiation Monitor Exhaust Stroke Q Leak R 1655 MV RCDT to Gas Analyzer Stroke Q Leak R l7l3 CV N2 to RCDT Stroke Q Leak R 172l AOV Suction line to RCDT Stroke Q Leak R 1723 AOV A Containment Sump Disch Stroke Q to Waste Holdup Tank Leak R 1728 AOV A Containment Sump Disch Stroke Q to Waste Holdup Tank Leak R 1786 AOV RCDT to VH Isolation Stroke Q

'eak R 1787 AOV RCDT to VH Isolation Stroke Q Leak R

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 17 40 Valve 4 ~Te Note Test ~Fze l789 AOV RCDT to GA Containment Stroke Q Isolation Leak R 1793 MV N2 to RCDT Isolation 11

• Stroke Leak 1819A MV Containment Pressure 21 Stroke C/R Transmitter 945 Isolation Leak R 1819B MV Containment Pressure 21 Stroke C/R Transmitter 946 Isolation Leak R 1819C MV Containment Pressure 21 Stroke C/R Transmitter 947 Isolation Leak R 1819D MV Containment Pressure 21 Stroke C/R Transmitter 948 Isolation Leak R 1819E MV Containment Pressure 21 Stroke C/R Transmitter 949 Isolation R Leak'troke 1819F MV Containment Pressure 21 C/R Transmitter 950 Isolation Leak R 1819G MV Containment Piessure 21 Stroke C/R Transmitter 944 Isolation Leak R 4601 CV 1A Service Water Pump 31 Stroke Q Discharge 31 Leak R 4602 CV 1B Service Water Pump 31 Stroke Q Discharge 31 Leak R 4603 CV 1C Service Water Pump 31 Stroke Q Discharge 31 Leak R 4604 CV 1D Service Water Pump 31 Stroke Q Discharge 31 Leak R 5129 MV Construction Fire Service 11 Stroke Water Containment Isolation Leak 5392 AOV Instrument Air to Contain- 19 Stroke R ment Isolation Leak R

TITLEs DATE QUAI ITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 18 pp 40 Valve 4 ~Te Note Test ~Fre 5393 CV Instrument Air to 19 Stroke R Containment Isolation Leak R 5701 MV A-S/G Blowdown Isolation Stroke Q Leak R 5702 MV B-S/G Blowdown Isolation Stroke Q Leak R 5733 MV A-S/G Sample Isolation Stroke Q Leak R 5734 MV B-S/G Sample Isolation Stroke Q Leak R 5735 AOV "A" S/G Blowdown Sample Stroke' Q Isolation Leak 5736 AOV "B" S/G Blowdown Sample Stroke Q Isolation Leak R 5737 AOV "B" S/G Blowdown Isolation Stroke Q Leak R 5738 AOV "A" S/G Blowdown Isolation Stroke Q Leak R 5869 APV Containment Purge Supply 22 Stroke Isolation Leak 5870 APV Containment Purge Supply 22 Stroke Isolation Leak 5878 APV .Containment Purge Exhaust 22 Stroke Isolation Leak 5879 APV Containment Purge Exhaust 22 Stroke Isolation Leak 6151 MV Auxiliary Steam Supply to Stroke Containment Leak 6152 MV Condensate Return from Stroke Containment Ieak

• See Note 22

TITLEs DATE QUAI ITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 19 DP 40 Valve 8 ~Te Note Test Free{

6165 Aux. Steam Supply to Stroke Containment Leak 6175 Condensate Return from Stroke Containment Leak 7141 Service Air Isolation Stroke Outside Containment Leak 7226 CV Service Air Isolation Stroke Inside Containment Leak 7443 MOV Containment Supply Air Test ll Stroke Leak R 7444 MOV Containment Air Test Vent ll Stroke Leak R 7445 MOV Containment Air Test Vent 11 Stroke Leak R 7448 MV Isolation Valve from 11 Stroke Containment to Local Ieak R Pressure Indicator for Containment Air Test 7452 MV Isolation Valve from 11 Stroke Containment to Local Leak R Pressure Indicator for Containment Air Test 7456 MV Isolation Valve from Containment to Iocal ll Stroke Leak R Pressure Indicator for Containment Air Test 7970 AOV Containment Depressuri- Stroke Q zation Valve Leak R 7971 AOV Containment Depressuri- Stroke Q zation Valve Leak R

8418 AOV Demin. Water to Contain- Stroke ment Isolation Leak R

TITLE) DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 20 DF 40 Valve 4 ~Te Note Test ~Fre 8419 CV .Demin. Water to Contain- Stroke ment Isolation Leak 8623 CV Nitrogen to Accumulators Stroke Isolation Leak 9227 AOV Fire Service Water Stroke Containment Isolation Leak 9229 CV Fire Service Water Stroke Containment Isolation Ieak 4.9 Category B Valves Valve 0 ~Te Note Test Free{

014 RCV Aux Building GDT Release Stroke Q 017 RCV Component, Cooling Surge Stroke Q Tank Vent 081 APV Control Room Ventilation Stroke Q Damper 082 APV Control Room Ventilation Stroke Q Damper 083 APV Control Room Ventilation Stroke Q Damper 084 APV Control Room Ventilation Stroke Q Damper 085 APV Control Room Ventilation Stroke Q Damper 086 APV Control Room Ventilation Stroke .

Q Damper ll2B LCV Emergency Makeup RWST to Stroke Q Charging Pump 112C LCV VCT Outlet Stroke Q

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 21 DF 40 Valve 5 ~Te Descri tion Note Test ~Fre 427 AOV Letdown From Loop B 3 Stroke C/R 430 PORV Pressurizer Power 16 Stroke C/R Operated Relief 431C PORV Pressurizer Power 16 Stroke C/R Operated Relief 515 MOV Pressurizer PORV Block 23 Stroke Q Valve 516 MOV Pressurizer PORV Block 23 Stroke Q Valve 590 SOV Reactor Head Vent 32 Stroke R 591 SOV Reactor Head Vent 32 Stroke R 592 SOV Reactor Head Vent 32 Stroke R 593 SOV Reactor Head Vent 32 Stroke R 624 HCV l-B RHR HX Outlet 26 Stroke C/R 625 HCV 1-A RHR HX Outlet 26 Stroke C/R 626 FCV RHR Loop Return Recirc. Stroke Q 700 MOV RHR Inlet Isolation From Stroke'/R Loop A 701 MOV RHR Inlet Isolation From 8 Stroke C/R Loop A 704A MOV Suction l-A RHR Pump 24 Stroke Q 704B MOV Suction l-B RHR Pump 24 Stroke Q 720 MOV RHR Return Isolation to 8 Stroke C/R Loop B 72l MOV RHR Return Isolation to 8 Stroke C/R Loop B

TITLE< DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 22 PP 40 Valve 4 ~Te Note . Test ~Fre 738A MOV CC to 1-A RHR HX Stroke Q 738B MOV CC to l-B RHR HX Stroke Q 825A MOV SI Pump Suction From RWST 9 Stroke C/R 825B MOV SI Pump Suction From RWST 9 Stroke C/R 826A MOV SI Pump Suction From 25 Stroke Q BA Tank 826B MOV SI Pump Suction From 25 Stroke Q BA Tank 826C MOV SI Pump Suction From 25 Stroke Q BA Tank 826D MOV SI Pump Suction From 25 Stroke Q BA Tank 836A HCV Spray Additive Tank Dis- 17/24 Stroke Q charge 836B HCV Spray Additive Tank Dis- 17/24 Stroke Q charge 850A MOV Sump B to RHR Pumps 24 Stroke Q 850B MOV Sump B to RHR Pumps 24 Stroke Q 851A MOV Sump B to RHR Isolation 30 Stroke 851B MOV Sump B to RHR Isolation 30 Stroke 852A MOV RHR Pumps to Reactor Vessel 18 Stroke C/R 852B MOV RHR Pumps to Reactor Vessel 18 Stroke C/R 856 MOV RWST to RHR Pumps 9 Stroke C/R 857A MOV lB RHR HX to CS and SI 27 Stroke C/R Pump Isolation

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DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 23 pp 40 Valve 4 T~e Note Test ~Fre 857B MOV 1A RHR HX to CS and SI 27 Stroke C/R Pump Isolation 857C MOV lA RHR HX to CS and SI 27 Stroke C/R Pump Isolation 860A MOV 1-A CSP Discharge 24 Stroke Q 860B MOV 1-A CSP Discharge 24 Stroke Q 860C MOV 1-B CSP Discharge 24 Stroke Q 860D MOV 1-B CSP Discharge 24 Stroke Q 871A MOV 1-A to 1-C SI Pump 24 .Stroke Q Discharge 871B MOV 1-B to l-C SI Pump 24 Stroke Q Discharge Q75A MOV CS Pump Discharge to 1A Stroke Q Charcoal Filter Deluge 875B MOV CS Pump Discharge to 1A Stroke Q Charcoal Filter Deluge 876A MOV CS Pump Discharge to 1B Stroke ,Q Charcoal Filter Deluge-876B MOV CS Pump Discharge to 1B Stroke Q Charcoal Filter Deluge 896A MOV RWST to CS and SI Pumps 9 Stroke C/R 896B MOV RWST to CS and SI Pumps 9 Stroke C/R 897 AOV SI Pump Recirc. to RWST 27 Stroke C/R 898 AOV SI Pump Recirc. to RWST 27 Stroke C/R 951 AOV Pressurizer Steam Space 33 Stroke Sample

TIT LE i DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 24 op 40 Valve 5 ~Te Note Test ~Fre 953 Pressurizer Liquid

'OV Space 33 Stroke Sample 955 AOV "B" Loop Hot Leg Sample Stroke Q 959 AOV RHR Loop Sample 20 Stroke C/R 1811A Reactor Coolant Drain Tank Isolation to RHR System ll 1811B Reactor Coolant Drain Tank 11 Isolation to RHR System 1815A MOV C-SI Pump Suction From RWST 24 Stroke Q 1815B MOV C-SI Pump Suction From RWST 24 Stroke Q 3504A MOV Main Steam to TAFP From 1-B Stroke Q S/G 3505A MOV Main Steam to TAFP From 1-A Stroke Q S/G 3652 Main Steam Throttle Valve Stroke Q to TAFP 3996 MOV TAFP Discharge Stroke M 4000A MOV Cross Over Valve For MAFP Stroke M 4000B MOV Cross Over Valve For MAFP Stroke M 4007 MOV 1-A MAFP Discharge Stroke M 4008 MOV 1-B MAFP Discharge Stroke M 4013 MOV TAFP Service Water Supply Stroke M Isolation 4027 MOV 1-A MAFP Service Water Stroke M Isolation

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TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 25 DP 40 Valve 0 ~Te Note Test ~Fre 4028 MOV 1-B MAFP Service Water Stroke M Isolation 4291 AOV TAFP Recir. Line Stroke M 4297 AOV TAFP Discharge to 1-A S/G Stroke M 4298 AOV TAFP Discharge to 1-.B S/G Stroke M 4304 AOV 1-A MAFP Recirculation Stroke M Control 4310 AOV 1-B MAFP Recirculation Stroke M Control 4561 AOV Containment Vent Recirc. Stroke Q Fans Discharge Flow Con-trol I 4562 AOV Containment Vent Recirc. Stroke Q Fans Discharge Flow Con-trol Bypass 4609 MOV lAl Screen House SW Stroke Q Isolation 4613 MOV 1B2 Turbine Building SW Stroke Q Isolation 4614 MOV lA1 Turbine Building SW Stroke Q Isolation 4615 MOV 1Bl Aux. Building SW Stroke Q Isolation 4616 MOV lA1 Aux. Building SW Stroke Q Isolation 4627 MV Service Water to A Fan Stroke. Q Cooler Isolation 4628 MV Service Water to B Fan Stroke Q Cooler Isolation

'0 'J TITLE< DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 26 OF 40 Valve 4 ~Te Descri tion Note Test ~Fre 4629 MV Service Water from A Fan Stroke Q Cooler Isolation 4630 MV Service Water from B Fan Stroke Q Cooler Isolation 4635 MV Reactor Compartment Cooling . Stroke Q Unit A Inlet Isolation 4636 MV Reactor Compartment, Cooling Stroke' Unit A Outlet Isolation 4641 MV Service Water to C Fan Stroke Q Cooler Isolation 4642 MV Service Water to D Fan Stroke Q Cooler Isolation 4643 MV Service Water from C Fan Stroke Q Cooler Isolation 4644 MV Service Water from D Fan Stroke Q Cooler Isolation 4663 MOV 1Al Air Cond. Chillers SW Stroke Q Isolation 4664 MOV 1A2 Turbine Building SW Stroke Q Isolation 4670 MOV 1B1 Turbine Building SW Stroke Q Isolation 4733 MOV 1A2 Air Cond. Chillers SW Stroke Q Isolation MOV 1B2 Aux. Build. SW Isolation- Stroke Q 4735 MOV 1A2 Aux. Build. SW Isolation Stroke Q 4757 MV Reactor Compartment Cooling Stroke Q Unit B Inlet Isolation

TITLE< DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 27 pF 40 Valve 4 ~Te Note Test ~Fre 4758 Reactor Compartment Cooling Stroke Q Unit B Outlet Isolation 4780 MOV 1A2 Screen House SW Stroke Q Isolation 5171 MOV Turbine Build. Fire Water Stroke Q Loop Supply Isolation 587l Containment Post Accident Stroke Q Filter Damper 5872 Containment Post Accident Stroke Q Filter Damper 5873 APV Containment Post Accident Stroke Q Filter Damper 5874 APV Containment Post Accident Stroke Q Filter Damper 5875 Containment Post Accident Stroke Q Filter Damper 5876 Containment Post Accident Stroke Q Filter Damper 9629A MOV 1C SAFP Service Water Stroke Q Isolation 9629B MOV 1D SAFP Service Water Stroke Q Isolation 9701A MOV 1C SAFP Discharge Stroke Q 9701B MOV 1D SAFP Discharge Stroke Q 9703A MOV SAFP Cross Over Stroke Q 9703B MOV SAFP Cross Over Stroke Q 9704A MOV 1C SAFP Containment Stroke Q Isolation

0 DATE QUALITY 1/30/86 AS SURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 28 oF 40 Valve 4 ~Te Note Test ~Fre 9704B MOV 1D SAFP Containment Stroke Q Isolation 9710A AOV 1C SAFP Recirc. Control Stroke Q 9710B AOV 1D SAFP Recirc. Control Stroke Q 4.10 Category C Check Valves Valve 5 ~Te Note Test ~Fre 710A CV 1-A RHR Pump Discharge Stroke Q 710B CV 1-B RHR Pump Discharge Stroke Q 723A CV 1-A CC Pump Discharge Stroke Q 723B CV 1-B CC Pump Discharge Stroke Q 847A CV A-CSP From Spray Additive Stroke Q Tank to Eductor 847B CV B-CSP From Spray Additive Stroke Q Tank to Eductor 854 CV RWST to RHR Pump Check Stroke Q 866A CV CS Pump.l-A to Charcoal 12 Stroke C/R Filter Deluge 866B CV CS Pump 1-B to Charcoal Stroke Q Filter Deluge 3516 CV lB Main Steam Isolation Stroke R 3517 CV 1A Main Steam Isolation Stroke R 3998 CV TAFP Discharge Check Stroke M 4000C CV lA MAFP Discharge Check Stroke M 4000D CV lB MAFP Discharge Check Stroke M

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 29 OP 40 Valve 0 ~Te Note Test ~Fre 4003 CV TAFP to S/G lA Stroke M 4004 CV TAFP to S/G lB Stroke M 4009 CV lA MAFP to S/G lA Stroke M 4010 CV lB MAFP to S/G lB Stroke M 4014 CV TAFP Suction Stroke M 4016 CV 1B MAFP Suction Stroke M 4017 CV lA MAFP Suction Stroke M 4023 CV TAFP Recirculation Stroke M 5133 CV Diesel Fire Pump Disch. Stroke Q 5136 CV Motor Fire Pump Discharge Stroke Q 9627A CV 1C SAFP SW Suction Stroke Q 9627B CV 1D SAFP SW Suction Stroke Q 9700A CV 1C SAFP Discharge Stroke Q 9700B CV 1D SAFP Discharge Stroke Q 9705A CV 1C SAFP to S/G 1A Stroke Q 9705B CV 1D SAFP to S/G 1B Stroke Q 4.11 Category C Relief Valve Valve 4 ~Te Note Test ~Fre 203 RV Letdown High Pressure 15 Safety Relief 209 RV Letdown Low Pressure 15 Safety Relief 434 RV Pressurizer Safety Relief 15

TITLEc DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 30 OP 40 Valve 0 ~Te Descri tion Note Test ~Fre 435 RV Pressurizer Safety Relief 15 732 RV CC Surge Tank Relief 15 RV CC From Excess Letdown 15 Heat Exchanger 755A RV CC From A RCP Thermal 15 Barrier 755B RV CC From B RCP Thermal 15 Barrier 758A RV CC From A-RCP Oil Coolers 15 758B 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 Zine Relief Valve 15 Inside Containment 1817 RV Alternate Suction From 15 RHR Pump to C SI Pump 3508 RV 1-B S/G PRV 15 3509 RV 1-A S/G PRV 15 3510 RV 1-B S/G PRV 15 3511 RV 1-A S/G PRV 15 3512. RV 1-A S/G PRV 15 3513 RV 1-A S/G PRV 15 3514 RV 1-B S/G PRV 15 3515 RV 1-A S/G PRV 15

TITLEt DATE QUALITY l/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 31 OF 40 Valve 5 T~e Note Test ~Fre 4653 RV .Service Water Relief 15 4654 RV Service Water Relief 15 4657 RV Service Water Relief 15 5134 RV Diesel Fire Pump Disch 15 Relief 5135 RV Motor'Fire Pump Disch 15 Relief 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.

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 32 DF 40 Total whole body dosage to test personnel is estimated to be 375 mrem. This valve will be stroked at cold shutdowns and refueling outages.

Note 5 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 Valves 813 and 814 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.

Note 7 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.

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program OF Note 9 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 and re-fueling outages.

Note 10- 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 indicators, system volume measuurements or by direct measurement.

Minimum test differential shall be greater than 150 psid. Technical Specification 4.3.3.4 defines the allowable leakage rates.

Note ll- Valves 820, 877A, 877B, 878F, 878H, 1076A, 1076B ~ 1 080Ag 1084Ag 1 084B g IV 3Ag IV 3B g IV 5Ag IV 5B g IV 2Ag IV 2B g 1554 g 1556 g 1557~ 1579 g 1560'562'563'565'566/

1568 g 1569 ~ 1571 1572 1574 g 1793 g 181 1Ag 1811Bg 5129 g 6151'152@ 6155'175@ 7141@

7226 g 7443 g 7444 g 7445 g 7448 g 7452 g 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-3700-1.

TIT LE i DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 34 DP 40 Note 12- 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 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, except for low power physics testing, 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 14- 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.

Note 15- 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.

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TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 35 Op 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.lb.

(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

TITLE: DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 36 DF 40 be disruptive to air operated valves inside.'hese valves will be stroked at refueling outages.

Not.e 20- 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.

Note 21- 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.

Note 22- 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.

Note 23- Valves 515 and 516 stroked quarterly except and if already closed or during cold refueling shutdowns'.

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 inop'erable in the open position.

TITLEc DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 37 OF 40 Note 26- As per Technical Speci failure of valves ficationsduring 624 and 625

3. 3.1.2. e, 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,

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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 stroked at cold shutdown and refueling outages.

Note 28- Check valves 842A and 842B (accumulator check valves) cannot and should not be exercised during plant operation.

Exercising of these valves requires the reactor coolant system pressure to be reduced to below accumulator pressure.

Therefore testing of these valves performed after refueling and cold will'e and after maintenance, repair 'hutdowns, 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 and 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.

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 valve, pressuring the line downstream of the check valves and measuring the upstream leakage, or (2) by measuring

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QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 38 PP 40 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.

Note 29- 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- Valves 851A and 851B are'ot 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.

Note 31- Valves 4601, 4602, 4603 and 4604 shall be leak tested each refueling outage using a back flow test method to determine

TITI.Kc DATE QUAJ ITY 1/30/86 AS SURANCE APPENDIX C PAGE MANUAZ Pump and Valve GINNA STATION Testing Program 39 DF 40 if'ack flow to the corresponding 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.

Note 32- Valves 590, 591, 592 and 593 shall not, be stroked quarterly as an unplanned pressure transient could result from a leaky alternate isolation valve. These valves will be stroked at refueling outages Note 33- 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 reactor coolant system boundary, 10CFR50.55a(c)(2) specifies that components which are connected 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 Records 5.1 Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article IWP-6000 of Section XI of the Code.

TITLEs DATE QUALITY 1/30/86 ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 40 DP 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.

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