Text

Rev 4 to Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990
	ML17255A571
Person / Time
Site:	Ginna
Issue date:	11/29/1983
From:	Anderson C; ROCHESTER GAS & ELECTRIC CORP.
To:	;
Shared Package
ML17255A570	List: ML17255A569; ML17255A571;
References
	NUDOCS 8312280356
	Download: ML17255A571 (74)
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QUALITY ASSURANCE MANUAL GINNA STATION ROCHESTER GAS

& ELECTRIC CORPORATION RE V.

PAGE 1.

DP 39 DR uar 1

1984 TITLE:

Appendix C Ginna Station Inservice Pump and Valve Testing Program for the January 1,

1981 through December 31, 1990 Period PREPARED BY:

REVIEW APPROVED BY:

SIGNATURE DATE ll Z.'f g$

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Pro ram Table of C ntents

==

Introduction:==

Definitions:

Program:

Discussion PVT 1.0 Sco e and Responsibility

/

PVT 2.0 de Edition and Testing Interval PVT 3.0 Inservice Pump Testing Program PVT 5.0 Records 228PSSh 83i22i

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QUALITY ASSURANCE MA5WAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 2

DP 39 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, 1990.

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.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 3

DF 39 Definitions AFP AOV APV BA Code CC CS CSP CV C/R ECCS FCV GA GDT HCV HX LCV MAFP MOV MV PCV PORV PRT PRV PVT Q

R RCDT RCP RCV RHR RMW RV RWST RX S/G SAFWP SI SOV SW.

Engineers r Pump Auxiliary Feedwater Pump Air Operated Valve Air Operated Piston Valve Boric Acid American Society of Mechanical 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 Feedwate Motor Operated Valve Manual Valve Pressure Cohtrol 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

'I Refueling Water Storage Tank Reactor Vessel Steam Generator Standby Auxiliary Feedwater Pump Safety Injection Solenoid Operated Valve Service Water

N

QUALITY ASSURANCE NANUAL GINNA STATION TlTLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 4

DP 39 42 52C 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).

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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE oF 39 Pum and Valve Testin Pro ram PVT 1.0 1.1 1.2 1.3 PVT 2.0 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.

h 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.

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 acceptab'le limits.

Code Edition and Testin Interval 2.1 PVT 3.0 The Inservice Pump and Valve Testing Program for the ten (10) year period starting January 1,

1981 through. December 31, 1990 was developed utilizing the 1977 Edition of Section XI of the Code through the Summer 1978 Addenda.

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 DATE1/1/84 PAGE 6

pF 39 42 52C 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) lB Safety Injection (e) lC Safety Injection (f) lA Residual Heat Removal (g) lB Residual Heat Removal (h) lA 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 (g) 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 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 plant operation.

Instead, the tests must be

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE j./z/s4 PAGE 7

DP 39 3.4 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 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 m'ay 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.

The test frequency for the pumps shall be as follows'.

Component cooling water pumps shall be tested monthly.

TITLE:

DATE 1/1/84 42 52C QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 8

DP 39 b.

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 ~

d.

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 on'e 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 teste'd 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.

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QUALITY ASSURANCE NANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 9

DF 39 4R 52C PVT 4.0 Inservice Valve Testin Pro ram 4.1 4.2 4.3 4.5 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.

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 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 requirementst.

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

notes, PVT 4.12.

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 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.

During each

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE1/1/84 PAGE 10 PP 39 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 1.2). 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 wogk goad 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 0

~Te 204A MV Letdown to NRHX 304A 304B CV 1-B RCP Seal Injection CV 1-A RCP Seal Injection Note Test

~Fre 3

Stroke C/R Leak R

1 Stroke C/R Leak R

1

, Stroke C/R Leak R

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 42 52C DF 39 Valve 5

~Te Note Test Freq 313 370B 371 383B 508 528 529.

MOV Seal Water Return Isolation CV Charging Zine Isolation AOV Letdown Isolation CV Alternate Charging Line AOV RMW to Containment Vessel Stop CV N

Supply to PRT CV RMW to PRT Stroke Leak Stroke Ieak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak C/R R

C/R R

Q R

546 547 743 745 749A 749B 750A AOV PRT Stop Valve to Gas

Analyzed, 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 Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q

R Q

R C/R R

C/R R

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k QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 12'9 OF Valve 5

~Te Note 'est

~Fre 750B 759A 759B t

813 8l4 820 CV CC to B RCP MOV Containment.

Stop CC From Loop A RCP MOV Containment Stop CC From Loop B RCP MOV CC Supply to RX Support Coolers MOV CC Return to RX Support Coolers MV Letdown to NRHX Stroke C/R Leak R

5 Stroke C/R Leak R

Stroke C/R Leak R

Stroke Leak R

842A 842B 846 853A 853B 862A 862B 867A 867B

,CV Loop A Accumulator Dump Line Check Valve CV Loop B Accumulator Dump Line Check.Valve AOV N

Supply to Accumulators CV Core Deluge Check CV Core Deluge Check CV 1-A CSP Disch CV 1-B CSP Disch CV Accumulator Dump and SI to Cold Leg Loop B

CV Accumulator Dump and SI to Cold Leg Loop A 28 28 10 10 10 10 13 13 13 13 Stroke C/R Leak C/R Stroke C/R Leak C/R Stroke Q

Ieak R

Stroke C/R Leak C/R Stroke C/R Leak C/R Stroke Q

Leak R

Stroke Q

Leak R

Stroke R

Leak C/R Stroke R

Leak C/R

~l

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 13 42 52C 39 OF 870B CV 1-B to 1-C SI Pump Disch Valve 4

~Te 870A CV 1-A to 1-C SI Pump Disch Note Test

~Fre Stroke Q

Leak R

Stroke Q

Leak R

877A 877B 878F 878G 878H 878 J 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 Leg Loop B

CV High Safety Injection Loop A Hot Leg CV 1-B SI Pump to Cold Leg Loop A I

MV SI Test Line Isolation CV 1-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 Monitor Inlet SOV Loop B Hydrogen Monitor Outlet ll 29 ll 29 ll 29 13 13 ll 29 13 13 Stroke Leak 40 Mo.

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

Sg

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/S4 42 52C PAGE 14 39 Valve 5

~Te 956D 956E 956F 966A 966B 966C 1003A 1003B 1076A IV-3A 1076B Note Hot Leg Loop Sample Containment Isolation PRZR Liquid Space Sample Containment Isolation PRZR Steam Space Sample Containment Isolation Pressurizer Steam Space Containment Isolation Pressurizer Liquid Space Containment Isolation Loop A and B Hot Leg Containment Isolation AOV AOV AOV LCV 1-A RCDT Pump Suction 1-B RCDT Pump Suction I

Hydrogen to "A" Recombiner ll Pilot Containment Isolation LCV SOV Hydrogen to "A" Recombiner ll Pilot Containment Isolation MV Hydrogen to "B" Recombiner 11 Pilot Containment Isolation Test Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Ieak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak

~Fre Q

R Q

R IV-3B SOV Hydrogen to "B" Recombiner ll Stroke.

Pilot Containment Isolation Leak 1080A IV-2A IV-2B MV Oxygen Make Up to Contain-11 ment Isolation Oxygen Make Up to Contain-11 ment. Isolation (A Recombiner)

Oxygen Make Up to Contain-ll ment, Isolation (B Recombiner)

Stroke Leak Stroke Leak Stroke Leak

+I QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 15 DF 39 Valve 0

~Te 1084A Hydrogen to "A" Recombiner Main Burner Containment Isolation Note Test Freq 11 Stroke Leak IV-5A 1084B IV-5B 1554 1556 1557 1559 1560 1562 1563 1565 1566 1568 SOV SOV 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 6 D Return Line Isolation A 8 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 ll Stroke Leak 11 Stroke Leak ll Stroke Leak 11 Stroke Leak ll Stroke Leak 11 Stroke Leak 11 Stroke Leak 11 Stroke Leak 11 Stroke Leak 11 Stroke Leak 11 Stroke Leak 11 Stroke Leak ll Stroke Leak

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QUALITY ASSURANCE MEGAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 16 DF 39 Valve 5

~Te Note Test

~Fre 1569 1571 1572 1574 1596 1597 1598 1599.

1655 17l3 1721 1723 i l728 l786 1787 C Recirc.

Fan Air Sample Isolation C Recirc.

Fan Air Sample Return Line Isolation C Recirc.

Fan Air Sample Return Zine 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 Tynk 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 Z eak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak R

Q R

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 17 OF 39 Valve 4

~Te Descri tion Note Test

~Fre 1789 1819A 1819B 1819C AOV MV MV MV RCDT to GA Containment Isolation Containment Pressure Transmitter 945 Isolation Containment Pressure Transmitter 946 Isolation Containment Pressure Transmitter 947 Isolation 21 21 21 Stroke Q

Leak Stroke C/R Leak R

Stroke C/R Leak R

1819D 1819E 1819F 1819G 4601 4602 4603 4604 MV MV MV MV CV CV CV CV Containment Pressure Transmitter 948 Isolation Containment Pressure Transmitter 949 Isolation Containment Pressure Transmitter 950 Isolation Containment Pressure Transmitter I944 Isolation I

1A Service Water Pump Discharge 1B Service Water Pump Discharge 1C Service Water Pump Discharge 1D Service Water Pump Discharge 21 Stroke C/R Leak R

21 Stroke C/R Leak R

31 Stroke Q

31 Leak R

31 Stroke Q

31 Leak R

31 Stroke Q

31 Leak R

31 Stroke Q

31 Leak R

5129 MV Construction Fire Service 11 Stroke Water Containment Isolation Leak R

5392 AOV Instrument Air to Contain-ment Isolation 19 Stroke R

Leak R

5393 CV Instrument Air to Containment Isolation 19 Stroke Leak R

QUALITY ASSURANCE KQKAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 18 DP 39 5702 MV B-S/G Blowdown Isolation 5733 MV A-S/G Sample Isolation Valve 8

~Te 5701 MV A-S/G Blowdown Isolation Note Test

~Fre Stroke Q

Leak R

Stroke Q

Leak R

Stroke Q

Ieak R

5734 5735 5736 5737 5738 5869 5870 5878 5879 6151 6152 MV B-S/G Sample Isolation AOV "A" S/G Blowdown Sample Isolation AOV "B" S/G Blowdown Sample

'solation AOV "B" S/G Blowdown Isolation 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 Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q

R Q

R

- See Note 22

I

s QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 19 OF 42 52C 39 Valve I

~Te Descri tion Note Test

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

Supply MOV Containment Air Test Vent 11 Stroke Leak s

Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak 7445 MOV Containment Air Test Vent 11 Stroke Leak R

7448 MV Isolation Valve from Containment,to Local PressuretIndicator for Containment Air Test.

11 Stroke Leak R

7452 MV Isolation Valve from Containment. to Local Pressure Indicator for Containment Air Test 11 Stroke Leak R

7456 7970 7971 8418 MV AOV Isolation Valve from Containment to Local Pressure Indicator for Containment Air Test Containment. Depressuri-zation Valve AOV Containment Depressuri-zation Valve AOV Demin. Water to Contain-ment. Isolation 11 Stroke Leak R

Stroke Q

Leak R

Stroke Q

Leak R

Stroke Leak

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program OATE 1/1/84 PAGE 20 OF 39 Valve 0

~Te 8419 CV Demin. Water to Contain-ment, Isolation Note Test

~Fre Stroke.

Leak 8623 9227 9229 CV Nitrogen to Accumulators Isolation AOV Fire Service Water Containment Isolation CV Fire Service Water Containment Isolation Stroke Leak Stroke Leak Stroke Leak

4. 9 Category B Valves Valve N

~Te Descri tion 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 APV APV APV APV APV LCV Control Room Ventilation Damper

~

I 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

1 l2C LCV VCT Outlet Stroke Q

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 21 39 OF Valve N

~Te Descri tion 427 430 AOV Letdown From Loop B PORV Pressurizer Power Operated Relief Note Test

~Fre 3

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

Stroke Q

516 624 625 626 700 701 704A 704B 720 721 738A 738B 825A 825B MOV Pressurizer PORV Block Valve HCV l-B RHR HX Outlet HCV l-A RHR HX Outlet FCV RHR Loop Return Recirc.

MOV RHR Inlet Isolation From Loop A MOV RHR Inlet Isolation From Loop A MOV Suction 1-A RHR Pump MOV Suction l-B RHR Pump MOV RHR Return Isolation to Loop B

MOV RHR Return Isolation to Loop B

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 23 Stroke Q

26 Stroke C/R 26 Stroke C/R Stroke Q

8 Stroke C/R 8

Stroke C/R 24 Stroke Q

24 Stroke Q

8 Stroke C/R 8

Stroke C/R Stroke Q

Stroke Q

9 Stroke C/R 9

Stroke C/R

~

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S

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 22 OF 39 826A MOV Valve N

~Te Descri tion SI Pump Suction From BA Tank Note Test Freer 25 Stroke Q

826B 826C 826D 836A 836B MOV MOV MOV HCV HCV SI Pump Suction From BA Tank SI Pump Suction From BA Tank SI Pump Suction From BA Tank Spray Additive Tank Dis-charge Spray Additive Tank Dis-charge 25 Stroke 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 24 24 MOV MOV Sump B to RHR Xsolation I

Sump B to RHR Isolation 30 30 MOV lB RHR HX to CS and SI Pump Xsolation 27 MOV RHR Pumps to Reactor Vessel 18 MOV RHR Pumps to Reactor Vessel 18 MOV RWST to RHR Pumps Stroke Q

Stroke Q

Stroke Stroke Stroke C/R Stroke C/R Stroke C/R Stroke C/R 857B MOV 1A RHR HX to CS and SI Pump Isolation 27 Stroke C/R 857C 8 60A MOV 1A RHR HX to CS and SI Pump Isolation MOV 1-A CSP Discharge 27 Stroke C/R 24 Stroke Q

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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE OF 39 Valve 5

~Te Note Test Free[

860B 860C 860D 871A MOV l-A to 1-C SI Pump Discharge MOV 1-A CSP Discharge MOV 1-B CSP Discharge MOV 1-B CSP Discharge 24 24 Stroke Q

Stroke Q

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

Stroke Q

876B 896A 896B 897 898 MOV MOV CS Pump Discharge to 1B Charcoal Filter Deluge 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 Stroke Q

27 Stroke C/R Stroke C/R Stroke C/R 27 Stroke C/R 951 953 AOV AOV Pressurizer Steam Space Sample Pressurizer Liquid Space Sample Stroke Q

Stroke Q

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

Stroke C/R

t

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 24 DF 39 Valve 0

~Te 1811A 1811B Reactor Coolant Drain Tank Isolation to RHR System Reactor Coolant Drain Tank Isolation to RHR System 1815A 1815B 3504 MOV Main Steam to TAFP From l-B S/G MOV C-SI Pump Suction From RWST 24 MOV C-SI Pump Suction From RWST 24 Stroke Q

Stroke Q

3505 3652 MOV Main Steam to TAFP From 1-A S/G Main Steam Throttle Valve to TAFP Stroke Q

Stroke Q

3996 4000A 4000B 4007 4008 4013 MOV TAFP Discharge MOV MOV Cross Over Valve For MAFP Cross Over Valve For MAFP MOV l-A MAFP Discharge MOV l-B MAFP Discharge MOV TAFP Service Water Supply Isolation Stroke M

Stroke M

4027 4028 MOV MOV l-A MAFP Service Water Isolation l-B MAFP Service Water Isolation Stroke M

Stroke M

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

Stroke M

C

~

)

~J I

/

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 25 DP 39 4304 AOV Valve 4

~Te 1-A MAFP Recirculation Control Note Test

~Fre Stroke M

4310 4561 4562 4609 4613 4614 4615 4616 4627 4628 4629 4630 AOV AOV AOV MOV MOV MOV MOV MOV MV 1-B MAFP Recirculation Control Containment Vent Recirc.

Fans Discharge Flow Con-trol Containment Vent Recirc.

Fans Discharge Flow Con-trol Bypass 1Al Screen House SW Isolation 1B2 Turbine Building SW Isolation lAl Turbine Building SW Isolation 1B1 Aux. Building SW Isolation lAl Aux. Building SW Isolation Service Water to A Fan Cooler Isolation Service Water to B Fan Cooler Isolation Service Water from A Fan Cooler Isolation Service Water from B Fan Cooler Isolation Stroke M

Stroke Q

4635 Reactor Compartment Cooling Stroke Q

Unit A Inlet Isolation

c J

l

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 42 52C PAGE 26 PP 39 Valve 5 T~e Note Test

~Fre 4636 MV Reactor Compartment Cooling

Stroke Q

Unit A Outlet Isolation 4641 4642 4643 4663 4664 4670 4733 4734 4735 4757 4758 4780 517l MV Service Water to C Fan Cooler Isolation MV Service Water to D Fan Cooler Isolation MV Service Water from C Fan Cooler Isolation MV Service Water from D Fan Cooler Isolation MOV lA1 Air Cond. Chillers SW Isolation MOV 1A2 Turbine Building SW Isolation MOV 1B1 Turbine Building SW Isolation MOV 1A2 Air Cond. Chillers SW Isolation MOV 1B2 Aux. Build.

SW Isolation MOV 1A2 Aux. Build.

SW Isolation MV Reactor Compartment Cooling Unit. B Inlet Isolation MV Reactor Compartment Cooling Unit B Outlet Isolation MOV 1A2 Screen House SW Isolation MOV Turbine Build. Fire Water Loop Supply Isolation Stroke Q

Stroke Q

~

I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 27 DP 39 Valve 5

~Te Note Test

~req 5871 5872 5873 5874 5875 5876 9629A 9629B APV APV APV APV APV APV MOV MOV 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 Isolatidn Stroke Q

Stroke Q

9701A 9701B 9703A 9703B 9704A 9704B 9710A 9710B MOV 1C SAFP Discharge MOV 1D SAFP Discharge MOV SAFP Cross Over MOV SAFP Cross Over MOV MOV 1C SAFP Containment Isolation 1D SAFP Containment Isolation AOV 1C SAFP Recirc. Control AOV 1D SAFP Recirc. Control Stroke Q

Stroke Q

(

~

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 28 39 OF 4.10 Category C Check Valves Valve 5

~Te 710A CV 1-A RHR Pump Discharge 723A 723B 847A CV 1-A CC Pump Discharge CV 1-B CC Pump Discharge CV A-CSP From Spray Additive Tank to Eductor 710B CV 1-B RHR Pump Discharge Note Test

~Fre Stroke Q

Stroke Q

847B 854 866A 866B 3516 3517 3998 4000C 4000D 4003 4004 4009 4010 4014 CV B-CSP From Spray Additive Tank to Eductor CV RWST to RHR Pump Check CV CS Pump 1-A to Charcoal Filter Deluge CV CS Pump 1-B to Charcoal Filter Deluge CV 1B Main Steam Isolation CV lA Main Steam Isolation CV TAFP Discharge Check CV lA MAFP Discharge Check CV 1B MAFP Discharge Check CV TAFP to S/G 1A CV TAFP to S/G lB CV lA MAFP to S/G lA CV 1B MAFP to S/G 1B CV TAFP Suction Stroke Q

Stroke Q

Stroke R

Stroke M

Stroke Stroke Stroke Stroke Stroke Stroke M

Stroke Q

12 Stroke C/R

I I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 29 OF 42 52C 39 Valve 0

~Te Note Test

~Fre 4016 4017 4023 5133 5136 9627A 9627B 9700A 9700B 9705A 9705B 4.11 Valve 5 203 209 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 'D SAFP Discharge CV 1C SAFP to S/G lA CV 1D SAFP to S/G 1B Category C Relief Valve

~Te RV Letdown High Pressure Safety Relief RV Letdown Low Pressure Safety Relief Stroke M

Stroke M

Stroke Q

Note Test

~Fre 15 RV Pressurizer Safety Relief 15 435 732 755A RV Pressurizer Safety Relief RV CC Surge Tank Relief RV CC From Excess Letdown Heat Exchanger RV CC From A RCP Thermal Barrier 15 15 15 15

I I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE j./z/84 PAGE 30 OF 39 Valve 5

~Te Note Test

~Fre 755B RV CC From B RCP Thermal Barrier 15 758A 758B 818 861 887 RV CC From A-RCP Oil Coolers 15 RV CC From B-RCP Oil Coolers 15 RV CC From Reactor Support 15 Coolers RV 1-B CS Pump Suction Relief 15 RV SI Test Line Relief Valve 15 Inside Containment 1817 3508 3509 3510 3511 3512 3513 3514 3515 4654 4657 5134 5135 RV Alternate Suction From RHR Pump to C SI Pump RV 1-B S/G PRV RV 1-A S/G PRV RV 1-B S/G >PRV t

RV 1-A S/G PRV RV 1-A S/G PRV RV 1"-A S/G PRV RV 1-B S/G PRV RV 1-A S/G PRV RV Service Water Relief RV Service Water Relief RV Service Water Relief RV Diesel Fire Pump Disch Relief RV Motor Fire Pump Disch Relief 15 15 15 15 15 15 15 15 15 15 15 15 15 15

{

I l

QUALITY ASSURANCE KQKAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 31 PP 39 4.12 Inservice Valve Testing Notes Note 1-Note 2

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.

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 Note Note 3

4.

5 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.

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.

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

I E

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 32 DP 39 checks and MOVs.

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

Note 6

Note 7 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.

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 Note 9 Valves 700 and 721 cannot. be stroked durin'g 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.

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.

c 1

QUALITY ASSURANCE

.MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 33 39 OF 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.

Note ll-Note 12-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.

Valves 820,'77A,

877B, 878F,

878H, 1076A, 1076B~

1080Ag 1084AJ 1084BJ IV 3Ag IV 3Bg IV 5AJ IV 5B/ IV 2A/ IV 2B J 1554 g 1556/

1557'579'560'562'563@

1565/

1566/

1568@

1569 g 1571 g 1572 g 1574 '811Ag

1811B, 5129,

6151, 6152,

6155, 6175,

7141, 7226 J 7443 g 7444

~

7445 ~

7448 /

7452 g

7456 f

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.

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.

l I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 34 DF 39 Note Note 13-14-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 repla'cement 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.

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.

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:

I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 PAGE 35 DF 39 (1)

Full stroke exercising during cool down prior to achieving water solid condition in the pressurizer and during cold shutdown prior to %eat 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-Valve's 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 be disruptive to air operated valves inside.

These valves will be stroked at refueling outages.

Note 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.

I

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:

APPENDIX C Pump and Valve Testing Program DATE 1/1/84 42 52C PAGE 36 DP 39 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 if already closed or during cold and refueling shutdowns.

Note 24-,Not to be done during time that redundant i

valve is inoperable per Technical Speci-fication.

Note 25-Note 26-Note 27-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.

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.

As per Technical Specifications 3.3.1.2.e, failure of valves

857A, 857B,

857C, 897 and 898 during quarterly stroking can

/t

~

lt

~

QUALITY ASSURANCE MANUAL GINNA STATION TlTLE:

APPENDIX C Pump and Valve Testing Program DATE1/1/84 42 52C PAGE 37 DP 39 Note 28-degrade the injection phase of the SI pumps.

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

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

Exercising of these valves reguires 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 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.

l 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 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.

I t

ML17255A571

Text

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