ML17255A298: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:QUALITY ASSURANCE MANUAL GINNA STATXON ROCHESTER GAS&ELECTRIC CORPORATIO | {{#Wiki_filter:QUALITY ASSURANCE MANUAL REY. PAGE GINNA STATXON 3A 1 DF 37 | ||
Definitions: | ~ | ||
EFFECTIVE DATE: | |||
ROCHESTER GAS & ELECTRIC CORPORATIO SIGHATURE DATE TITLE: PREPARED BY: | |||
Lg g (~ 3g Appendix C Ginna Station Inservice Pump and Valve Testing 6-iX-68 Program for the January 1, 1981 REYIEW through December 31, 1990 Period APPROVED BY: | |||
Q g>> /+ Q P | |||
Pro ram Table of Contents Xntroduction: 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 S.O Records 8306240302 830620 PDR ADOCK 05000244 P ' | |||
PDR | |||
ll J | |||
l ti | |||
TITLE: DATE QUAL ITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 2 37 OF 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 |
Latest revision as of 19:48, 29 October 2019
ML17255A298 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 06/15/1983 |
From: | Anderson C ROCHESTER GAS & ELECTRIC CORP. |
To: | |
Shared Package | |
ML17255A297 | List: |
References | |
NUDOCS 8306240302 | |
Download: ML17255A298 (68) | |
Text
QUALITY ASSURANCE MANUAL REY. PAGE GINNA STATXON 3A 1 DF 37
~
EFFECTIVE DATE:
ROCHESTER GAS & ELECTRIC CORPORATIO SIGHATURE DATE TITLE: PREPARED BY:
Lg g (~ 3g Appendix C Ginna Station Inservice Pump and Valve Testing 6-iX-68 Program for the January 1, 1981 REYIEW through December 31, 1990 Period APPROVED BY:
Q g>> /+ Q P
Pro ram Table of Contents Xntroduction: 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 S.O Records 8306240302 830620 PDR ADOCK 05000244 P '
ll J
l ti
TITLE: DATE QUAL ITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 2 37 OF 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.
'J P
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 3 37 OF Definitions AFP Auxiliary Feedwater Pump AOV Air Operated Valve APV Air Operated Piston Valve BA Boric Acid Code American Society of Mechanical En gineers 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 MAFP Motor Driven Auxiliary Feedwater Pump MOV Motor Operated Valve MV 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
i l
f P% P
42 52C TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 4 OF 37 Definitions TAFP Turbine Driven Auxiliary Feedwater Pump VC Volume Control VCT Volume Control Tank VH Vent Header
TITLEi DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 5 37 OF 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 J
2.1 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.
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.
I (
1 J . V
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 6 37 OF 3.2 The following pumps shall be tested in accordance with Article IWP of Section XI:
(a) lA Component Cooling (b) 1B Component Cooling (c) 1A Safety Injection (d) 1B Safety Injection (e) 1C Safety Injection (f)'A Residual Heat Removal 1B Residual Heat Removal (g)
(h) lA Containment Spray (i) 1B Containment Spray (j) lA 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) 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 plant operation. Instead, the tests must be
I 1
I
TITLE: DATE QUAL ITY A'SSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 7 37 Of 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 failure is imminent. Finally, test conditions bearing 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 monthly.
l TITLE: DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 8 pp 37
- 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 test one month.
C ~ Residual heat removal pumps shall be tested monthly except during cold or refueling shutdown. The pumps shall be tested prior to startup exceeds if the time since the last text one month. When the reactor coolant system temperature is between 3504F and 200'F or the plant is at. cold or refueling shutdown the plant Technical Specifications may require one or both pumps to be operable.
then the required pumps Ifresidual shall heat this is the removal case, 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 one month.
time since the last test
- 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 is declared inoperable without the testing.
if that Consistent with plant Technical Specifications, specified intervals may be extended by 25% to accommodate normal test schedules.
TITLE> DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 9 37 OF PVT 4.0 Inservice Valve Testin Pro ram 4.1 The Inservice Valve Testing Program was developed in accordance with the requirements of Article IWV of Section XI of the Code. All those valves that are required to perform a specific function either to shut down the reactor to the cold shut-down condition or in mitigating the consequences of an accident and maintain the reactor in a safe shutdown condition are included in the program.
4.2 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 their 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.
4.5 Category A and B valves operation shall be timed each time they are stroked utilizing switch initiation and the position indicators, which are accessible during plant operation. During each
I g I
~.
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 10 37 OF 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.
4.8 Category A Valves Valve 4 ~Te 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
0 ~ g
\
'N" )
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 11 37 OF Valve N ~Te Descri tion Note Test Freer 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 Line 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 Q Leak R 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 5 Stroke C/R Leak R 750A CV CC to. A RCP 5 Stroke C/R Leak R
s I p 3
'I
'J
TITLEs DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 12 pF 37 Valve ¹ ~Te Descri tion Note Test ~Fre 750B CV CC to B RCP Stroke C/R Leak R 759A MOV Containment Stop CC From Stroke C/R Loop A RCP Leak R 759B MOV Containment Stop CC From Stroke '/R Loop 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 .'V Core Deluge Check 10 10 Stroke Leak C/R C/R 853B CV Core Deluge Check 10 Stroke C/R 10 Leak C/R CV l-A CSP Disch Stroke Q
'62A 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
I I
~ ~
t 1t
TITLE: DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 13 PP 37 Valve ¹ ~Te Note Test ~Fre y
870A CV l-A to l-C SI Pump Disch Stroke Q Leak R 870B CV l-B to l-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 11 Stroke Loop B Hot Leg 29 Leak 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 Loop 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 Loop A Hydrogen Monitor Stroke Q Outlet Leak R 923 SOV Loop B Hydrogen Monitor Stroke Q Inlet Leak R 924 , SOV Loop B Hydrogen Monitor Stroke Q Outlet Leak R
g I
yS I
TITLE: DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 14 PP 37 Valve 4 ~Te Descri tion Note Test ~Fre 956D MV Hot Leg Loop Sample Stroke Containment Isolation Leak 956E MV PRZR Liquid Space Sample Stroke Q Containment Isolation Leak R 956F MV 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 Leak R 966C AOV Loop A and B Hot Leg Stroke Q Containment Isolation Leak R 1003A LCV l-A RCDT Pump Suction Stroke Q Leak R 1003B LCV. l-B RCDT Pump Suction Stroke Q Leak R 1076A MV Hydrogen to "A" Recombiner 11 Stroke Pilot Containment Isolation Leak IV-3A SOV Hydrogen to "A" Recombiner 11 Stroke Pilot Containment Isolation Leak 1076B MV Hydrogen to "B" Recombiner 11 Stroke Pilot Containment Isolation I
Leak IV-3B SOV Hydrogen to "B" Recombiner 11 Stroke Pilot Containment Isolation Leak 1080A MV Oxygen Make Up to Contain- 11 Stroke ment Isolation Leak IV-2A Oxygen Make Up to Contain- 11 Stroke ment Isolation (A Recombiner) Leak IV-2B Oxygen Make Up to Contain- 11 Stroke ment Isolation (B Recombiner) Leak
y I g
s TITLEi DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 15 PP 37 Valve I ~Te Descri tion noae Test ~Fre 1084A MV Hydrogen to "A" Recombiner 11 Stroke Main Burner Containment Leak R Isolation IV-5A SOV Hydrogen to "A" Recombiner 11 Stroke Main Burner Containment Leak Isolation 1084B MV Hydrogen to "B" Recombiner 11 Stroke Main Burner Containment Leak Isolation IV-5B SOV Hydrogen to "B" Recombiner 11 Stroke Main Burner Containment Leak Isolation 1554 MV D Recirc. Fan Air Sample 11 Stroke Isolation Leak 1556 MV D Recirc. Fan Air Sample 11 Stroke Isolation Leak 1557 MV A Recirc. Fan Air Sample 11 Stroke Isolation Leak 1559 MV A Recirc. Fan Air Sample Stroke Isolation l Leak 1560 MV A 6 D Return Line Stroke Isolation Leak 1562 MV A 6 D Return Line Stroke Isolation Leak 1563 MV B Recirc. Fan Air Sample 11 Stroke Isolation Leak R' 1565 MV B Recirc. Fan Air Sample 11 Stroke Isolation Leak 1566 MV B Recirc. Fan Air Sample 11 Stroke Return Line Isolation Leak 15'68 MV B Recirc. Fan Air Sample 11 Stroke Return Line Isolation Leak
s I p I
1
)
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 16 37 OF Valve 4 ~Te Descri tion Note 'est Freer 1569 MV C Recirc. Fan Air Sample 11 Stroke Isolation Leak 1571 MV C Recirc. Fan Air Sample Stroke Isolation Leak 1572 MV C Recirc. Fan Air Sample Stroke Return Line Isolation Leak 1574 C Recirc. Fan Air Sample Stroke Return Line Isolation Leak 1596 MV Radiation Monitor Supply Stroke Leak 1597 AOV Radiation Monitor Supply Stroke Q Leak R 1598 AOV Radiation Monitor Exhaust Stroke Q Leak R 1599 AOV Radiation Monitor Exhaust Stroke Q Leak R 1655 MV RCDT to Gas Analyzer Stroke Q Leak R l713 CV N2 to RCDT Stroke Q Leak R 1721 AOV Suction line to RCDT Stroke Q Leak R
'1723 AOV A Containment Sump Disch Stroke Q to Waste Holdup Tank Leak R l728 AOV A Containment Sump Disch Stroke Q to Waste Holdup Tank Leak R 1786 AOV RCDT to VH Isolation Stroke Q Leak R l787 AOV RCDT to VH Isolation Stroke Q Leak R
I
~ ~
TITLEi DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 17 OF 37 Valve 4 ~Te Descri tion Note Test ~Fse l789 AOV RCDT to GA Containment Stroke Q Xsolation Leak R 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 Leak R 1819F MV Containment Pressure , 21 Stroke C/R Transmitter 950 Isolation Leak R 1819G MV Containment Pressure 21 Stroke C/R Transmitter 944 Isolation 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 5393 CV Xnstrument 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 Xsolation Stroke Q Leak R 5734 MV B-S/G Sample Isolation Stroke Q Leak R
~ I ~
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 18 37 OF Valve 0 ~Te Descri tion Note Test Freer 5735 AOV "A" S/G Blowdown Sample Stroke Q Isolation Leak R 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 C Isolation Leak
- 5870 APV Containment Purge Supply 22 Stroke C Isolation Leak
- 5878 APV Containment Purge Exhaust 22 Stroke C Isolation Leak
- 5879 APV Containment Purge Exhaust 22 Stroke C Isolation Leak
- 6151 MV Auxiliary Steam Supply to 11 Stroke Containment Leak R 6152 MV Condensate Return from 11 Stroke Containment Leak R 6165 MV Aux. Steam Supply to 11 Stroke Containment Leak R 6175 MV Condensate Return from 11 Stroke Containment Leak R 7141 MV Service Air Isolation 11 Stroke Outside Containment Leak R 7226 CV Service Air Isolation 11 Stroke Inside Containment Leak R
- See Note 22
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 19 OF 37 Valve 4 ~Te Descri tion Note Test ~Fre 7443 MOV Containment Air Test Stroke Supply Leak 7444 MOV Containment Air Test Vent 11 Stroke Leak 7445 MOV Containment Air Test Vent 11 Stroke Leak 7448 MV Isolation Valve from Stroke Containment to Local Leak 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 11 Stroke Containment to Local 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 8419 CV Demin. Water to Contain- Stroke ment Isolation Leak 9227 AOV Fire Service Water Stroke Containment Isolation Leak 9229 CV Fire Service Water 11 Stroke Containment Isolation Leak R
I
~ I i ~
II, I' N
~ ~
y 4'UALITY
~
TITLE: DATE ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 20 37 OF 4.9 Category B Valves Valve N ~Te Descri tion Note Test Freer 014 RCV Aux Building GDT Release Stroke Q OX7 RCV Component Cooling Surge Stroke Q Tank Vent 081 APV Control Room Ventilation Stroke Q Damper 082 APV Control Room Ventilation Stroke Q Damper d 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 112B LCV Emergency Makeup RWST to Stroke Q Charging Pump 112C LCV VCT Outlet Stroke Q 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 I
624 HCV 1-B RHR HX Outlet 26 Stroke C/R
0 ~
J I I
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump'nd Valve PAGE GINNA STATION ~
Testing Program 21 37 OF Valve 4 ~T pe Descri tion Note Test Freer 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 C/R Loop A 701 MOV RHR Inlet Isolation From 8 Stroke C/R Loop A 704A MOV Suction 1-A RHR Pump 24 Stroke Q 704B MOV Suction 1-B RHR Pump 24 Stroke Q 720 MOV RHR Return Xsolation to 8 Stroke C/R Loop B 721 MOV RHR Return Isolation to 8 Stroke C/R Loop B 738A MOV CC to 1-A RHR HX Stroke Q 738B MOV CC to 1-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 SX Pump Suction From 25 Stroke Q BA Tank 826D MOV SI >Pump Suction From 25 Stroke Q BA Tank 8 36A HCV Spray Additive Tank Dis- 17/24 Stroke Q charge 836B HCV Spray Additive Tank Dis- 17/24 Stroke Q charge
TITLEs DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 22 Of 37 Valve N ~Te Descri tion Note Test Freer 850A MOV Sump B to RHR Pumps 24 Stroke Q 8 50B ,MOV Sump B to RHR Pumps 24 Stroke Q 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 Stroke C/R 857A MOV 1B RHR HX to CS and SI 27 Stroke C/R Pump Isolation 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 8 60A 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 l-A to l-C SI Pump 24 Stroke Q Discharge 87lB MOV l-B to l-C SI Pump 24 Stroke Q Discharge 875A 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
'L' I
I'
)
I ~
TITI.E) DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 23 37 OF Valve 4 ~Te Descri tion Note Test ~Fre 896A MOV RWST to CS and SI Pumps Stroke C/R 896B MOV RWST to CS and SI Pumps 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 Stroke Q Sample 953 AOV Pressurizer Liquid Space Stroke Q Sample 955 AOV "B" Loop Hot. Leg Sample Stroke Q 959 AOV RHR Loop Sample 20 Stroke C/R 1811A MV Reactor Coolant Drain Tank Isolation to RHR System 1811B MV Reactor Coolant Drain Tank 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 3504 MOV Main Steam to TAFP From l-B Stroke Q S/G 3505 MOV Main -Steam to TAFP From l-A Stroke Q S/G 3652 MV Main Steam Throttle Valve Stroke Q to TAFP 3996 MOV TAFP Discharge Stroke Q 4000A MOV Cross Over Valve For MAFP Stroke Q 4000B MOV Cross Over Valve For MAFP Stroke Q 4007 MOV l-A MAFP Discharge Stroke Q
( I I J V
aa c TITLEt DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 24 37 OF Valve ¹ ~Te. Note Test ~Fre 4008 MOV 1-B MAFP Discharge Stroke Q 4013 MOV TAFP Service Water Supply Stroke Q Isolation 4027 MOV 1-A MAFP Service Water Stroke Q Isolation 4028 MOV 1-B MAFP Service Water Stroke Q Isolation 4291 AOV TAFP Recir. Line Stroke Q 4297 AOV TAFP Discharge to 1-A S/G Stroke Q 4298 AOV TAFP Discharge to 1-B S/G Stroke Q 4304 AOV 1-A MAFP Recirculation Stroke Q Control 4310 AOV 1-B MAFP Recirculation Stroke Q Control 4561 AOV Containment Vent Recirc. Stroke Q Fans Discharge Flow Con-trol 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 lAl Turbine Building SW Stroke Q Isolation 4615 MOV lB1 Aux. Building SW Stroke Q Isolation 4616 MOV 1A1 Aux. Building SW, Stroke Q Isolation
0 (+I ~ I C
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 25 37 OF Valve N ~Te Descri tion Note Test ~Fre 4627 MV Service Water to A Fan Stroke Q Cooler Isolation 4628 MV Service Water to B Fan Stroke Q Cooler Isolation 4629 , MV Service .Water from A Fan Stroke Q Cooler Isolation 4630 MV Service Water from B Fan Stroke Q Cooler Isolation 4635 Reactor Compartment Cooling Stroke Q Unit A Inlet Isolation 4636 MV Reactor Compartment Cooling Stroke Q 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 1A1 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 4734 MOV 1B2 Aux. Build. SW Isolation Stroke Q 4735 MOV 1A2 Aux. Build. SW Isolation Stroke Q
I 1 P l
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 26 OF 37 Valve 4 ~Te Descri tion Note Test ~Fre 4757 MV Reactor Compartment Cooling Stroke Q Unit B Inlet Isolation 4758 MV Reactor Compartment Cooling Stroke Q Unit' Outlet Isolation 4780 MOV 1A2 Screen House SW Stroke Q Isolation 5171 MOV Turbine Build. Fire Water Stroke Q Loop Supply Isolation 5871 APV Containment Post Accident Stroke Q Filter Damper 5872 APV 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 APV Containment Post Accident Stroke Q Filter Damper 5876 APV 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 97 03A MOV SAFP Cross Over Stroke Q 9703B MOV SAFP Cross Over Stroke Q
t I l I
~ ~
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 27 37 OF Valve 4 ~Te Note Test ~Fre 9704A MOV 1C SAFP Containment Stroke Q Isolation 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 N ~Te Descri tion Note Test Freer 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 1-A to Charcoal 12 Stroke C/R Filter Deluge 866B 3516
'V CV CS Pump Filter Check 1-B Deluge to Charcoal lB S/G Main Steam Swing 14 Stroke Stroke Q
Start-up 3517 CV lA S/G Main Steam Swing 14 Stroke Start-Check up 3998 CV TAFP Discharge Check Stroke Q 4000C CV lA MAFP Discharge Check Stroke Q
~ ~
I J L
H I
I v y
P h
E 4J.
I lf
~ ~
TITLEi DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 28 37 OF Valve N ~Te Descri tion Note Test ~Fre 4000D CV 1B MAFP Discharge Check Stroke Q 4003 CV TAFP to S/G lA Stroke Q 4004 CV TAFP to S/G 1B Stroke Q 4009 CV 1A MAFP to S/G lA Stroke Q 4010 CV 1B MAFP to S/G 1B Stroke Q 4014 CV TAFP Suction Stroke Q 4016 CV 1B MAFP Suction Stroke Q 4017 CV lA MAFP Suction Stroke Q 4023 CV TAFP Recirculation Stroke Q 4601 CV 1A Service Water Pump 'Stroke Q Discharge 4602 CV 1B Service Water Pump Stroke Q Discharge 4603 CV 1C Service Water Pump Stroke Q Discharge 4604 CV 1D Service Water Pump Stroke Q Discharge 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 97 00A 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
TITLE: DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 29 DF 37 4.11 Category C Relief Valve Valve I ~Te Descri tion Note Test ~Fre 203 RV Letdown High Pressure 15 Safety Relief 209 RV Letdown Low Pressure 15 Safety Relief 434 RV Pressurizer Safety Relief 15 435 RV Pressurizer Safety Relief 15 732 RV CC Surge Tank Relief 15 744 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 818 RV RV CC CC From B-RCP From Reactor Coolers Oil Coolers Support '515 861 RV 1-B CS Pump Suction Relief 15 887 RV SI Test Line 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
I I ~ I IIl In
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 30 37 OF Valve 4 ~Te Descri tion Note Test ~Fze 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 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.
s
'k
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 31 37.
OF Note 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.
Note 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 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 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 Valves 700 and 72l 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
TlTLE: DATE QUALITY ASSURANCE APPENDIX C PAGE MANUAL Pump and Valve GINNA STATION Testing Program 32 pf 37 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.
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 l0- 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, 1076BI 1080Ag 1084Ag 1084Bg IV 3Ag IV 3B/
IV 5Ag IV 5Bg IV 2Ag IV 2Bg 1554/ 1556/
1557 I 1579 g 1560 g 1562 g 1563 g 1565 g 1566/
1568~ 1569'571 '572I 1574'81 1Ag 1811Bg 5129 I 6151 I 6152'155'175'141/
7226'443'444@ 7445'448'452'456 f 8418, 8419, 9227 and 9229 are considered passive valves wh'ich are not re uired to
'1 c >~ ~
4~
TITLE: DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 33 37 OF 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.
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 13- Valves 867A, 867B, 878G, and 878J cannot be stroked during normal operation on a quarterly basis or at cold shutdown condition when the primary system is full. This test may only be done when the plant is in a refueling shutdown condition with a partially full primary system in order to prevent an over-pressurization. Leakage testing of check valves 867A, 867B, 878G and 878J shall be accomplished prior to criticality following (1) refueling, (2) cold shutdown, and (3) maintenance, repair or replacement work on the valves. Leakage may be measured indirectly from the performance of pressure indicators, system volume measurements or by direct measurement.
Check valves 878G and 878J shall also be tested for leakage following each safety injection flow test. Minimum test differential shall be greater than 150 psid. Technical Specification 4.3.3.4 defines the allowable leakage rates.
Note 14- Valves 3516 and 3517 cannot be stroked during normal plant operation on a quar-terly basis because they are the main steam swing check stop valves. These valves are stroked during each plant startup.
T IT I.E: DATE QUAL ITY ASSURANCE APPENDIX MANUAL and Valve C'ump PAGE GINNA STATION Testing Program 34 37 OF Note 15- Category C Relief Valves shal l be tested in accordance with the extent and fre-quency requirements of Paragraph IWV-3510 of Article IWV of Section XI of the Code.
Not e 16- Valves 430 and 43lC are the power operated relief valves associated with the overpressurization system. These valves shall not be stroked quarterly as an unplanned pressure transient could result from a leaky block valve.
Operability of these valves shall be verified as follows:
(1) Full stroke exercising during cool down prior to achieving water solid condition in the pressurizer and during cold shutdown prior to heat up+
(2) Stroke timing to be performed as a minimum once each refueling cycle as a part of the channel calibration specified by Technical Specifications 4.16.1b.
(3) Fail safe actuation testing is permitted by the code to be per-formed at each cold shutdown if valve cannot be tested during power operation.
(4) Technical specification 4.16.1a and 4.16.1c delineate additional re-quirements for operability verifi-cation of the PORV actuation channel and valve position.
Note 17- Additional stroking will be consistent with Technical Specifications.
Note 18- Valves 852A and 8523 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-
~ / ' r S'>>
I < ='L ~ =, 'l\, -+4 ~,
PLhl 8
3
TITLEt DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 35 37 OF 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 outage s.
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 normal ly 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 Valves 515 and 516 stroked quarterly except and if already closed or during cold refueling shutdowns.
Note 24- Not to be done during time that redundant valve is inoperable per Technical Speci-fication.
Note 25- As per Technical Specifications 3.3.1.2.f, no cycling shall be done if normally open valve in other flow path is inoperable in the open position.
~ .
<. r
TITLEt DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 36 OF 37 Note 26- As per Technical Specifications 3.3.1.2.e, failure of valves 624 and 625 during quarterly stroking in the closed position can degrade LPSI system function. How-ever, these valves shall be stroked at cold shutdown and refueling outages.
Note 27- As per Technical Specifications 3.3.1.2.e, failure of valves 857A, 857B, 857C, 897 and 898 during quarterly stroking can degrade the injection phase of the SI pumps. However, these valves shall be stroked at cold shutdown and refueling outage s.
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 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.
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.
<p a ie I
TITLEi DATE QUALITY ASSURANCE APPENDIX C MANUAL Pump and Valve PAGE GINNA STATION Testing Program 37 37 OF 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.
PVT 5.0 Records 5.1 Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article IWP-'000 of Section XI of the Code.
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.
4 JC '
~ pp ~
'I I