ML17261A638
| ML17261A638 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/01/1987 |
| From: | Anderson C, Bryant D ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A637 | List:
|
| References | |
| NUDOCS 8710200364 | |
| Download: ML17261A638 (59) | |
Text
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PAGE 42 ~ 52 A QUALITY ASSURANCE MANUAL GINNA STATION EFFECTIVE DATE)
ROCHESTER GAS Sc ELECTRIC CORPORATION SIGNATURE 1
oF 40 DATE TITLE:
Appendix C - Ginna Station Inservice Pump and Valve Testing Program for the January 1,
1981 through December 31, 1989 Period PREPARED SY REVIEW APPROVED SY Pro ram Table of Contents
==
Introduction:==
Definitions:
Discussion Program PVT 1.0 Scope and Responsibility PVT 2.0 Code Edition and Testing Interval PVT 3.0 Inservice Pump Testing Program PVT 4.0 Inservice Valve Testing Program PVT 5.0 Records 87102003 h4 871013 PDR ADOCK 0500024'4: II, PDR
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 2
oF 40 Introduction This appendix to the Quality Assurance Manual defines the Inservice Pump and Valve Testing Program for the ten year period starting January 1,
1981 through December 31, 1989.
Included in this program are the Quality Groups A,
B and C
Pumps which are provided with an emergency power source and those Quality Groups A, B and C Valves which are required to shut down the reactor or to mitigate the consequences of an accident and maintain the reactor in a safe shutdown condition.
This program has been developed as required by Section 50.55a{g) of 10CFR50 following the guidance of the ASME Boiler and Pressure Vessel Code Section XI - "Rules for Inservice Inspection of Nuclear Power Plant Components,"
{hereafter referred to as the "Code" ) excluding the controls of the Authorized Inspector, Enforcement Authority, Reporting Systems and N-Stamp Symbol.
The inservice testing program'shall be controlled by the Ginna Station Quality Assurance Program for Station Operation.
Quality Groups A,
B and C components correspond to those defined in NRC Regulatory Guide 1.26.
Further addenda and editions of Section XI of the Code shall be used for clarification of test. requirements and performance.
The Inservice Pump and Valve Testing Program substantially augments but. does not affect the pump and valve surveillance program required by Technical Specifications.
Technical Specification requirements associated with pump and valve surveillance, shall continue to be implemented as specified.
When changes to Technical Specifications create conflicts with this Appendix, the revised Technical Specifications will provide guidance until this Appendix is revised to incorporate the changes.
I I
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 9
DP 40 Definitions AFP AOV APV BA C
Code CC CS CSP CV C/R ECCS FCV GA GDT HCV HX LCV M
MAFP MOV MV
R RCDT RCP RCV RHR RMW RV RWST RX S/G SAFWP SI SOV SW Engineers ages Pump Auxiliary Feedwater Pump Air Operated Valve Air Operated Piston Valve Boric Acid Cold Shutdown American Society of Mechanical Boiler and Pressure Vessel Code Component; Cooling Containment Spray Containment Spray Pump Check Valve Cold Shutdown and Refueling Out, Emergency Core Cooling System Flow Control Valve Gas Analyzer, Gas Decay Tank Hand Control Valve Heat Exchanger Level Control Valve Monthly Motor Driven Auxiliary Feedwater Motor Operated Valve Manual Valve Pressure Control Valve Power Operated Relief Valve Pressurizer Relief Tank Pressure Relief Valve Pump and Valve Testing Quarterly Refueling Outage Reactor Coolant Drain Tank Reactor Coolant Pump Radiation Control Valve Residual Heat Removal Reactor Makeup Water Relief Valve Refueling Water Storage Tank Reactor Vessel Steam Generator Standby Auxiliary Feedwater Pump Safety Injection Solenoid Operated Valve Service Water
QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Pump and Valve Testing Program DATE PAGE 1.0/1/'87
.4 DF 40 Definitions TAFP VC VCT VH Turbine Driven Auxiliary Feedwater Pump Volume Control Volume Control, Tank Vent Header CAT A VALVE Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
CAT B VALVE Valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.
CAT C VALVE Valves which are self-actuating in response to some characteristic, such as pressure (relief valves) or flow direction {check valves).
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 42 ~ 02 C S
oF 40 Pum and Valve Testin Pro ram PVT 1.0 Sco e and Res onsibilit The inservice testing program defines the testing program for Quality Groups A,
B and C Pumps and Valves in accordance with the requirements of Articles IWP and IWV of Section XI of the Code.
The results of these tests are to assure the operational readiness of pumps and valves.
1.2 1.3 It is.the responsibility of the Ginna Station Results and Test 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 acceptable limits.
PVT 2.0 Code Edition and Testin Interval 2.1 The Inservice Pump and Valve Testing Program for the ten (l0) year period starting January 1, 198l through December 31, 1989 was developed utilizing the 1977 Edition of Section XI of the Code through the Summer 1978 Addenda.
PVT 3.0 Inservice Pum Testin Pro ram 3.1 The Inservice Pump" Testing Program was developed in accordance with the requirements of Article IWP of Section XI of the Code.
This program includes all Quality Group A, B and C pumps which are provided with an emergency power source and are required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident and maintaining the reactor in a safe shutdown condition.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 0F Q0 3.2 The following pumps shall be tested in accordance with Article IWP of Section XI:
3.3 (a) lA Component Cooling (b) 1B Component, Cooling (c) lA Safety Injection (d) 1B Safety Injection (e) 1C Safety Injection (f) lA Residual Heat Removal (g) lB Residual Heat Removal (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) lC Service Water (p) lD Service Water
{g) lC 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'easurement of pump bearing temperatures and there are several reasons why this measurement is either undesirable or inconclusive.
Specifically:
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.
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 tempera-tures this causes an unnecessary extended tempera-ture'transient in the feedwater line.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 oF g0 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 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'emperature will normally only occur if bearing.
failure is imminent.
Finally, test conditions cannot be easily controlled to produce temperature repeatability since readings are subject to a large number of variables such as ambient air temperature, cooling water temperature (where applicable),
location of temperature probe attach-ment, temperature of the fluid pumped and quantity of the fluid pumped.
One or both residual heat removal pumps may be required to be operable, by the plant Technical Specifications, when the average reactor coolant temperature is between 350 degrees F. and 200 degrees F. or the plant is at cold or refueling shutdown.
Typically, in this case, at least one residual heat removal pump will be in operation.
Testing will be performed in accordance with IWP-3400, which, includes operating the pump at reference condi-tions, 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 in-service reactor inspections as well as decay heat removal rate.
'I 1
QUALITY ASSURANCE MANUAL GINNA STATION TITLEi APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 8
oF 40 3.4 The test frequency for the pumps shall be as follows:
a
~
b.
Component cooling water pumps shall be tested monthly.
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 or prior to exceeding 350'F if the time since the last test exceeds one month.
e.
Motor driven auxiliary feedwater
- pumps, turbine driven auxiliary feedwater
- pump, and the standby auxiliary feedwater pumps shall be tested monthly except during cold or refueling shutdowns.
The pumps shall be tested prior to exceeding 5% power if the time since the last test exceeds one month.
Testing of a pump need not be performed if that pump is declared inoperable without the testing.
Service water pumps shall be tested monthly.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
~ 2 ~ 5RC
~9 OF 40 PVT 4.0 Consistent with plant Technical Specifications, specified intervals may be extended by 25% to accommodate normal test schedules.
The total combined interval time for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
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 maintaining 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 4.8 and 4.9, respectively.
Category C Valves are broken down into two categories, Check Valves and Relief Valves, which are in Tables PVT 4.10 and 4.ll, 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 IbV 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 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 func-tional tests shall be verified by the operation of the required system.
A valve which malfunc-tions during stroking will not be considered
I
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 10 oF 40 4.5 4.6 inoperable as defined by Technical Specifica-
- tions, when the malfunction does not prevent the valve from performing its safety function.
Category A and 8 valves operation shall be timed each time they are stroked for the purpose of satisfying the requirements of this program, utilizing switch initiation and the position indicators, which are accessible during plant operation.
During each refueling outage a visual verification shall be made to confirm direct correspondence between valve operators and the position indicators.
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.
I
<2 ~ '52 C TITLE:
DATE QUALITY ASSURANCE MANUAL GINNA STATION 10/1/87 APPENDIX C Pump and Valve Testing Program PAGE 11 DF 40 Category A Valves 4.8 Valve 0
~Te MV Letdown to NRHX 204A CV l-A RCP Seal Injection 304A CV l-B RCP Seal Injection 304B MOV Seal Water Return Isolation 313 CV Charging Line Isolation 370B AOV Letdown Isolation 371 CV Alternate Charging Line 383B AOV RMW to Containment Vessel Stop 508 CV N2 Supply to PRT CV RMW to PRT 528 529 AOV PRT Stop Valve to Gas Analyzer MV PRT to Gas Analyzer 539 546 MV Nitrogen to PRT 547
743 Note Test
~Fre Stroke C/R Leak R
Stroke C/R Leak R
Stroke C/R Leak R
Stroke C/R Leak R
Stroke C/R Leak R
Stroke C/R Leak R
Stroke C/R Leak R
Stroke Q
Leak R
Stroke Q
Leak
.R Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
~12 40 Valve 4 T~e 745 AOV Return From Excess Let-down HX.
Note Tes t Stroke Zeak
~Fre Q
R 749A 749B 750A 750B 759A MOV CCW to A RCP MOV CCW to B RCP CV CC to A RCP CV CC to B RCP MOV Containment Stop CC From Z oop A RCP Stroke Z eak Stroke Z,eak Stroke Z eak
'Stroke Leak Stroke Leak C/R R
C/R R
C/R R
C/R R
C/R R
759B 813 814 820 MOV Containment Stop CC From Z oop B RCP MOV CC Supply to RX Support, Coolers MOV CC Return to RX Support Coolers MV Letdown to NRHX Stroke C/R Zeak R
6 Stroke C/R Leak R
6 Stroke C/R Zeak R
Stroke Leak R
842A 842B 846 853A 853B CV Loop A Accumulator Dump Line Check Valve CV Loop B Accumulator Dump Line Check Valve AOV N
Supply to Accumulators 2
CV Core Deluge Check CV Core Deluge Check 28 28 10 10 10 10 Stroke C/R Leak C/R Stroke.
C/R Leak C/R Stroke Q
Z,eak R
Stroke C/R leak C/R Stroke C/R Leak C/R
QUALITY ASSURANCE MANUAL GINNA STATION TIT LE t APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 13 DF 40 Valve 4
~Te 862A CV 1-A CSP Disch Note Test
~Fre Stroke Q
Leak
, R 862B 867A 867B 870A 870B 877A CV l-B CSP Disch CV Accumulator Dump and SI to Cold Leg Loop B CV Accumulator Dump and SI to Cold Leg Loop A CV 1-A to 1-C SI Pump Disch CV l-B to l-C SI Pump Disch
.CV.
High Safety Injection Z oop B Hot Z,eg 13 13 13 13 11 29 Stroke Q
Leak R
Stroke R
Leak'/R Stroke R
Leak C/R Stroke Q
Leak R
Stroke Q
Zeak R
Stroke Leak 40 Mo.
877B 878F CV High Safety Injection Loop A Hot Z eg CV High Safety Injection Loop B Hot Leg 11 Stroke 29 Leak 40 Mo.
11 Stroke 29 Leak 40 Mo.
878G 878H CV 1-A SI Pump to Cold Z,eg Loop B
CV High Safety Injection Loop A Hot Leg 13 13 11 29 Stroke R
Leak Monthly Stroke Leak 40 Mo.
878J 879 889A 889B CV 1-B SI Pump to Cold Leg Loop A MV SI Test, Line Isolation CV 1-A SI Pump Disch CV 1-B SI Pump Disch 13 13 Stroke Leak Stroke Leak Stroke Leak Stroke Leak R
Monthly Q
R Q
R
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 OF 40 Valve 5
~Te 921 922 923 924 956D SOV Loop A Hydrogen Monitor Inlet SOV Loop A Hydrogen Monitor
.Outlet SOV Loop B Hydrogen Monitor Inlet SOV Loop B Hydrogen Monitor Outlet MV Hot Leg Loop Sample Containment Isolation Note Stroke Leak Q
R Stroke Leak Q
R Stroke Leak Stroke Leak Test
~Fre Stroke Q
Leak R
956E MV PRZR Liquid Space Sample Containment Isolation Stroke Leak 956F MV PRZR Steam Space Sample Containment Isolation Stroke Leak 966A AOV Pressurizer Steam Space Containment Isolation Stroke Leak 966B AOV Pressurizer Liquid Space Containment Isolation Stroke Leak 966C 1003A 1003B 1076A IV-3A 1076B AOV Loop A and B Hot Leg Containment Isolation LCV 1-A RCDT Pump Suction LCV 1-B RCDT Pump Suction MV Hydrogen to "A" Recombiner ll Pilot Containment Isolation SOV Hydrogen to "A" Recombiner 11 Pilot Containment Isolation MV Hydrogen to "B" Recombiner ll Pilot Containment Isolation Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q
R Q
R
QUALITY ASSURANCE MANUAL GINNA STATION TlTLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.15 DF 40 Valve 8
~Te IV-3B SOV 1080A IV-2A SOV IV-2B 'OV 1084A Descri tion Note 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)
Hydrogen to "A" Recombiner ll Main Burner Containment Isolation Hydrogen to "B" Recombiner 11 Pilot Containment Isolation Test Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak
~Fre IV-5A 1084B IV-5B 1554 1556 1557 1559 SOV SOV Hydrogen to "A" Recombiner 11 Main Burner Containment Isolation Hydrogen to "B" Recombiner 11 Main Burner Containment Isolation Hydrogen to "B" Recombiner 11 Main Burner Containment Isolation D Recirc.
Fan Air Sample 11 Isolation D Recirc.
Fan Air Sample ll Isolation A Recirc.
Fan Air Sample 11 Isolation A Recirc.
Fan Air Sample 11 Isolation Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak 1560 MV A
Sc D Recirc.
Fan Air Sample Return Line Isolation 11 Stroke Leak-R
QUALITY ASSURANCE MANUAL GINNA STATION TITl.E:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 16 o"
40 Valve 5 T~e 1562 MV A 6 D Recirc.
Fan Air Sample Return Line Isolation Note Test
~Fre Stroke Leak R
1563 1565 1566 MV B Recirc.
Fan Air Sample 11 Isolation MV B Recirc.
Fan Air Sample 11 Isolation MV B Recirc.
Fan Air Sample 11 Return Line Isolation Stroke K,eak Stroke Leak Stroke I eak 1568 1569 MV B Recirc.
Fan Air Sample Return Line Isolation MV C Recirc.
Fan Air Sample Isolation 11 Stroke Leak R
11 Stroke Leak R
1571 1572 1574 1596 1597 1598 1599 1655 17l3 MV C Recirc.
Fan Air Sample Isolation MV C Recirc.
Fan Air Sample Return Kine Isolation MV C Recirc.
Fan Air Sample Return Line Isolation MV Radiation Monitor Supply AOV Radiation Monitor Supply AOV Radiation Monitor Exhaust.
AOV Radiation Monitor Exhaust MV RCDT to Gas Analyzer CV N2 to RCDT 11 Stroke Leak R
Stroke Leak R
Stroke Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Keak R
Stroke Q
Leak R
QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 17 oF 40 Valve 8
~Te Descri tion Note Test
~Fre 1721 AOV Suction line to RCDT Stroke Q
Leak R
1723 1728 1786 1787 1789 1793 1819A 1819B 1819C 1819D 1819E 1819F 1819G 4601 AOV A Containment Sump Disch to Waste Holdup Tank AOV A Containment Sump Disch to Waste Holdup Tank AOV RCDT to VH Isolation AOV RCDT to VH Isolation AOV RCDT to GA Containment Isolation MV N2 to RCDT Isolation MV Containment Pressure Transmitter 945 Isolation MV Containment Pressure Transmitter 946 Isolation MV Containment Pressure Transmitter 947 Isolation NV Containment Pressure Transmitter 948 Isolation Containment Pressure Transmitter 949 Isolation Containment Pressure Transmitter 9SO Isolation MV Containment Pressure Transmitter 944 Isolation CV 1A Service Water Pump Discharge Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
21 Stroke C/R Leak R
21 21 Stroke C/R Leak R
Stroke C/R Leak R
21 Stroke C/R Leak R
21 Stroke C/R Zeak R
31 Stroke Q
31 Leak R
Stroke Leak R
21 Stroke C/R Leak R
21 Stroke C/R Zeak R
QUALITY ASSURANCE MANUAL
. GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
'18 OF 40 Valve 4 T~e Descri tion Note Test
~Fre 4602 4603 4604 CV CV CV 1B Service Water Pump Discharge 1C Service Water Pump Discharge 1D Service Water Pump Discharge 31 31 31 31 31 31 Stroke Leak Stroke Leak Stroke Leak Q
R Q
R 5129 5392 AOV Construction Fire Service 11 Water Containment Isolation Instrument Air to Contain-19 ment Isolation Stroke Leak Stroke Leak
\\0 R
R R
5393 CV Instrument Air to Containment Isolation 19 Stroke Leak R
R 5701 5702 5733 5734 5735 5736 5737 5738 6151
.MV.
A-S/G Blowdown Isolation MV B-S/G Blowdown Isolation MV A-S/G Sample Isolation MV B-S/G Sample Isolation AOV "A" S/G Blowdown Sample Isolation AOV "B" S/G Blowdown Sample Isolation AOV "B" S/G Blowdown Isolation AOV "A" S/G Blowdown Isolation MV Auxiliary Steam Supply to Containment Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Q
R Q
R Q
'R Q
R Q
R Q
R Q
R Q
R
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.19 oF 40 Valve 0
~Te Note Test grec[
6152 MV Condensate Return from Containment Stroke Leak 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 Stroke Leak Stroke Leak 11 Stroke Leak R
11 Stroke Leak R
11 Stroke Leak R
ll Stroke Leak R
7445 7448 7452 AOV Containment Air Test Vent/
Mini-Purge supply MV Isolation Valve from Containment to Local Pressure Indicator for Containment Air Test MV Isolation Valve from Containment to Local Pressure Indicator for Containment Air Test Stroke Q
Leak 11 Stroke Leak R
11 Stroke Leak R
7456 7478 MV Isolation Valve from Containment to Local Pressure Indicator for Containment Air Test AOV Containment Air Test Vent/
Mini-Purge Supply 11 Stroke Leak R
Stroke Q
Leak These valves must be leak tested every 6 months for the first two years following their installation (reference Section 4.4.2.4a of Ginna Technical Specifications).
4 I
QUALITY ASSURANCE MANUAL GINNA'TATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/'1/'87
.2O oP 4O 7970 AOV Valve O
~Te Containment Depressuri-zation Valve Mini-Purge Exhaust Note Test Freq Stroke Q
Leak R
7971 8418 8419 8623 AOV AOV CV CV Containment Depressuri-zation Valve Mini-Purge Exhaust Demin. Water to Contain-ment Isolation Demin. Water to Contain-ment Isolation Nitrogen to Accumulators Isolation Stroke Q
Leak R
ll Stroke Leak R
11 Stroke Leak R
ll Stroke Leak R
9227 9229 4.9 AOV Fire Service Water Containment Isolation CV Fire Service Water Containment Isolation Category B Valves 11 Stroke Leak R
11 Stroke Leak R
Valve 4
~Te 014 017 RCV Component Cooling Surge Tank Vent RCV Aux Bui1ding GDT Release Note Test
~Fre Stroke Q
Stroke Q
081 082 083 084 APV Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Stroke Q
Stroke Q
Stroke Q
Stroke Q
0
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 21 0F 40 085 APV 086 Valve 4 T~e Control Room Ventilation Damper Control Room Ventilation Damper Note Test
~Fre Stroke Q
Stroke Q
112B LCV Emergency Makeup RWST to Charging Pump Stroke Q
ll2C 427 430 LCV VCT Outlet AOV Letdown From Loop B PORV Pressurizer Power Operated Relief 16 Stroke Q
Stroke C/R Stroke C/R 431C PORV Pressurizer Power Operated Relief 16 Stroke C/R 515 MOV Pressurizer PORV Block Valve 23 Stroke Q
516 MOV Pressurizer PORV Block Valve 23 Stroke Q
590 591 592 593 624 625 626 700 701 SOV Reactor Head Vent SOV Reactor Head Vent SOV Reactor Head Vent SOV Reactor Head Vent, HCV l-B RHR HX Outlet HCV 1-A RHR HX Outlet FCV RHR Loop Return Recirc.
MOV RHR Inlet Isolation From Loop A MOV RHR Inlet Isolation From Loop A 32 Stroke R
32 Stroke R
32 Stroke R
32 Stroke R
26 Stroke C/R 26 Stroke C/R Stroke Q
Stroke C/R Stroke C/R
U
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
~22 oF 40 Valve 0 T~e 704A 704B 720 MOV Suction 1-A RHR Pump f
MOV Suction l-B RHR Pump MOV BHR Return Isolation to Loop B Note Test
~Fre Stroke Q
Stroke Q
Stroke C/R 721 738A 738B MOV RHR Return Isolation to Loop B MOV CC to 1-A RHR HX MOV CC to 1-B RHR HX 8
Stroke C/R Stroke Q
Stroke Q
825A 825B MOV SI Pump Suction From RWST 9
Stroke C/R MOV SI Pump Suction From RWST 9
Stroke C/R 826A 826B MOV SI Pump Suction From BA Tank MOV SI Pump Suction From BA Tank 25 Stroke Q
25 Stroke Q
826C 826D 836A MOV HCV SI Pump Suction From BA Tank SI Pump Suction From BA Tank Spray Additive Tank Dis-charge 25 Stroke Q
25 Stroke Q
17/24 Stroke Q
836B 850A 850B 851A 851B HCV Spray Additive Tank Dis-charge MOV Sump B to RHR Pumps MOV Sump B to RHR Pumps MOV Sump B to RHR Isolation MOV Sump B to RHR Isolation 17/24 Stroke Q
24 Stroke Q
24 Stroke Q
30 30
QUALITY ASSURANCE MANUAL GINNA STATION TlTLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 23 OF 40 Valve 5
~Te Note 852A MOV RHR Pumps to Reactor Vessel 18 Test
~Fre Stroke C/R 852B 856 857A MOV NOV NOV RHR Pumps to Reactor Vessel 18 RWST to RHR Pumps 9
1B RHR HX to CS and SI 27 Pump Isolation Stroke C/R Stroke C/R Stroke C/R 857B 857C MOV MOV 1A RHR HX t,o CS and SI Pump Isolation 1A RHR HX to CS and SI Pump Isolation 27 Stroke C/R Stroke C/R 860A 860B 860C 860D'71A MOV 1-A to 1-C SI Pump Discharge MOV 1-A CSP Discharge MOV 1-A CSP Discharge MOV 1-B CSP Discharge MOV 1-B CSP Discharge 24 Stroke Q
24 Stroke
'Q 24 Stroke Q
24 Stroke Q
24 Stroke Q
871B 875A 875B 876A NOV MOV MOV MOV l-B to 1-C SI Pump Discharge CS Pump Discharge to lA Charcoal Filter Deluge CS Pump Discharge to 1A Charcoal Filter Deluge CS Pump Discharge to 1B Charcoal Filter Deluge 24 Stroke Q
Stroke Q
Stroke Q
Stroke Q
876B 896A 896B MOV CS Pump Discharge to 1B Charcoal Filter Deluge MOV RWST to CS and SI Pumps MOV RWST to CS and SI Pumps Stroke Q
Stroke C/R Stroke C/R
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.24 D"
40 Valve 0
~Te 897 898 AOV SI Pump Recirc. to RWST AOV SI Pump Recirc. to RWST Note Test
~Fre 27 Stroke C/R 27 Stroke C/R 951 AOV Pressurizer Steam Space Sample 33 953 AOV Pressurizer Liquid Space 33 Sample 955 959 AOV AOV B<< Loop Hot, Leg Sample RHR Loop Sample 20 Stroke Q
Stroke C/R 1811A 1811B 1815A 1815B 3504A MOV C-SI Pump Suction From RWST 24 MOV Main Steam to TAFP From 1-B S/G Stroke Q
Stroke Q
Reactor Coolant Drain Tank 11 Isolation to RHR System Reactor Coolant Drain Tank ll Isolation to RHR System MOV C-SI Pump Suction From RWST 24
~
Stroke Q
3505A 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 MOV TAFP Discharge MOV MOV Cross Over Valve For MAFP l-A MAFP Discharge MOV l-B MAFP Discharge MOV Cross Over Valve For MAFP Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
QUALITY ASSURANCE MANUAL GINNA STATION TlTLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.25 oF 40 Valve I T~e 4013 TAFP Service Water Supply Isolation Note Test Stroke Free[
4027 4028 MOV MOV 1-A MAFP Service Water Isolation 1-B MAFP Service Water Isolation Stroke M
Stroke M
4291 4297 4298 43 04.
AOV 1-A MAFP Recirculation Control A'OV TAFP Recir. Line AOV TAFP Discharge to 1-A S/G AOV TAFP Discharge to 1-B S/G Stroke Stroke Stroke Stroke 4310 AOV 1-B MAFP Recirculation Control Stroke M
4561 4562 4609 4613 4614 4615 4616 AOV Containment Vent Recirc.
Fans Discharge Flow Con-trol AOV Containment Vent Recirc.
Fans Discharge Flow Con-trol Bypass MOV lAl Screen House SW Isolation MOV 1B2 Turbine Building SW Isolation MOV lAl Turbine Building SW Isolation MOV 1Bl Aux. Building SW Isolation MOV lAl Aux. Building SW Isolation Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 26 D"
40 Valve 0 T~e Note
- Test,
~Fze 4627 4628 4629 4630 4635
'4636 4641 4642 4643
- 4644, MV Service Water to A Fan Cooler Isolation MV Service Water to B Fan Cooler Isolation MV Service Water from A Fan Cooler Isolation MV Service Water from B Fan Cooler Isolation MV Reactor Compartment Cooling Unit A Inlet Isolation MV Reactor Compartment Cooling Unit A Outlet Isolation 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 Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
4663 4664 4670 MOV lA1 Air Cond. Chillers SW Isolation MOV 1A2 Turbine Building SW Isolation MOV 1B1 Turbine Building SW Isolation Stroke Q
Stroke Q
Str'oke Q
4733 MOV 1A2 Air Cond. Chillers SW Stroke Q
Isolation 4734 MOV 1B2 Aux. Build.
SW Isolation
Stroke Q
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 27 DF 40 Valve 4 T~e Note 4735 MOV lA2 Aux. Build.
SW Isolation-Test
~Fre Stroke Q
4757 4758 4780 5171 5869 587l 5872 5873 5874 5875
'876 5879 MOV MOV Reactor Compartment Cooling Unit B Inlet Isolation Reactor Compartment Cooling Unit, B Outlet Isolation 1A2 Screen House SW Isolation Turbine Building Fire Water Loop Supply Isolation Containment, Purge Supply.
.Isolation Containment Post Accident Filter Damper Containment Post Accident Filter Damper Containment Post Accident Filter Damper Containment Post Accident Filter Damper Containment Post Accident Fil'ter Damper Containment Post Accident Filter Damper Containment Purge Exhaust Isolation 22 22 Stroke Q
Stroke Q
Stroke Q
.Stroke Q
Stroke R
Leak Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Leak 9629A MOV 1C SAFP Service Water Isolation Stroke Q
9629B MOV 1D SAFP Service Water Isolation Stroke Q
- See Note 22
QUALITY ASSURANCE MANUAL GINNA STATION TITLEs APPENDIX C Pump and Valve Testing Program DATE PAGE 10//'1/ 87 28 DF 40 Valve 4
~Te Note Test
~Fre
~
~
9701A 9701B 9703A 9703 B'704A 9704B 9710A 9710B MOV 1C SAFP Discharge MOV 1D SAFP Discharge MOV SAFP Cross Over MOV SAFP Cross Over MOV 1C SAFP Containment Isolation MOV 1D SAFP Containment Isolation AOV 1C SAFP Recirc. Control AOV 1D SAFP Recirc. Control Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
4.10 Category C Check Valves Valve 4
~Te Descri tion Note Tes t
~Fre 710A 710B 723A 723B 847A CV l-A RHR Pump Discharge CV l-B RHR Pump Discharge CV 1-A CC Pump Discharge CV l-B CC Pump Discharge A-CSP From Spray Additive Tank to Eductor Stroke Stroke Stroke Stroke Stroke Q
847B B-CSP From Spray Additive Tank to Eductor Stroke 854 866A 866B CV RWST to RHR Pump Check CV CS Pump l-A to Charcoal Filter Deluge CV CS Pump l-B to Charcoal Filter Deluge 12 Stroke Q
Stroke C/R 1
Stroke Q
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 29 oF 40 Valve 4 T~e 3516 3517 3998 4000C 4000D 4003 4004 4009 4010 4014 4016 4017 4023 5133 5136 9627A 9627B 9700A 9700B 9705A 9705B CV 1B Main Steam Isolation CV lA Main Steam Isolation CV TAFP Discharge Check CV lA MAFP Discharge Check CV lB MAFP Discharge Check CV TAFP to S/G lA CV TAFP to S/G 1B CV lA MAFP to S/G 1A CV lB MAFP to S/G 1B CV.
TAFP Suction CV lB MAFP Suction CV lA MAFP Suction CV TAFP Recirculation CV Diesel Fire Pump Disch.
CV Motor Fire Pump Discharge CV 1C SAFP SW Suction CV 1D SAFP SW Suction CV 1C SAFP Discharge CV 1D SAFP Discharge CV 1C SAFP to S/G 1A CV 1D SAFP to S/G 1B Note 14 Test
~Fre Stroke R
Stroke R
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke M
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
QUALITY ASSURANCE NANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 30 D"
40 4.11 Category C Relief Valve Valve 4 T~e Note Test F~ec[
203 209 RV RV Letdown High Pressure Safety Relief Letdown Low Pressure Safety Relief 15 15 434 732 RV Pressurizer Safety Relief 15 RV Pressurizer Safety Relief 15 RV CC Surge Tank Relief 15 744 755A 755B RV RV RV CC "From Excess Letdown Heat Exchanger CC From A RCP Thermal Barrier CC From B RCP Thermal Barrier 15 758A 758B RV CC From A-RCP Oil Coolers 15 RV CC From B-RCP Oil Coolers 15 818 861 887 1817 RV RV RV RV CC From Reactor Support 15 Coolers 1-B CS Pump Suction Relief 15 SI Test Line Relief Valve 15 Inside Containment Alternate Suction From RHR Pump to C SI Pump 3508 3509 3510 RV 1-B S/G PRV RV 1<<A S/G PRV RV l>>B S/G PRV 15 15 15
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.31 oP 40 Valve 0
~Te Note Test F~ec[
3511 3512 3513 3514 3515 4653 4654 4657 5134 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 15 15 15 15 15 15 15 15 15 5135 RV Motor Fire Pump Disch Relief 4.12 Inservice Valve Testing Notes 15 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 val've 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.
0 4
cr
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 32 0F 40 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 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'est 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 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.
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 721 cannot be stroked during normal plant operation on a quarterly basis because there is an interlock system which prevents these
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program OATE PAGE 10/1/87 33 oP 40 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 re fue 1ing outages
~
Note Note 1 0 Note l1 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 s afety inject ion and residual heat removal pumps
~
These valves will be stroked at cold shutdowns and re-fueling outages
~
Valves 853A and 853B cannot be stroked during normal plant operation on a quarterly basis because this test requires pressurizing the RHR system to the primary system operation pressure These valves will be stroked't co 1d shutdown and 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 1 50 psid Technical Specification 4 ~ 3
~ 3
~ 4 defines the allowable leakage rates
~
Valves 820,
- 877A, 877B,
- 878F, 878H,
- 1076A, 1076B,
- 1080A, 1084A,
- 1084B, IV"3A, IV-3B IV-SA, IV<<5B, IV-2A, IV-2B, 1554,
- 1556, 1557,
- 1579, 1560,
- 1562, 1563,
- 1565, 1566,
- 1568, 1569,
- 1571, 1S72,
- 1574, 1793, 181 1A, 181 1B 5129 6151 6152 6166 6175 I 7141 g
QUALITY ASSURANCE NANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.34 0F 40
- 7226, 7443,
- 7444, 7448,
- 7452, 7456,
- 8418, 8419,
- 8623, 9227 and 9229 are con-sidered passive valves which are not required to change position to acccomplish their specific function.
Stroking these valves would serve no useful function and will therefore not be done as per IWV-3700-1.
Note 12 Valve 866A cannot be stroke tested during normal plant operation on a quarterly basis because this test would result in a substantial radiation exposure to test personnel.
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-pressuriration.
Leakage testing of check valves
- 867A, 867B, 878G and 878J shall be accomplished prior to criticality, except for low power physics testing, following (1) refueling, (2) cold shutdown, and (3) maintenance, repair or replacement work on the valves.
Leakage may be measured indirectly from the performance of pressure indicators, system volume measurements or by direct measurement.
Check valves 878G and 878J shall also be tested for leakage following each safety injection flow test.
Minimum test. differential shall be greater than 150 psid.
Technical Specification 4.3.3.4 defines the allowable leakage rates.
QUALITY ASSURANCE NANUAL GINNA STATION TITLE>
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.35 oP 40 Note 14 - Valves 3516 and 3517 cannot be stroked during normal plant operation on a quar-terly basis because they are the main steam isolation valves.
These valves are stroked during each plant refueling.
Note 15 Category C.Relief Valves shall be tested in accordance with the extent and fre-quency requirements of Paragraph IWV-3510 of Article IWV of Section XI of the Code.
Note l6 - 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:
(3)
'(4)
Note 17 Addi with Full stroke exercising during cool down prior to achieving water solid condition in the pressurizer and during cold shutdown prior to heat up o
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.
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.
Technical specification 4.16.la and 4.16.1c delineate additional re-quirements for operability verifi-cation of the PORV actuation channel and valve position.
tional stroking will be consistent Technical Specifications.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
. 36 OF 40 Note 18 Valves 852A and 852B cannot be stroked during normal plant operation. as these
- valves, when cycled, could subject the Residual Heat Removal System to a pressure in excess of its design pressure.
These valves will be stroked at cold shutdowns and refueling outages.
Note 19 Stroking Valves 5392 and 5393 during operation and cold shutdown would inter-rupt instrument air to containment and be disruptive to air operated valves inside.
These valves will be stroked at, refueling outages.
20 Valve 959 is normally closed and in the
'ontainment isolating position during normal operation.
These valves will be stroked at cold shutdown and refueling outage s.
'Note Note 21 22 Valves 1819A, B,
C, D, E, F and G cannot be stroked during normal plant operation a s this tes t would interrupt containment pres sure monitoring transmitters from performing their intended function.
These valves will be stroked at cold shutdown and refueling outages.
Category B valves 5869 and 5879 are used only for refueling integrity, and need to be stroked qnly when the flanges are removed.
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 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.
4
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87 42 ~ 52 C 37 oF 40 Note 26As per Technical Speci fications 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 degrade the injection phase of the SI pumps.
- However, these valves shall be stroked at cold shutdown and refueling outages.
Note 28 Check valves 842A and 842B (accumulator check valves) cannot and should not be exercised during plant operation.
Exercising of these valves requires the reactor coolant system pressure to be reduced to below accumulator pressure.
Therefore testing of these valves 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 achiev-ing normal reactor coolant system pressure and prior to reactor criticality.
Testing will be performed by either (1) closing each accumulator motor operated discharge valve, pressurizing 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.
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE 10/1/87 PAGE 38 OP 40 Therefore, the test acceptance criterion shall be that of Technical Specification 3.1.5.
Note 29 Valves
- 877A, 877B, 878F and 878H are currently not listed in our valve test
- program, however, a pair of these valves in each hot leg high head safety injec-tion line (877A nd 878F in loop B hot leg and 877B and 878H in loop A hot leg) together form one of the two pressure boundaries required to be tested by Technical Specification 4.3.3.3.
Because these valves are normally closed and the piping contains motor operated valves (MOV's) which are also closed and deener-
- gized, the check valves will not move with the possible exception of when the MOVs are required to be opened to test the check valves.
- Thus, once tested, the check valves will remain closed.
An NRC order dated April 20, 1981 established an appropriate test frequency for these valves to be once every 40 months or after each opening of the MOVs.
These valves are listed as passive valves in our valve testing program with testing required to meet Technical Specification 4.3.3.3.
Note 30Valves 851A and 851B are not required to perform a post-accident
- function, and therefore are not qualified to operate in the post-accident containment environment.
Since the valves are normally open and in their post accident position, stroking of these valves will not be required.
Note 31Valves 4601,
- 4602, 4603 and 4604 shall be leak tested each refueling outage using a back flow test method to determine if back flow to the corresponding idle pump is minimal (i.e.
2 psid as monitored by pressure change in the discharge header between pump discharge isolated
QUALITY ASSURANCE MANUAL GINNA STATION TITLE:
APPENDIX C Pump and Valve Testing Program DATE PAGE 10/1/87
.39 oP 40 and unisolated).
Quarterly valve stroking shall be limited to verifying
- that, a normally closed valve will open concurrent with the start of an idle pump.
An open check valve for a pump already in service will be deemed operable without having to stop and restart the pump since the open valve is considered to be performing its normal safety function.
Note 32 - Valves 590,
- 591, 592 and 593 shall not be stroked quarterly as an unplanned pressure transient could result from a leaky alternate isolation valve.
These valves will be stroked at, refueling outages.
Note 33 - Sampling valves 951 and 953 need not be stroked as part of this program as they are not required to perform a safety function.
Although considered to be part of the reactor coolant system boundary, 10CFR50.55a(c)(2) specifies that compon-ents which are connected to the reactor coolant system and are part of the boundary as defined in 50.2(v) of this part need not meet the requirements of paragraph (c)(1) of this section, provided:
In the event of postulated failure of the component during normal reactor operation, the reactor can be shut down and cooled down in an orderly
- manner, assuming makeup is provided by the reactor coolant makeup system.
The valves are exercised during routine sampling operations.
PVT 5.0 Records 5.1 Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article IWP-6000 of Section XI of the Code.
pt
TITLE:
DATE 42 52C QUAI ITY AS SURANCE MANUAZ GINNA STATION APPENDIX C Pump and Valve Testing Program PAGE 10/1/87
.40 DF 40 5.2 Records for the Inservice Valve Testing Program shall be developed and maintained in accordance with Article IWV-6000 of Section XI of the Code.
VQ +V