ML17263A623

Rev 2 to QA Manual App C Inservice Pump & Valve Testings Program for 1990-1999.

ML17263A623
Person / Time
Site:	Ginna
Issue date:	03/02/1994
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
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ML17263A624	List: ML17263A623 ML17309A541
References
NUDOCS 9404190377
Download: ML17263A623 (208)

Text

QUALITY ASSURANCE MANUAL REV. 2 AGE 1 oF 14 GINNA STATION EImmrvE DATE: December 1, 1993 ROCHESTER GAS AND ELECTRIC SIGNATURE DATE PREPARED BY:

APPENDIX C QUALITY ASSURANCE INSERVICE PUMP AND VALVE TESTING REVIEW PROGRAM NUCLEAR FOR THE 1990-1999 SAFETY 4 INTERVAL LICENSING MANAGER, MECHANICAL ENGINEEIUNG Table of ontents 1.0 Introduction 2.0 References 3.0 Terms and Definitions 4.0 General Requirements 5.0 Pump Testing Program 5.1 Scope 5.2 Exemptions 5.3 Test Requirements 5.4 Pump Testing Program Plan Description 6.0 Valve Testing Program 6.1 Scope 6.2 Exemptions 6.3 Test Requirements 6.4 Valve Testing Program Plan Description 7.0 Records 8.0 System Index Attachment A: Pump Testing Program Plan Rev. 2 Attachment B Valve Testing Program Plan Rev. 2 Attachment C: Cold Shutdown Justifications Rev. 2 Attachment D Relief Requests Rev. 2

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TlTLE: REV.

QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL GINNA STATION I

NS ERV CE PUMP AND VALVE TEST NG I PAoE PROGRAM FOR THE 1990-1999 INTERVAL oF 14

1.0 INTRODUCTION

This Appendix to the Ginna Station Quality Assurance Manual establishes and defines the Inservice Pump and Valve Testing Program for the ten year interval from January l, l990 through December 3l, 1999. This program has been developed as required by Title 10 Code of Federal Regulations Part 50 Paragraph 50.SSa(g), in accordance with the ASME Boiler and Pressure Vessel Code - Section XI - "Rules for Inservice Inspection of Nuclear Power Plant Components".

1.2 The purpose of this Inservice Testing Program is to verify operational readiness of those pumps and valves whose function is required for safety. It is not intended to place the R.E. Ginna plant in a degraded safety condition for the purpose of conducting system or component tests. Therefore, as normally viewed for Code compliance, testing of a safety train will not be performed when the redundant train is out of service. Instead, equipment will be positioned to provide the necessary safety lineup. Pumps and valves included in the program, are those in systems or portions of systems (Section 8.0 - System Index) which are required to accomplish specified safety functions or tasks, as identified within various plant safety analyses.

1.3 In addition to those pumps and valves required to be tested by the Code, other components are included in the program from a good engineering and management practice standpoint. These components are identified with an asterisk (*) and need not be tested to specific Code criteria.

1.4 The ~IST Program substantially augments (but does not'ffect, replace, or supersede) the pump and valve surveillance program required by Technical Specifications. Technical Specification requirements associated with pump, and valve surveillances shall continue to be implemented as specified.

A QUALITY TlTLE: APPENDIX C REV.

ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING GINNA STATION PROGRAM FOR THE PAGE 1990- 1999 INTERVAL 3 oP 14

2.0 REFERENCES

2.1 ASME Boiler & Pressure Vessel Code - Section XI Division 1, "Rules for Inservice Inspection and Testing of Nuclear Power Plant Components", 1986 Edition (hereaf'ter referred to as the Code) 2.2 ASME/ANSI OMa-1988, "Operation and Maintenance of Nuclear Power Plants" Parts 6 and 10.

2.3 ASME/ANSI OM-1987, "Operation and Maintenance of Nuclear Power Plants" Part 1.

2.4 Ginna Station Quality Assurance Manual 2.5 Ginna Station Technical Specifications 2.6 Ginna Station Updated Final Safety Analysis Report (UFSAR) 2.7 NUREG-0821, Systematic Evaluation Program (SEP) topics 2.8 Title 10 Code of Federal Regulations Part 50 Para.

50.55a, Codes and standards.

2.9 USNRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, April 3, 1989.

2. 10 Minutes of the Public Meetings on Generic Letter 89-04, October 25, 1989.

2.11 Supplement to Minutes of the Public Meetings on Generic Letter 89-04, September 26, 1991.

3.0 TERMS AND DEFINITIONS 3.1 Obturator - Valve closure member (e.g., disk, gate, plug, ball, etc.)

3.2 Operational readiness - the ability of a pump or valve to perform its intended function when required.

3.3 Reference values - one or more values of test parameters measured or determined when the equipment is known to be operating acceptably.

QUALITY 8 EV.

APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL F 3.4 Active valves - valves required to change obturator position to accomplish a safety function.

3.5 Passive valves - valves that maintain obturator position and are not required to change obturator position to accomplish required safety functions.

4.0 GENERAL RE UIREMENTS 4.1 Inservice 'shall pump and performed in accordance 'ithtesting valve ASME Boiler and Pressure Vessel Code - Section XI Division 1, be Subsections IWP E IWV to the extent practicable within limits of design, geometry and materials of construction of the components. The guidelines of the ASME/ANSI OM Code, NRC Generic Letter 89-04 and the minutes of the public meetings regarding Generic Letter 89-04 have also been used in the development of this program.

4.1.1 Code requirements related to Enforcement Authority, Authorized Inspection Agency, Authorized Nuclear Inspector Supervisors and Inspectors are excluded, as the R.E. Ginna Nuclear Power Plant is located in the state of New York which has not endorsed ASME Codes. The Ginna Station Quality Assurance Program shall continue to be used in lieu of Code administrative functions to verify implementation. However, ANII services from the Hartford Steam Boiler Inspection and Insurance Company will be used for the review of this program and documentation generated as a result of this program.

4.1.2 Where a Code test requirement is determined to be impractical, the Program Plan identifies applicable Relief Requests or Cold Shutdown Justifications which describe the bases for determination and alternative test methods and/or frequencies.

4.1.3 Inservice testing requirements shall be in accordance with the Code edition and addenda specified in para. 2.1.

TITLE: REV.

QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 5 " 14 4.2 Implementation of the program shall be controlled in accordance with the Ginna Station Quality Assurance Program, including but not limited to responsibilities, procedures, specifications, personnel qualifications, test performance and evaluation, and records.

4,3 Changes to this program, in accordance with the guidance provided by Reference 2.10, should not be implemented prior to review and approval by the Nuclear Regulatory Commission.

The program and/or implementing procedures shall be revised as necessary following applicable changes to Technical Specifications, or plant modifications .

4.5 If the revised program conflicts with Technical Specifications, an amendment of Technical Specifications shall be submitted to eliminate the conflict.

5.0 PUMP TESTING PROGRAM 5.1 Sco~

The Inservice Pump Testing Program includes all safety related centrifugal and . positive displacement type pumps that are provided with an emergency power source, and are not exempt by paragraph 5.2, and which function to:

a. mitigate the consequences of an accident or,

b. shutdown the reactor to a cold shutdown condition.

5.2 Exem ions The following are exempt from requirements of this program:

a ~ pumps that are supplied with emergency power solely for operating convenience.

TITLE: REV.

QUALITY APPENDIK C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL OF

b. drivers of pumps, except where the pump and driver form an integral unit and the pump bearings are in the driver.

5.3 T t Re irements 5.3.1 Inservice pump tests shall be conducted in accordance with Article IWP-3000 of the Code, unless specific relief is granted by the Commission.

5.3.2 Inservice pump tests shall be conducted nominally every three months during normal plant operation.

5.3.3 Inservice pump test intervals may be extended by 25% to accommodate normal test schedules. The total combined interval for any three consecutive tests shall not exceed 3.25 times the specified interval.

5.3.4 For a pump in a system declared inoperable or not required to be operable, the test schedule need not be followed. Within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> prior to placing the system in an operable status, the pump shall be tested and the test schedule resumed.

5.3.5 After a pump has been replaced, or when pump repairs or maintenance may have affected any reference value, the pump shall be tested prior to declaring it operable to determine new reference values or reconfirm previous values.

5.3.6 With the exception of measuring bearing temperatures, pump parameters that shall be measured or observed during testing shall be consistent with the guidelines of Article IWP-3000 as identified in the. Pump Program Plan (Attachment A) . Relief Request No. PR-1 provides the bases for excluding bearing temperature measurements.

5.3.7 All test data shall be analyzed within 96 hours after completion of a test, however when data is recorded which exceeds the Required Action range, the pump shall immediately be declared inoperable.

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QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVI CE PUMP AND VALVE TESTING p~g~

GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 7 " 14 5.4 Pum Testin Pro ram Plan Descri tion Pumps that are required to be tested for the program are identified in Attachment A - Pump Testing Program Plan. The plan is organized as a table to provide the following information:

a ~ System - plant system of which the pump is a component.

b. Pump ID - pump identification number.

C. Drawing (Dwg) - Piping and Instrumentation Diagram (PE ID) where the pump is located (RGEE Drawing Number 33013 series) .

d. Coordinates (Coor) - PAID coordinates.

e. Safety Class - designated safety class of the pump (SSC = safety significant, NC non-safety).

Frequency (Freq) - test frequency

g. Measured Parameters - these columns show applicable pump testing parameters that shall be measured. When an "X" is shown in a particular column, that parameter shall be measured or observed during inservice pump testing in accordance with the Code. If alternate testing is planned or if a test is being waived, the applicable pump relief request (PR) number will be shown.

Measured Parameters include the following:

Pump Speed N Inlet Pressure Pi Differential Pressure Pd Flow Rate Qf Vibration Amplitude V Bearing Temperature Tb Lube Oil Level/Pressure L

TITLE: R EV.

QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 8 oF 14 6.0 VALVE TESTING PROGRAM 6.1 ~Sco e The Inservice Valve Testing Program includes all safety related valves that are not exempt by paragraph 6.2, and which function to:

a ~ mitigate the consequences of an accident or,

b. shutdown the reactor to a cold shutdown condition or, C. provide overpressure protection to a system or component.

6.2 Exem tions The following are exempt from requirements of this program:

a ~ Maintenance Valves - valves that are used only to isolate components to perform maintenance.

b. Operating Convenience Valves - valves used only for operating convenience, such as manual vent, drain, instrument and test valves.

C. System Control Valves - valves such as pressure regulating, flow control and manual throttle valves.

d. External Control and Protection Systems valves in systems responsible for sensing plant conditions and providing signals for valve operation.

'e. Thermal Reliefs - valves that provide overpressure protection for a component that can be isolated for maintenance during operation.42-528 TITLE: REV.

QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL GINNA STATION I

NSERV CE PUMP AND VALVE TEST NG I PAgE PROGRAM FOR THE 1990-1999 INTERVAL 9 14 6.3 Test Re irements 6.3.1 Inservice valve tests shall be conducted in accordance with Article IWV-3000 of the Code unless specific relief is granted by the Nuclear Regulatory Commission.

6.3.2 Inservice valve tests shall be conducted nominally every three months during normal plant operation.

6.3.3 Inservice valve test intervals may be extended by 25% to accomodate normal test schedules. The total combined interval for any three tests shall not exceed 3.25 times the specified intervals.

6.3.4 Valve testing that is specified in Attachment B to, be conducted during cold shutdowns, shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown (as defined in plant Technical Specifications), and continue until all testing is 'complete or the plant is ready to xeturn to power. However, not required to keep the plant in cold shutdown in it is order to complete all cold shutdown testing. Any testing not completed at one cold shutdown due to outage duration, shall commence and continue as above during any subsequent cold shutdown that may occur before the next refueling outage to meet the specified testing frequency.

6.3.5 For extended outages, testing need not commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that all valves required to be tested. during cold shutdown prior to plant startup.

will be tested 6.3.6 For cold shutdown intervals of less then three months, testing is not required unless three months have passed since the last cold shutdown test.

6.3.7 All valve testing required to be performed during a refueling outage shall be completed prior to returning the plant to operation.

QUALITY REV.

APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 10 " 14 6.3.8 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 returning the system to operable status, exercising tests shall be conducted and test schedules resumed.

6.3.9 When a valve or its control system has been replaced or repaired or has undergone maintenance that could affect its performance, and prior to declaring the valve operable, it shall be retested to demonstrate that the performance parameters which could be affected by the replacement, repair or maintenance are within acceptable limits.

6.3.10 Containment Isolation Valves shall be tested in accordance with 10CFR50 Appendix J (LT-J) and controlled in accordance with the Local Leak Rate Testing Program as described in Technical Specifications.

6.3.11 Those valves which perform both a containment isolation function and a pressure isolation function shall be tested to both 10CFR50 Appendix J and IWV requirements of the Code.

6.3.12 Relief Test (RT) - relief valves shall be tested in accordance with ASME/ANSI OM - 1987 Part 1, to verify set pressure and seat tightness.

6.3. 13 Exercising check valves to the full utilizing flow is considered acceptableopenbyposition Generic Letter 89-04 if the maximum required accident flowrate is passed through the valve.

6.3.14 Where system design or operation prevents full stroke check valve exercising, Generic Letter 89-04 allows the valve to be disassembled and manually exercised as an alternative, using a sample disassembly program. When a check valve is disassembled and manually exercised a partial stroke test shall be performed upon reassembly if possible.

6.3.15 At the time of the test, valves which have exceeded their stroke time limiting value, shall immediately be declared inoperable.

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QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE ~

GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 6.3.16 Check valves whose obturator movement will be verified by a mechanical exerciser, shall be demonstrated operable by comparing a breakaway force to reference value as described by OMa-1988-Part 10.

6.4 Valve Testin Pro ram Plan Descri tion Valves that are required to be tested for the program are identified in Attachment B - Valve Testing Program Plan. The plan is organized as a table to provide the following information:

a) System - Dwg Number: each page of the valve plan contains a heading which identifies the plant system and associated Piping and Instrumentation Diagram (P&ID) for valves on the page.

b) Valve Number - valve identification number.

c) Coor./PAID - location coordinates of the valve on the PAID and the P&ID Number (RGEE Drawing Number 33013 series).

d) Type/Size - valve design type as indicated by the following abbreviations, and nominal size of the valve in inches.

BAV Ball Valve BFV Butterfly Valve CV Check Valve DIV Diaphragm Valve GTV Gate Valve GLV Globe Valve REV Relief Valve SCV Stop Check Valve TWV Three-way Valve e) Actuator - type of valve actuator as indicated by the following abbreviations:

MOV - Motor Operator AOV - Air Operator SOV - Solenoid Operator

TITLE:

QUALITY APPENDIX C REV.

ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE'TESTING RAgE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 12 " 14 MAN - Manual Operator HYD - Hydraulic Operator SAV - Self Actuated f) Normal Position (Norm Pos) - position of the valve during normal plant operation as indicated by the following:

0 - Open C - Closed g) Safety Class - designated safety class of the valve (SSC = safety siginificant, NC =

non-safety).

h) Category/Act-Pas - ASME category A, B, C,

,BC, or AC assigned to the valve, and identification of the valve as ACTIVE or PASSIVE.

Required Tests - required inservice test to be performed are indicated by the following:

LT-J Leak test per 10CFR50 Appendix J LT-X Leak test per ASME Section XI EX Exercising test (for Category A or B valves)

ST (0, C) Stroke Time (0=open, C=closed)

FS (0, C) Fail Safe Test (0=open, C=closed)

PIT Position Indication Test CV-C Check Valve Exercise - Full closed CV-0 Check Valve Exercise - Full open CV-P Check Valve Exercise - Partial open RT Relief Valve Test Frequency (Freq) - test frequency described bye Quarterly (Q) - at least once every three months.

'Cold Shutdown (CS) - during cold shutdowns.

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QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL NSERVICE PUMP AND VALVE TESTING PAGE GINNA STATION PROGRAM FOR THE 1990-1999 INTERVAL 1 30F 14

'Refueling (R) - nominally at least once every 18 months not to exceed two years.

'Relief valve 5 year/10 .year (5Y/10Y),

Category A-5Y; Category B, C-10Y.

k) Rel.Req/CSJ - identifies applicable Relief Request or Cold Shutdown Justification number, where:

CS Cold Shutdown Justification CR Code Administrative Relief Request GR Generic Relief Request VR Valve Relief Request l) Remarks - applicable pertinent clarification or additional information is provided or referenced.

7.0 Records Records of the Inservice Pump and .Valve Testing Program shall be developed and maintained in accordance with criteria established by the Code.

s TITLE: REV.

QUALITY APPENDIX C ASSURANCE 12/1/93 2 MANUAL GINNA STATION I I NSERV CE PUMP AND VALVE TEST NG PAgE PROGRAM FOR THE 1990-1999 INTERVAL 14" 8.0 SYSTEM Main Steam 33013-1231 Main Feedwater 33013-1236-2 Auxiliary Feedwater 33013-1237 Standby Auxiliary Feedwater 33013-1238 Diesel Generators 33013- 1239- 1, 2 Component Cooling Water 33013-1245 Component Cooling Water 33013-1246-1 Residual Heat Removal 33013-1247 Spent Fuel Pool Cooling 33013-1248 Service Water 33013-1250-1,2,3 Reactor Coolant Pressurizer 33013-1258 Reactor Coolant 33013-1260 Containment Spray 33013-1261 Safety Injection 8 Accumulators 33013-1262-1,2 RCS Overpressure Protection 33013-1263 CVCS Letdown 33013-1264 CVCS Charging 33013-1265-1,2 Reactor Coolant Drain Tank 33013-1272-2 Waste Disposal - Gas 33013-1273-2 Hydrogen Recombiners 33013-1275-1,2 Steam Generator Blowdown 33013-1277-1 Nuclear Sampling 33013-1278-1,2 Post Accident Sampling 33013-1279 Containment HVAC, Recirculation 33013-1863 Containment HVAC, Purge Supply 33013-1865 Containment HVAC, Purge Exhaust 33013-1866 Auxiliary/Intermediate Bldg HVAC 33013-1870 Containment Vessel Air Test 33013-1882 Service Air 33013-1886-2 Instrument Air 33013-1887 Instrument Air 33013-1893 Primary Water Treatment - DI Water 33013-1908-3 Containment Heating-Steam 8 Cond. 33013-1915 Fire Protection 33013-1989 Fire Protection 33013-1990-1 Fire Protection 33013-1991 Construction Fire Service Water 33013-1991

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Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment B PAGE CHANGE Changed safety class for 3518 and 3519 to class 3 per Q-List.

Changed safety class for 4269, 4270 and 4271 to class 3 per Q-List.

Changed safety class for 4272 to class 3 per Q-List.

Changed frequency for open and closed stroke time test for 4291 to Refueling per the revised relief request VR-13. Added position indication test (PIT).

10 Added Cold Shutdown frequency open stroke time test for 4297 and 4298. Deleted relief request GR-6 and added cold shutdown justification CS-35. Added position indication test (PIT).

10 Added Refueling frequency open and closed stroke time tests for 4304 and 4310 per the revised relief request VR-13. Added position indication test (PIT).

Added Cold Shutdown frequency close stroke time test for 4480 and 4481. Deleted relief request GR-6 and added cold shutdown .

justification CS-35. Added position indication test (PIT).

14 Added Refueling frequency open stroke time test for 9710A and 9710B per the revised relief request VR-13. Added position indication test (PIT).

20 Changed size for vacuum breaker 651 from 1 inch to 2 inches (replaced per EWR 4755B).

20 Changed size for check valves 723A and 723B from 10 inches to 8 inches (replaced per EWR 5284).

22 Changed frequency for exercise and close stroke time tests for 813 and 814 to quarterly and deleted cold shutdown justification CS-12.

23 Added asterisked component 817 to valve plan.

29 Added component 8152 per Tech. Spec. CIV revision.

30 Deleted the partial check valve exercise test and changed the frequency for the open exercise test for 4601, 4602, 4603 and 4604 to quarterly. Deleted relief request VR-17 and the disassembly remarks.

32 Deleted 4627, 4628 and 4635 from the IST Program (administratively locked open with no CIV function).

Page 1 of 3

Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment B PAGE CHANGE 32 Changed the category to A-Passive and deleted the exercise test for 4629, 4630 and 4636.

32 Deleted 4641 and 4642 from the IST Program (administratively locked open with no CIV function).

32. Changed the category to A-Passive and deleted the exercise test for 4643 and 4644.

33 Added components 4655, 4656, 4658, 4659 and 4660 per Tech.

Spec. CIV revision.

35 Deleted 4757 from the IST Program (administratively locked open with no CIV function).

35 Changed the category to A-Passive and deleted the exercise test for 4758.

35 Added component 4759 per Tech. Spec. CIV revision.

40 Added asterisked component 427 to valve plan.

43 Changed size for vacuum breakers 845C and 845D from ~~~ inch to 2 inches (replaced per EWR 4755B).

44 Added components 859A, 859B and 859C per Tech. Spec. CIV revision. I 45 Added components 864A, 864B, 869A and 869B per Tech. Spec. CIV revision.

48 Added components 2825, 2825A, 2826 and 2826A per Tech. Spec.

CIV revision.

49 Added components 2829, 2830, 2856 and 2858 per Tech. Spec. CIV revision.

49 Deleted vacuum breakers 2850 and 2851 from the IST Program per modification per EWR 4755B.

50 Deleted components 825A, 825B, 826A, 826B and 826C from the IST Program since these MOVs will no longer be operable during power operations as a result of NRC acceptance of the boric acid Tech. Spec. submittal.

51 Deleted component 826D from the IST Program since this MOV will no longer be operable during power operations as a result of NRC acceptance of the boric acid Tech. Spec. submittal.

Page 2 of 3

Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment B PAGE CHANGE 56 Added components 885A and 885B per Tech. Spec. CIV revision.

58 Deleted component 1828 from the IST Program since this check valve's safety function was to keep the SI pump suction lines full when MOV 825A and MOV 825B were closed. these MOVs will now be maintained open with power removed,Since per the boric acid Tech. Spec. submittal, this check valve no longer has an ASME XI safety function and may be deleted from the IST Program.

58 Added components 12406 and 12407 per Tech. Spec. CIV revision.

63 Changed frequency for open stroke time test for 142 to Cold Shutdown per cold shutdown justification CS-23. Added position indication test (PIT).

67 Added component 1709G per Tech. Spec. CIV revision.

68 Added component 1722 per Tech. Spec. CIV revision.

Changed safety class for 8423A, 8425A and 8427A to class 3 per Q-List.

72 Changed safety class for 8433A and 8435A to class 3 per Q-List.

73 Deleted 5701, 5702, 5733 and 5734 from the IST Program per Tech. Spec. Amendment for CIVs.

73 Changed the leakage test requirement to ASME Section XI and deleted relief request GR-2 for 5735, 5736, 5737 and 5738.

79 Added components 1555, 1558 and 1561 per Tech. Spec. CIV revision.

80 Added components 1564 and 1567 per Tech. Spec. CIV revision.

81 Added components 1570 and 1573 per Tech. Spec. CIV revision.

88 Changed frequency for close exercise test for 8419 to quarterly and deleted cold shutdown justification CS-20.

92 Changed frequency for exercise, close stroke time and close fail position tests for 9227 to quarterly and deleted cold shutdown justification CS-29.

92 Changed frequency for close exercise test for 9229 to quarterly and deleted cold shutdown justification CS-29. Also added LT-Z test per Tech. Spec'. CIV revision.

Page 3 of 3

System: MAIN STEAM QUAL7ZY-ASSURANCE MANUAL ATZACHMERZ B Dwg No: 33013-1231 GINNA. STATION APPENDIX C VALVE Tf~lNG HKGRAM PIAN Date: 1/6/94 Page: -1 of 92 FOR 'IHE 1990 1999 IPZ2267AL PREPARED BT: DATE:

APPROV~ BY: ~ 7 DATE:

Valve Coor. +pe Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3410 I-5 GTV AOV

~12 1 ACTIVE EX CS CS-3 MANUAL EXERCISE METISSE PIT R FS-C CS CS-3 3411 C-5 GTV AOV 2 B EX CS CS-3 MANUAL EXERCISE PIT R FS-C CS CS-3 3504A F 4 GTV MOV

~12 1 ACTIVE EX Q ST-0 Q ST-C Q PIT R 3504B E-4 CV SAV ACTIVE CV-0 Q CV-C Q 3505A B-4 GTV MOV

~12 1 ACTIVE EX Q ST-0 Q.

ST-C Q PIT R

gJAIZTE ASSURANCE KQKJAL ATZMZMERZ B System: MAIN STBAM GINNA PZAXXON Dwg No: 33013-1231 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 INZlWiTAL Date: 1/6/94 Page: 2 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Sx.ze Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 3505B D-4 CV SAV 3 C

~12 I ACTIVE CV-0 Q CV-C Q 3508 G-5 RBV SAV 2 C

~12 1 AAAIVE RT 5Y 3509 A-5 REV SAV

~11 2 C WCTV7E RT SY 3510 G-6 REV SAV

~11 C

~ATIVE RT SY 3511 A-6 REV SAV

~11 C MOTIVE RT SY 3512 G-7 REV SAV

~11 2 C AATIVE RT 5Y 3513

~i A-7 REV SAV 2 C XVITVE RT 5Y 3514 G-8 REV SAV

~11 2 C

~ATIVE SY

gJALITY ASSURANCE MANUAL ATZACSMENZ B System: MAIN STEAM GINNA. STATION Dwg No: 33013-1231 APPENDIX C VALVE TESTING HKGRAM PIAN H)R 'LHE 1990 1999 ZÃZERVAL Date: 1/6/94 Page: 3 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 3515 A-7 REV SAV 2 C

~12 I ~ATIVE RT 5Y 3516 G-10 CV AOV 2 B

~11 WVI'IVE EX CS CS-1 ST-C CS CS-1 PIT R FS-C CS CS-1 3517

~IIA-11 CV AOV 2 B

~ATIVE EX CS CS-1 ST-C CS CS-1 PIT R FS-C CS CS-1 3518 G-10 SAV

~11 CV 3 C

%VITAE CV-C CS CS-2 3519 A-11 CV SAV 0 ~ 3 C 1231 30 AATIVB CV-C CS CS-2 3652 D-2 GTV HYD 3 B 1111 ~ATIVE

QEIZTY ASSURANCE MANUAL ATZACSMEPZ B System: MAIN FEEDWATER GINNA. SZLTION Dwg No: 33013-1236 APPENDIX C VALVE TESTING HIRAM PIAN FOR %HE 1990 1999 INZEZUTAL Date: 1/6/94 Page: 4 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3992 J-3 CV SAV 2 C 111 -2 14 ACTIVE CV-C CS VR-21 3993 A-3 CV SAV 0 2 C 1.76~ 14 XCTVZ CV-C CS VR-21 4269 D-3 14.Y6 ~ GLV 12 AOV ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8 4270 G-3 GLV AOV 3 B R-2 ~1 ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8 4271 D-3 GLV AOV 111 -2 4 ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8

QUAIZTY ASSUIQNCE MANUAL ATI'ACHMEÃZ B System: MAIN FEEDWATER GINNA, SIX%ON Dwg No: 33013-1236 APPENDIX C VALVE TESTING BIGRAM PIAN FOR 'IHE 1990 1999 INTERVAL Date: 1/6/94 Page: 5 of 92 Rev: 2 Valve Number Coor.

P&ZD.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 4272 H-3 GLV AOV

~123 -2 4 ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8

QEQZTY ASSURANCE MANUAL ATZKCHMEPZ B System: AUXILIARY FEEDWATER GINNA 8ZATION Dwg No: 33013-1237 APH~ZDDIX C VALVE TARRING PE%GRAM PIAN FOR %K 1990 1999 IÃKRVAL Date: 1/6/94 Page: 6 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Requi red Tests Fre Rel.Req CSJ Remarks 3996 I-6 SCV MOV BC 1237 5 ACTIVE EX Q ST-0 Q ST-C Q PIT R CV-0 Q 3998 I-8 CV SAV 3 C 7 MVi'IVB CV-0 Q CV-C Q VR-26 4000A D-7 GLV MOV 3 B 111 XCTTVDf EX Q ST-0 Q ST-C Q PIT R 4000B D-8 GLV MOV 3 B

~1 XVPDlE EX Q ST-0 Q ST-C Q PIT R 4000C B-10 CV SAV 2 C

~1 AAAIvE CV-0 Q CV-C Q VR-26 4000D E-10 CV SAV C 111 MOTIVE CV-0 Q CV-C Q VR-26

glALITYASSUEQNCE MANUAL System: AUXILIARY FEEDWATER

'GINNA SIATION Dwg No: 33013-1237 APPENDIX C VALVE TESTING HIRAM PIAN FOR 'IHE 1990 1999 IPZERVAL Date: 1/6/94 Pa e: 7 of 92 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 4003 I-11 CV SAV 2 C

~1 WCTU; CV-0 Q CV-C Q VR-26 4004 J-10 CV SAV 2 C

~1 WCTX%;

CV-0 Q CV-C Q VR-26 4007 B-8 'CV. MOV BC

~1 XVFIVE EX Q ST-0 Q ST-C Q PIT R CV-0 Q CV-C Q VR-26 4008 E-8 SCV MOV 3 BC 111 ACTIVE EX Q ST-0 Q ST-C Q PIT R CV-0 Q CV-C Q VR-26 4009 B-5 CV SAV 3 C

~1 WVI'IVE CV-0 Q CV-C Q

QUALITY ASSURANCE MANUAL AITACSMENZ B System: AUXILIARY FEEDWATER GINNA 8ZATION Dwg No: 33013-1237 APHM)IX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 1ÃIKUTM Date: 1/6/94 Page: 8 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4010 B-5 CV SAV 1237 ACTIVE CV-0 Q CV-C Q 4013 I-2 GTV MOV 1237 4 ACTIVE BX Q ST-0 Q PIT - R 4014 H-2 CV SAV 3 C MVPXVE CV-0 Q CV-C Q 4016 B-2 CV SAV C

~1 4 ACTIVE CV-0 Q CV-C Q 4017 B-2 CV SAV

~1 4 A( TTl" CV-0 Q CV-C Q 4020 I-3 RBV SAV 3 C rFVt . 75 XCTVra RT 10Y 4021 B-2 RBV SAV 3 C 2 ~2 ACTIVE RT 10Y

QUALITY ASSUEQHCE ANNUAL ATZKCHMEÃZ B System: AUXILIARY FEEDWATER GINNA SZAXXON Dwg No: 33013-1237 APPENDIX C VALVE TESTING HKGRAM PIAN FOR 'IHE 1990 1999 IRZERVAL Date: 1/6/94 Page: 9 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4022 E-3 REV SAV 3 C 1237 ~7 ~ATIV2 RT 10Y 4023 I-5 CV SAV 111 ~1.

CV-0 Q 4027 C-3 GTV MOV 3 B 1117 4 ACTIVE EX Q ST-0 Q PIT R 4028 D-3 GTV MOV 3 B WCVDH~

EX Q ST-0 Q PIT R 4098 I-2 GTV 3 B 1237 4 ~ATIVE EX 4291 H-5 GTV AOV 0 3 B 111 11 > ~'IVE EX Q THROTTLE DISCH TO ACTIVATE ST-0 R VR-13 ST-C R VR-13 PIT R FS-0 Q

QUAIZTY ASSURANCE MANUAL ATZACHMEPZ B System: AUXILIARY FEEDWATER GINNA SZATION Dwg No: 33013-1237 APPENDIX C VALVE TESZWG BIGRAM PIAN FOR 'IHE 1990 1999 IRIHUTAL Date: 1/6/94 Page: 10 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4297 I-10 GLV AOV 0 3 B

~12 7 ACTIVE EX Q ST-0 CS CS-35 PIT R FS-0 Q 4298 J-8 GLV AOV 1237 ACTIVE EX Q ST-0 CS CS-35 PIT R FS-0 Q 4304 C-6 GTV AOV

~17 I 3 B

~ATIVE EX Q THROTTLE DISCH TO ACTIVATE ST-0 R VR-13 ST-C R VR-13 PIT R FS-0 Q 4310 E-6 GTV 'OV B XTTV1; EX Q THROTTLE DISCH TO ACTIVATE ST-0 R VR-13 ST-C R VR-13 PIT R FS-0 Q 4324 J-3 GTV SOV 3 B 1337 . 7E ~ATIVE EX Q ST-0 VR-6

QUALITY ASSURANCE MANUAL ATZACHMEÃZ B System: AUXILIARY FEEDWATER GINA'ZAXXON Dwg No: 33013-1237 APHXDIX C VALVE TE'SZlNG HKGRM PXAN POR %HE 1990 1999 IÃXKRQK) Date: 1/6/94 Page: 11 of 92 Rev: 2 Valve . Coor. Tyge Norm Safety Cate o Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4325 C-4 DIV SOV B

~17 3

~ATIVE EX Q ST-0 VR-6 4326 F-3 DIV SOV 1237 .5 A TIVE EX Q ST-0 VR-6 4344 E-3 GTV

~17 4 ACTIVE 4345 C-3 GTV t4AN 3 B

~1 ~TYPE; EX 4480 B-6 GTV AOV 3 B ACTIVE EX Q ST-C CS S-35 PIT R FS-C Q 4481 F-6 GTV AOV 3 B 1117 1.5 ~ATIVE EX Q ST-C CS Cs-35 PIT R FS-C Q

r g MZTY ASSURANCE MANUAL ATI'ACHMEMI' System: STANDBY AUXILIARY FEEDWATER 33013-1238 GINNA STATION Dwg No:

APPENDIX C VALVE TEST'ING ESOGRAM PIAN FOR IHE 1990 1999 IÃHHZVAL Date: 1/6/94 Page: 12 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 9629A B-3 GTV MOV C' B 1238 4 ACTIVE EX Q ST-0 Q PIT R 9629B I-3 GTV MOV 111 4 EX Q ST-0 Q PIT R 9700A B-6 CV SAV C 3

~12 8 ACTIVE CV-0 Q CV-C Q 9700B I-6 CV SAV C 1238 ~ATIVE CV-0 Q CV"C Q 9701A B-7 GTV MOV 3 B 1238 AATIVE EX Q ST-0 Q PIT R 9701B I-7 GTV MOV 111 EX Q ST-0 Q PIT R

QJAIZTY ASS%ENCE MANUAL ATZACHMENZ B System: STANDBY AUXILIARY FEEDWATER GINNA. STATION Dwg No: 33013-1238 APPENDIX C VALVE TESTING PRO2mM PIAN FOR THE 1990 1999 IRZ19UTAL Date: 1/6/94 Page: 13 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 9703A F-8 GLV MOV

~1 ACTIVE EX Q ST-0 Q PIT R 9703B F 8 GLV MOV 3 B

~1 ACTIVE.

EX Q ST-0 Q PIT R 9704A B-9 SCV MOV BC

~1 ACTIVE EX Q ST-0 Q ST-C . Q PIT R CV-0 Q CV-C Q VR-27 9704B I-9 SCV MOV BC 1238 3 EX Q ST-0 Q ST-C Q PIT R CV-0 Q CV-C Q VR-27 9705A B-10 CV- SAV 2 C

~1 ~ATIVB CV-0 Q CV-C Q VR-27

gJALITY ASSUEQNCE MANUAL ATZACHMENI' System: STANDBY AUXILIARY FEEDWATER GINNA. STATION Dwg No: 33013-1238 APPENDIX C VALVE TESTING HKGRAM PZAN FOR %K 1990 1999 IWZEiUTAL Date: 1/6/94 Page: 14 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 9705B I-10 CV SAV C 111 8 ACTIVE CV-0 Q CV-C Q VR-27 9709A B-3 REV SAV 3 C

~138 1 ~ATIVE METISSE RT 10Y 9709B I-3 REV SAV 3 C 111 1 RT 10Y 9710A C-7 Grv AOV 3 B 131 ~1. ACTIVE EX Q ST-0 R VR-13 PIT R FS-0 Q 9710B H-7 GLV AOV 3 B

~1 ~1. ACTIVE EX Q ST-0 R VR-13 PIT R FS-0 Q 9721A C-3 CV SAV 3 C 111 .5 ACTIVE CV-0 Q CV-C Q

gJAIZTY ASSURANCE MANUAL ATZACSMEPZ B System: STANDBY AUXILIARY FEEDWATER GINNA. STATION Dwg No: 33013-1238 APHKDIX C VALVE TESTING HKCRAM PIAN FOR 'IHE 1990 1999 IFIKRVAL Date: 1/6/94 Pa e: 15 of 92 Rev': 2 Valve Number Coor.

PaID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 9721B G-3 CV SAV

~12 .5 ACTIVE CV-0 Q CV-C Q 9746 I-8 GTV MOV 1238 3 ACTIVE EX Q ST-C Q PIT R

gJALITE ASSURANCE MANUAL ATI'ACSMEPZ B System: DIESEI GENERATOR GINNA, SZATION Dwg No: 33013-1239 APPENDIX C VALVE TOTING BIGRAM PIAN FOR 'IHE 1990 1999 IPIKUTAL Date: 1/6/94 Page: 16 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 5907 E-3 GTV SOV 3 B 1121-1 1 ACTIVE EX Q ST-0 Q VR-18 ST-C Q VR-18 FS-C Q 5907A E-3 GTV SOV 3 B

~139-I .75 ACTIVE EX Q ST-0 Q VR-18 ST-C Q VR-18 FS-0 Q 5908 E-9 GTV SOV 3 B

~ATIVE EX Q ST-0 Q VR- 18 ST-C Q VR- 18 FS-C Q 5908A E-9 GTV SOV 3 B 1121-2 .75 AATIVE EX Q ST-0 Q VR-18 ST-C Q VR-18 FS-0 Q 5933A

~1-I G-11 GTV 1.5 SOV 3 B ACTIVE EX Q ST-0 Q VR- 1

QUALITY ASSURANCE MANUAL ATZKCHHEÃZ B System: DIESEL GENERATOR GINNA STATION Dwg No: 33013"1239 APPENDIX C VALVE TESTING PROGRAM PIAN FOR %K 1990 1999 IN'IKVAL Date: 1/6/94 Page: 17 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5933B F-11 GTV SOV 111-1 1.5 ACTIVE EX Q ST-0 Q VR-1 5934A C-2 GTV SOV C 111'~ 1..5 A TIVE EX Q ST-0 Q VR-1 5934B B-2 GTV SOV 3 B 1239-2 1.5 ACTIVE EX Q ST-0 Q VR-1 F-1 5941A

~1-I CV

.75 SAV 3 C

~ATIVE CV-C Q'942A F-11 CV SAV 3

~I.P~ C ACTIVE CV-C Q 5943A F-1 REV SAV

~123 -1 .75 ACTIVE RT 10Y 5944A F-11 RBV SAV 3 C XVPXVE RT 10Y 5947B F-1 RBV SAV C 1121-1 . 75 ~ATIVE RT 10Y

QUAIZTY ASSURANCE MANUAL ATZAQBKNZ B System: DIESEL GENERATOR GINNA STATION Dwg No: 33013-1239 APPENDIX C VALVE TESTING HKGfQM PIAN H)R THE 1990 1999 INTERVAL- Date: 1/6/94 Page: 18 of 92 Rev: 2 Valve Coor. Tp>e Norm Safety Cate o Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5947C G-1 SAV

~1-1 REV C

~AT1%;

RT 10Y 5948B G-10 REV SAV 112 12 . 75 ACTIVE RT 10Y 5948C F-10 REV SAV 3 C MVP~V RT 10Y 5955 I-1 CV SAV

~1-1 3 3 C ACTIVE CV-0 Q CV-C Q 5956 I-10 CV SAV 1239-2 ACTIVE CV-0 Q CV-C Q 5959 G-3 REV SAV 1239-1 1.5 ACTIVE RT 10Y 5960 G-8 REV SAV 3 C

~3.B-2 MOTIVE RT 10Y

QUAIZTY ASSURANCE KQKJAL ATZKCSMEPZ B System: DIESEL GENERATOR GINNA STATION Dwg No: 33013-1239 APPENDIX C VALVE TESTING HKGBAM PIAN FOR 'IHE 1990 1999 IHZERVAL Date: 1/6/94 Page: 19 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P6 ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5960A C-1 CV SAV 3 C 111 1 1.5 ACTIVE CV-0 VR-2 R SAMPLE DISASSEMBLY CV-C R VR-2 SAMPLE DISASSEMBLY 5960B 11'.

C-11 CV 5

SAV ACTIVE CV-0 CV-C R

R VR-2 VR-2 SAMPLE DISASSEMBLY SAMPLE DISASSEMBLY 5961 I-4 CV SAV

~1-1 2 ACTIVE CV-0 Q CV-C Q 5962 I-8 CV SAV C ACTIVE CV-0 Q CV-C Q

QUALZXY ASSUBANCE MM1hL System: COMPONENT COOLING WATER GINNA SZhTXGH Dwg No: 33013-1245/1246 APHXDIX C VALVE TRSEKG HKGRAN PIAN FOR 'IHE 1990 1999 IPXKRVAL Date: 1/6/94 20 of Rev: 2 Page: 92 Valve Coor. Type Norm Safety Cate o Required Rely Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSIT Remarks 17 A-3 GLV AOV

~143 I ACTIVE EX Q ST-C Q PIT R FS-C Q 651 A-3 REV SAV 3 C 1245 2 AAAIUB RT 10Y 733A 0

'~ID-G CV 3

SAU C 3 C XESTIVE CV-P Q CS-31 CV-0 CS CS-31 CV-C Q 723B E-6 CV SAV 0 C 3

~143 .8 ACTIVE CV-P Q CS-31 CV-0 CS CS-31, CV-C Q 732 A-3 REV SAV 3 C WCTXVE RT 10Y 738A F-3 GTV MOV 1314 111 A IVE EX Q ST-0 Q PIT R

gJALITY ASSURANCE MANUAL ATZACHMENZ B System: COMPONENT COOLING WATER GINNA. SZhXXON Dwg No: 33013-1245/1246 APPENDIX C VALVE 'IKSTING HKGRAM PIAN H)R LEE 1990 1999 INZERVAL Date: 1/6/94 Page: 21 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 738B H 4 GTV MOV 1245 ~1 ACTIVE EX Q ST-0 Q PIT R

• 823 D-2 GTV MOV 3 B 1114 KZBIVE PIT 743 C-6 CV SAV AC

~124 -1 2 ACTIVE LT-J R GR-2 CV-C Q 745 B-6 GLV AOV 12~!2-1 A TIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 749A B-5 GTV MOV 2 A 1114-1 Al. FIVE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2 749B B-4 GTV MOV 2 A 1114-1 XV1TVE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2

QUAIZTY ASSUEQHCE ANNUAL ATI'ACHMEWI' System: COMPONENT COOLING WATER GINNA SI'ATION Dwg No: 33013-1245/1246 APPDH)IX C VALVE TESTING PROGRAM PZAN FOR 'IHE 1990 1999 IPHZUTAL Date: 1/6/94 Page: 22 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PEID. xze Actuator Pos Class Act Pas Tests Pre CSJ Remarks 750A C-5 CV SAV

~14 -1 4 CV-C CS CS-7 750B C-3 CV SAV 12412-1 4 ACTIVE CV-C CS CS-7 I-5 759A

~E-i GTV MOV EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2 759B I-2 GTV MOV A 1114-1 METISSE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2 813 B-8 GTV MOV EX Q ST-C Q PIT R LT-J R GR-2 8 14 I-8 GTV MOV 2 A 111 -1 MVPIVE EX Q ST-C Q PIT R LT-J R GR-2

QUAIZTY ASSURANCE MANKG ATZACHMENZ B System: COMPONENT COOLING WATER GINNA STATION Dwg No: 33013-1245/1246 APHXDIX C VALVE TEFZING PROGRAM PIAN FOR 'IHE 1990 1999 IPZEUTAL Date: 1/6/94 Pa e: 23 of 92 Rev: 2 Valve Coor. +pe Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• S17 A-4 GTV MOV 0 3 B

~14 -1 TKBBIVE EX R ST-C R PIT R

gJALETY ASSURANCE MANUAL ATZACSMENZ B System: RESIDUAL HEAT REMOVAL GINNA..STATION Dwg No: 33013-1247 APHM)IX C VALVE TESTING PstXBAM PIAN FOR 'IHE 1990 1999 IÃXK5VZ Date: 1/6/94 Pa e: . 24 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks

• 624 J-7 BFV AOV B

~147 PASSIVE EX Q

• 625 I-8 BFV AOV 2 B 1114 VXBBTVE EX

• 626 H-7 BFV AOV

~14 7 PASSIVE EX Q 697A F-9 CV SAV 2 C Xl.'TIVE CV- P CS CS-30 CV-0 R VR-29 CV-C Q 697B B-9 CV SAV

~Z. 47 ACTIVE CV-P CS CS-30 CV-0 R VR-29 CV-C Q 700 G-1 GTV MOV 1 A

~14 ~1 XVFIVE EX CS CS-13 ST-0 CS CS-13 PIT R LT-X R

QUAIZTY ASSUEQNCE MANUAL ATZACHMEtfZ B System: RESIDUAL HEAT REMOVAL GINNK SZhTION Dwg No: 33013-1247 APPENDIX C VALVE TESTING HGRAM PIAN EQR THE 1990 1999 INIHVlAL Date: 1/6/94 Page: 25 of 92 Valve Number Coor.

P5 ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks.

701 G-2 GTV MOV 1247 10 ACTIVE EX CS CS-14 ST-0 CS CS-14 PIT R LT-X R 704A D-4 GTV MOV B 1247 10 ACTIVE EX Q ST-C Q PIT R 704B C-4 GTV MOV 2 B 111 111 XCVVHP EX Q ST-C '

Q PIT 710A F-6 CV SAV

~147 ACTIVE CV-P Q VR-20 CV-0 R VR-20 CV-C CS CS-32 710B B-6 CV SAV 2 C METISSE CV-P Q VR-20 CV-0 R VR-20 CV-C CS CS-32

QUAIZTY ASSURANCE MANUAL ATZAQiMEMZ B System: RESIDUAL HEAT REMOVAL GINNA SZATION Dwg No: 33013-1247 APPENDIX C VALVE Tl~lNG BIGRAM PIAN H)R 'lHE 1990 1999 INZHUTAL Date: 1/6/94 Page: 26 of 92 Rev: 2 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PAID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 720 I-2 GTV MOV 1 A

~147 10 ~ATTVE EX CS CS-14 ST-0 CS CS-14 PIT R LT-X R 721 I-1 GTV MOV 1247 ~1 ACTIVE EX CS CS-13 ST-0 CS CS-13 PIT R LT-X R 850A F-4 GTV MOV

~147 ~1 ACTIVE EX Q ST-0 Q PIT R 850B B-4 GTV MOV 2 B 111 ~1 XllTXVE EX Q ST-0 Q PIT R

• 851A B-1 GTV MOV 2 B 1247 ~1 PA~I E PIT

• 851B B-2 GTV MOV 2 B KQ!i~PE PIT

QUAIZZY ASSURANCE MANUAL System: RESIDUAL HEAT REMOVAL GINNK PVZXCN Dwg No: 33013-1247 APHUDIX C VALVE TfXTING PROGRAM PIAN FOR LHE 1990 1999 IPX19UTAL Date: 1/6/94 Page: 27 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 854 G-4 CV SAV 2 C 1247 10 ~ATIVE CV-0 R 856 G-5 GTV MOV 2 B

~14 ~1 MCTVHf EX CS .CS-28 ST-C "

CS CS-28 PIT R 857A C-11 GTV MOV 1247 A TIVE EX Q ST-0 Q PIT R 857B B-11 GTV MOV 2 B XVI'IVE EX Q ST-0 Q PIT R 857C B-11 GTV MOV 1247 ACTIVE EX Q ST-0 Q PIT R

• 1813A E-3 GTV MOV A

~14 KZBTVE PIT R TEST NOT REQ BY ASME LT-J R GR-2

QUAL'ITZL ASSUEQNCE ANNUAL ATZAQBKPZ B System: RESIDUAL HEAT REMOVAL GINNK STATION Dwg No: 33013-1247 APHM)IX C VALVE TESTING PROGRAM PIAN FOR '?HE 1990 1999 IN'ZlMQL Date: 1/6/94 Page: 28 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required . Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 1813B B 4 GTV MOV 2 A 1247 PASSIVE PIT R TEST NOT REQ BY ASME LT-J R GR-2

QOAIZTY ASSURANCE MAKlAL ATZA.CHMKPZ B System: SPENT FUEL POOL COOI ING GINNA STATION Dwg No: 33013-1248 APPENDIX C VALVE 'HXTING BIGRAM PXAN 83R %K 1990 1999 INIKRVAL Date: 1/6/94 Page: 29 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 8152 C-5 GTV A

~148 1 ,5zvz LT-J 8614 H-8 GTV MAN 3 B ACTIVE 8654 H-2 GTV MAN 1248 ACTIVE 8655 H-4 CV SAV C SSC C

~1 AATXVL~

CV-0 Q CV-C Q 8658 I-4 CV SAV C

~1 XVITVE CV-0 Q CV-C Q

QKGZTY ASSURANCE MANUAL ATZACHMEtfZ B System: SERVICE WATER GINNA SZhXXON Dwg No: 33013-1250 APPENDIX C VALVE TEPHNG PROGRAM PIAN FOR LHE 1990 1999 IN'XKVTAL Date: 1/6/94 Page: 30 of 92 . Rev: 2 Valve Number Coor.

PfiID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests

• Fre Rel.Req-CSJ Remarks 4561 G-9 BFV AOV 1250-3 14 ACTIVE EX Q ST-0 Q PIT R FS-0 Q 4562 G-10 BFV AOV 1250-3 14 A TIVE EX Q ST-0 Q PIT R FS-0 Q 4601 D-2 CV SAV 0 C 3 1115 I 14 ACTIVE CV-0 Q CV-C Q 4602 E-2 CV SAV 0 C 3 C 1250-1 14 ~ATIVE CV-0 Q CV-C Q 4603 F-2 CV SAV 0 C 3 C 1115-1 14 ~ATIVE CV-0 Q CV-C Q 4604 G-2 CV SAV 0 C 3 1115 I 14 ACTIVE CV-0 Q CV-C Q

QKKZTY ASSURANCE MANUAL ATZACHMENZ B System: SERVICE WATER GINNA SZATION Dwg No: 33013-1250 APPENDIX C VALVE TKSTING PfKGBAM PIAN H)R '?HE 1990 1999 INIKRVAL Date: v.

1 6 94 Pa e: 31 of 92 R Valve Coor. age Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4609 C-2 BFV MOV 3 B 1250-1 8 ~ATIVE EX Q ST-C Q PIT R 4613 D-6 BFV MOV 0 111 -1 ~1 EX Q ST-C Q PIT R 4614 H-2 BFV MOV 3 B 12151 ~1 ~ATIVB EX Q ST-C Q PIT R 4615 J-9 GTV MOV B 111 -1 MOTIVE EX Q ST-0 Q ST-C Q PIT R 4616 A-9 GTV MOV 111 -1 EX Q ST-0 Q ST-C Q PIT R F-6 4619C IIK~ GTV

~1 MAN 3 B WCTVHV EX CS CS-4

QUAIZIY ASSUEQHCE MARIAL ATZACHMEPZ B System: SERVICE WATER GINNA. STATION Dwg No: 33013-1250 APPENDIX C VALVE TZSTING BIGRAM PIAN FOR 'IHE 1990 1999 INZERVAL Date: 1/6/94 Page: 32 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P5ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4620B E-6 GTV B 1250-2 ~3 ACTIVE EX CS CS-4 MANUALLY OPERATED MOV 4622A H-7 GTV MAN B AV?'IVE EX CS CS-4 4629 B-7 BFV A 1115l-3 8 PASSIVE LT-X R IN LIEU OF LT-J 4630 C-7 BFV MAN 2 A PAEETVE LT-X R IN LIEU OF LT-J 4636 F-7 BFV 0 2 A 1250-3 2.5 PASSIVE LT-X R IN LIEU OF LT-J 4643 G-7 BFV MAN 0 2 A IVE LT-X R IN LIEU OF LT-J 4644 H-7 BFV

~15 - 8 PASSIVE LT-X LT-J 55.

R IN LIEU OF 4653 F-6 REV SAV C WllTXKi RT 10Y

QJAIZTY ASSURANCE MANUAL ATTACHMENT B System: SERVICE WATER GINNA STATION Dwg No: 33013-1250 APPENDIX C VALVE TEASING BIGRAM PIAN FOR 'IHE 1990 1999 INIKVTAL Date: 1/6/94 Page: 33 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4654 D-6 REV SAV 3 C 1250-2 .75 ACTIVE RT 10Y 4655 A-7 RBV SAV AC 7AABTVE LT-X R IN LIEU OF LT-J 4656 C-7 REV SAV AC 125 t21 . 75 PASSIVE LT-X R IN LIEU OF LT-J 4657 H-8 RBV SAV 3 C ACTOR RT 10Y 4658 B-7 RBV SAV 2 AC 125 t21 . 75 ~PAS IVE LT-X R IN LIEU OF LT-J 4659 G-7 RBV SAV 2 AC VXBETV>f LT-X R IN LIEU OF LT-J 4660 H-7 REV SAV 2 AC 1125- . 75 PASSIVE LT-X R IN LIEU OF LT-J 4663 I-3 GTV MOV 3 B

~TIVE EX Q ST-C Q PIT R

gJAIZTE ASSURANCE MHKG ATZACHMEPZ B System: SERVICE MATER GINNA SXRTI(N Dwg No: 33013-1250 APPENDIX C VALVE T1~1NG HE@RAM PIAN FOR 'XHE 1990 1999 IPHZUTAL Date: 1/6/94 Page: 34 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. z.ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4664 H-2 GTV MOV 3335- 10 A IVE EX Q ST-C Q PIT R 4670 D-5 GTV

~1-3 133 MOV 3 B 7iVPIVE EX Q ST-C Q PIT R 4733 I-3 BFV MOV 3 B

~35 -3 ~ATIVE EX Q ST-C Q PIT R 4734

~1~

E-3 BFV 14 MOV AC%IIV EX Q ST-0 Q ST-C Q PIT R 4735 B-2 BFV MOV 3 B XESTIVE EX Q ST-0 Q ST-C Q PIT R 4739B B-11 GTV MAN B 111-3 XCTIVE EX CS CS-4

QUALZIY ASSURANCE MANUAL System: SERVICE WATER GINNA 8ZATION Dwg No: 33013-1250 APPENDIX C VALVE Tt~3TGG PROGRAM PIAN FOR 'IHE 1990 1999 IN'IKRVAL Date: 1/6/94 Page: 35 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Saze Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 4758 D-7 BFV

'250-3 ~5 P SIVE LT-X R IN LIEU LT-J OF 4759 D-7 REV SAV AC

~1 VX~IVE LT-X R IN LIEU OF LT-J 4780 C-2 BFV MOV 1250-1 ACTIVE EX Q ST-C Q PIT R 9627A B-9 CV SAV IF3~

3 C 4 MOTIVE CV-P Q VR-5 ALSO REQ AFTER DISASSEMBLY CV-0 R VR-5 SAMPLE DISASSEMBLY CV-C R VR-5 SAMPIE DISASSEMBLY 9627B B-10 CV SAV 1250-2 4 A TIVE CV-P Q VR-5 ALSO REQ AFTER DISASSEMBLY CV-0 R VR"5 SAMPLE DISASSEMBLY CV-C R VR-5 SAMPLE DISASSEMBLY 9632A

~1~ E-9 GTV

~1.

AOV 0 3 B

~IVE EX Q ST-0 Q GR-4 FS-0 Q

QJAIZTY ASSURANCE MANUAL System: SERVICE WATER GINNA. STATION Dwg No: 33013-1250 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 ZRIKRVAL Date: 1/6/94 Page: 36 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 9632B E-10 GTV AOV 0

~15 1.5 ACTIVE EX Q ST-0 Q GR-4 FS-0 Q 9633A E-9 SCV SAV 3 BC I-2 UCTIVE.

EX Q CV-0 Q 9633B E-10 SCV SAV 3 BC 1Pa~ 11 > WCTU; EX Q CV-0 Q 9634B F-10 GLV MAN 3 B XVI'IVE CS CS-4

gJAl2TY ASSURANCE MANUAL ATZACHMEPZ B System: REACTOR COOLANT PRZR GINNA SI'ATION Dwg No: 33013-1258 APHM)IX C VALVE TEEING BIGRAM PIAN FOR LHE 1990 1999 ?NERVAL Date: 1/6/94 Page: 37 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e

'ize Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 430 B-8 GLV AOV 125I2 A TIVE EX CS CS-10 ST-0 CS CS-10 ST USING NITROGEN ST-C CS CS-10 ST USING NITROGEN PIT R FS-C CS CS-10 431C C-8 GLV AOV 1 B 111 WCvzUE EX CS CS-10 ST-0 CS CS-10 ST USING NITROGBN ST-C CS CS-10 ST USING NITROGEN PIT R FS-C CS CS-10 434 A-9 REV SAV 1258 ACTIVE PIT R RT 5Y 435 C-9 RBV SAV C

~15 4 ~ATIVE PIT R RT SY 508 F-7 DIV AOV A TIVE BX Q ST-C Q PIT R FS-C Q LT-J R GR-2

gJALKTY AS%RANCE MANUAL ATZKQBKHI' System: RBACTOR COOLANT PRZR GINNA SATION Dwg No: 33013-1258 APHM)IX C VALVE TEMPTING BIGRAM PIAN FOR 'IHE 1990 1999 IFZERVAL Date: 1/6/94 Page: 38 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. z.ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 515 C-8 GTV MOV B

~15 ACTIVE EX Q ST-C Q PIT R 516 B 8 GTV MOV 1 B

~1 XVPIVE EX Q ST-C Q PIT R 528 SAV AC 125 ACTIVE LT-J R GR-2 CV-C Q 529 F-9 CV SAV 2 AC 1258 2 ACTIVE LT-J R GR-2 CV-C Q 539 B-7 GLV AOV 2 A

~155 ~

. 375 ~ATIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 546 B-8 GLV MAN 0

~1 ~75 BX Q LT-J R GR-2

g JAIZTY ASSUEQHCE MANUAL ATZACSMEPZ B System: REACTOR COOLANT PRZR GI'S. STATION Dwg No: 33013-1258 APPENDIX C VALVE TOUTING HK(2%M PIAN FOR 'IHE 1990 1999 ZRX19UTAL Date: 1/6/94 Page: 39 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 547 E-8 GLV 2 A

~15 . 75 LT-J R GR-2

QJALITY ASSURANCE MNUAL ATZACHMENZ B System: CVCS LETDONN GINNA SZhTION Dwg No: 33013-1260 APHRIDIX C VALVE TESTING E%0GRAM PIAN FOR 'IHE 1990 1999 INZEfUlAL Date: 1/6/94 Pa e: 40 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. 1ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 427

~lE-2 GLV AOV B PASSIVE PIT

tern:

gJAIZTY ASSURANCE MANUAL ATTACZMEPl' Sys REACTOR COOLANT GINNA SZATION Dwg No: 33013-1260 APPENDIX C VALVE TESZlNG HIRAM PIAN FOR %HE 1990 1999 1ÃH26TAL Date: 1/6/94 Page: 41 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PS ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 590 E 7 GLV SOV 2 B 111 1 AATIVE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9 591 E-8 GLV SOV 2 B

~1 1 WCTXVE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9 592 F-7 GLV SOV

~1 1 ACTIVE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT- R FS-C CS CS-9 593 F-8 GLV SOV 2 B

~1 1 XUPIVE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9

gJAIZTY ASSURANCE MANUAL ATZLCSMEMZ B System: RESIDUAL HEAT REMOVAL GINNA SZATXON Dwg No: 33013-1260 APPENDIX C VALVE TESZWG HKGBAM PXAN FOR %K 1990 1999 Ill;RVAL Date: 1/6/94 Page: 42 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 852A F-4 GTV MOV

~1 ACTIVE EX CS CS-15 ST-0 CS CS-15 ST-C CS CS-15 PIT R

,LT-X R 852B F-4 GTV MOV 1 A ACTIVE BX CS CS-15 ST-0 CS CS-15 ST-C CS CS-15 PIT R LT-X R 853A F-5 CV SAV 12120 ACTIVE LT-X R GR-5 EVENT V PIV T.S. 4.3.3 CV-P CS VR-3 CV-0 R VR-3 CV-0 AT 120 PSID CV-C R VR- 14 853B

~2F-5 CV SAV AC ACTIVE LT-X R GR-5 EVENT V PIV T.S. 4.3.3 CV-P CS VR-3 CV-0 R VR-3 CV-0 AT 120 PSID CV-C R VR-14

g1ALKTY ASSURANCE MANUAL ATZACSNEPZ B System: CONTAINMENT SPRAY GINNA STATION Dwg No: 33013-1261 APPENDIX C VALVE TESTING BIGRAM PIAN FOR %K 1990 1999 INZERVAL Date: 1/6/94 Page: 43 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number P&ID. ~ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 357 B-3 CV SAV 2 C 12f21 4 AATIVE CV-0 CS CS-25 836A

~ll H-3 GLV AOV 2 B MCTXVE EX Q ST-0 Q FS-0 Q 836B H-3 GLV AOV 12!21 ACTIVE EX Q ST-0 Q FS-0 Q 845C F-4 REV SAV 3 C

.~1 XVPIVE RT 10Y 845D F-4 REV SAV 12f21 ACTIVE RT 10Y 847A G-5 CV SAV C

~1 XllTTVE CV-0 Q CV-C Q 847B H-5 CV SAV 111 CV-0 Q CV-C Q

QUAIZH ASSURANCE MANUAL ATZLCHMENZ B System: CONTAINMENT SPRAY GINtQ. STATION Dwg No: 33013-1261 APHXDIX C VALVE TESTING HKGBAM PIAN FOR LHE 1990 1999 1ÃZERVAL Date: 1/6/94 Page: 44 of 92 Rev: 2 Valve Coor. age Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 859A E-6 GLV MAN 2 A

~22 1 PASSIVE LT-J R VR-31 859B G-6 GLV 2 A 122 1 7%BSTUE LT-J R VR-31 859C D-6 GLV A 12221 2 PAAP IVB LT-J R VR-31 860A

~ll E-7 GTV MOV 2 B

%CTHE BX Q ST-0 Q PIT R 860B E-7 GTV MOV ACTIVE BX Q ST-0 Q PIT R 860C I-7 GTV

~11 MOV EX Q ST-0 Q PIT R 860D I-7 GTV MOV 2 B

~12 1 ~ATTVE BX Q ST-0 Q PIT R

glAIZTY ASSURANCE MANUAL ATZLCSMEMZ B GINNA STATION System: CONTAINMENT SPRAY Dwg No: 33013-1261 APPENDIX C VALVE 'IKST'ING PROGRAM PIAN FOR 'IHE 1990 1999 INZERVAL Date: 1 6 94 Pa e: 45 of 2 R v: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 861 J-2 REV SAV 2 C 1111 . 75 MOTIVE RT 10Y 862A CV SAV 2

~II8 I E AC

~ATIV5 LT-J R GR-2 CV-0 Q VR-24 MECH EXERCISE CV-C

'C Q

862B I-8 CV

~11 SAV 2 ACTIVE LT-J GR-2 R

CV-0 Q VR-24 MECH EXERCISE CV-C Q 864A E-8 GLV A

~11 . 75 ~PAS IV5 LT-J R VR-31 864B H-8 GLV 2 A

~11 MAN VXEEV1E LT-J VR-31 R

869A

~llE-9 GLV

. 75 2 A PZZEIVE LT-J R GR-2 869B I-9 GLV MAN 2 A 11EX . 75 %BEIGE LT-J R GR-2

QUAIL ASSURANCE KNUAL System: CONTAINMENT SPRAY GINNA.'SZATION Dwg No: 33013-1261 APHXDIX C VALVE TESTING BIGRAM PIAN H)R 'IHE 1990 1999 IÃKRVAL Date: 1/6/94 Pa e: 46 of 92 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PaID. Bxze Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 875A

~ll F-9 GLV 2

MOV B PASSIVE EX Q ST-0 Q PIT R

• 875B G-9 GLV

~21 MOV 2 B KEFDTR EX Q ST-0 Q PIT . R

• 876A H-9 GLV MOV l2!21 2 PASSIVE EX Q ST-0 Q PIT R

• 876B G-9 GLV

~11 MOV 2 B TKBBTVE EX Q ST-0 Q PIT R 896A C-2 GTV MOV 12121 111 ACTIVE EX CS CS-17 ST-C CS CS-17 PIT R 896B D-2 GTV

~11 MOV 2 B KETTLE EX CS CS-17 ST-C CS CS-17 PIT R

g3AIZTY ASSUEQNCE MANUAL ATZLCSMERZ B System: CONTAINMENT SPRAY GI'S, STATION Dwg No: 33013-1261 APPENDIX C VALVE TESTING PROGRAM PIAN H)R 'IHE 1990 1999 INTERVAL Date: 1/6/94 page: 47 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 897 C-7 GLV MOV 2 B 12f21 ACTIVE EX Q ST-C Q PIT R 898 C-7 GLV MOV B

~11 MOTTLE EX Q ST-C Q PIT R 1802 F-3 REV SAV 12121 . 75 ACTIVE RT 10Y 1819A A-10 GLV MAN 2 A 1111 ACTIVE EX CS CS-19 LT-J R GR-2 1819B A-9 GLV 2 A

~11 MAN MOTIVE EX CS CS-19 LT-J R GR-2 1819C B-10 GLV MAN 2 A

~11 XCTTUE EX CS CS-19 LT-J R GR-2 1819D B-9 GLV

~1 EX LT-J CS R

'S-19 GR-2

gJAL'ETY ASSUMNCE MANUAL ATI'ACHMEWZ B System: CONTAINMENT SPRAY GI'S. STATION Dwg No: 33013-1261 APHXDIX C VALVE Ti~lNG ESOGRAM PIAN FOR 'IHE 1990 1999 IRZZZVAL Date: 1/6/94 Page: 48 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1819E C-10 GLV

~11 MAN 2 A XCTYVE EX CS CS-19 LT-J R GR-2 1819F C-9 GLV

~11 2 A ACTIVE CS-19' EX CS LT-J GR-2 1819G C-10 GLV

~11 MAN 2 A WVPTVE EX CS CS-19 LT-J R GR-2 2825

~ll E-8 GTV MAN 2 A PXBEVH; LT-J R GR-2 2825A F-8 BAV 2 A

~12 1 .5 ~PA5 IV5 LT-J R GR-2 2826 I-8

~11 BAV 2 A

%%BETISE LT-J R GR-2 2826A J-8 BAV 2 A PASSIVE LT-J R GR-2

QUAIZT'll ASSURANCE MANUAL ATZA.QiMEPZ B System: CONTAINMENT SPRAY GINNA SZATION Dwg No: 33013-1261 APPENDIX C VALVE TEETHING PROGRAM PIAN FOR 'IHE 1990 1999 lÃZERVAL Date: 1/6/94 Page: 49 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Pre CSJ Remarks 2829 E-9 GTV 2 A

~12 1 .75 ~PAE 2VE LT-J R VR-31 2830 I-9 GTV A

~11 MAN 2 VXEBTVE LT-J VR-31 R

2856 D-9 GTV 2 A 12121 . 75 PASSIVE LT-J R GR-2 2858 I-9 GTV 2 A 1111 . 75 VXEBTVE LT-J R GR-2

QUAIZZY ASSURANCE MANUAL System: SAFETY INJECTION AND ACCUMULATORS GINNA. STATION Dwg No: 33013-1262 APHM)IX C VALVE T1~)TGG BIGRAM PIAN FOR 'IHE 1990 1999 IPZlZUTAL Date: 1/6/94 Page: 50 of 92 Rev: 2 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PAID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks THIS PAGE INTENTIONALLY LEFT BLANK

QUAIZTY ASSURANCE MANUAL ATZACRMENZ B System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No: 33013-1262 APPENDIX C VALVE Tl&ZING PKIGRAM PIAN FOR 'IHE 1990 1999 INZHVTAL Date: 1/6/94 Page: Sl of 92 Rev: 2 Valve Number Coor.

P6ID.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 830A A-6 REV SAV 12122-2 1 ACTIVE RT 10Y 830B

~1~E-6 REV 1

SAV 2 C ACTVTI.

RT 10Y

• 834A A-5 GLV AOV

~12 2-2 1 PASSIVE PIT

• 834B E-5 GLV AOV 2 B 1 VXBBTPE PIT

• 835A C 4 GLV AOV C =

2 12t2-2 1 PASSIVE PIT 835B G-5 GLV AOV 11K~ 1 PIT

• 839A C-8 GLV AOV B 1:BY~ . 75 PASSIVE PIT

QUAIZTY ASSURANCE MANUAL System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No: 33013-1262 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 INXKRVAL Date: 1/6/94 Page: 52 of 92 Rev: 2 Valve Number Coor.

PE ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks

• 839B D-8 GLV AOV 1 B 22E:1 .75 VXEFG7F PIT

• 840A G-7 GLV AOV 2 B

~12-2 . 75 ~PEE EVE PIT

• 840B H-7 GLV AOV 1 B

~1 HEEIVE PIT 841 C-7 GTV MOV

~12-2 10 ACTIVE EX CS CS-33 ST-C CS CS-33 PIT CS 842A D-7 CV SAV AC

~121 Itt MOTIVE LT-X R CV-P Q VR-8 ALSO REQ AFTER DISASSEMBLY CV-0 6Y VR-8 VALVE DISASSEMBLY CV-C 6Y VR-8 VALVE DISASSEMBLY 842B G-7 CV SAV AC 11521 ~1 ~TOTE LT-X R CV-P Q VR-8 ALSO REQ AFTER DISASSEMBLY CV-O 6Y VR-8 VALVE DISASSEMBLY CV-C 6Y VR-8 VALVE DISASSEMBLY

QUMZTY ASSKQNCE MANUAL ATZACSMEPZ B System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No: 33013-1262 APPENDIX C VALVE T1XTING K%OGHAM PlAN FOR 'IHE 1990 1999 IN'ZAN Date: 1/6/94 Page: 53 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Baze Actuator Pos Class- Act Pas Tests Fre CSJ Remarks

• 844A C-8 GLV AOV 2 B 1Yt)~ 1 ~PA EIVE PIT

• 844B G-8 GLV AOV 2 B 11K~ 1 PXBETVE PIT 846 A-6 GLV AOV 2 A

~ATIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 865 G-7 GTV MOV 2 B 11E~ ~1 MCTXVE EX CS CS-33 ST-C CS CS-33 PIT CS 867A D-7 CV SAV AC 1121-2 ~1 LT-X R GR-5 EVENT V PIV - T.S. 4.3.3 CV-P R VR-9 ALSO REQ AFTER DISASSEMBLY CV-0 6Y VR-9 VALVE DISASSEMBLY CV-C 6Y VR-9 VALVE DISASSEMBLY 867B H-7 CV SAV AC 1121 Itt ACTIVE LT-X R GR-5 EVENT V PIV - T.S. 4.3.3 CV-P R VR-9 ALSO REQ AFTER DISASSEMBI Y CV-0 6Y VR-9 VALVE DISASSEMBLY CV-C 6Y VR-9 VALVE DISASSEMBLY

AITACHMENZ B System: SAFETY INJECTION AND ACCUMULATORS Dwg No: 33013-1262 VALVE TESTING PROGRM PIAN FOR 'IHE 1990 1999 lÃZlWEAL Date: 1/6/94 Page: of 54 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 870A C-7 CV SAV AC

~12-3 3 ACTIVE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR-11 CV-C Q 870B E-7 CV SAV AC 111 -1 ACTIVE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR-11 CV-C Q 871A D-7 GTV MOV 0 1212-3 3 ACTIVE EX Q ST-C Q PIT R 871B E-7 GTV MOV 0 2 B 111-3 %CTIME EX Q ST-C Q PIT R 872A C-2 CV SAV 2 C

~12 2-2 .75 ~ATTV5 CV-0 Q CV-C Q 872B I-3 CV SAV 111-2 . 75 ACTIVE CV-0 Q CV-C Q

QUAIZTE ASSURANCE MANUAL ATZACHMENZ B System: SAFETY INJECTION AND ACCUMULATORS GINNK STATION Dwg No: 33013-1262 APPENDIX C VALVE TESTING BIGRAM PIAN FOR 'IHE 1990 1999 INZERVAL Date: of 1/6/94 Page: 55 92 Rev: 2 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 877A E-3 CV SAV AC 1262-2 2 PASSIVE LT-X R GR-5 EVENT V PIV T.S. 4.3.3 877B I-6 CV SAV AC I.IE2- .. TKBEVH; LT-X R GR-5 EVENT V PIV - T.S. 4.3.3 878A E-3 GLV MOV A

~1 PASSIVE PIT R PIT DURING LT-X ONLY LT-X R GR-5 TECH SPEC PIV T.S. 4.3.3

• 878B D-4 GLV MOV 2 B 12122-2 2 PASSIVE PIT I-5 A 878C

~IE~ GLV MOV 2 VXBZTUE PIT R PIT DURING LT-X ONLY LT-X R GR-5 TECH SPEC PIV - T.S. 4.3.3

• 878D H-5 GLV MOV B 11K~ VXBBPH; PIT 878 F E-3 CV SAV 1 AC 12122-2 ~FEE IVE LT-X R GR-5 EVENT V PIV T.S. 4.3.3

QJMZTY ASSURANCE MANUAL System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No': 33013-1262 APHRlDIX C VALVE TESTING HIRAM PIAN FOR %HE 1990 1999 Ill."RVAL Date: 1/6/94 Page: 56 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 878G D-5 CV SAV 1 AC

~IE2-2 ACTIVE LT-X R GR-5 EVENT V PIV - T.S. 4.3.3 CV-0 R VR-10 CV-C Q 878H I-6 CV SAV AC 115~ KEETVE IT-X R GR-5 EVENT V PIV - T.S. 4.3.3 878J H-6 CV SAV AC ACTIVE LT-X R GR-5 EVENT V PIV - T.S. 4.3.3 CV-0 R VR-10 CV-C Q 879 G-5 GI V 2 A 75 VXBBTVE.

LT-J R GR-2 885A C-7 GLV 111-1 .75 ACTIVE EX Q LT-J R GR-2 885B F-8 GTV 0 2 A 111-1 .75 AETIVE EX Q LT-J R GR-2 887 H-8 REV SAV 2 C 111~ . 75 EATIVE RT 10Y

QUAlZTY ASSURANCE MANUAL ATZACKKWI' System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No: 33013-1262 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 IÃHWTAL Date: 1/6/94 Page: 57 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Sz.ze Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 889A C-5 CV SAV AC 12122-1 ACTIVE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR-11 CV-C Q F-6 889B

~1- I CV SAV 2 AC

~ATIVE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR-11 CV-C Q 891A B-3 CV SAV

~12 2-1 1.5 ACTIVE CV-0 Q CV-C Q 891B D-5 CV SAV C

~1 1 1.5 ~ATIV5 CV-0 Q CV-C Q 891C E-5 CV SAV 2 C 1112-1 1.5 ACTIVE CV-0 Q CV-C Q 1815A D-4 GTV MOV 0 1121-1 4 ACTIVE EX Q ST-0 Q PIT R

QUAIZTY ASSURANCE MANUAL ATZACHMEÃP B System: SAFETY INJECTION AND ACCUMULATORS GINNA STATION Dwg No: 33013-1262 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'IHE 1990 1999 IRZ196lAL Date: 1/6/94 Page: 58 of 92 Rev: 2 Valve Number Coor.

PE ID.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 1815B D-3 GTV 0

~1-1 4 MOV ACTIVE EX Q ST-0 Q PIT R 1817 D-4 REV SAV 2 O 111 -1 ACTIVE RT 10Y 8623

~1~A-3 CV 1

SAV 2 AC AATTVE IT-J R GR-2 CV-C Q 12406 B-7 GTV A

~1-1 MAN 2 VXBEXVE LT-J R GR-2 12407 E-8 GTV 111-1 .75 PASSIVE LT-J R GR-2

QJAIZTY ASSURANCE MANUAL ATZKCHMEÃZ B System: RCS OVERPRESSURE PROTECTION GINNA SIATION Dwg No: 33013-1263 APPENDIX C VALVE TESTING PELHAM PIAN FOR 'XHE 1990 1999 INTERVAL Date: 1/6/94 Page: 59 of 92 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 8606A B-4 CV SAV AC

~32 3 1 ACTIVE LT-X R CV-C R VR-19 8606B G-4 CV SAV AC ACTIVE LT-X R CV-C R VR-19 8608A C-4 REV SAV 1263 .75 ACTIVE RT 10Y 8608B G-4 REV SAV 2 C

~3 .75 %CTHE RT 10Y 8615A B-6 REV SAV 2

~13 1 C

~ATIVE RT 10Y 8615B F-6 REV SAV 2 C

~3 1 WVPIVE RT 10Y 8616A B-7 TWV SOV 2 B 12123 . 75 ACTIVE EX CS CS-11 ST-0 VR-15

QUAIZTY ASSURANCE MANUAL System: RCS OVERPRESSURE PROTECTION GINNK SZhTION Dwg No: 33013-1263 APHM)IX C VALVE Ti~NG PROGRAM PIAN FOR 'IHE 1990 1999 INXKfUTAL Date: 1/6/94 Page: 60 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 8616B G-7 TWV SOV B

~12 3 .75 ACTEVE EX CS CS"11 ST-0 'R-15 8619A C-9 TWV SOV

~12 3 1 ACTIVE EX CS CS-11 ST-0 VR-15 ST-C VR-15 8619B G-9 TWV SOV 2 B

~3 1 METISSE EX CS CS-11 ST-0 VR-15 ST-C VR-15 8630A C-9 CV SAV 2 C 12123 1 ACTEVE CV-0 CS CS-11 BY PORV TEST CV-C CS CS-11 8630B G-9 CV SAV 2 C 12123 1 ~ATIVE CV-0 CS CS-11 BY PORV TEST CV-C CS CS-11

gJAIZZY ASSURANCE MANUAL System: CVCS LETDOWN GINNA. STATION Dwg No: 33013-1264 APPENDIX C VALVE TESTING BIGRAM PXAN H)R %HE 1990 1999 IPZERVAL Date: 1/6/94 Page: 61 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre 'CS J Remarks 123 E-9 GLV AOV 1 A

~22 4 .75 ~PAE IVE LT-X R B-11 '

200A GLV AOV O,C

~14 EX CS-26 CS ST-C CS CS-26 PIT R, FS-C CS CS-26 LT-J R GR-2 LT-X R 200B B-10 GLV AOV O,C A

~14 1 EX CS-26 CS ST-C CS CS-26 PIT R FS-C CS CS-26 LT-J R GR-2 LT-X R 202 B-10 GLV AOV 1 A 111 4 XVFXVE EX CS CS-26 ST-C CS CS-26 PIT "R FS-C CS CS-26 LT-J R GR-2 LT-X R 203 A-8 REV

~14 SAV 2 AC ACTIVE LT-J R GR-2 RT 10Y

QJAIZTY ASSURANCE MANUAL AITACHMEFZ B System: CVCS LETDOWN GINNA. STATION Dwg No: 33013-1264 APPlM3IX C VALVE TESTING HIRAM PIAN FOR %HE 1990 1999 INITIAL Date: 1/6/94 Page: 62 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 310 C-9 GLV AOV

~14 . 75 1 B PASSIVE PIT 371 B-7 GLV AOV 2 A Wl'TIVE EX CS CS-26 ST-C CS CS-26 PIT R FS-C CS CS-26 LT-J R GR-2 702 A-10 CV SAV

~15 . 75 ACTIVE CV-0 CS-18 CS

gJAl~ ASSURANCE MANUAL ATZACHMEÃZ B System: CVCS CHARGING GINNA, SZATION Dwg No: 33013-1265 APPENDIX C VALVE Tl&ZBlG PROGRAM PIAN FOR 'IHE 1990 1999 ZPXKfUTAL Date: 1/6/94 Page: 63 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 112B F-3 BFV AOV 2 B 1115- 4 ~ATIVE EX CS CS-25 ST-0 CS CS-25 PIT R FS-C CS CS-25 112C D-3 BFV AOV 2 B 1115- 4 ~ATIVE EX CS CS-24 ST-C CS CS-24 PIT R FS-0 CS CS-24 142 E-10 GLV AOV 12125-2 2 ACTIVE EX CS CS-23 ST-0 CS CS-23 PIT R FS-0 CS CS-23 257 A-4 REV SAV 2 C 12!25-2 ~ATIVE RT 10Y 268 F-3 BFV 2 B 111~ 4 MOTIVE CS CS-24 270A F-3 GLV AOV 2 B

~15 -I 2 ACTIVE EX CS CS-21 ST-C CS CS-21 PIT R

QUAIZZY ASSURANCE MANUAL ATZA.GENT B System: CVCS CHARGING GINNA. STATION Dwg No: 33013-1265 APPENDIX C VALVE 'HXTING PROGRAM PIAN FOR THE 1990 1999 IÃIKRVAL Date: 1/6/94 Pa e: 64 of 92 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 270B F-6 GLV AOV

~12 5-1 ACTIVE BX CS CS-21 ST-C CS CS-21 PIT R 283 H-6 REV SAV C 2255~ . 75 WVPTVB RT 10Y 284 F-6 REV SAV 2 C 11215- . 75 AAAIvE RT 10Y 285 E-6 REV SAV 2 C 1ZP>~ Wl'.~v RT 10Y 302C G-6 CV SAV 2 C 12125-1 2 ACTIVE CV-0 Q NORMAL OPS SEAL FLOW 302D G-3 CV SAV 2 C 111 -1 WVFXOE CV-0 Q NORMAL OPS SEAT FIOW 304A H 3 CV SAV AC 12f2-1 ACTIVE LT-J R GR-2 CV-0 Q NORMAL OPS SEAL FLOW CV-C CS CS-21

QEKZTY ASSUEQÃCE MANUAL ATZACHMERZ B System: CVCS CHARGING GINNA SZhXION Dwg No: 33013-1265 APPENDIX C VALVE TESZING PROGRAM PXAN FOR 'IHE 1990 1999 lÃHZU1AL Date: 1/6/94 Page: 65 of 92 Rev: 2 Valve Coor. Tp>e Norm Safety Cate o Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 304B H-6 CV SAV 2 AC 12125-1 2 ~ATIVE LT-J R GR-2 CV-0 Q NORMAL OPS SEAL FLOW CV-C CS CS-21 313 D-8 GTV MOV EX CS CS-22 ST-C CS CS-22 PIT R LT-J R GR>>2 314 B-4 REV SAV C 111-1 METTLE RT 10Y 358 F-3 BFV 1115- 5 ACTIVE CS CS-25 370B B-2 CV SAV

~1-2 1 AC Ml.'TXVE LT-J R GR-2 LT-X R CV-0 CS CS-23 CV-C CS CS-23 383B H-2 CV SAV 111 -1 LT-J R GR-2 LT-X R CV-C CS CS-27

0 QUAIZZY ASSURANCE MANUAL ATZACHMENZ B System: CVCS CHARGING GINNA IZATION Dwg No: 33013-1265 APPENDIX C VALVE TESTING PROGRAM PIAN FOR 'HK 1990 1999 IÃZlURAL Date: 1/6/94 Page: 66 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 386 C-4 GTV AOV 12125-1 1 ACTIVE EX CS CS-22 ST-C CS CS-22 PIT R FS-C CS CS-22 392A A-9 GLV AOV BC 1115-1 2 ACTIVE PIT RT VR-16 393 A-10 CV SAV 12125-1 2 ACTIVE CV-0 CS CS-23 9315 A-9 CV SAV 1 C 111-1 XESTIVE CV-0 CS CS-23

QUAIZZY ASKHQNCE MANUAL ATZACHMENZ B System: RCDT GINNA SIATXON Dwg No: 33013-1272 APPENDIX C VALVE TESTING HKGBAM PIAN PDR THE 1990 1999 INTERVAL Date: 1/6/94 Page: 67 of 92 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1003A D-4 DIV AOV 12171 ACTIVE EX ST-C PIT FS-C LT-J GR-2 1003B E-4 DIV AOV 2 A XCTXV1~

EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1655 B-2 GLV A

~17~ ~75 MAN ACTIVE EX Q LT-J R GR-2 1709G E-3 GTV 1272-2 .75 PASSIVE LT-J R GR-2 1713 A-3 CV SAV AC XCTXVE LT-J R GR-2 CV-C CS CS-34

gJAIZTY ASSURANCE MANUAL ATZKCHMENZ B System: RCDT GINNA, STATION Dwg No: 33013-1272 APPENDIX C VALVE TESTING PROGRAM PIAN FOR LHE 1990 1999 IFHZUlAL Date: 1/6/94 Pa e: 68 of 92 Valve Coor. T}rpe Norm Safety Cate o Required Rel.Req Number P&ID. Fize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1721 D-3 DIV AOV 1117 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1722 D-3 DIV A IFT2-2 4 HiBBTVF LT-J R GR-2 1786 B-5 DIV AOV 2 A MVPV7E EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1787 B-5 DIV AOV

~172-2 1 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J GR-2 75.

R 1789 B-5 DIV AOV 0 2 A 111'2-.~ MOTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

QJAIZTY ASSURANCE MANUAL System: RCDT GINNA. SZAXXGN Dwg No: 33013-1272 APHM)IX C VALVE TESTING PROGRAM PXAN.

FOR THE 1990 1999 IPZERVAL Date: 1/6/94 Page: 69 of 92 Rev: 2 Valve Coor. Tg>e Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1793 A-3 DIV A 1272-2 1 ~PAS IVE LT-J R GR-2

• 1811A D 7 GTV MAN 2 B 117~ PAKTVE CLASS BOUNDARY ID - NO TEST REQ

• 18 1 1B E-7 GTV MAN 2 B

~1272- PPPSIVE CLASS BOUNDARY ID - NO TEST REQ

QUALMY ASQHQNCE KQKAL ATZA.CSMENZ B System: WASTE DISPOSAL - GAS GINNA SZAXXON Dwg No: 33013-1273 APHM)IX C VALVE TESTING HK)Sf'XAN FOR THE 1990 1999 IÃIKRVAL Date: 1/6/94 Page: 70 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 14 I-3 GLV AOV C SSC B 1273-2 2 ACTIVE EX Q PIT R FS-C Q

g3K~Y ASSUEQNCE MANUAL ATZKCHMENZ B System: H2 RECOMBINERS GINNA STATICN Dwg No: 33013-1275 APHZDIX C VALVE TESTING BIGRAM HAH FOR 'IHE 1990 1999 INZKRVAL Date: 1/6/94 Page: 71 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P6ID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1076A B-7 DIV

~17E-I 1 PASSIVE LT-J R GR-2 E-8 1076B

~1-I DIV 1

LT-J R GR-2 1080A E-1 GTV A 1275-1 1 ~PAE IVE LT-J R GR-2 1084A

~1-I D-7 DIV 1

2 EPi&s A

LT-J R GR-2 1084B G-8 DIV 2 A 1275-1 1 PASSIVE LT-J R GR-2

• 8423A IF~

A-6 CV 1

SAV 3 MCTVK C

CV-0 R

• 8425A G-5 CV SAV 3 C 1275-2 2 ~ATIVE CV-0 R

• 8427A F-5 CV SAV 3 C WCTVH; CV-0 R

gJAIZTY ASSURANCE MANUAL ATZA.QiMEWZ B System: H2 RECOMBINERS GINNA STATION Dwg No: 33013-1275 APHXDIX C VALVE TESTING HKGBAM PIAN FOR 'IHE 1990 1999 ZÃH56lAL Date: 1/6/94 Page: 72 of 92 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 8433A D-5 CV SAV I 1275-2 2 ACTIVE CV-0 R C

CV-0 R 10205Sl B-7 GTV SOV A

~127 -1 1 PASSIVE LT-J R GR-2 10209S1 D-7 GTV A

~1-2 1 SOV 2 VABEXVE IT-J R GR-2 10211Sl E-8 GTV SOV 1275-1 1 PASSIVE LT-J R GR-2 10213S1 G-8

~1-2 GTV 1

SOV 2 A VXBBTvH LT-J R GR-2 10214S1 C-1 GTV SOV 1275-1 1 PASSIVE LT-J R GR-2 10215S1 E-1 GTV SOV 111-1 1 LT-J R GR-2

QUALMY ASSURANCE MANUAL ATZACHMEMZ B System: S/G BLOWDOWN GINNK SZhTION Dwg No: 33013-1277 APPENDIX C VALVE TESTING HE@RAM PIAN FOR IHE 1990 1999 IFZERVAL Date: 1/6/94 Page: 73 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5735 A-4 GTV AOV 0 2

~177-1 .75 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J 5736 F-4 GTV AOV A

~1-1 2 WV?'IVB EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J 5737 H-5 GTV AOV 2 A

~177-1 ~ATIVE EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J 5738 C-5 GTV AOV 2 A

~1 1 MVPIVE EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J

gJAIZTY ASSURANCE MANUAL AITACHMENZ B System: NUCLEAR SAMPLING GINNA. STATION Dwg No: 33013-1278 APHXDIX C VALVE TEST:WG BIGRAM PIAN FOR 'IHE 1990 1999 lÃHZRAL Date: 1/6/94 Page: 74 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 921 G-1 GTV SOV 1278-1 .375 ACTIVE EX Q ST-0 Q GR-4 ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 922 H-2 GTV SOV 2 A 1278-1 ~75 ACTIVE EX Q ST-0 Q GR-4 ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 923 J-1 GTV SOV 1278-1 ~75 ACTIVE EX Q ST-0 Q GR-4 ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 924 I-2 GTV SOV 12171- 1 ~75 ACTIVE

'Q EX ST-0 Q GR-4 ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2

QUAIZTY ASSURANCE MANUAL ATZLCSMENZ B System: NUCLEAR SAMPLING GINNA, SIX%ON Dwg No: 33013-1278 APPENDIX C VALVE TESTING HKGBAM PIAN FOR '?HE 1990 1999 IPZERVAL Date: 1/6/94 Page: 75 of 92 Valve Coor. Tg>e Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 951 E-8 GLV AOV 1 B

~178-I .375 ~ATIV8 EX Q ST-C Q PIT R FS-C Q 953 D-8 GLV AOV 0 127I2-1 . 375 ACTIVE EX Q ST-C Q PIT R FS-C Q 955 B-8 GLV AOV 1 B ACTIVE EX Q ST-C Q PIT R FS-C Q 956D B-9 GLV 11271-1 .375 ACTIVE EX Q LT-J R GR-2 956E D-9 GLV MAN 1117 -I ~75 ACTIVE EX Q LT-J R GR-2 956F E-9 GLV MAN 2 A 1278-1 ~75 ~ATIV8 EX Q LT-J R GR-2

QUALITY ASSKQNCE MANUAL ATZACHMENZ B System: NUCLEAR SAMPLING GINNA STATION Dwg No: 33013-1278 APPENDIX C VALVE TtXT'ING BIGRAM PZAN FOR 'IHE 1990 1999 IÃZERVAL Date: 1/6/94 Page: 76 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 959 C-3 GLV AOV B

~PEE IVE PIT 966A E-9 GLV AOV A 111-3 ~7 WVFO7E EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 966B D-9 GLV AOV 12171-3 ~75 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 966C B-9 GTV AOV 2 A 111 -1 175 Xl.'THATS EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 7448 G-1 GTV A

~17 -1 . 375 PASSIVE LT-J R GR-2 7452 H-2 GTV MAN 2 A 111 -1 175 VXBEVHF LT-J R GR-2

gJAIZTY ASSURANCE MANUAL System: NUCLEAR SAMPLING GINNK SATION Dwg No: 33013-1278 APPED)IX C VALVE TESTING PROGRAM PIAN KR 'IHE 1990 1999 I FERIAL Date. 1/6/94 Page: 77 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 7456 I-1 GTV MAN A 12171-1 ~75 PASSIVE LT-J R GR-2

QUAIZTY ASSUEQÃCE MANUAL ATZLCHMEÃZ B System: POST ACC SAMP GINNK SZATION Dwg No: 33013-1279 APPENDIX C VALVE 'IESTXNG PE%GRAM PIAN FOR IHE 1990 1999 IPZERVAL Date: 1/6/94 Page: 78 of 92 Rev: 2 Valve Coor. Tg>e Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1723 E-2 DIV AOV

~>27 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1728 F-2 DIV AOV 2 A 111 WCTTUE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

g3AIZTY ASSURANCE MANUAL AITACHMEFZ B System: CONTAINMENT HVAC & RECIRC GINNA STATION Dwg No: 33013-1863 APE%ÃDIX C VALVE TESTING ESQGRAM PXAN FOR 'IHE 1990 1999 ZRZlHRAL Date: 1/6/94 Page: 79 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 1554 C-5 DIV 38383 . 75 PASSIVE LT-J R GR-2 1555 C-6 GTV MAN A P~D7E LT-J R GR-2 1556 C-5 DIV A 18183 . 75 PASSIVE LT-J R GR-2 1557 C-5 DIV MAN 2 A VABBTVE LT-J R GR-2 1558 C-5 GTV 18183 . 5 PASSIVE LT-J GR-2 1559 C-4 DIV MAN 2 A EKVH; LT-J R GR-2 1560 D-5 DIV 2 A 3383 . 75 PASSIVE LT-J R GR-2 1561 D-S GTV 2 A GR-2

QUALITY ASSURANCE MANUAL ALTACHMENZ B System: CONTAINMENT HVAC &. RECIRC GINNA STATION Dwg No: 33013-1863 APPENDIX C VALVE TESTING PROGRAM PIAN H)R 'LHE 1990 1999 IN'IKRVAL Date: 1/6/94 Pa e: 80 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 1562 D-5 DIV

~13 . 75 PAS IVE LT-J R GR-2 1563 J-5 DIV A KWiIVE LT-J R GR-2 1564 J-6 GTV A

~33 .5 PASSIVE LT-J R GR-2 1565 J-6 DIV MAN 2 A VXEBIUE LT-J R GR-2 1566 J-5 DIV C

~15 3 .75 PASSIVE LT-J R GR-2 1567 I-6 GTV MAN 2 A VR3iVE LT-J R GR-2 1568 J-6 DIV A

~13 . 75 2

PASSIVE LT-J R GR-2 1569 B-11 DIV 2 A

~1 .75 H>KHVR LT-J R GR-2

QUAIZTY ASSUEQHCE MANUAL ATZKCHMEtfZ B System: CONTAINMENT HVAC & RECIRC GINNA. SZhXXOH Dwg No: 33013-1863 APHM3IX C VALVE TESTING PROGRAM PIAN BDR 'IHE 1990 1999 IVZERVAL Date: 1/6/94 Page: 81 of 92 Rev: 2 Valve Number Coor.

PaID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 1570 B-11 GTV A

.5 LT-J R GR-2 1571 B-ll DIV MAN A PXBBVH; LT-J R GR-2 1572 B-12 DIV A 1818 . 75 PASSIVE

%XESTIVE LT-J R GR-2 1573 B- 12 GTV MAN 2 A LT-J R GR-2 1574 B-12 DIV 2 A

.75

. LT-J R GR-2

QJAIITY ASSURANCE MANUAL ATZACHMENT B System: CONTAINMENT HVAC PURGE SUPPLY GINNh. SZh'ZION Dwg No: 33013-1865 APPENDIX C VALVE TESTING PROGRAM PIAN FOR %HE 1990 1999 INZEZVAL Date: 1/6/94 Page: 82 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5869 F-9 BFV AOV SSC

~15 ~4 C

ACTIVE EX R OOS WITH FLANGE INSTALLED ST-C R PIT R FS-C R 7445 H-7 BFV AOV O,C 2 18f85 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 7478 H-8 BFV AOV 0, C 2 A XCTIVE; EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

g1AIZTY ASSURANCE MATERIAL ATZACHMENZ B System: CONTAINMENT HVAC PURGE EXHAUST GINNK STATION Dwg No: 33013-1866 APPENDIX C VALVE TESTING PROC%9M PIAN FOR 'IHE 1990 1999 IRZERVAL Date: 1/6/94 Page: 83 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 1596 I-10 GLV 111 1 ACTIVE EX Q LT-J R GR-2 1597 I-9 DIV AOV 1 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1598 G-10 DIV AOV 2 A 1 XVFXVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1599 G-10 DIV AOV 1181 1 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 5879 I-2 BPV AOV 2 B 111 ~4 WVl'V7E EX R OOS WITH FLANGE INSALLED ST-C R PIT R

~ FS-C R

g JAIZTY ASSURANCE MANUAL ATZACKKNZ B System: AUX/INT BUILDING HVAC GINNA SZATION Dwg No: 33013-1870 APPENDIX C VALVE TESTING PROGRAM PIAN FOR THE 1990 1999 IÃKRVAL Date: 1/6/94 Page: 84 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 7970 G-2 BFV AOV O,C 2 1117l ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 7971 G-4 BFV AOV O,C 2 EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

QEKZTY ASSUEQNCE MANDE System: CONTAINMENT VESSEL AIR TEST GINNA. SZAXXON Dwg No: 33013-1882 APPED)IX C VALVE TESTING HIRAM PIAN FOR 'THE 1990 1999 INTERVAL Date: 1/6/94 Page: 85 of 92 Rev: 2 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PEID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 7443 E-10 BFV MOV 2 A

~PA )~IVE PIT R LT-J R GR-2 7444 J-5 BFV MOV PASSIVE PIT R LT-J R GR-2

QUAIZTY ASSURANCE MANUAL ATZA.CHMEPZ B System: SERVICE AIR GINNA STATION Dwg No: 33013-1886 APPENDIX C VALVE TlM'ING PROGRAM PIAN FOR 'IHE 1990 1999 lÃZKUlAL Date: 1/6/94 Page: 86 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 7141 C-3 GTV xii-z PASSIVE LT-J R GR-2 C-5 7226 iiB~ CV SAV AC WVPIVE LT-J R GR-2 CV-C CS CS-34

QUAIZTY ASSUEQNCE MANUAL ATZKCHMEFZ B System: INSTRUMENT AIR GINNA, SZAXXGN Dwg No: 33013-1887 /1893 APPENDIX C VALVE TlXTING PROGRAM PIAN FOR 'IHE 1990 1999 INZERVAL Date: 1/6/94 Page: 87 of 92 Rev: 2 Valve Coor. age Norm Safety Cate o Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5393 D-4 CV SAV 0 AC 1887 ACTIVE LT-J GR-2 CV-C GR-3 5392 A-11 GTV AOV 2 A

~a WVPTR~

EX R VR-12 ST-C R VR-12 PIT R FS-C R VR-12 LT-J R GR-2

QUALITY ASSKQNCE MANUAL ATTACHMEÃZ A GINNA, SZATIOH H3MP TESTING PROGRAM PIAN APHXDIX C Date: 12 22 93 Pa e: 1 of 2 Rev: 2 FOR 'IHE 1990 1999 INTERVAL PREPARED BY: DATE:

APPPR~fEO Yi Y~ OAIE:y Pump Pump Dwg. Coor Safety Measured Parameters ID Class Fre N Pz MOTOR AUX FEED PAF01A 1237 B-5 3 Q N/A X PR-ll PR-1 X MOTOR. AUX FEED PAF01B 1237 E-5 3 Q N/A X PR-11 PR-1 X TURBINE AUX FEED PAF03 1237 I-5 3 X PR-11 PR-1 X STANDBY AUX FEED PSF01A 1238 '-5 3 Q N/A X PR-11 PR-1 X STANDBY AUX FEED PSF01B 1238 I-5 3 Q N/A X PR-11 PR-1 X D/G FUEL OIL PDG02A 1239-1 I-3 3 Q N/A PR-10 PR-10 PR-2 PR-11 PR-1 D/G FUEL OIL PDG02B 1239-2 I-9 3 Q N/A PR-10 PR-10 PR-2 PR-11 PR-1 COMPONENT COOLING PAC02A 1245 D-5 3 Q N/A X PR-11 PR-1 COMPONENT COOLING PAC02B 1245 E-5 3 Q N/A X PR-11 PR-1 RESIDUAL HT REMOVAL PAC01A 1247 F-5 2 Q N/A X PR"8 PR-8 PR-8/11 PR"1 X RESIDUAL HT REMOVAL PAC01B 1247 B-5 2 Q N/A X PR-8 PR-8 PR-8/ll PR-1 X

QUAIZTY ASSURANCE MANUAL GINNA. STATION APPENDIX C H3MP TESTING PROGRAM PIAN FOR %HE 1990 1999 IÃIKRVAL ate: 12/22/93 Page: 2 of 2 Rev: 2 Pump Pump Dwg. Coor Safety Measured Parameters ID Class Fre N Pi SPENT FUEL POOL PAC07A 1248 H-3 SSC Q N/A X PR-11 PR-1 X SPENT FUEL POOL PAC07B 1248 I-3 3 Q N/A X X PR-11 PR-1 X SERVICE WATER PSW01A 1250-1 D-2 3 Q N/A PR-4 X PR-12 PR-5/11 PR-1 SERVICE WATER PSW01B 1250-1 E-2 3 Q N/A PR-4 X PR-12 PR-5/11 PR-1 SERVICE WATER PSW01C 1250-1 F-2 3 Q N/A PR-4 X PR-12 PR-5/11 PR-1 SERVICE WATER PSW01D 1250-1 G-2 3 Q N/A PR-4 X PR-12 PR-5/11 PR-1 CONTAINMENT SPRAY PSI02A 1261 E-3 2 Q N/A PR-3 X X PR-11 PR-1 X CONTAINMENT SPRAY PSI02B 1261 I-3 2 Q N/A PR-3 X X PR-11 PR"1 X SAFETY INJECTION PSI01A 1262-1 C-4 2 Q N/A PR-3 X X PR-11 PR-1 X SAFETY INJECTION PSI01B 1262-1 F-4 2 Q N/A PR-3 X X PR-11 PR-1 X SAFETY INJECTION PSZ01C 1262-1 D-4 2 Q N/A PR-3 X X PR-11 PR-1 X CHARGING PCH01A 1265-2 E-5 2 PR-9 PR-9 X PR-11 PR-1 X CHARGING PCH01B 1265-2 G-5 PR-9 PR-9 X PR-11 PR-1 X CHARGING PCH01C 1265-2 H-5 2 PR-9 PR-9 X PR-11 PR-1 X

Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment C CSJ CHANGE CS-2 Revised to "valves will be verified to be capable of closing to agree with test method employed for 3518 and 3519.

CS-12 Deleted CSJ for 813 and 814. To be tested quarterly.

CS-20 Deleted CSJ for 8419. To be tested quarterly.

CS-24 Added that testing may be performed "during the process of shutting down when boric acid addition will not adversely affect plant operation".

CS-29 Deleted CSJ for 9227 and 9229. To be tested quarterly.

CS-35 Added CSJ for stroke time testing of 4297, 4298, 4480 and 4481 per phone conversation with NRC (formerly GR-6).

Page 1 of 1

QUALITY ASSURANCE MANUAL REV. 2 AGE 1 OF 8 GINNA STATION APPENDIK C PUMP AND VALVE EFHxrxvEDAm December 1, 1993 TESTING PROGRAM SIGNATURE ROCHESTER GAS AND ELECTRIC Dh'IE PREPARED BY:

ATTACHMENT C NUCLEAR PUMP 'AND VALVE COLD SHUTDOWN SAFETY Ec LICENSING

(/~pi<y JUSTIFICATION FOR THE 1990-1999 INTERVAL MANAGER, MECHANICAL EN GINEEIUNG Cold Shutdown Justification CS No. Valve ID CS-1 3516, 3517 CS-2 3518, 3519 CS-3 3410, 3411 CS-4 4619C, 4620B, 4622A, 4739B, 9634B CS-5 Deleted (3992, 3993, see VR-21)

CS-6 749A/B, 759 A/B CS-7 750A/B CS-8 4269, 4270, 4271, 4272 CS-9 590, 591, 592, 593 CS-10 430, 431C CS-11 8616A/B, 8619A/B, 8630A/B CS-12 Deleted (813, 814)

CS-13 700, 721 CS-14 701, 720 CS-15 852A/B CS-16 Deleted (853A/B, see VR-3)

CS-17 896A/B CS-18 702 CS-19 1819A through G CS-20 Deleted (8419)

CS-21 270A/B, 304A/B CS-22 313, 386 CS-23 142, 370B, 393, 9315 CS-24 112C, 268 CS-25 112B, 357, 358 CS-26 371, 200A/B, 202 CS-27 383B CS-28 856 CS-29 Deleted (9227/9229)

CS-30 697A/B CS-31 723A/B CS-32 710A/B CS-33 841,865 CS-34 1713,7226 CS-35 4297, 4298, 4480, 4481

REV.

QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE GINNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL Cold Sh tdown Justification CS - 1: Valves 3516 and 3517 are main steam isolation valves.

Closure of these valves during power operation could result in a reactor trip. Testing will be performed during cold shutdown.

CS - 2: Valves 3518 and 3519 are main steam line non-return valves. Exercising these valves to the closed position is not possible without isolating the main steam header. This would require a power reduction and possible undesirable system transients that can result in a reactor trip which is unacceptable from an operational view point. These valves will be verified to be capable of closing during normal plant shutdown to cold shutdown, when, the main steam isolation valves are closed. If the plant shutdown is a result of a plant trip, these valves will be verified to be capable of closing subsequent to the plant trip.

CS -. 3: Valves 3410 and 3411 are atmospheric relief valves.

Exercising these valves during power operation would cause severe system transients that could result in a plant trip. Testing will be performed during cold shutdown.

CS - 4: Valves 4619C, 4620B, 4622A, 4739B and 9634B are redundant Station Service Water (SSW) outlet valves from Component Cooling Water heat exchangers, spent fuel pit heat exchangers, Safety Injection Pump motor coolers and Standby Auxiliary Feedwater room coolers.

These valves are required to open to provide a flowpath for service water to the Deer Creek discharge pipe. These flowpaths would only be required when the normal discharge canal became blocked. Due to environmental restrictions on discharges to Deer Creek, quarterly testing is not practical. Testing will be performed during cold shutdown.

CS - 5: Deleted (3992 and 3993 are addressed in VR-21).

CS - 6: Valves 749 A 8 B and 759 A E B are Component Cooling Water (CCW) supply and return valves to the Reactor Coolant Pump (RCP) thermal barriers. Stroking these valves to the closed position during power operation would interrupt cooling flow to the RCP thermal

REV.

QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE GINNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL barriers. This could result in damage to an operating reactor coolant pump and a reactor trip.

Testing will be performed during cold shutdown.

CS - 7: Valves 750 A 9 B are Component Cooling Water (CCW) supply check valves to the reactor coolant pump thermal barriers. Reverse flow exercising of these valves would require isolation of CCW to the thermal barriers. This could result in damage to an operating reactor coolant pump and a reactor trip.

Testing will be performed during cold shutdown.

CS - 8: Valves 4269 and 4270 are main feedwater regulating valves. Valves 4271 and 4272 are their respective bypass valves. During power operation, exercising these valves would be impractical. Closing the valves during operation could isolate feedwater to the steam generators which can result in severe transients including loss of RCS heat sink and a reactor trip. Testing will be performed during cold shutdown.

CS - 9: Valves 590, 591, 592 and 593 are reactor vessel head vent valves. Stroking these valves during power operation should not be performed since exercising these valves would allow discharge of reactor coolant into the containment atmosphere. Also, exercising the inboard valve at power tends to burp the system, which could possibly unseat the closed valve.

Furthermore, failure of any one of these valves in the open direction would reduce the system to single-valve-protection between RCS and Containment atmosphere. Testing will be performed during cold shutdown.

CS - 10: Valves 430 and 431C are Pressurizer Power Operated Relief Valves (PORV). Normally closed, these valves open to protect against excessive pressure surges.

Exercising these valves during power operation could cause unplanned pressure transients in the RCS resulting in a reactor trip. Testing will be performed following power operation during cooldown (at a point >330 F, <<350'F, <<410 psig) to verify operability prior to LTOP operation. Testing will also be performed during cold shutdown prior to heatup.

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QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE GINNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL CS - 11: Valves 8616 A 8 B are Overpressure Protection System (OPS) surge tank charging valves. Valves 8619 A R B are Nitrogen three way solenoid actuating valves for the power operated relief valves (PORVs). Valves 8630 A 8 B are the PORV actuating line check valves.

Exercising these valves during power operation would actuate the power operated relief valves. Valve testing will be performed at cold shutdown in conjunction with the PORV exercising as described in CS - 10.

CS - 12: Deleted (813, 814)

CS - 13: Valves 700 and 721 are the inboard isolation valves isolating the Reactor Coolant System (RCS) from Residual Heat Removal (RHR) suction and return lines.

Exercising these valves is not possible due to a high pressure interlock which prevents the valves from is above 410 psig. Testing will be performedpressure opening when RCS during cold shutdown.

CS - 14: Valves 701 and 720 are outboard isolation valves isolating the Reactor Coolant System (RCS) from Residual Heat Removal (RHR) suction and return lines.

Exercising these valves during power operation is impractical. Failure of one of these valves in the open position would reduce the system to single-valve-protection between the RCS and RHR systems.

Leakage of the associated inboard valve could cause an inter-system LOCA. Testing will be performed during cold shutdown.

CS - 15: Valves 852A & B are Residual Heat Removal (RHR) discharge motor operated valves to the reactor vessel. These valves open to provide safety injection flow to the reactor vessel. These valves should not be exercised during normal power operation as this would reduce the system to single-valve-protection between the RCS and RHR system and could result in an intersystem LOCA outside of containment.

Testing will be performed during cold shutdown; CS - 16:

/

Deleted (853A/B are addressed in VR-3)

CS - 17: Valves 896 A E B are Refueling Water Storage Tank (RWST) outlet isolation valves. Exercising these valves during power operation is impractical.

Failure of one of these valves in the'closed position

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QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP'ND VALVE COLD SHUTDOWN PAGE ~

GINNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL during power operation would render both containment spray and safety injection trains inoperable which would require shutting down the reactor. Testing will be performed during cold shutdown.

CS - 18 Valve 702 provides a flow path from the Residual Heat Removal (RHR) discharge line to the letdown header for pressure relief. Exercising this check valve during power operation would require isolating letdown which could result in loss of pressurizer level control and cause a reactor trip. Testing will be performed during cold shutdown.

CS - 19: Valves 1819A thru G are containment pressure transmitter isolation valves. These normally open valves are containment isolation valves. Exercising these valves during power operation can disable associated pressure channels and cause a plant trip function to be inoperable. Testing will be performed during cold shutdown.

CS - 20: Deleted (8419)

CS - 21: Valves 304 A & B are Reactor Coolant Pump (RCP) seal injection line check valves. Valves 270 A & B are RCP seal water return line isolation valves.

Exercising these valves would require isolation of seal injection/return to RCP seals which could damage seals and require the plant to shut down. Full flow capability will be verified quarterly based on normal operating seal injection flow, and valve exercising will be performed during cold shutdown.

CS - 22: Valves 313 and 386 are seal water return and seal bypass return line isolation valves. Stroking these valves in the closed position during normal operation would interrupt flow from RCP seals which could damage seals and require the plant to shut down.

Testing will be performed during cold shutdown.

CS - 23: Valves 142 and 370 B are the charging flow control valve and charging header check valve. Valves 393 &

9315 are charging line to Reactor Coolant System (RCS) Loop B hot leg check valves. Exercising these valves during power operation would isolate charging flow to the RCS which could result in loss of pressurizer level control and cause a reactor trip.

In addition, exercising these valves during power

QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE INNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL operation may result in excessive thermal cycles to the regenerative heat exchanger which could cause premature equipment failure and reduction in its expected service life. Testing will be performed during cold shutdown.

CS - 24: Valve - 112 C is the Volume Control Tank (VCT) outlet and valve 268 is the manual isolation. Exercising these valves during power operation would isolate the charging pumps normal suction path, and require placing an alternate flow path in service. Alternate suction flow paths would cause a sudden increase in RCS boron inventory and thereby cause a plant transient and possible shutdown. Testing will be performed during cold shutdown or during the process of shutting down when the addition of boric acid during valve manipulation will not adversely affect plant operation.

CS - 25: Valve - 112 B is the Refueling Water Storage Tank (RWST) to charging supply valve. Valve 357 is the RWST to charging suction line check. Valve 358 is the bypass valve for 112 B. Exercising these valves during power operation would cause a sudden increase in the RCS boron inventory, and thereby cause a plant transient and possible shutdown. Testing will be performed during cold shutdown.

CS - 26: Valves 200A, 200B, 202 and 371 are letdown isolation and containment isolation valves. Exercising these valves during power operation could isolate letdown flow from the Reactor Coolant System (RCS) which would result in loss of pressurizer level control and cause a reactor trip. Testing will be performed during cold shutdown.

CS - 27: Valve 383 B is the containment isolation valve for the alternate charging line. Reverse flow exercising of this valve is impractical during power operation because this test would result in substantial radiation exposure to test personnel. Surveys in the area of test connections 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 reverse flow exercised at cold shutdowns.

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QUALITY ATTACHMENT C ASSURANCE MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE GINNA STATION JUSTIFICATION OF APPENDIX C FOR THE 1990-1999 INTERVAL CS - 28: Valv'e 856 is the Residual Heat Removal (RHR) pump suction supply valve from the RWST. This valve should not be exercised during power operation as this would isolate the RWST from the RHR system.

This would render both RHR trains inoperable which would rec(uire plant shutdown. Testing will be performed during cold shutdown.

CS - 29: Deleted (9227, 9229)

CS - 30: Valves 697A and 697B are Residual Heat Removal (RHR) heat exchanger outlet check valves. These valves open to allow safety injection flow to the reactor vessel. Exercising these valves during power operation is not possible as RHR pump discharge is insufficient to overcome reactor coolant system pressure. These valves will be partial stroke exercised at cold shutdown and full stroke exercised at refueling outages.

CS - 31: Valves 723A and 723B are Component Cooling Water (CCW) pump discharge check valves. These valves open to allow CCW flow through the system. Exercising these valves during power operation to the full open position may cause the standby pump to auto start on low header pressure and possibly cause check valve cycling. These valves will be partial stroke open exercised to 2500 GPM quarterly and full stroke open exercised to 2980 GPM during cold shutdown.

CS - 32: Valves 710A and 710B are Residual Heat Removal (RHR) pump discharge check valves. These valves close to prevent reverse flow during cold shutdown when the pump discharge headers are crosstied. Exercising these valves during power operation is not practical as this would require crosstying the discharge headers thus rendering both trains of RHR inoperable.

Testing will be performed during cold shutdown.

CS - 33: Valves 841 and 865 are Saf ety Inj ection (SI) accumulator isolation valves. These valves are closed to isolate the SI accumulators during Reactor Coolant System (RCS) cooldown. Exercising these valves during power operation is not practical due to the Technical Specification requirement to maintain these valves locked open with power removed when RCS pressure is above 1600 psig. Failure of these valves in the closed position would require shutting down

QUALITY ATTACHMENT C ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE COLD SHUTDOWN PAGE GINNA STATION JUSTIFICATION APPENDIX C FOR THE 1990-1999 INTERVAL 8, 8 Coolant System (RCS) cooldown. Exercising these valves during power operation is not practical due to the Technical Specification requirement to maintain these valves locked open with power removed when RCS pressure is above 1600 psig. Failure of these valves in the closed position would require shutting down the reactor. Testing will be performed during cold shutdown.

CS - 34: Valves CV1713 and CV7226 are nitrogen and service air supply check valves to containment. CV1713 is isolated during power operation via locked closed manual valve 1793 thus precluding quarterly testing.

CV7226 is used only during refueling outages and is isolated during power operation on both the upstream and downstream sides thus precluding quarterly testing. Testing of these valves will be performed during cold shutdown.

CS - 35: Valves 4297 and 4298 open to provide and control auxiliary feedwater flow from the turbine-driven auxiliary feedwater pump to the steam generators Valves 4480 and 4481 are bypass flow control valves from the motor-driven auxiliary feedwater pumps that close on an SI signal to isolate the steam generators. During startup, valves 4480 and 4481 are used to provide better flow control to the steam generators.

These valves are hand control valves which operate using a variable set air signal. They do not have a typical control switch. Position indication is not directly indicated, only the control air signal is indicated. Manual activation of these valves is not possible in the present configuration. Lifting of leads or jumpers for the valve controls would be necessary. Stroke timing during power operation would require rendering these valves inoperable and entering a Limiting Condition for Operation (LCO).

Valves 4297 and 4298 perform their safety function by opening, are normally open and fail open. Valve 4480 and 4481 perform their safety function by closing, are normally closed and fail close.

Measurement and evaluation of stroke times shall be performed during cold shutdown. These valves will be excercised and fail-safe tested quarterly.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990- 1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. CR - 1 CODE RE UIREMENT CONSIDERED -IMPRACTICAL IWA-1400 of the ASME Boiler and Pressure Vessel Code,Section XI, 1986 Edition requires that arrangements be made with an Authorized Inspection Agency to provide inspection services.

In addition, the Code requires that certain administrative functions be performed by the "Enforcement Authority" and "Authorized Inspector".

Rochester Gas & Electric's Ginna Nuclear Power Plant is located in the state of New York. This state has not endorsed the ASME Nuclear Codes and therefore does not provide administrative'rganization and controls such as "Enforcement Authority" "Authorized Inspector" and "Reporting Systems".

However, Ginna Station's Quality Assurance Program does provide for these administrative control requirements.

Therefore, Rochester Gas R Electric requests that the Ginna Station Quality Assurance Program continue to be used in lieu of Code administrative functions.

2. BASIS F R RELIEF Rochester Gas a Electric's program for inservice pump and valve testing, governed by the Ginna Station Quality Assurance Manual, contains requirements and responsibilities for implementation of the program and procedures. Procedures have been prepared and approved by responsible organizations within Rochester Gas s Electric, (i.e., Ginna Station, Engineering, Research and Science, Electric Transmission and Distribution and Purchasing).

Approved procedures will be. implemented to control the performance of tests and evaluation of corresponding r'esults.

These procedures include test personnel requirements, and provisions for recording names of test personnel.

Qualifications for test personnel are in accordance with USNRC Regulatory Guide 1.58 "Qualification of Nuclear Plant Inspection, Examination and Testing personnel".

TITLE:

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 These procedures also include the method of performing the test, acceptance and rejection criteria, and test result reporting, evaluation and approval requirements.

In addition, Ginna Station procedures prescribe actions required when test results are determined to be unacceptable.

Procedures are also utilized to govern repair, replacement and related retesting.

IST records and reports are developed and maintained by Rochester Gas 8 Electric and include such items as completed test procedures, data sheets, schedules and corrective action documentation.

The functions of the ASME authorized inspector, namely their reviews and verifications, will be performed by personnel of the Hartford Steam Boiler Inspection and Insurance Company.

The qualifications of the inspectors, inspection specialists and inspection agency are in compliance with the Code.

3. ALTERNATIVE PROVISI NS An NRC endorsed Quality Assurance Program that meets the requirements of 10CFR50 Appendix B shall assure that the inservice pump and valve testing related activities are conducted in accordance with the commitments of the IST Program.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. PR-1 SYSTEM: Various PUMPS: All Safety Related Pumps SAFETY CLASS: 2 and 3 FUNCTION: Various TEST REQUIREMENT: Yearly Measurement of Bearing Temperature BASIS FOR RELIEF: A) Bearings of certain pumps addressed in this relief request are cooled by their respective process fluid.

Thus, bearing temperature measurements would be highly dependent on the temperature of the cooling medium.

B) Bearing temperatures taken at one-year intervals provide little data toward determining incremental degradation of a bearing or providing any meaningful trend information.

C) All pumps addressed by this relief request are subjected to vibration measurements on a quarterly basis in accordance with IWP-4500. Vibration measurements are a signif icantly more reliable indication of pump bearing degradation than are temperature measurements.

ALTERNATE TESTING: Pump mechanical condition of its bearings will be determined by quarterly vibration monitoring. Bearing temperatures will not be measured.

R EV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 6 66 RELIEF REQUEST NO. PR-2 SYSTEM: D/G Fuel Oil Transfer System PUMPS: Diesel Fuel Oil Transfer Pumps (PDG02A, PDG02B)

SAFETY CLASS:

FUNCTION Various TEST REQUIREMENT: Flow rate shall be measured using a rate or quantity meter installed in the pump test circuit. (IWP-4680) .

BASIS FOR RELIEF: Measurement of diesel fuel oil transfer pump flowrate is determined by observing the rate of change in the diesel generator day tanks as they are being filled. A graduated sight glass located on the day tank is the only practical means available to calculate flow rates.

ALTERNATE TESTING: Flow rate will be determined by calculation of day tank level increase vs. time.

TITLE: R EV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 7 66 RELIEF REQUEST NO. PR-3 SYSTEM: a. Containment Spray (CS)

b. Safety Injection (SI)

PUMPS a. Containment Spray 'Pumps (SIAPCS 1, 2)

b. Safety Injection Pumps (SIAPSI 1, 2, 3)

SAFETY CLASS:

FUNCTION: Various TEST REQUIREMENT: Measure pump inlet pressure before pump start and during test (Table IWP-3100-1).

BASIS. FOR RELIEF: Due to system design, the SI and CS pumps do not have installed local or remote inlet pressure reading devices. The pumps are aligned to the Refueling Water Storage Tank (RWST) during testing and calibrated level indication is provided in the control room.

ALTERNATE TESTING: Pump suction pressure for these systems will be calculated utilizing RWST levels.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 8 66 RELIEF REQUEST NO. PR-4 SYSTEM: Service Water (SW)

PUMPS Service Water Pumps (PSWO 1A, 1B, 1C, 1D)

SAFETY CLASS:

FUNCTION: Supply Station Service Water 'to equipment and cooling units in the plant.

TEST REQUIREMENT: - Measure pump inlet pressure before pump start and during test (Table IWP-3100-1).

BASIS FOR RELIEF: Service water pumps are submerged multistage vertical pumps and inlet pressure is assumed to correspond to that of the static head of the medium in which the pumps reside (lake). Since the lake level remains essentially constant throughout the duration of the test, only one measurement is required.

ALTERNATE TESTING: For the Service Water pumps a single suction pressure will be calculated for each test based on submergence of the pump.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 9 66 RELIEF REQUEST NO. PR-5 SYSTEM: Service Water (SW)

PUMPS: Service Water Pumps (PSWO 1A, 1B, 1C, 1D)

SAFETY CL'ASS:

FUNCTION: Supply Station Service Water to equipment and cooling units in the plant.

TEST REQUIREMENT: On a pump coupled to the driver, the vibration measurement shall be taken on the bearing housing near the coupling. (IWP-4510).

BASIS FOR RELIEF: The Service Water pumps are vertical, multistage pumps submerged in their process fluid and thus are inaccessible.

Therefore, vibration measurement is impractical.

ALTERNATE TESTING: Vibration measurements will be taken on the pumps'ssociated motor bearing housing for indication of pump bearing degradation.

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QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990- 1999 INTERVAL OF APPENDIX C 10 66 RELIEF REQUEST NO. PR-6 SYSTEM: Various PUMPS All safety related pumps SAFETY CLASS: 2 and 3 FUNCTION: Various TEST REQUIREMENT: The full scale range of each instrument shall be three times the reference value or less. (IWP-4120)

BASIS FOR RELIEF: Vibration detectors usually have multiple overlapping scales rather than a single full range scale. It is not practical to apply the requirement of three times the reference value or less. When the reference value falls under 0.5 mils, a detector in the three-times-or-less scale would not allow a measurement in the required action range of 1.5 mils. (e.g, with a 0.3, mil reference value, using a detector with a range of 0.9 mils, determination of"Alert Range" (1-1.5 mils) or "Required Action Range" (>1.5 ,mils) could not be accomplished.

ALTERNATE TESTING: A vibration detector with multiple overlapping scales will be used. The amplitude of vibration for each test will determine which scale is to be used.

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QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 11 66 RELIEF REQUEST NO. PR-7 THIS PAGE INTENTIONALLY LEFT BL'ANK (DELETED FOR SERVICE WATER PUMP FLOW)

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIK C 12 66 RELIEF REQUEST NO. PR-8 SYSTEM: Residual Heat Removal (RHR)

PUMPS Residual Heat Removal Pumps (ACAPRH1,2)

SAFETY CLASS: 2 FUNCTION: Supply safety injection flow to the reactor vessel.

TEST REQUIREMENT: The resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value (IWP-3100).

BASIS FOR RELIEF: During power operation the RHR pumps can only be tested utilizing the minimum-flow return lines. These lines have flow orifices installed and do not allow throttling to an established reference value for either flow or pressure.

ALTERNATE TESTING: These pumps shall be tested quarterly measuring 'observed flow,,differential pressure and vibration. During cold shutdowns/refueling outages these pumps shall be tested using the main flow path.

Data from both test frequencies shall be trended as required by IWP-6000. (re, Generic Letter 89-04, Attachment 1 Position 9)

42428 TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 13 66 RELIEF REQUEST NO. ~PR-SYSTEM: CVCS Charging PUMPS Charging Pumps A, B R C (PCH01A, 1B, 1C)

SAFETY CLASS:

FUNCTION: The charging pumps function to control RCS inventory, chemistry conditions, activity level, boron concentration and to provide seal water to the RCPs.

TEST REQUIREMENT: The test quantities shown in Section XI, Table IWP-3100-1 (inlet pressure in particular) shall be measured or observed and recorded.

BASIS FOR RELIEF: The charging pumps are positive displacement type pumps. The measurement of pump inlet (suction) pressure provides no useful data for evaluation of pump performance or for detecting pump degradation.

ALTERNATE TESTING: Pump discharge pressure shall be measured in lieu of pump differential pressure per OMa-1988, Part 6 Table 2.

TITLE:

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 14 66 RELIEF REQUEST NO. PR-10 SYSTEM: D/G Fuel Oil Transfer System PUMPS Diesel Fuel Oil Transfer Pumps (PDG02A, PDG02B)

SAFETY CLASS:

FUNCTION: Various TEST REQUIREMENT: The test quantities shown in Section XI, Table IWP-3100-1 (differential pressure in particular) shall be measured or observed and recorded.

BASIS FOR RELIEF: The D/G fuel oil transfer pumps are positive displacement type pumps. The measurement of pump inlet (suction) pressure provides no useful data for evaluation of pump performance or for detecting pump degradation. Therefore, pump differential pressure, as required by the Code, will provide no useful data.

ALTERNATE TESTING: Pump discharge pressure shall be measured in lieu of pump differential pressure per OM-1987, Part 6 Table 2.

REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 15 66 RELIEF REQUEST NO. PR-11 SYSTEM: Various PUMPS: All safety related pumps SAFETY CLASS: 2 and 3 FUNCTION: Various TEST REQUIREMENT: The test quantities shown in Section XI, Table IWP-3100-1 (vibration amplitude in particular) shall be measured or observed and recorded.

BASIS FOR RELIEF: The monitoring of pump vibration by measuring displacement amplitude has been the convention in the past. However, advances made in vibration monitoring technology indicate peak velocity to be a more encompassing indication of pump degradation. Through use of state-of-the-art equipment, peak velocity has shown to be more predictive of pump failure and, subsequently, more cost effective regarding preventive maintenance and spare parts inventory.

ALTERNATE TESTING: Test measurement of vibration using peak velocity (in accordance with OMa-1988, Part 6, Table 2) vice displacement amplitude shall be phased into this program coinciding with the maintenance schedule of pump overhauls. In the interim, prior to the next pump overhaul, pump vibration shall be measured as displacement amplitude.

8 EV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS I'A+E GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 16 66 RELIEF REQUEST NO. PR-12 SYSTEM: Service Water (SW)

PUMPS Service Water Pumps (PSWO 1A, 1B, 1C, 1D)

SAFETY CLASS:

FUNCTION: Supply Station Service Water to equipment arid cooling units in the plant.

TEST REQUIREMENTS: Instrument accuracy shall be within the limits of table IWP-4110-1 (IWP-4110). The full-scale range of each instrument shall be three times the reference value or less (IWP-4120) .

BASIS FOR RELIEF: The present system configuration and instrumentation does not provide permanently installed flow indication at the SW pump discharge piping to provide a positive means of determining full flow during pump tes ts. Employing a clamp - on ultrasonic flowmeter to measure full SW pump discharge flow is not currently addressed in ASME Section XI, Subsection IWP (Code).

The Code requires an instrument accuracy of 2 - percent of full scale. The clamp-on ultrasonic flowmeter possesses an instrument accuracy of 3 percent of actual flow. Although the percentage error (3 percent of actual flow as compared with 2 percent of full scale) is stated as a larger numerical value, the actual absolute value of instrument inaccuracy at the reference flow rate of 5,600 gpm (approximate SW pump design) is actually less for the clamp-on ultrasonic flowmeter.

The accuracy of the reading from a 0-10,000

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QUALITY ATTACHMENT D ASSURANCE PAGE

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MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. PR-12 CONT.

gpm analog gauge is 5,600 + 200 gpm (2 percent of full scale). The accuracy of the reading from the clamp-on ultrasonic flowmeter is 5,600 + 168 gpm (3 percent of actual flow).

Thus, the actual maximum instrument error of the flow reading, as read on the clamp-on ultrasonic flowmeter, is less than the error as read on the analog gauge at the specified flow rate of 5,600 gpm.

The full-scale range (calibrated) of the clamp-on ultrasonic flowmeter is 40 ft/sec.

This corresponds to a flow rate of approximately 17,000 gpm (for 14 inch pipe), which exceeds three times the reference value of 5600 gpm.

Relief is requested since the clamp-on ultrasonic flowmeter yields a more accurate flow reading at the specified SW pump test flow rate of 5600 gpm and since the range of the clamp-on ultrasonic flowmeter meets the requirement of ASME/ANSI OMa-1988, Part 6, Paragraph 4.6.1.2(b) (i.e. reference flow rate c 70% of calibrated range).

This substantial improvement in test method provides for the measurement of a sufficiently accurate and repeatable value for SW pump flow rate. By employing this test method and obtaining the pump's corresponding differential pressure, the hydraulic performance of the SW pump can be more accurately assessed. Repeatability of flow rate measurement will be ensured through the permanent installation of clamp-on ultrasonic flowmeter instrumentation via the Ginna Station minor modification process.

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QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF RELIEF REQUEST NO. PR-12 CONT.

ALTERNATE TESTING: SW pump flow testing will utilize a permanently installed clamp-on ultrasonic flowmeter to allow flow rate measurement at a reference flow equivalent to the design point of the SW pumps.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 1 SYSTEM: Various VALVES: All Power Operated Valves CATEGORY: A and B SAFETY CLASS: Various FUNCTION: Various TEST REQUIREMENT: Vylves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdown. (IWV-3412(a))

BASIS FOR RELIEF: All motor operated and air operated valves in the Ginna IST Program have a design logic that prohibits part-stroking of the valve. The circuits are such that when an open or close signal is received, the valve must complete a full stroke before the relay is released to allow the valve to stoke in the other direction.

impractical to part-stroke the valves.

It is ALTERNATE TESTING: Valves for which full-stroke exercise is not practical during power operation, will be full-stroke exercised during cold shutdown.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 2 SYSTEM: Containment Isolation VALVES: All those valves identified with "LT-J" in the "Required Tests" column of the Pump and Valve Program Plan.

CATEGORY: A. or A/C SAFETY CLASS: Various FUNCTION: Provide containment isolation.

TEST REQUIREMENT: a ~ IWV-3421 through 3425 regarding leak rate test methodology.

b. IWV-3427(b) regarding leak rate trending requirements.

BASIS FOR RELIEF: a ~ It is NRCs staff position as in Generic Letter No. 89-04, outlined Position 10 that leak test procedures and requirements for containment isolation valves specified in 10CFRSO, Appendix J are equivalent to requirements of IWV-3421 through 3425.

b. Industry data shows that the variability of leak rates for valves six inches and larger is excessive.

Ginna feels that this excessive variability shows the relative independence of one leak rate test to another. The tendency towards random leak rate data would cause unnecessary testing per IWV-3427(b), with no identifiable increase in benefit to public health and safety.

REV.

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 2 CONT.

ALTERNATE TESTING: Containment isolation valves will be tested under the requirements of 10CFR50 Appendix J. Leakage shall be analyzed as required by IWV-3426 and corrective action initiated in accordance with IWV-3427 (a).

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 3 SYSTEM: Instrument Air VALVES: 5393 CATEGORY: A/C SAFETY CLASS:

FUNCTION: Provide containment isolation.

TEST REQUIREMENT: Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: When this valve is in operation there is no practical means to test valve closure.

Valve closure cannot be verified due to system design. To perform a closure verification constitutes a leak test which presents a significant hardship during cold shutdown. Leak testing requires an extended period of time where instrument air must be secured. Securing instrument air would cause the loss of vital safety and operational functions.

ALTERNATE TESTING: Verification of valve closure will be done in conjunction with the 10 CFR 50 Appendix J Type C leak tests (LT-J) conducted at least once every two years.

REV.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 4 SYSTEM: See Attachment VALVES: See Attachment CATEGORY: See Attachment SAFETY CLASS: See Attachment FUNCTION: See Attachment TEST REQUIREMENT: ASME Code Section XI, Subarticle IWV-3417(a) requires trending stroke time test results for power operated valves and taking appropriate corrective action.

BASIS FOR RELIEF: Since these valves are fast acting and stroke rapidly, measurement of the stroke time of these valves to the nearest second per IWV-3413 (b) means that a very small increase in stroke time results in an extremely large percentage of change.

Verification that test values meet a specified maximum stroke time of a relatively short duration provides adequate assurance of their operability.

ALTERNATE TESTING: -A maximum stroke time of two (2) seconds will be. assigned for these valves. If this limiting stroke time is exceeded, the valve will be declared inoperable and corrective action taken. (re: Generic Letter 89-04, Attachment 1 - Position 6)

~ .r QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF GR - 4 Attachment Valve ~S stem Cate~cry Safet Class Function 590 RCS B F1 591 RCS B F1 592 RCS B F1 593 RCS B F1 5907 EDG B F2 5907A EDG B F2 5908 EDG B F2 5908A EDG B F2 921 Nuc. Sample A F3 922 Nuc. Sample A F3 923 Nuc. Sample A F3 924 Nuc. Sample A F3 9632A SW B F4 9632B SW B F4 F1: Provide venting capability from reactor vessel head to ensure core cooling during natural circulation,cooldown.

F2: Provide diesel fuel oil transfer from fuel oil storage tanks to Diesel Generator day tanks.

F3: Isolate Containment Hydrogen Monitors F4: Provide Service Water to Standby Auxiliary Feedwater (SAFW)

Room Coolers

42428 TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. GR - 5 SYSTEM: See Attachment VALVES: See Attachment CATEGORY: See Attachment SAFETY CLASS: See Attachment FUNCTION: Provide reactor coolant system pressure isolation.

TEST REQUIREMENT: Valve leak rate testing per ASME Code Section XI, Subarticle INV-3421 through IWV-3427.

'BASIS FOR RELIEF: Leakage testing, including testing requirements is governed by plant Technical Specifications. These valves are adequately tested per Technical Specifications. Testing criteria utilized meets the intent of ASME Section XI leak rate testing. Therefore it is impractical to perform separate leak rate tests.

ALTERNATE TESTING: These valves will be leak rate tested in accordance with RCS Pressure Isolation Valve leak rate testing per Technical Specifications.

REV.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF GR - 5 Attachment Valve ~sstem CategoOr Safet Class 853A RHR A/C 853B RHR A/C 867A SI A/C 867B SI A/C 878G SI A/C 878J SI A/C 878A SI A 2 878C SI 2 877A SI A/C 1 877B SI A/C 1 878F SI A/C 1 878H SI A/C 1

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF RELIEF REQUEST NO. GR-6 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 142, 4297, 4298, 4480 AND 4481)

(See CS-23 s CS-35)

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OFi RELIEF REQUEST NO. GR - 7 SYSTEM: Various VALVES: All Power Operated Valves CATEGORY: A and B SAFETY CLASS: Various FUNCTION: Various TEST REQUIREMENT: Evaluation of power operated valve stroke time and initiation of corrective action

( IWV-3417 (a) ) .

BASIS FOR RELIEF: The intent of the Code requirement is to initiate increased testing to verify a valve can continue to perform its intended function when it has degraded. Due to the variance in testing frequencies some valves may degrade over a period of time.

Measuring changes in stroke time from the reference value (established when the valve is known to be in good condition) is a better indication of valve degradation.

ALTERNATIVE TESTING: Changes in stroke time shall be measured from the reference value when determining increased test frequency requirements and initiation of corrective action per IWV-3417(a). (re: Generic Letter 89-04, Attachment 1 - Position 5)

REV.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF RELIEF REQUEST NO. VR - 1 SYSTEM: Emergency Diesel Generator Air Starting System I VALVES: 5933A 5933Bi 5934A 5934B CATEGORY: B-SAFETY CLASS:

FUNCTION: These valves open to provide starting air to the diesel generators.

TEST REQUIREMENT: Stroke time of power operated valves shall be measured per IWV-3413 and evaluated per IWV-3417.

BASIS FOR RELIEF: These are rapid acting solenoid valves whose design prohibits visual observance of

, stroking as there are no external indicators on these valves. Diesel start times are affected by valve stroke times.

ALTERNATE TESTING: Measurement and evaluation of stroke times shall not be performed. Valve exercising is performed monthly in conjunction with diesel generator start testing. Valve stroking parameters will be considered acceptable if the associated Ifdiesel generator start is acceptable. the diesel generator failed to start, due to other identified malfunctions, repairs would be made and the air start valve stroking parameters will be verified during a restart following diesel generator corrective action.

REV.

QUALITY ATTACHMENT D ASSURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. VR - 2 SYSTEM: Emergency Diesel Generator Fuel Oil VALVES: 5960A, 5960B CATEGORY:

SAFETY CLASS:

FUNCTION: These check valves open to provide a flow path for overflow from the fuel oil day tank to the fuel oil storage tank. These valves close to prevent reverse flow into the fuel oil day tank during recirculation of the fuel oil storage tank.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: During operation there is no practical means to exercise these valves. Valve closure cannot be verified due to system design. To perform a closure verification would require disassembly of mechanical joints in the piping, which would place the diesel in an inoperable condition.

ALTERNATE TESTING: One valve will be disassembled, full-stroke exercised and inspected each refueling outage on a rotating basis.

fails, the remaining valve will be If that valve disassembled, full-stroke exercised and inspected for operability during that same outage. (re: Generic Letter 89-04, Attachment 1 - Position 2)

REV.

QUALITY ATTACHMENT D AS SURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. VR - 3 SYSTEM: Residual Heat Removal (RHR)

VALVES: 853A, 853B CATEGORY: A/C SAFETY CLASS:

FUNCTION: These RHR discharge check valves to the reactor vessel are normally closed valves and open with differential pressure to provide a flow path for reactor vessel low-head safety injection flow. In the closed position, they. serve as reactor coolant system pressure isolation valves.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Full or partial stroking during power operation is not possible because RHR pump discharge pressure is insufficient to overcome reactor coolant system (RCS) pressure.

were high Even enough, if any pump discharge pressures stroking could cause the injection of cold borated water into the system, resulting in power and thermal transients.

These valves cannot be full-stroke exercised during cold shutdown because establishing required safety analysis flow through them could result in excessive RCS cooldown.

QUALITY ATTACHMENT D AS SURANCE PAGE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF RELIEF REQUEST NO. VR - 3 CONT ALTERNATE TESTING: These valves will be partial stroke exercised at cold shutdown and full stroke exercised at refueling during the refueling cavity fill;-

REV.

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. VR - 4 SYSTEM: Residual Heat Removal (RHR)

VALVES: 854 CATEGORY:

SAFETY CLASS:

FUNCTION: Valve 854 opens with differential pressure to provide a flow path from the Refueling Water Storage Tank (RWST) .to low head safety injection pumps (RHR) during safety injection. This valve is normally closed during operation.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3421)

BASIS FOR RELIEF: Valve stroking is not possible during power operation because RHR pump discharge pressure is insufficient to overcome reactor coolant system (RCS) pressure.

This valve cannot be full-stroke exercised during power operation since downstream valves to the Reactor Coolant System (RCS) cannot open against the higher RCS pressure.

This valve cannot be full-stroke exercised during cold shutdown because establishing required safety analysis flow through could result in excessive RCS cooldown.

it ALTERNATE TESTING: Valve 854 will be full stroke exercised during the refueling cavity refueling outages.

fill at

Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment D CHANGE PR-7 Deleted relief request for reduced flow testing for service water pumps.

PR-10, Relief requested from the requirement for measuring differential and inlet pressure for diesel generator fuel oil transfer pumps since they are positive displacement type pumps. Discharge pressure is measured per OMa-1988, Part 6.

PR-11 Relief requested from the requirement for measuring vibration in displacement amplitude. Vibration measurement in peak velocity to be phased in.

PR-12 Relief requested from the requirement for instrument accuracy.

Service water pump testing to employ Controlotron ultrasonic flow instruments.

GR-6 Deleted relief request for stroke time testing of hand control valves. HCVs to be stroke time tested annually.

VR-2 Corrected typo. Safety class is class 3 for 5960A/B.

Revised to include additional basis.

VR-13 Revised to stroke time test yearly.

VR-17 Deleted relief request for disassembly of service water pump discharge check valves. Service water pump testing allows full open exercise.

VR-30 Deleted relief request per NRC letter dated 11/4/93.

Submitted CS-35 in its place.

VR-3 1 Submitted request for relief from App. J testing of CS valves 859A, 859B, 859C, 864A, 864B, 2829 and 2830 per NSGL CIV submittal.

VR-32 Submitted request for relief from App. J testing of check valve 9229, Fire Service Water containment isolation valve per NS&L CIV submittal.

Page 1 of 1

QUALITY ASSURANCE MANUAL REV. 2 IAGE 1 OF 66 GINNA STATION APPENDIX C PUMP AND VALVE EIvzcnvEnATE: December 1, 1993 TESTING PROGRAM SIGNATURE ROCHESTER GAS 8e ELECTRIC CORPORATION PREPARED EY:

gRutJa > 1<h 4 ATTACHMENT D NUCLEAR SAFETY A PUMP AND VALVE RELIEF REQUESTS LICENSINO ~j'Z7/WP FOR THE 1990-1999 INTERVAL MANAOER, MECHANICAL ENOINEERINO LW~~ ~ ee Relief No. ~TC iC CR-1 Administrative Aspects of the Code..........

PR-1 Bearing Temperature Measurement.............

PR-2 D/G Fuel Oil Transfer System Flowrate.......

PR-3 Cnmt. Spray/SI Pump Inlet Pressure..........

PR-4 Service Water Pump - Inlet Pressure.........

PR-5 Service Water Pump Vibration Measurement....

PR-6 Test Instrumentation Scale Ranges...........

PR-7 Deleted (Service Water Pump - Flow Rate)....

PR-8 Residual Heat Removal - Flow Rate...........

PR-9 Charging Pump - Differential Pressure.......

PR-10 D/G Fuel Qil Transfer Pumps - Differential Pressure PR-11 Vibration Measurement.......................

PR-12 Service Water Pump - Flow Measurement.......

GR- 1 MOV and AOV Partial Excercising........

GR-2 App J Isolation Valves - Leak Testing.......

GR-3 Reverse Closure in Conjunction with App J GR-4 Leak Tests................................

Rapid Acting Valves - Trending.........

GR-5 RCPB Isolation Valves - Leak Testing........

GR-6 Deleted (Hand Control Valve Stroke Timing)..

GR-7 Valve Stroke Time - Evaluation and Corrective Action..........

VR- 1 5933A/B, 5934A/B..

VR-2 5960A/B..

VR- 3 853A/B ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR-4 8 54 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR- 5 9627A/B.

VR- 6 4324, 4325, 4326....

VR- 7 434, 435............

VR- 8 842A/B....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR-9 867A/B. ~

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 VR- 10 8 78G/ J ~ ~ ~

870A/B......................

o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR- 11 889A/B, VR- 12 5 392 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR- 13 VR- 14 4291, 4304, 4310, 9710A/B...........

VR- 15 8616A/B, 8619A/B....

VR- 16 3 92A o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR- 17 Deleted (4601, 4602, 4603, 4604)....

VR- 18 VR- 19 5907, 5907A, 5908, 5908A............

8 6 0 6A/B ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR-20 7 1 OA/B ~

3993..........................

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR-21 3992/

VR- 22 Deleted (841, 865, see CS-33).......

VR- 23 Deleted (4023)...................... ~ \ ~ ~ ~ ~ ~ ~

VR- 24 862A, 862B......

VR- 25 VR-26 Deleted (5941A, 5942A)............

998, 4000 C/D, 4003, 4004, 4007, 400 8 VR- 27 VR- 28 9704 A/B, 9705 Deleted (8655)......

A/B................ ~ ~ o ~ ~ ~

VR- 29 6 9 7A/B ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VR- 30 Deleted (4297, 4298, 4480, 4481).... ~ ~ ~ ~ ~ ~ ~ ~

VR-31 859A, 859B, 859C, 864A, 864B, 2829, 2830....

VR- 32 9229. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

REV.

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. VR - 5 SYSTEM: Standby Auxiliary Feedwater VALVES: 9627A, 9627B CATEGORY:

SAFETY CLASS:

FUNCTION: These service water suction check valves close to prevent reverse flow. from Standby Auxiliary Feedwater System (SAFW) piping back into the Service Water (SW) System and open to provide a flow path for service water to the SAFW pumps.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Full-stroke exercising cannot . be accomplished during power operation or cold shutdown as this would introduce Service Water to the Standby Auxiliary Feedwater system. Service water does not meet water purity requirements for the system or steam generators. Service water would be supplied to steam generators during required monthly pump tests valves 9627A and B was performed.

if exercising ALTERNATE TESTING: Partial stroke exercising will be performed each quarter. One valve will be disassembled, full-stroke exercised and inspected each refueling outage on a rotating basis. If that valve fails, the remaining valve will be disassembled, full-stroke exercised and inspected for operability during that same outage. (re.

Generic Letter 89 Position 2).

REV.

QUALITY ATTACHMENT D ASSURANCE MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF RELIEF REQUEST NO. VR - 6 SYSTEM: Station Service Water System VALVES: 4324, 4325, 4326 CATEGORY:

SAFETY CLASS:

FUNCTION: Valves open upon an auxiliary feedwater pump bearing cooling water supply high strainer differential pressure to provide cooling water to the driver's bearings.

TEST REQUIREMENT: Measure stroke time and analyze per IWV-3413.

BASIS FOR RELIEF: These are rapid acting valves. These valves automatically actuate on high differential pressure across the supply strainer. Measurement of stroke times during manual actuation, for testing, is not practical and would not produce consistent, meaningful or trendable results. On a monthly basis, these valves are tested during auxiliary feedwater pump testing. This testing includes strainer cleaning, strainer isolation, high differential pressure simulation, verification of valve operation and flow observation. Failure of these valves to stroke in conjunction with a clogged strainer would result in a lack of pressure at the bearing cooler inlet and a high DP alarm, to which an Operator would be dispatched who would manually trip the respective valve. Stroke timing of these vylves using conventional methods would be extremely difficult and unrepeatable. RGSE is actively pursuing non-intrusive diagnostic test methods, however, commitment of this methodology for testing of these valves is not practicable at this time.

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 36 66 RELIEF REQUEST NO. VR - 6 ALTERNATE TESTING: These valves will be stroke tested during associated auxiliary feedwater pump testing by closing the valve downstream of the strainer. Acceptable valve operation will be based on acceptable service water pressure at the bearing cooler inlet.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 37 66 RELIEF REQUEST NO. VR - 7 SYSTEM: Reactor Coolant Pressurizer VALVES: 434, 435 CATEGORY: C SAFETY CLASS:

FUNCTION: Pressurizer Safety Relief valves provide overpressurization protection for the reactor coolant system/pressurizer.

TEST REQUIREMENT: Valves with remote position indicators shall be observed at least once every 2 years to verify that valve operation is accurately indicated. (IWV-3300).

BASIS FOR RELIEF: These valves are mechanical spring-actuated valves. If these valves were actuated for a position indication test, they would need to be retested to ensure the set relief pressure is correct. This involves increased testing and unnecessary radiation exposure to testing personnel.

ALTERNATE TESTING: These valves will be simulated to actuate using existing station calibration procedures. The procedure utilizes movement of the valve's coil (up/down) and verifies position via an alarm in the Control Room. Calibration of these position indicators is governed by Plant Technical Specifications and is, performed on a refueling basis.

REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL- PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OP APPENDIX C 38 66 RELIEF REQUEST NO. VR - 8 SYSTEM: Safety Injection VALVES: 842A, 842B CATEGORY: A/C SAFETY CLASS:

FUNCTION: These valves open to provide flow from Safety Injection (SI) Accumulators to the reactor coolant system (RCS) .

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522. (INV-3521)

BASIS FOR RELIEF: Full-stroke open and close exercising during normal power operation cannot be accomplished as system pressures required to perform the test are not enough to overcome RCS pressure. Full stroke exercising during cold shutdown requires injection into the RCS which could result in low temperature overpressuriation of the RCS, nitrogen binding of the RHR pumps, or flooding/radiological contamination test is conducted with the reactor vessel if the head removed. Also, additional radiological exposure (3-5 person-rem) would result and the plant would have to be maintained in an unusual condition. Use of freeze-plugs or core offloading (with consequential

TlTLE: R EV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 39 66 RELIEF REQUEST NO. VR-8 CONT additional radiological exposure and increase in potential fuel handling incidents) would be required.

Partial- stroke exercising is perf ormed quarterly using the SI test header.

Maintenance history and valve disassembly and inspection have shown these valves to exhibit no evidence of excessive degradation.

ALTERNATE TESTING: Disassembly of both valves once every six years. Each valve shall be disassembled as determined by scheduling and plant conditions. If a valve fails, the remaining valve will be disassembled and inspected for operability at that same time.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990- 1999 INTERVAL OF APPENDIX C 40 66 Q

SYSTEM: Safety Injection VALVES: 867A, 867B CATEGORY: A/C SAFETY CLASS:

FUNCTION: Provides a flowpath from the accumulators or safety injection pumps to the Reactor Coolant System (RCS) cold legs.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Full-stroke or part stroke exercising dUring normal power operation cannot be accomplished since system pressures rec(uired to perform the test are not enough to overcome RCS pressure. Full-stroke exercising during cold shutdown requires injection into the RCS, which could cause low temperature overpressurization of the RCS, nitrogen binding of the RHR pumps, or flooding/radiological contamination test is conducted with the reactor vessel if the head removed. Also, additional radiological exposure (3-5 person-rem) would result and the plant would have to be maintained in an unusual condition. Use of freeze-plugs or core offloading (with consequential additional radiological exposure and increase in potential fuel handling incidents) would be required.

Partial flow exercising is accomplished each refueling by actual SI flow into the RCS. Maintenance history and valve

42428 TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIK C 41 66 RELIEF REQUEST NO. VR-9 CONT disassembly and inspection have shown these valves to exhibit no evidence of excessive degradation.

ALTERNATE TESTING: Di.sassembly of both valves once every six years. Each valve shall be disassembled as determined by scheduling and plant conditions. If a valve fails, the remaining valve will be disassembled and inspected for operability at that same time.

TITLE: REV.

QUALITY ATTACHMENT, D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIK C 66 RELIEF REQUEST NO. VR - 10 SYSTEM: Safety Injection VALVES: 878G, 878J CATEGORY: A/C SAFETY CLASS:

FUNCTION: Provides a flowpath from safety injection pumps to A and B Accumulator cold leg injection lines.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Full or partial stroking during power operation is not possible because safety injection pump discharge pressure is insufficient to overcome reactor coolant system pressure. Exercising during cold shutdowns could cause low temperature overpressurization of the reactor coolant system.

ALTERNATE TESTING: These valves will be full-stroke exercised during refueling outages.

0 TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 43 66 RELIEF REQUEST NO. VR - 11 SYSTEM: Safety Injection VALVES: 889A, 889B, 870A, 870B CATEGORY:

SAFETY CLASS: 2 FUNCTION: These normally closed valves open with differential pressure to provide a flow path from Safety Injection (SI) pumps to the Reactor Coolant System (RCS).

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: During operation, the safety injection pump discharge pressure is insufficient to overcome RCS pressure. SI pump recirculation test line size is insufficient to allow full stroke exercising during operation.

Exercising during cold shutdowns could cause low temperature overpressurization of the Reactor Coolant System.

ALTERNATE TESTING: These valves will be part-stroke exercised every three months during operation and full-stroke exercised during refueling outages.

TITLE: R EV.

QUALITY ATTACHMENT D ASSURANCE 12/1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990- 1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. VR - 12 SYSTEM: Instrument Air VALVES: 5392 CATEGORY:

SAFETY CLASS:

FUNCTION: Provides containment isolation for the instrument air line.

TEST REQUIREMENT: Valves shall be exercised to the position required to fulfill (IWV-3412) every three months.

their function once BASIS FOR RELIEF: Stroking valve 5392 during operation and cold shutdown is impractical because would interrupt instrument air to it containment and be disruptive to air-operated valves inside containment.

Loss of instrument, air would cause all air-operated valves to be actuated to their fail-safe position. During power operation, this would lead to a reactor trip and during cold shutdowns, this would compromise plant operation due to the loss of various components used in maintaining the reactor in a cold shutdown condition.

ALTERNATE TESTING: This valve will be full-stroke exercised during refueling outages.

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS R4+E GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 45 66 Q

SYSTEM: Auxiliary Feedwater/Standby Auxiliary Feedwater (AFW/SAFW)

VALVES: 4291, 4304, 4310, 9710A, 9710B CATEGORY: B SAFETY CLASS:

FUNCTION: These valves open to allow recirculation of the AFW/SAFW pumps to prevent pump cavitation, overheating or deadheading upon low flow to the steam generators.

TEST REQUIREMENT: Stroke time of power operated valves shall be measured per IWV-3413 and evaluated per IWV-3417.

BASIS FOR RELIEF: These valves operate based upon a pressure/flow signal only. Manual activation of these valves is not practical in the present configuration. Lifting of leads or jumpers, or installation of new instrumentation or controls would be necessary. Stroke timing during normal valve operation is affected by variations in system parameters, therefore measurement of stroke times for these valves could only be performed by simulating these parameters in a controlled manner.

ALTERNATE TESTING: Measurement and evaluation of stroke times shall be performed will be exercised yearly. These valves and fail-safe tested quarterly.

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 46 66 RELIEF REQUEST NO. VR-14 SYSTEM: Residual Heat Removal (RHR)

VALVES: 853A, 853B CATEGORY: A/C SAFETY CLASS:

FUNCTION: To provide reactor coolant boundary pressure isolation.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by INV-3522. (IWV-3521)

BASIS FOR RELIEF: During power operation, there is no practical means to test valve closure.

Valve closure cannot be verified due to system design. To perform a closure verification constitutes a leak test which presents significant hardships during cold shutdown, such as excessive radiation exposure to test personnel and extended outage time.

ALTERNATE TESTING: Verification of valve closure will be made in conjunction with ASME XI leak tests conducted during refueling outages.

0 TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. VR - 15 SYSTEM: Overpressure Protection Nitrogen Supply System VALVES: 8616A, 8616B, 8619A, 8619B CATEGORY:

SAFETY CLASS:

FUNCTION: These valves open to provide nitrogen to cycle power operated relief valves (PORV) providing Reactor Coolant System (RCS) overpressure protection'.

TEST REQUIREMENT: Stroke time of power operated valves shall be measured per IWV-3413 and evaluated per IWV-3417.

BASIS FOR RELIEF: These are rapid acting valves whose design prohibits visual observance of stroking.

These valves do not have remote position indicators. PORV stroke times are affected by stroke times of 8616A, 8616B, 8619A and 8619B.

ALTERNATE TESTING: Valve stroke testing is performed during plant shutdown in conjunction with PORV ozerpressure protection testing. Valve stroking parameters will be considered acceptable if the associated PORV cycling is acceptable.

operate, due If theotherPORV identified to failed to malfunctions, nitrogen valve stroking parameters will be considered acceptable and reverified during a retest following PORV corrective action.

TITLE: 8 EV.

QUALITY ATTACHMENT D ASSURANCE 12/1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990- 1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. VR - 16 SYSTEM: CVCS Charging VALVES: 392A CATEGORY: B/C SAFETY CLASS:

FUNCTION: Valve 392A functions as a relief valve when closed to provide a charging system flowpath to the reactor coolant system loop B hot leg.

TEST REQUIREMENT: Relief valves shall be tested per ANSI OM-1 (IWV-3510).

BASIS FOR RELIEF: Valve 392A is a welded, in line air-operated valve and will open with a 250 pound differential pressure across the disc. Due to its design, set pressure and seat tightness testing is not appropriate.

ALTERNATE TESTING: Valve 392A will be tested in place each refueling outage by verifying that it open and pass the required flow at design will differential pressures.

TlTLE:

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 RELIEF REQUEST NO. VR - 17 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR SERVICE WATER PUMP DISCHARGE CHECK'ALVES)

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 50 66 RELIEF REQUEST NO. VR - 18 SYSTEM: Emergency Diesel Generator Fuel Oil VALVES: 5907, 5907A, 5908, 5908A CATEGORY:

SAFETY CLASS:

FUNCTION: These valves open and close to direct fuel oil to Diesel Generator (D/G) day 'tanks or back to the diesel oil storage tanks.

TEST REQUIREMENT: Stroke time of power operated valves shall be measured per IWV-3413 and evaluated per IWV-3417.

BASIS FOR RELIEF: These are rapid acting solenoid valves whose design prohibits visual observation of stroking as there are no external indicators -on these valves. These valves are automatically actuated as necessary bqsed upon diesel oil day tank levels.

These valves do not have control switches.

Diesel generators are tested monthly (per Tech. Specs.), during which these valves actuate for filling the day tanks and for diesel oil recirculation. No history of diesel generator testing failure has been attributed to performance of these valves.

ALTERNATE TESTING: Measurement and evaluation of stroke time shall not be performed. These valves shall be exercised and fail safe tested at least quarterly during diesel generator testing.

Valve stroking parameters will be considered acceptable based upon satisfactory actuation as demonstrated by adequate fuel flow. during the D/G tests'

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 51 66 RELIEF REQUEST NO. V~R-I SYSTEM: Overpressure Protection Nitrogen Supply System VALVES: 8606A, 8606B CATEGORY: A/C SAFETY CLASS:

FUNCTION: To provide pressure isolation for the overpressure protection system nitrogen accumulators.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: When these valves are in operation, there is no practical means to test valve closure. Valve closure cannot be verified due to system design. To perform a closure verification constitutes a leak test which presents a significant hardship during cold shutdown. Leak testing requires an extended period of time where the overpressure protection system would be out of service.

ALTERNATE TESTING: Valve closure verification will be performed in conjunction with ASME XI leak tests conducted during refueling outages.

TITLE:

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 52 66 RELIEF REQUEST NO. VR - 20 SYSTEM: Residual Heat Removal (RHR)

VALVES: 710A, 710B CATEGORY:

SAFETY CLASS: 2 FUNCTION: These check valves must open to allow full rated flow from each RHR pump for low pressure safety-injection.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, to the position required to fulfill their safety function, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: These valves cannot be full-stroke exercised during power operation since downstream valves to the Reactor Coolant System (RCS) cannot open against the higher RCS pressure. These valves cannot be full-stroke exercised during cold shutdown because establishing required safety analysis flow thru them could result in excessive RCS cooldown.

ALTERNATE TESTING: These check valves are partial-flow exercised at least quarterly during RHR system testing. Full-stroke testing of these valves shall be performed during each refueling outage.

4242B TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 53 66 RELIEF REQUEST NO. VR - 21 SYSTEM: Main Feedwater VALVES: 3992, 3993 CATEGORY:

SAFETY CLASS:

FUNCTION: These check valves open to provide feedwater to the steam generators and close to prevent diversion of auxiliary feedwater from the steam generators.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months except as provided by IWV-3522 (IWV-3521).

BASIS FOR RELIEF: During operation there is no practical means to exercise these valves. These valves are tested only enroute to a cold/refueling shutdown not caused by a reactor trip. Personnel are dispatched prior to cessation of feedwater flow to install field instrumentation for local check valve closure verification. Due to time required to dispatch personnel and install test gauges, this test cannot be performed at the time of unplanned reactor trip. During cold shutdowns resulting from a plant trip, valves 3992 and 3993 cannot be exercised due to system operating conditions.

ALTERNATE TESTING: Testing of these valves will be performed during normal plant shutdowns to cold shutdown when feedwater flow is transferred to auxiliary feedwater system. If the valves cannot be tested during normal cold shutdown they will be tested for closure during refueling outages.

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION. FOR THE 1990-1999 INTERVAL OF APPENDIX C 54 66 RELIEF REQUEST NO. VR - 22 THIS PAGE INTENTIONALLY LEFT BLANK (SEE CS-33 FOR 841 AND 865)

R EV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL APPENDIX C 55 66 RELIEF REQUEST NO. VR - 23 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 4023)42-52B TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 56 66 RELIEF REQUEST NO. VR - 24 I

SYSTEM: Containment Spray (CS)

CLASS: 862A, 862B CATEGORY: AC SAFETY CLASS:

FUNCTION: These check valves open to provide flow from CS pumps to the containment spray header.

TEST REQUIREMENT: A mechanical exerciser shall be used to move the valve disk when - testing is performed without flow through the valve.

"The force or torque delivered to the disk by the exerciser must be limited to less than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk..."

BASIS FOR RELIEF: The existing system configuration does not allow for measurement of pressure differential acting on the disk.

ALTERNATE TESTING: Verification of valve movement will be conducted quarterly by measuring and recording the breakaway force of the valve and comparing it to a reference value established when the valve was known to be in .good condition. This method is consistent with guidelines in paragraph 4.3.2.4(b) of ASME/ANSI OMa-1988, Part 10.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 57 66 RELIEF REQUEST NO. VR - 25 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 5941A AND 5942A)

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 58 66 RELIEF REQUEST NO. VR - 26 SYSTEM: Auxiliary Feedwater VALVES: 3998, 4000C, 4000D, 4003,4004, 4007, 4008 CATEGORY: BC/C SAFETY CLASS: 2/3 FUNCTION: These check valves open to allow Auxiliary Feedwater flow to the steam generators.

These valves close to prevent reverse flow thus preventing steam binding of the Auxiliary Feedwater Pumps.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Plant Technical Specifications require the Auxiliary Feedwater System to be operable prior to exceeding 350'F in the Reactor Coolant System. At this condition there is insufficient pressure in the steam generators to perform a reverse flow verification of these valves. During normal operation the Plant Technical Specifications require monthly full flow pump tests. To retest the Auxiliary Feedwater pumps after achieving sufficient steam generator pressure would be an unwarranted burden on the plant and equipment.

I ALTERNATE TESTING: During startup from cold shutdown or refueling outages when plant condtions do not exist to perform a reverse flow verification together with the normal pump operability test, the reverse flow verification will be performed at the next regularly scheduled monthly pump operability test when the required plant conditions exist.

TlTLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 59 66 RELIEF -REQUEST NO. VR - 27 SYSTEM: Standby Auxiliary Feedwater (SAFW)

VALVES: 9704A, 9704B, 9705A, 9705B CATEGORY: BC/C SAFETY CLASS:

FUNCTION: These check valves open to allow Standby Auxiliary Feedwater flow to the steam generators. These valves close to prevent reverse flow thus preventing steam binding of the pumps.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, except as'rovided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Plant Technical Specifications require the Standby Auxiliary Feedwater System to be operable prior to exceeding 350'F in the Reactor Coolant System. At this condition there is insufficient pressure in the steam generators to perform a reverse flow verification of these valves. During normal operation the plant Technical Specifications require monthly full flow pump tests. To retest the Standby Auxiliary Feedwater pumps after achieving sufficient steam generator pressure would bq an unwarranted burden on the plant and equipment.

ALTERNATE TESTING: During startup from cold shutdown or refueling outages when plant conditions do not exist to perform a reverse flow verification together with the normal pump operability test, the reverse flow verification will be performed at the next regularly scheduled monthly pump operability test when the required plant conditions exist.

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 60 66 RELEIF REQUEST NO. VR - 28 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 8655)

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 61 66 Q

SYSTEM: Residual Heat Removal (RHR)

VALVES: 697A, 697B CATEGORY: C SAFETY CLASS:

FUNCTION: These check ~alves must open to allow*full rated flow from each RHR pump for low pressure safety injection.

TEST REQUIREMENT: Check valves shall be exercised at least once every three months, to the position required to fulfill their safety function, except as provided by IWV-3522 (IWV-3521).

BASIS FOR RELIEF: These valves cannot be full-stroke exercised during power operation since downstream valves to the Reactor Coolant System (RCS) cannot open against the higher RCS pressure. These valves cannot be full-stroke exercised during cold shutdown because establishing required safety analysis flow through them could result in excessive RCS cooldown.

ALTERNATE TESTING: These valves will be full stroke exercised during each refueling outage.

TITLE REV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 62 66 RELIEF REQUEST NO. VR - 30 THIS PAGE INTENTIONALLY LEFT BLANK (SEE CS-35 FOR 4297, 4298, 4480, 4481)

TITLE:

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 63 66 RELIEF REQUEST NO. VR - 31 SYSTEM: Containment Spray VALVES: 859A, 859B, 859C, 864A, 864B, 2829, 2830 CATEGORY:

SAFETY CLASS:

FUNCTION: Two inch valves 859A, 859B and 859C and 3g inch valves 864A and 864B are manually-operated normally closed isolation valves in the test line for the containment spray pumps and must provide containment isolation.

Valves 2829 and 2830 are 34 inch manually-operated normally closed isolation valves in unused test connection lines with welded caps located. off each spray header outside containment and must provide containment isolation.

TEST REQUIREMENT: Category A valves shall be leak tested, except that valves which function in the course of plant operation in a manner that demonstrates functionally adequate seat tightness need not be leak tested. In such cases, the valve record shall provide the basis for the conclusion that operational observations constitute satisfactory demonstration (IWV-3421) .

BASIS FOR RELIEF: The containment spray pump test line and spray header have the necessary containment isolation valves and boundaries; however, the components for which relief is requested cannot be leak tested since there are no available test connections.

However, the containment spray headers,.are normally filled with water to a level at least 45 feet above the elevation of the test lines and containment penetration in order to facilitate faster response of the system during an accident. RGEE has performed an analysis of the filled spray

TITLE: REV.

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS PAGE GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 64 66 header and concluded that the water would not boil off during a LOCA. Since the test and drain lines are constantly exposed to this head of water during power operations',

any leakage would be observed either during normal operator walkdowns (i.e., indication of water on valve or floor), or during monthly tests . of the containment spray pumps which require confirmation of the head of water. Consequently, a verifiable water barrier. between the containment atmosphere and the valves will always be in place such that leak testing with air should not be required. Additionally; these valves, with the exception of 859C, are administratively maintained locked closed during power operations and all are only opened for periodic testing. RGsE estimates that

$ 40,000 it would cost approximately to install the necessary test connections for these lines. As such, RG&E proposes to fill the Containment Spray injection lines using the RWST each refueling outage to a minimum level of 66.9 feet (or 29 psig) . This is the maximum height of water that can be used without creating the potential for flooding the containment charcoal filter units. Each test and drain line containment isolation valve or boundary would then be evaluated for any observed leakage either through visual inspection or the use of local pressure indication. RGEE believes that this test meets the underlying purpose of Appendix J without creating undue hardships on the licensee.

ALTERNATE TESTING: Leak tightness of 2829 and 2830 shall be verified each refueling outage by visual examination for leakage. Leak tightness of 859A, 859B, 859C, 864A and 864B shall be verified each refueling outage by observation of pressure drop of the containment spray header.

filled

QUALITY ATTACHMENT D ASSURANCE 12/1/93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS F4+E GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 65 66 RELIEF REQUEST NO. VR - 32 SYSTEM: Fire Service Water VALVES: 9229 CATEGORY: AC SAFETY CLASS:

FUNCTION: Valve 9229 is a 4 inch check valve in the Fire Service Water System inside the Containment Building and must provide containment isolation.

TEST REQUIREMENT: Category A valves shall be leak tested, except that valves which function in the course of plant operation in a manner that demonstrates functionally adequate seat tightness need not be leak tested. In such cases, the valve record shall provide the basis for the conclusion that operational observations constitute satisfactory demonstration (IWV-3421).

BASIS FOR RELIEF: Fire Service Water penetration 307 contains check valve 9229 which is located inside containment. 9229 is leak tested, however, it cannot be assured that all water has been drained from the valve seat prior to Appendix J testing. Its location with respect to the penetration and the fire service water header inside containment and the lack of available drain lines prohibit the complete draining of residual water downstream of the check valve. RG&E estimates that it would cost approximately $ 20,000 to install the necessary drain line to ensure downstream line drainage prior to the Appendix J test. Since valve 9229 is outside the missile shield, it is highly unlikely that the fire service water pipe would break in a location such that all

TITLE: IIEV.

QUALITY ATTACHMENT D ASSURANCE 12 1 93 2 MANUAL PUMP AND VALVE RELIEF REQUESTS ~4+E GINNA STATION FOR THE 1990-1999 INTERVAL OF APPENDIX C 66 66 RELIEF REQUEST NO. VR-32 water would be completely drained from the area downstream of the check valve seat.

Therefore, testing 9229 in its current configuration is represen-tative of the conditions that the valve would most likely see during an accident (i.e. air pressurizing an entrapped water pocket).

Upstream AOV 9227 is fully tested 'and normally closed during power operation.

Closure of AOV 9227 meets all requirements for Ginna Station Technical Specification 3.6.3 if check valve 9229 were declared inoperable.

ALTERNATE TESTING: RG&E will continue to try and remove as much water as possible before testing 9229 to Appendix J. RGEE will continue to prompt closure test 9229 quarterly which demonstrates that the valve will close when required.

QUAIZTY ASSURANCE MAM.JAL ATIR.CHMEPZ B System: PRIMARY WATER TREATMENT GINNA SZhXXON Dwg No: 33013-1908 APPENDIX C VALVE TESTING BIGRAM PIAN FOR 'IHE 1990 1999 INXKRVAL Date: 1/6/94 'Page: 88 of 92 Rev: 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 8418 A-4 GLV AOV 1110- 2 ACTIVE EX ST-C PIT FS-C LT-J GR-2 8419 A-5 CV SAV AC

~zJVI~ WVTTVE LT-J R GR-2 CV-C Q

QJAIZTY ASSURANCE MANUAL System: CNMT HEATING STEAM & CONDENSATE GINNh SIXHON Dwg No: 33013-1915 APHM)IX C VALVE 'K%TING PROGRAM PIAN FOR 'IHE 1990 1999 IRIKRVAL Date: 1/6/94 Page: 89 of 92 Rev: 2 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 6151 C-1 GTV MAN 2 A

~115 PASSIVE LT-J R GR-2 6152 E-2 DIV MAN 2 A 111 MBETVE.

LT-J R GR-2 6165 C-1 GTV A 111 1S PA!:)~IVE LT-J R GR-2 6175 8-1 DIV A PASSIVE LT-J R GR-2

QUAIZTY ASSURANCE MAKJAL System: FIRE PROTECTION GINNA STATION Dwg No: 33013-1989 APHM)IX C VALVE TESXXNG EBDGRM PXAN FOR 'lHE 1990 1999 INITIAL Date: 1/6/94 Page: 90 of 92 'ev;. 2 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks

• 5133 C-8 CV SAV C SSC C 1999 All ACTIVE

• 5134 C-7 REV SAV C SSC C

~ATIVE RT 10Y

• 5135 H-2 REV SAV C SSC C WVl'V7E RT 10Y 5136 I-3 CV SAV C SSC 10 ACTIVE

QEGZTY ASSURANCE MANUAL ATZLCHMEPZ B System: FIRE PROT-TB-TSC GINNA STATION Dwg No: 33013-1990 APPENDIX C VALVE TE~~G BIGRAM PlAN FOR THE 1990 1999 3ÃIHUTAL Date: 1/6/94 Page: 91 of 92 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 5171 B-11 GTV MOV 0 SSC B 111 -1 ~1 ~ATIVE EX Q ST-0 Q ST-C Q PIT R

QUAIZTY ASSURANCE MANtSL ATZLCSMEHZ B System: CONSTRUCTION FIRE SERV WATER GINNA SZAXXOH Dwg No: 33013-1991 APPENDIX C VALVE TESTING E%0GRAN PIAN FOR THE 1990 1999 INZHIAL Date: 1/6/94 Page: 92 of 92 Rev: 2 Valve Number Coor.

PAID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 5129 D-7 GTV 2 A

~191 PASSIVE LT-J R GR-2 9227 B-5 GTV AOV A UCTVHF EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 9229 C-5 CV SAV AC 1991 4 ACTIVE VR-32 LT-J R GR-2 CV-C Q

Quality Assurance Manual Appendix C Revision 2 Summary of Changes to Attachment A PAGE CHANGE Added relief request PR-10 to test matrix for DG Fuel Oil Pumps PDG02A and PDG02B for measured parameters Pi (Inlet Pressure) and Pd (Differential Pressure).

Deleted relief request PR-7 from test matrix for Service Water Pumps PSW01A, PSW01B, PSW01C and PSW01D for measured parameter Qf (flowrate) .

Added relief request PR-9 to test matrix for Charging Pumps PCH01A, PCH01B and PCH01C for measured parameter Pd (Differential Pressure).

Added relief request PR-12 to test matrix for Service Water Pumps PSW01A, PSW01B, PSWOiC and PSW01D for measured parameter Qf (flowrate).

1/2 Added relief request PR-11 to test matrix for all pumps for measured parameter V (vibration) .

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