ML17265A149

Rev 1 to Inservice Testing Program.

ML17265A149
Person / Time
Site:	Ginna
Issue date:	12/31/1997
From:	Robert Davis, Muller K ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17265A150	List: ML17265A149 ML17309A625
References
PROC-971231, NUDOCS 9802020239
Download: ML17265A149 (257)

Text

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AA'0 / INSERVICE TESTING Revision 1 if PROGRAM Page 1 of 91 INSERVICE TESTING PROGRAIV1 Effective Date:

Pzepared by: i6 ~A il Date: I> 8 Quality Assurance Review by:

Approved by: Date: ~~ ~/ 07 S

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AA0 / INSERVICE TESTING Revision 1 PROGRAM Page 2 of 91 Table of Contents

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . 3

2.0 REFERENCES

3.0 TERMS AND DEFINITIONS 4 4.0 GENERAL RE UIREMENTS 5 5.0 PUMP TESTING PROGRAM 6 S. 1 ~Sco e 6 6

5.3 Test Re uirements 6 5.4 Pum Testin Pro ram Plan Descri ion 7 6.0 VALVE TESTING PROGRAM 8 6.1 ~Sco e 8 6.2 8 6.3 Test Re uirements ~ ~ ~ ~ ~ 0 9 6.4 Valve Testin Pro ram Plan Descri tion 11 7.0 RECORDS 13 8.0 SYSTEM INDEX 9.0 COLD SHUTDOWN JUSTIFICATIONS 15 10.0 RELIEF RE UESTS 24 Table 1 Table of Acronyms 87 Attachment A: Pump Testing Program Plan Attachment B: Valve Testing Program Plan

INSERVICE TESTING Revision 1 PROGRAM Page 3 of 91

1.0 INTRODUCTION

This document establishes and defines the Inservice Pump and Valve Testing Program for the ten year interval from January 1, 1990 through December 31, 1999. This program has been developed as required by Title 10 Code of Federal Regulations Part 50 Paragraph 50.55a(f), 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.

2.0 REFERENCES

2.1 ASME Boiler 6 Pressure Vessel Code - Section XI Division 1, "Rules for Inservice Inspection and Testing of Nuclear Power Plant Components", 1986 Edition (hereafter 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.

INSERVICE TESTING Revision 1 PROGRAM Page 4 of 91 Nuclear Directive ND-IIT, Inservice inspection and Testing.

2.5 Interface Procedure IP-IIT-2, Inservice Testing Program for Pumps and Valves.

2.6 Ginna Station Technical Specifications.

2.7 Ginna Station Updated Final Safety Analysis Report (UFSAR) .

2.8 NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants.

2.9 NUREG-0821, Systematic Evaluation Program (SEP) topics.

2.10 Title 10 Code of Federal Regulations Part 50 Para.

50.55a, Codes and standards.

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

2. 12 Minutes of the Public Meetings on Generic Letter 89-04, October 25, 1989.

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

2.14 Supplement 1 to USNRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, April 4, 1995.

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.

3.4 Active valves - valves required to change obturator position to accomplish a safety function.

INSERVICE TESTING Revision 1 PROGRAM Page 5 of 91 3.5 Passive valves - valves that maintain obturator position and are not required to change obturator position to accomplish required safety functions.

3.6 Testing Frequencies specified as follows:

Weekly - at least once per 7 days Monthly - at least once per 31 days Quarterly or every 3 months - at least once per 92 days Semiannually or every 6 months.- at least once per 184 days Every 9 months - at least once per 276 days Yearly or annually - at least once per 366 days Biennially or every 2 years - at least once per 731 days 4.0 GENERAL RE UIREMENTS Inservice pump and valve testing shall be performed in accordance with ASME Boiler and Pressure Vessel Code Section XI Division 1, Subsections IWP &: 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, the minutes of the public meetings regarding Generic Letter 89-04, associated supplements and NUREG-1482 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.

Nuclear Directive ND-IIT shall be used in lieu of Code administrative functions to provide controls to verify implementation. However, ANII services 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, this Program Document identifies applicable Relief Requests or Cold Shutdown Justifications which describe the bases for determination and alternative test methods and/or frequencies.

INSERVICE TESTING Revision 1 PROGRAM Page 6 of 91 4.2 Implementation of the program shall be controlled in accordance. with the Nuclear Directive ND-IIT, Inservice Inspection and Testing and Interface Procedure IP-IIT-2, Inservice Testing Program for Pumps and Valves, 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-2.12, should not be implemented prior to review and approval by the Nuclear Regulatory Commission.

4.4 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 e 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 The following are exempt from requirements of this program:

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

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

I -/ INSERVICE TESTING PROGRAM Revision 1 Page 7 of 91 5.3 Test Re uirements 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 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of a test, however when data is recorded which exceeds the Required Action range, the pump shall immediately be declared inoperable.

INSERVICE TESTING Revision 1 PROGRAM Page 8 of 91 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 (P&ID) where the pump is located (RGSE Drawing Number 33013 series) .

d. Coordinates (Coor) PAID coordinates.

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

f. 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

INSERVICE TESTING Revision 1 PROGRAM Page 9 of 91 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.

6.3 Test Re uirements 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.

INSERVICE TESTING Revision 1 .

PROGRAM Page 10 of 91 Xnservice 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.

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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 return to power. However, in cold shutdown in it is not required to keep the plant 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.

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 will be tested prior to plant startup.

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

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

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.

When a valve or its control system has been replaced or repaired or has undergone maintenance that could affect its performance, and pxior 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.

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INSERVICE TESTING Revision 1 PROGRAM Page 11 of 91 Containment Isolation Valves shall be tested in accordance with 10CFR50 Appendix J (LT-J) and controlled, in accordance with the Containment Leakage Rate Testing Program.

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.

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

Exercising check valves to the full open position utilizing flow is considered acceptable by Generic Letter'9-04 if the maximum required accident flowrate is passed through the valve.

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.

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

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.

AND

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

b) Valve Number - valve identification number.

c) Coor./PAID - location coordinates of the valve on the PAID and the PAID Number (RG&E 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

- Check Valve CV 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 MAN - Manual Operator HYD - Hydraulic Operator SAV - Self Actuated Normal Position (Norm Pos) position of the valve during normal plant operation as indicated by the following:

0 Open C Closed

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A o'D PROGRAM Page 13 of 91 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.

i) 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 j) Frequency (Freq) - test frequency described by:

'Quarterly (Q) - at least once every three months,

'Cold Shutdown (CS) - during cold shutdowns.

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

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

Category A-SY; 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.

AIN'T

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INSERVICE TESTING Revision 1 PROGRAM Page 14 of 91 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 as delineated by ND-IIT and IP-IIT-2.

r j -./ INSERVICE TESTING PROGRAM Revision 1 Page 15 of 91 8.0 SYSTEM INDEX SYSTEM PI&D Number Main Steam 33013-1231 Main Feedwater 33013-1236-1,2 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 & 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 Fire Protection 33013-1989 Fire Protection 33013-1990-1 Fire Protection 33013-1991 Construction Fire Service Water 33013-1991

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INSERVICE TESTING Revision 1 PROGRAM Page 16 of 91 9.0 COLD SHUTDOWN JUSTIFICATIONS 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 4269i 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 Deleted (723A/B)

CS-32 710A/B CS-33 841,865 CS-34 1713,7226 CS-35 4297, 4298, 4480, 4481 CS-36 3506, 3507 CS-37 897, 898 CS-38 951C, 953C, 955C

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) PROGRAM Page 17 of 91 Cold Shutdown Justification 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).

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INSERVICE TESTING Revision

/ PROGRAM 1

Page 18 of 91 Valves 749 A & B and 759 A 8 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 barriers. This 'could result in damage to an operating reactor coolant pump and a reactor trip. Testing will be performed during cold shutdown.

. Valves 750 A &: B and 753 A 8 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.

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.

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.

t INSERVICE TESTING Revision 1 PROGRAM Page 19 of 91 CS 10: Valves 430 and 431C are Pressurizer Power Operated-Relief Valves (PORV). Normally closed, these valves op'n 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. When the plant is in a cold shutdown condition, testing will be performed on a quarterly (92 day) basis. Testing will also be performed prior to reaching LTOP conditions when cooling down from power operations and it has been greater'than 92 days + 25'. since the last test.

CS 11: Valves 8616 A &. B are Overpressure Protection System (OPS) surge tank charging valves. Valves 8619 A S 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 (RES) 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, opening when RCS pressure is above 410 psig. Testing will be performed 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.

I I INSERVICE TESTING Revision 1 PROGRAM Page 20 of 91 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 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)

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J O'D INSERVICE TESTING Revision 1 PROGRAM Page 21 of 91 Valves 304 A 6 B are Reactor Coolant Pump (RCP) seal injection line check valves. Valves 270 A E 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.

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.

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 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.

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.

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INSERVICE TESTING Revision 1 PROGRAM Page 22 of 91 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.

CS 28: Valve 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 require 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.

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/i INSERVICE TESTING Revision 1 i/

/ I I PROGRAM Page 23 of 91 CS 31: Deleted (723A, 723B)

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 Safety Injection (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 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.

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INSERVICE TESTING Revision 1 PROGRAM Page 24 of 91 Valves 4297 and 4298 open to provide and control auxiliary feedwater flow from the turbine-driv'en 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'ail 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.

Valves 3506 and 3507 serve as main steam inlet block valves to the atmospheric relief valves (ARVs 3410 and 3411) for both steam generators. Each valve must close to isolate its respective ARV; if failed. Each valve must open to permit emergency heat removal from the RCS through its respective ARV. During power operation, these normally-open valves are exposed to steam generator steam pressure. These valves also have bypass valves installed around them. Although test connections are currently installed downstream of each set of inlet block valves and bypass valves, quarterly testing at power is impractical since this testing would require costly modifications to install test manifolds to minimize the potential for test personnel injury. This testing would require the manual operation of the associated ARV at power which creates the unnecessary potential for a reactor power excursion due to excessive heat removal. A safety hazard would always exist if periodic exercising of these valves

INSERVICE TESTING Revision 1 PROGRAM Page 25 of 91 under high pressure steam were performed due to the unknown potential for leakage past either the inlet or bypass valve. Radiographic testing has been performed for valves 3506 and 3507 and proven to successfully demonstrate positive indication of=disk position.

Exercising of these valves will be performed during cold shutdown employing radiographic testing of the valves in both the open and closed positions which provides positive indication of the required change of disk position per IWV-3412.

Valves 897 and 898 serve as return isolation valves to the Refueling Water Storage tank (RWST) from the recirculation piping for the safety injection (SB pumps. These normally-open valves must remain open to provide low flow recirculation for the SI pumps during accident mitigation. The close function is used during post accident recirculation to isolate the recirculation path from the RWST. During power operation, these valves are maintained open to provide minimum flow protection for the high head SI pumps.

Closing of either of these valves renders all three high head SI pumps inoperable. Section 3.1.1 of NUREG-1482 indicates that these valves may be excluded from quarterly testing during power operation.

Testing of these valves will be performed during cold shutdown.

Check valves 951C, 953C and 955C serve as pressure relief check valves for penetrations 207, 206 and 205 respectively. In response to NRC Generic Letter 96-06, pressure relief loops with check valves, isolation valves and test connections were installed to provide overpressure protection from thermal expansion under accident conditions. Testing these check valves quarterly requires entry into containment inside the missle barrier which, under power operating conditions, is a high radiation area to connect test equipment, perform the test and disconnect test equipment. Since the personnel safety risks far outweigh the benefit achieved with a quarterly test, testing of these check valves will be performed during cold shutdown.

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INSERVICE TESTING Revision 1 PROGRAM Page 26 of 91 10.0 RELIEF RE UESTS Relief No. ~To 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 Oil 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 Leak Tests GR-4 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-4 854 VR-5 9627A/B VR-6 4324, 4325, 4326 VR-7 434, 435 VR-8 842A/B VR-9 867A/B VR-10 878G/J VR-11 889A/B, 870A/B VR-12 5392 VR-13 4291 4304 43 10 / 97 10A/B g

VR-14 853A/B VR-15 8616A/B, 8619A/B VR-16 392A VR-17 Deleted (4601, 4602, 4603, 4604)

INSERVICE TESTING Revision 1 PROGRAM Page 27 of 91 11.0 RELlEF RE UESTS (Con')

Relief No. T~01 C VR-18 5907, 5907A, 5908, 5908A VR-19 8606A/B VR-20 710A/B VR-21 3992, 3993 VR-22 Deleted (841, 865, see CS-33)

VR-23 Deleted (4023)

VR-24 862A, 862B VR-25 Deleted (5941A, 5942A)

VR-26 998, 4000 C/D, 4003, 4004, 4007, 4008 VR-27 9704 A/B, 9705 A/B VR-28 Deleted (8655)

VR-29 697A/B VR-30 Deleted (4297, 4298, 4480, 4481)

VR-31 859A, 859B, 859C, 864A, 864B, 2829, 2830 VR-32 9229

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J IVD 1 PROGRAM Page 28 of 91 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 8 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 organization 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 6 Electric requests that the Ginna Station Quality Assurance Program be used in lieu of Code administrative functions.

BASIS FOR RELIEF Rochester Gas E Electric's program for inservice pump and valve testing, governed by the Nuclear Policy Manual, contains requirements and responsibilities for implementation of the program and procedures. Procedures have been prepared and approved by responsible organizations within Rochester Gas E Electric.

Approved procedures will be implemented to control the performance of tests and evaluation of corresponding results. 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".

These procedures also include the method of performing the test, acceptance and rejection criteria, and test result reporting, evaluation and approval requirements.

INSERVICE TESTING Revision 1 PROGRAM Page 29 of 91 RELIEF REQUEST NO. CR - 1 CONT 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 ANII contract personnel. The qualifications of the inspectors, inspection specialists and inspection agency will be in compliance with the Code.

ALTERNATIVE PROVISIONS 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.

INSERVICE TESTING Revision 1 PROGRAM Page 30 of 91 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 significantly 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.

INSERVICE TESTING Revision 1 PROGRAM , Page 31 of 91 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.

INSERVICE TESTING Revision 1 PROGRAM Page 32 of 91 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.

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/ INSERVICE TESTING Revision 1 i/ PROGRAM Page 33 of 91 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'ump 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.

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INSERVICE TESTING Revision 1 PROGRAM Page 34 of 91 RELIEF REQUEST NO. PR-5 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: 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.

INSERVICE TESTING Revision 1 PROGRAM Page 35 of 91 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.

INSERVICE TESTING Revision 1 PROGRAM Page 36 of 91 RELIEF REQUEST NO. PR-7 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR SERVICE WATER PUMP FLOW)

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INSERVICE TESTING Revision 1 i PROGRAM Page 37 of 91 RELIEF REQUEST NO. PR-8 SYSTEM: Residual Heat Removal (RHR)

PUMPS: Residual Heat Removal Pumps (ACAPRH1,2)

SAFETY CLASS:

FUNCTION: Supply safety injection flow to the reactor vessel.

r 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'hese 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)

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-* t'NSERVICE TESTING Revision 1 PROGRAM Page 38 of 91 RELiEF REQUEST NO. PR-9 Rev. 1 SYSTEM: CVCS Charging PUMPS: Charging Pumps A, B 9 C (PCH01A, 1B, 1C)

SAFETY CLASS: 2 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: (1) 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)

(2) The test quantities shown in Table IWP-3100-1 (inlet and differential pressures in particular) shall be measured or observed and recorded. (IWP-3100)

(3) Pump discharge pressure shall be measured in lieu of pump differential pressure per OM,-1988, Part 6, Table 2 (Relief request PR-9)

BASIS FOR RELIEF: The charging pumps are variable-speed positive-displacement type pumps.

1) The test method developed for these pumps involves attaining the reference baseline speed (N) and the measurement of flow rate (Q), discharge pressure (PD),

vibration (V) and oil level (L) . Since the resistance of the system is fixed by RCP seal and letdown flow, an unnecessary perturbation upon it would cause Pressurizer level control to vary the charging flow rate to the RCS. The establishment of the reference speed and the verification of acceptable flow rate has been proven to provide an accurate and repeatable indication of pump/varidrive performance degradation.

I INSERVICE TESTING Revision 1 PROGRAM Page 39 of 91 RELIEF REQUEST NO. PR-9 Rev. 1 CONT (2) The measurement of pump inlet (suction) pressure provides no useful data for evaluation of pump performance or for detecting pump degradation and since pump discharge pressure is dependent upon RCS pressure, the recording of pump differential pressure for positive-displacement type pumps is not applicable.

ALTERNATE TESTING: (1) In lieu of varying the resistance of the system until the differential pressure or flow rate equals the corresponding reference value, the speed of the pump will be adjusted to the corresponding reference value.

(2) Pump discharge pressure shall be measured in lieu of pump inlet and differential pressures per OMa-1988, Part 6, Table 2.

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INSERVICE TESTING Revision 1

-j/ PROGRAM Page 40 of 91 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, wi.'ll provide no useful data.

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

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I INSERVICE TESTING Revision 1 I

/ PROGRAM Page 41 of 91 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 utilized.

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INSERVICE TESTING Revision 1 PROGRAM Page 42 of 91 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 and 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 tests. 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 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).

INSERVICE TESTING Revision 1 PROGRAM Page 43 of 91 RELIEF REQUEST NO. PR-12 CONT.

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 < 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.

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.

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PROGRAM Page 44 of 91 RELIEF REQUEST NO. GR - 1 SYSTEM: Various VALVES: All" Power Operated Valves CATEGORY: A and B SAFETY CLASS: Various FUNCTION: Various TEST REQUIREMENT: Valves 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. It is impractical to part-stroke the valves.

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

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INSERVICE TESTING Revision 1 PROGRAM Page 45 of 91 RELIEF REQUEST NO. GR 2 SYSTEM: Containment Isolation VALVES: All'hose 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 outlined in Generic Letter No. 89-04, Position 10 that leak test procedures and requirements for containment isolation valves specified in 10CFR50, 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.

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

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/ INSERVICE TESTING Revision 1 PROGRAM Page 75 of 91 RELIEF REQUEST NO. VR-19 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 ~

t --/ INSERVICE TESTING PROGRAM Revision 1 Page 76 of 91 RELIEF REQUEST NO. VR 20 SYSTEM: Residual Heat Removal (RHR)

VALVES: 710A, 710B CATEGORY:

SAFETY CLASS:

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 fulfilltheir 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'

INSERVICE TESTING Revision 1 PROGRAM Page 77 of 91 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 fegdwater system.

If the valves cannot be tested during normal cold shutdown they will be tested for closure during refueling outages.

I' INSERVICE TESTING Revision 1 PROGRAM Page 78 of 91 RELIEF REQUEST NO. VR - 22 THIS PAGE INTENTIONALLY LEFT BLANK (SEE CS-33 FOR 841 AND 865)

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INSERVICE TESTING Revision 1 PROGRAM Page 79 of 91 RELIEF REQUEST NO. VR - 23 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 4023)

INSERVICE TESTING Revision 1 PROGRAM Page 80 of 91 RELIEF REQUEST NO. VR 24 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 act'ing on the disk.

ALTERNATE TESTING: Verification of va3.ve 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.

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INSERVICE TESTING Revision 1 PROGRAM Page 81 of 91 RELIEF REQUEST NO. VR 25 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 5941A AND 5942A)

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-- // INSERVICE TESTING Revision 1 PROGRAM Page 82 of 91 RELIEF REQUEST NO. VR - 26 SYSTEM: Auxiliary Feedwater VALVES: 3998, 4000C, 4000D, 4003, 4004 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'EST 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 progressing from Mode 4 to Mode

3. At this condition there is insufficient pressure in the steam generators to perform a reverse flow verification of these valves. During normal operation the IST Program requires quarterly 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.

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 quarterly pump operability test when the required plant conditions exist.

'*/ INSERVICE TESTING PROGRAM Revision 1 Page 83 of 91 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 provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF: Plant Technical Specifications require the Standby Auxiliary Feedwater System to be operable prior to progressing from Mode 4 to Mode 3. At this condition there is insufficient pressure in the steam generators to perform a reverse flow verification of these valves. During normal operation the IST Program requires quarterly full. flow pump tests. To retest the Standby Auxiliary Feedwater pumps after achieving sufficient steam generator pressure would be 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 quarterly pump operability test when the required plant conditions exist.

INSERVICE TESTING Revision 1 PROGRAM Page 84 of 91 RELIEF REQUEST NO. VR - 28 THIS PAGE INTENTIONALLY LEFT BLANK (DELETED FOR 8655)

f INSERVICE TESTING Revision 1 PROGRAM Page 85 of 91 RELIEF REQUEST NO. VR - 29 SYSTEM: Residual Heat Removal (RHR)

VALVES: 697A, 697B CATEGORY:

SAFETY CLASS:

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 through them could result in excessive RCS cooldown.

ALTERNATE TESTING: These valves will be full stroke exercised during each refueling outage.

'-// INSERVICE TESTING PROGRAM Revision 1 Page 86 of 91 RELIEF REQUEST NO. VR 30 THIS PAGE INTENTIONALLY LEFT BLANK (SEE CS-35 FOR 4297, 4298, 4480, 4481)

-*/ INSERVICE TESTING PROGRAM Revision Page 87 1

of 91 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 Y<

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 Yiinch 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

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INSERVICE TESTING Revision 1 I I PROGRAM Page 88 of 91 RELIEF REQUEST NO. VR 31 con't 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 quarterly tests of the containment spray pumps which require conf irmation 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. RGEE estimates that to it would cost approximately install the necessary test

$ 40,000 connections for these lines. As such, RG&E proposed to Spray injection fill lines the Containment 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 during each quarterly pump test by observation of pressure drop of the filled containment spray header.

'i I I

AJND /

I INSERVICE TESTING Revision 1

/ PROGRAM Page 89 of 91 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. RGEE 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 water would be completely drained from the area downstream of the check valve seat.

Therefore, testing 9229 in its current configuration is representative of the

INSERVICE TESTING Revision 1 PROGRAM Page 90 of 91 RELIEF REQUEST NO. VR - 32 con't 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: RGEE will continue to try and remove as much water as possible before testing 9229 to Appendix J. RG&E will continue to prompt closure test 9229 quarterly which demonstrates that the valve will close when required.

INSERVICE TESTING Revision 1 PROGRAM Page 91 of 91 Table 1 PUMP AND VALVE TEST PROGRAM PLAN TABLE OF ACRONYMS VALVETYPE NORMAL POSITION BAY - Ball Valve 0- Open EX - Exercise for Category A or B Valves BFV - Butterfly Valve C - Closed ST (O,C) - Stroke Time (o-open, c-closed)

CV - Check Valve FS (O,C) - Fail Safe Test (o-open, c-closed)

DIV - Diaphragm PIT - Position Indication Test GTV - Gate Valve LT-J - Leak Test - Appendix J GLV - Globe Valve LT-X - Leak Test - ASME Section XI REV - Relief Valve RT - Relief Valve Setpoint Test SCV - Stop Check Valve CV-P - Check Valve Exercise - partial TWV - Three-way Valve CV Check Valve Exercise - Full Open CV-C - Check Valve Exercise - Full Closed ACTUATOR SAFETY CLASS ASME MOV - Motor Q - Quarterly 1 CATEGORY AOV - Air CS - Cold Shutdown 2 A SOV - Solenoid R - Refueling - not to exceed 3 B MAN - Manual 2 years NC - non class C HYD - Hydraulic Sy - At least once every five SSC - safety significant AC SAV - Self Actuated years BC 10y - At least once every ten years CR - Code Administrative Relief MEASURE PUMP TEST PARAMETERS Request N - Pump Speed GR - Generic Relief Request Pi - Inlet Pressure VR - Valves Relief Request Pd - Differential Pressure PR - Pump Relief Request Qf - Flow Rate CS - Cold Shutdown V - Vibration Amplitude/Velocity Justifications Tb - Bearing Temperature L - Lube Oil Level/Pressure

INSERVICE TESTING PROGRAM ATTACHMENT A GINNA STATION PUMP TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 1 of 2 Rev: 1 Pump Pump Dwg. Coor Safety Measured Parameters ID Class Fre N Px PAF01A 1237 B-5 3 N/A X PR-11 PR-1 X MOTOR AUX FEED Q MOTOR AUX FEED PAF01B 1237 E-5 3 Q N/A PR-11 PR-1 X TURBINE AUX FEED PAF03 1237 I-5 3 X PR-11 PR-1 X STANDBY AUX FEED PSF01A 1238 B-5 3 Q N/A 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 Q N/A PR-10 PR-10 PR-2 PR-11 PR-1 1239-2 I-9 N/A PR-10 PR-10 PR-2 PR-11 PR-1 D/G FUEL OIL PDG02B Q PAC02A 1245 D-5 N/A X PR-11 PR- 1 COMPONENT COOLING Q PAC02B 1245 E-5 3 N/A X PR-11 PR-1 COMPONENT COOLING Q PAC01A 1247 F-5 2 Q N/A X PR-8 PR-8 PR-8/11 PR-1 RESIDUAL HT REMOVAL RESIDUAL HT REMOVAL PAC01B 1247 B-5 2 Q N/A X PR-8 PR-8 PR-8/11 PR-1 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 PR-11 PR-1 X SPENT FUEL POOL PSW01A 1250-1 D-2 3 Q N/A PR-4 X PR-12 PR-5/1R PR-1 SERVICE WATER

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INSERVICE TESTING PROGRAM ATTACHMENT A GINNA STATION PUMP TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL ate: 10/8/97 Page: 2 of 2 Rev: 1 Pump Pump Dwg. Coor Safety Measured Parameters ID Class Fre N Px P Q V.

SERVICE WATER PSWO1B 1250-1 E-2 3 Q N/A PR-4 X PR-12 PR"5/11 PR-1 SERVICE WATER PSWolc 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 XPR11PR1X 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"ll PR-1 X SAFETY INJECTION PSI01B 1262-1 F-4 2 Q N/A PR-3 X PR-11 PR-1 X SAFETY INJECTION PSI01C 1262-1 D-4 2 Q N/A PR-3 X X PR-11 PR-1 X CHARGING PCH01A 1265-2 E-S 2 PR-9 PR-9 X PR" 11 PR-1 X CHARGING PCH01B 1265-2 G-5 2 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

System: MAIN STEAM INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1231 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 1 of 90 Rev: 1 Valve Coor. e Norm Safety Cate o Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3410 I-5 GTV AOV

~12 ACTIVE EX CS CS-3 MANUAL EXERCISE PIT R FS-C CS CS-3 3411 C-5 GTV AOV 2 B ~

111 1 ACTIVE EX CS CS-3 MANUAL EXERCISE PIT R FS-C CS CS-3 3504A F-4 GTV MOV 1231 ACTIVE EX Q ST-0 Q ST-C Q PIT R 3504B E-4 CV SAV 111 1 ACTIVE CV-0 Q MECHANICAL INDICATION CV-C Q 3505A B-4 GTV MOV 2 B 111 1 ACTIVE EX Q ST-0 Q ST-C Q PIT R 3505B D-4 CV SAV 3 C 1121 ~ATIVE CV-0 Q MECHANICAL INDICATION CV-C Q

System: MAIN STEAM INSERVICE TESTING PROGRAM ATTACHMENT B Dwg, No: 33013-1231 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 2 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number TI~& D. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3506 H-4 GTV MAN 2 B 111 1 ~ACT VE EX RADIOGRAPHY 3507 C-4 GTV 2 B 1111 6 ACTIVE EX RADIOGRAPHY 3508 G-5 REV SAV 2 C 111 1 AATAIE RT 5Y 3509 A-5 REV SAV 2 C 111 1 ACTIVE RT SY 3510 G-6 REV SAV 2 C 111 1 AATAVE RT SY 3511 A-6 , REV SAV 2 C 1111 ACTIVE RT 5Y 3512 G-7 REV SAV 2 C 111 1 ~CT VE RT SY 3513 A-7 REV SAV C 111 1 ~ATIVE RT ~ 5Y

System: MAIN STEAM INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013"1231 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 3 of 90 Rev: 1 Valve Coor. e Norm Safety Cate o Required Rel.Req Number N&30. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3514 G-8 REV SAV C ACTIVE RT SY 3515 A-7 REV SAV C ACTIVE RT SY 3516 G-10 CV AOV

~12 1 30 AC~TI CS-1 EX CS ST-C CS CS-1 PIT R FS-C CS CS-1 3517 A-11 CV AOV 0 1111 3 II ACTIVE EX CS CS-1 ST-C CS CS-1 PIT R FS-C CS CS-1 3518 G-10 CV SAV 3 C 1111 333 ACTIVE CV-C CS CS-2 3519 A-11 CV SAV 3 C 111 1 ~CTXVE CV-C CS CS-2 3652 D-2 GTV HYD B 1111 3 AVI~V$

EX '

System: MAIN FEEDNATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1236 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 4 of 90 Rev: 1 Valve Number Coor.

~PG D.

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

• 3976 I-6 SCV MOV 0 NS 1121- 2 14 ACTIVE EX R ST-C R PIT R

• 3977 B-6 SCV MOV 0 NS B 1121-1 14 ACTIVE EX R ST-C R PIT R 3992 112 1 J-3 CV 14 SAV 0 C ACTIVE CV-C CS VR-21 3993 A-3 CV SAV 0 C 1211 14 ACTIVE CV-C CS VR-21 4269 D-3 GLV AOV 1211 . 12 ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8 4270 G-3 GLV AOV 0 1122 ~1 ~A~TTB EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8

System: MAIN FEEDNATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1236 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 5 of 90 Rev: 1 Valve Coor. e Norm Safety Cate o Required Rel.Req Number PAID. a.ze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 4271 D-3 GLV AOV 1236-2 4 ACTIVE EX CS CS-8 ST"C CS CS-8 PIT R FS-C CS CS-8 4272 H-3 GLV AOV 1121 4 ACTIVE EX CS CS-8 ST-C CS CS-8 PIT R FS-C CS CS-8

System: AUXILIARYFEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Rev: 1 Date: 10/8/97 Page: 6 90 Valve Coor. Norm Safety Cate or Required Rel.Req Number P&ID. pxzee Actuator Pos Class Act Pas Tests Fre CSJ Remarks 3996 I-6 SCV MOV 3 BC 1117 5 ~ATIVE EX Q ST-0 Q ST-C Q PIT R CV-0 Q 3998 I-8 CV SAV C 1337 5 ACTIVE CV-0 Q CV-C Q VR-26 4000A D-7 GLV MOV 1137 3 ACTIVE EX Q ST-0 Q ST-C Q PIT R 4000B D-8 GLV MOV 3 B 111 7 7\CTIVE EX Q ST-0 Q ST-C Q PIT R 4000C B-10 CV SAV 2 C 111 ~:T3.VE CV-0 Q CV-C Q VR-26 4000D E-10 CV SAV 2 C 1137 3 ~ATIVE CV-0 Q CV-C Q VR-26

System: AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 7 of 90 Rev: 1 Valve Number Coor.

~pa D.

~e Ezze Actuator Norm Safety pos Class Cate or Act pas Required Tests pre Rel.Req CSJ Remarks 4003 I-11 CV SAV 2 C 1237 1ICTI VE CV-0 Q CV-C Q VR-26 4004 J- 10 CV SAV 2 C

~ATIVE CV-0 Q CV-C Q VR-26 4007 B- 8 - GLV MOV 3 B 111 3 ~ACT VE EX Q ST-0 Q ST-C Q PIT R 4008 E-8 GLV MOV 3 . B 1117 3 AACTI AE EX Q ST-0 Q ST-C Q PIT R 4009 B-5 CV SAV 3 C 1237. AIITVE CV-0 Q CV-C Q 4010 E-5 CV SAV 1117 3 ACTIVE CV-0 Q CV-C Q

System: AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 8 of 90 Rev: 1 Valve Coor. Tg) e Norm Safety Cate o Required Rel.Req Number 0&ID. Sz.ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4013 I-2 GTV MOV 3 B 1117 4 7ICTIVE EX Q ST-0 Q PIT R 4014 H-2 CV SAV 3 C 1117 4 ~CTIVE CV-0 Q CV-C Q 4016 E-2 CV SAV C 1117 4 AIITVE CV-0 Q CV-C Q 4017 B-2 CV SAV 3 C

~12 7 4 ~ATIVE CV-0 Q CV-C Q 4020 I-3 .REV SAV 3 C 1117 ~7 XH.'XVE RT 10Y 4021 B-2 REV SAV 3 C 1127 . 75 ~ATTQE RT 10Y 4022 E-3 REV SAV 3 C 1237 .75 ~ATTVE RT 10Y

System: AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 9 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number ~P& D. 1ze Actuator Pos Class Act pas Tests Pre CSJ Remarks 4023 I-5 CV SAV C

~12 7 1.5 AATAIE CV-0 Q 4027 C-3 GTV MOV 3 B 112 liCTIVR EX Q ST-0 Q PIT R 4028 D-3 GTV MOV

~12 7 4 Al TFVE EX Q ST-0 Q PIT R 4098 I-2 GTV 3 B

~22 7 4 ~ATIVE 4291 H-5 GTV AOV 3 B 1227 ~ATIVE EX Q THROTTLE DISCH TO ACTIVATE ST-0 R VR- 13 ST-C R VR-13 PIT R FS-0 Q 4297 I-10 GLV AOV 3 B 111 7 ~ATIVE EX Q ST-0 CS CS-35 PIT R FS"0 Q

System: AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 10 of 90 Rev: 1 Valve Number Coor.

Dazo.

~e Ezze Actuator Norm pos Safety class Cate Act pas or Required Tests Pre Rel.Req CSJ Remarks 4298 J-8 GLV AOV 3 B

~12 7 3 ACTZACE EX Q ST-0 CS CS-35 PIT R FS-0 Q 4304 C-6 GTV AOV 3 B 111 1 ACTIVE EX THROTTLE DISCH TO ACTIVATE Q

ST-0 R VR-13 ST-C R VR-13 PIT R FS-0 Q 4310 E-6 GTV AOV

~32 7 1 ACTIVE 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

~1 ~7 X~TUB EX ST-0 VR-6 ~

4325 C-4 DIV SOV 3 B 1117 A~TVE EX ST-0

INSERVICE TESTING PROGRAM ATTACHMENT B System: AUXILIARY FEEDWATER Dwg No: 33013-1237 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 11 of 90 Rev: 1 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate or ct Pas Required Tests Fre Rel.Req CSJ Remarks 4326 F-3 DIV SOV 1121 .5 ACTXVE EX ST-0 4344 E-3 GTV B

~12 7 4 ~ATIVE EX 4345 C-3 GTV B

~12 7 4 ACTIVE EX 4480 B-6 GTV AOV

~12 7 ~1. ACTIVE EX Q ST-C CS CS-35 PIT R FS-C Q 4481 F-6 GTV AOV 1237 ~1. ACT VE EX Q ST-C CS CS-35 PIT R FS-C Q

0 N I l

System: STANDBY AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1238 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 12 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PP& P). xze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 9629A B-3 GTV MOV 3 B

~12 8 4 ~ACT VE EX Q ST-0 Q PIT R 9629B I-3 GTV MOV 3 B

~18 4 ACTIVE EX Q ST-0 Q PIT R 9700A B-6 CV SAV C 1118 3 ACTIVE CV-0 Q CV-C Q 9700B I-6 CV SAV 3 C 111 ACTIVE CV-0 Q CV-C Q 9701A B-7 GLV MOV 3 B

~13 8 ~TTVE EX Q ST-0 Q PIT R 9701B I"7 GLV MOV 3 B 112 AATAZE EX Q ST-0 Q PIT , R

System: STANDBY AUXILIARY FEEDNATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1238 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 13 of 90 Valve Coor. ~T e Norm Safety Cate or Required Rel.Req Number ~P& D. Size Actuator Pos Class Act Pas Tests Pre CSJ Remarks 9703A F-8 GLV MOV 3 B

~12 8 3 ~ATZVE EX Q ST-0 Q PIT R 9703B F-8 GLV MOV 1238 ACTIVE EX Q ST-0 Q PIT R 9704A B-9 SCV MOV BC 1238 ACTIVE EX Q ST-0 Q ST-C Q PIT R CV-0 Q CV-C Q VR-27 9704B I-9 SCV MOV 2 BC

~TIVE

~12 8 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 111 8 AATAVE CV-0 Q CV-C, Q VR-27

System: STANDBY AUXILIARY FEEDNATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1238 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Date: 10/8/97 Page: 14 90 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 9705B I-10 CV SAV 2 C

~138 3 ACTIVE CV-0 Q CV-C Q VR-27 9709A B-3 REV SAV 1238 1 ACTIVE RT 10Y 9709B I-3 REV SAV

~138 ACTIVE RT 10Y 9710A C-7 GLV AOV 1118 ~1. ACTIVE EX Q ST-0 R VR- 13 PIT R FS-0 Q 9710B H-7 GLV AOV 3 B 1238 1.5 ~ATIVE EX Q ST"0 R VR" 13 PIT R FS-0 Q 9721A C-3 , CV SAV 112 ACTIVE CV-0 Q CV-C Q

System: STANDBY AUXILIARY FEEDWATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1238 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 15 of 90 Rev: 1 Valve Coor. ~T e Norm Safety Cate or Required Rel.Req Number FAD. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 9721B G-3 SAV 1238 .5 ACTIVE CV-0 Q CV-C Q 9746 I-8 GTV 0 B

~18 MOV ACTIVE EX Q ST-0 Q ST-C Q PIT R

System: DIESEL GENERATOR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1239 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 16 of 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number ~Pa D. Sz.ze Actuator Pos class Act Pas Tests Fre CSJ Remarks 5907 E-3 GTV SOV 3 B 1139-1 ACTIVE EX Q ST-0 Q VR-18 ST-C Q VR-18 FS-C Q 5907A E-3 GTV SOV 3 B 1239-1 ~7 ACTIEEE EX Q ST-0 Q VR-18 ST-C Q VR-18 FS-0 Q 5908 E-9 GTV SOV

~1239- 1 ACTIVE EX Q ST-0 Q VR-18 ST-C Q VR- 18 FS-C Q 5908A E-9 GTV SOV 3 B 1239-2 ~7 EECTI 3E EX Q ST-0 Q VR- 18 ST-C Q VR- 18 FS-0 Q 5933A G-11 GTV SOV 3 B 111 - 1 ~1. AACTT AE EX Q ST-0 Q

System: DIESEL GENERATOR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1239 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 17 of 90 Rev: 1 Valve Coor. ~T e Norm Safety Cate or Required Rel.Req Number ~pa D. Size Actuator Pos Class Act pas Tests Pre CSJ Remarks 5933B F-11 GTV SOV 3 B

~12 9-1 1.5 ~CTTITR EX Q ST-0 Q VR" 1 5934A C-2 GTV SOV 11219- ~3. ACTIVE EX Q ST-0 Q VR-1 5934B B-2 GTV SOV 12119- ~1. OVATE EX Q ST-0 Q 5941A F-1 CV SAV 3 C 1239-1 ~7 ACTIVE CV-C Q 5942A F-11 CV SAV C 111 -2 ~7 ACTIVE CV-C Q 5943A F-1 REV SAV C

~139-1 .75 ~ATIVE RT 10Y 5944A F-11 REV SAV C 1121-2 . 75 %ACTI AN RT 10Y 5947B F-1 REV SAV 3 C

~139-1 ~7 ~ATTVE RT 10Y

ATTACHMENT B System: DIESEL GENERATOR INSERVICE TESTING PROGRAM Dwg No: 33013-1239 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Rev: 1 Date: 10 8 97 Pa e: 18 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number Va)~D. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5947C G-1 REV SAV 3 C 1121- I ~7 7ICTIVE RT 10Y 5948B G-10 REV SAV 13239- .75 ACTIVE RT 10Y 5948C F-10 REV SAV 3 C 111 -2 .75 ACATI AE RT 10Y 5955 I-1 CV SAV 3 C 1121-1 ACTIVE CV-0 Q CV-C Q 5956 I-10 CV SAV 3 C 1113- 3 ~ATIVE CV-0 Q CV-C Q 5959 G-3 REV SAV 3 C 111 - I ~1. A~TV1 RT 10Y 5960 G-8 REV SAV 3 C

~1239- ~1. ACT~YE RT 10Y

ATTACHMENT B System: DIESEL GENERATOR INSERVICE TESTING PROGRAM Dwg No: 33013-1239 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL e: of Date: 10 8 97 Pa 19 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5960A C-1 SAV 111 - I ICV9

. ACTIVE CV-0 R VR-2 SAMPLE DISASSEMBLY CV-C R VR-2 SAMPLE DISASSEMBLY C"ll 5960B

~1~ CV

1. 5 SAV C ACTIVE CV-0 R VR-2 SAMPLE DISASSEMBLY CV-C R VR-2 SAMPLE DISASSEMBLY 5961 1-4 CV SAV 3 C 111 -I 2 ACTIVE CV-0 Q CV-C Q 5962 I-8 CV SAV 3 C 1239-2 EEATI /E CV-0 Q CV-C Q

System: COMPONENT COOLING WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1245 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 20 of 90 Rev: 1 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 17 A-3 GLV AOV

~124 I ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q 651 A-3 REV SAV

~124 2 ACTIVE RT 10Y 723A D-6 CV SAV 0 C 3 1245 8 ACTIVE CV-0 Q CV-C Q 723B E-6 CV SAV 0, C 3 C

~124 AAcTI AE CV-0 Q CV-C Q 732 A-3 ~ REV SAV 3

~124 3 ACTIVE RT 10Y 738A F-3 GTV MOV 3 B 1245 Itt ACTIVE EX Q ST-0 Q PIT R

System: COMPONENT COOLING WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1245/1246 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Date: 10/8/97 Pa e: 21 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 738B H-4 GTV MOV

~324 111 ACTIVE EX Q ST-0 Q PIT R

• 823 D-2 GTV MOV 3 B

~34 PAFSSfE PIT 743 C-6 CV SAV 2 AC 11143 AttTVE LT-J R GR-2 CV-C Q 745 B-6 GLV AOV 2 A 12412-1 2 AAITV2 EX Q ST-C Q GR-4 PIT R FS"C Q LT-J R GR-2 749A B-5 GTV MOV 2 A 12412-1 MOTIVE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2 749B B-4 GTV MOV 2 A

~124 -1 ~AT.KE 3

EX ST-C PIT

'S.CS R

CS-6 CS-6 LT-J R GR-2

System: COMPONENT COOLING WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1245/1246 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 22 of 90 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate or ct Pas Required Tests Fre Rel.Req CSJ Remarks 750A C-5 CV SAV 2 C 11142 4 ACTIVE CV-C CS CS-7 750B C-3 CV SAV 12412-1 4 ACTIVE CV-C CS CS-7 753A F-5 CV 'AV 0

~124 - 1 ~1. ACTIVE CV-C CS CS-7 753B F-2 CV SAV 0 12412-1 ~2. ACTIVE CV-C CS CS-7 758A H-5 REV SAV 2 C

~124 -1 2 ~ATIVE RT 10Y 758B H-2 REV SAV 2 C 12412-1 2 ACTIVE RT 10Y 759A I-5 GTV MOV 1224-2 CTIVE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2

System: COMPONENT COOLING WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1245/1246 GINNA STATION VALVE TESTING PROGRAM PL'AN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 23 of 90 Rev: 1 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number ~PG D. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 759B I"2 GTV MOV 0

~124 -1 3 CTIVE EX CS CS-6 ST-C CS CS-6 PIT R LT-J R GR-2 813 B-8 GTV MOV 1114 1 A TIVE EX Q ST-C Q PIT R LT-J R GR-2 814 I-8 . GTV MOV 0 2 A 3334-3 ~CTXVE EX Q ST-C Q PIT R LT-J R GR-2

• 817 A-4 GTV MOV 0 3 B 12412-3 8 V~S(VE EX R ST-C R PIT R

System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1247 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 24 of 90 Rev: 1 Valve Coor. +pe Norm Safety Cate or Required Rel.Req Number VELD. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 624 J-7 BFV AOV 1247 8 PASSIVE EX

• 625 I-8 BFV AOV 0 1247 PASSIVE EX

• 626 H-7 BFV AOV 2 B 1 47 1>ASSIVE EX 697A F-9 SAV 1247 ACTIVE CV-P CS m CS-30 CV-0 R VR-'29 CV-C Q 697B B-9 CV SAV 2 C 1247 8 ~CT VE CV-P CS CS-30 CV-0 R VR-29 CV-C Q 700 G- 1 GTV MOV 1247 111 A TIVE EX CS CS-13 ST-0 CS CS-13 PIT R LT-X R

II System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1247 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 25 of 90 Rev: 1 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number PAID. xze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 701 G-2 GTV MOV 111 ACTIVE EX CS CS-14 ST-0 CS CS-14 PIT R LT-X R 704A D-4 GTV MOV B

~147 10 ACTIVE EX Q ST-C Q PIT R 704B C-4 GTV MOV 2 B

~147 111 ~CTIVE

-'X Q ST-C Q PIT R'10A F-6 CV SAV 2 C 1114 8 71CTIVE CV- P Q VR-20 CV-0 R VR-20 CV-C CS CS-32 710B B-6 CV SAV

~147 8 A T VE CV-P Q VR-20 CV-0 R VR-20 CV-C CS CS-32

System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1247 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 26 of 90 Valve Number Coor.

KGXD.

~e Size Actuator Norm Safety Pos Class Cate or ct Pas Required Tests Fre Rel.Req CSJ Remarks 720 I-2 GTV MOV 1 A 1247 10 ~ATZVE EX CS CS-14 ST-0 CS CS-14 PIT R LT-X R 721 I-1 GTV MOV 1247 10 ACTIVE EX CS CS-13 ST-0 CS CS-13 PIT R LT-X R 850A F-4 GTV MOV 2 B

~147 10 ~ATIVE EX Q ST-0 Q PIT R 850B B-4 'TV MOV 2 B 1247 10 ACTIVE EX Q ST-0 Q PIT R

• 851A B-1 GTV MOV 0 B

~147 111 VXSEXVE PIT

• 851B B-2 GTV MOV 1114 10 PIT R

System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1247 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 27 of 90 Rev: 1 Valve Number Coor.

A&ID.

~e Ezze Actuator Norm Safety pos Class Cate or Act pas Required Tests pre Rel.Req CSJ Remarks 854 G-4 CV SAV C

~147 ~1 ~CTIVE CV-0 R VR-4 CV-C R VR-4 856 G-5 GTV MOV 2 B 1247 10 ACTIVE EX CS CS-28 ST-C CS CS-28 PIT R 857A C-11 GTV MOV B 1247 ~CTIVE EX Q ST-0 Q PIT R 857B B-11 GTV MOV

~147 ACTIVE EX Q ST-0 Q PIT R 857C B- 11 GTV MOV 2 B 1247 ~ATIVE EX Q ST-0 Q PIT R 1813A E-3 GTV MOV A

~14 7 PASSIVE PIT R TEST NOT REQ BY ASME LT-J R GR-2

System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1247 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 28 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number F&&). ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1813B B-4 GTV MOV 2 A

~147 ~PASS VE PIT R TEST NOT REQ BY ASME LT-J R GR-2

System: SPENT FUEL POOL COOLING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1248 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Date: 10/8/97 Page: 29 90 Valve Coor. e Norm Safety Cate o Required Rel.Req Number V&ID. 1ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 8152 C-5 GTV A 1248 1 VAA'~E LT-J R 8614 H-8 GTV 1248 4 ACTIVE EX 8654 H-2 GTV MAN B 1248 ~ATTVE EX 8655 H-4 CV SAV O'SC C ACTIVE 1248 4 CV-0 Q CV-C Q 8658 I-4 CV SAV 3 C 1248 ACTIVE CV-0 Q CV-C Q

INSERVICE TESTING PROGRAM ATTACHMENT B System: SERVICE WATER Dwg No: 33013-1250 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 30 of 90 Rev: 1 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o ct Pas Required Tests Fre Rel.Req CSJ Remarks 4561 G-9 BFV AOV 3 B 112 1I -3 14 XCTTVE EX Q ST-0 Q PIT R FS-0 Q 4562 G-10 BFV AOV 3 B 122lt-3 14 ~CTIVE EX Q ST-0 Q PIT R FS-0 Q 4601 D-2 CV SAV O,C 3 C

~12 0-1 14 ~AT1VE CV-0 Q CV-C Q 4602 E-2 CV SAV 0 C 3 C 1211-3 14 ~ACT VE CV-0 Q CV-C Q 4603 F-2 CV SAV O,C 3 C 1110-1 14 W0'. TIVE'V-0 Q CV-C Q 4604 G-2 CV SAV 0 C 3 C 1211I 3 14 ACTI:VE CV-0 Q CV-C Q

System: SERVICE WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1250 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 31 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required . Rel.Req Number V&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4609 C-2 BFV MOV 3 B 1250-1 8 ~CTIVE EX Q ST-C Q PIT R 4613 D-6 BFV MOV 3 B 1110-1 10 ACTIVE EX Q ST--C Q PIT R 4614 H-2 BFV MOV B

~1250- 10 ACTIVE EX Q ST-C Q PIT R 4615 J-9 GTV MOV 1250-1 20 ACTIVE EX Q ST-0 Q ST-C Q PIT R 4616 A-9 GTV MOV 3 B

~12 0-1 ~0 ~ATIVE EX Q ST-0 Q ST-C Q PIT R 4619C F-6 GTV 11210- ~1 ACTIVE EX CS CS-4

4 J

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System: SERVICE WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1250 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 33 of 90 Rev: 1 Valve Number Coor.

PaID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 4654 D-6 REV SAV 3 C

~12 0-2 ~7 ACTIVE RT 10Y 4655 A-7 REV SAV 2 AC 1250-3 .75 P~SIVE LT-X R IN LIEU OF LT-J 4656 C-7 REV SAV 2 AC 112.10-3 ~7 PASSIVE LT-X R IN LIEU OF LT-J 4657 H-8 REV SAV 3 C 1110-2 ~7 ACTIVE 10Y RT 4658 E-j REV SAV 2 AC

~150-3 PASSIVE LT-J LT-X R IN LIEU OF 4659 G-7 BEV SAV AC 1250-3 PPPS IVE LT-X R IN LIEU OF LT-J 4660 H-7 REV SAV AC

~12 0-3 . 75 PPPSSIVE LT-J LT-X R IN LIEU OF 4663 I-3 GTV MOV B 1130-3 6 CTIVE EX, ST-C Q

Q PIT R

System: SERVICE WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1250 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 34 of 90 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Fre Rel.Req CSJ Remarks 4664 H-2 GTV MOV 0 1125- 10 ACTIVE EX Q ST-C Q PIT R 4670 D-5 GTV MOV 0 12111 10 ACTIVE EX Q ST-C Q PIT R 4733 I-3 BFV MOV 0 3 B

~1250- ~ATXVE EX Q ST-C Q PIT R 4734 E-3 BFV MOV 11150- 14 ACTIVE EX Q ST-0 Q ST-C Q PIT R 4735 B-2 BFV 1125 1 15 MOV A IVE EX Q ST-0 Q ST-C Q PIT . R 4739B B-11 GTV MAN B 1250-1 AATAYE EX CS CS-4

h System: SERVICE WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1250 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 35 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 4758 D-7 BFV 1250-3 2.5 ~PA.> VE LT-X R IN LIEU OF LT-J 4759 D-7 REV SAV AC 1250 ~7 PASSIVE LT-X R IN LIEU OF LT-J 4780 C-2 BFV MOV 1250-1 8 ACTIVE EX Q ST" C Q PIT R 9627A B-9 CV SAV IF52~) 4 ACTIVE CV-P Q VR-5 ALSO REQ AFTER DISASSEMBLY CV-0 R VR-5 SAMPLE DISASSEMBLY CV-C R VR-5 SAMPLE DISASSEMBLY 9627B B-10 CV SAV 3 C 12511-2 4 ACTIVE CV-P Q VR-5 ALSO REQ AFTER DISASSEMBLY CV-0 R VR-5 SAMPLE DISASSEMBLY CV-C R VR-5 SAMPLE DISASSEMBLY 9632A E-9 GTV AOV 3 B llll-2 1. 5 ~ATTVE EX Q ST-0 Q GR-4 FS-0 Q

I System: REACTOR COOLANT PRZR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1258 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 37 of 90 Valve Number Coor.

~P& D.

~e Size Actuator Norm Safety Pos Class Cate o ct Pas Required Tests Fre Rel.Req CSJ Remarks 430 B-8 GLV AOV 1 B 1258 3 AEETVE 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 111 8 ACTIVE 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-10 434 A-9 REV SAV 1 C 1118 4 ACTIVE PIT VR-7 RT 435 C-9 REV SAV 1 C 1121 4 EETETE PIT RT 508 F-7 DIV AOV 112 TIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

System: REACTOR COOLANT PRZR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013"1258, GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 38 of 90 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number E&ID. Baize Actuator Pos Class Act Pas Tests Pre CSJ Remarks 515 C-8 GTV MOV 0

~12 8 ACTIVE EX Q ST-0 Q ST-C Q PIT R 516 B-8 GTV MOV 0 1 B 111 8 ~ATD/E EX Q ST-0 Q ST-C Q PIT R 528 E-9 CV SAV AC ACTIVE LT-J R GR-2 CV-C Q 529 F-9 CV SAV 2 AC 1138 2 ~A~T3TE LT-J R GR-2 CV-C Q 539 E-7 GLV AOV 2 A 111 ~7 AACT AE EX Q ST"C Q PIT R FS-C Q LT-J R GR-2 546 E-8 GLV 0 1338 . 378 ACTIVE EX Q LT-J R GR-2

System: REACTOR COOLANT PRZR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1258 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL ate: 10/8/97 Page: 39 of 90 Rev: 1 Valve Number Coor.

~aD.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 547 E-8 1118

'LV

. 75 A

PASSIVE LT-J R GR-2 568R F-9 REV SAV 1118 . 75 ACTIVE RT 10Y ADDED PER NRC GL 96"06

System: CVCS LETDOWN INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1260 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 40 of 90 Valve Number Coor.

P&ID.

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

• 427 E-2 GLV AOV 1 B

~12 0 ~PA S~V~

PIT

~ ~

0

System: REACTOR COOLANT INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1260 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 41 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 590 E-7 GLV SOV 1110 1 ACTIVE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9 591 E-8 GLV SOV 12!20 1 ACTIVE EX CS , CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9 592 F-7 GLV SOV 2 B 112 1  %%TIVE 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 12 1 AA~T AE EX CS CS-9 ST-0 CS GR-4 CS-9 PIT R FS-C CS CS-9

Pt E,

l)

System: RESIDUAL HEAT REMOVAL INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1260 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 42 of 90 Rev: 1 Valve Coor. +pe Norm Safety Cate or Required Rel.Req Number ~pa D. Ez.ze Actuator Pos Class Act pas Tests Pre CSJ Remarks F-4 A 852A 111l GTV MOV 1

~A:TV'X CS CS-15 ST-0 CS CS-15 ST-C CS CS-15 PIT R LT-X R 852B F-4 GTV MOV 1212 0 ACTIVE EX CS CS-15 ST-0 CS CS-15 ST-C CS CS-15 PIT R LT-X R 853A F-5 CV SAV 1 AC 12120 ~ATIVE LT-X R GR-5 EVENT V PIV CV-P CS VR-3 CV-0 R VR-3 CV-0 AT 120 PSID CV-C R VR-14 853B F-5 CV SAV AC 111 ACTIVE LT-X R GR-5 EVENT V PIV CV-P CS VR-3 CV-0 R VR-3 CV-0 AT 120 PSID CV-C R VR-14

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 43 of 90 Rev: 1 Valve Number Coor.

F&&D.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 357 B-3 CV SAV 2 C

~12 1 4 ACTIVE CV-0 CS-25 CS 836A H-3 GLV AOV 12f2 1 2 ACTIVE EX Q ST-0 Q FS-0 Q 836B H-3 GLV AOV 111 1 ATVE EX Q ST-0 Q FS-0 Q 845C F-4 REV SAV 1212 1 ACTIVE RT 10Y 845D F-4 REV SAV 3 C 1111 . 2 AAcT AE RT 10Y 847A G- 5 CV SAV 2 C 12121 2 AATXVE CV-0 Q CV-C Q 847B H-5 CV SAV 2 C 1111 2 ~ATIWE CV-0 Q CV-C Q

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 44 of 90 Rev: 1 Valve Number Coor.

~P& D.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 859A E-6 GLV 2 A 1212 1 2 PASSIVE LT-J R VR-31 859B G-6 GLV 2 A 12!21 2 PPASSI PE LT-J R VR-31 859C D-6 GLV MAN 2 A

~22 1 KAAETVE LT-J R VR-31 860A E-7 GTV MOV 2 A

~12 I AATIVE EX Q ST-0 Q PIT R LT"X R 860B E-7 GTV MOV 2 A 111 1 ACATTU 2 EX Q ST-0 Q PIT R LT-X R 860C I-7 GTV MOV 2 A

~12 1 MITRE EX Q ST-0 Q PIT R LT-X R

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 45 of 90 Rev: 1 Valve Number Coor.

~&TD.

~e Sate Actuator Norm Safety pos Class Cate or Act pas Required Tests pre Rel.Req CSJ Remarks 860D I-7 GTV MOV 12121 6 ACTIVE EX Q ST-0 Q PIT R LT-X R 861 J-2 REV SAV 111 1 ACTIVE RT 10Y 862A E-8 CV SAV AC 12f2 1 ACTIVE LT-J R GR-2 CV-0 Q VR-24 MECH EXERCISE CV-C Q 862B I-8 CV SAV AC 12!21 ACTIVE LT-J R GR-2 CV-0 Q VR-24 MECH EXERCISE CV-C Q 864A E-8 GLV 2 A 12f21 . 75 PASSIVE LT-J R VR-31 864B H-8 GLV MAN A 12!21 ~7 P~SPPE LT-J R VR-31 869A E-9 GLV A 12f21 . 75 ~PAS.>~E LT-J R GR-2

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 46 of 90 MOULD.

Valve Coor. T~e Norm Safety Cate or Required Rel.Req Number Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 869B I-9 GLV A 111 1 ~PA SZVE LT-J R GR-2 875A F-9 GLV MOV

~12 1 2 PASSIVE EX Q ST-0 Q PIT R 875B G-9 GLV MOV 2 B 1111 2 PP~S PE EX Q ST-0 Q PIT R

• 876A H- 9 GLV MOV 2 B

~12 1 ~AP IVE EX Q ST-0 Q PIT R

• 876B G-9 GLV MOV B 12121 2 Tasszvz EX Q ST-0 Q PIT R 896A C-2 GTV MOV 2 A 22221 10 AATAVE EX CS CS-17 ST-C CS CS-17 PIT R LT-X R

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 47 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number KAID. Size Actuator Pos Class ct Pas Tests Fre CSJ Remarks 896B D-2 GTV MOV 2 A 1111 10 AAAIVE EX CS CS-17 ST-C CS CS-17 PIT R LT-X R 897 C-7 GLV MOV 2 A

~12 1 2 ~ATIVE CS-37 EX CS ST-C CS CS-37 PIT R LT-X R 898 C-7 GLV MOV 2 A

~22 1 2 AATAVE CS'-37 EX CS ST-C CS CS-37 PIT R LT-X R 1802 F-3 REV SAV C 12!21 ~7 ~ATIVE 10Y RT 1819A A- 10 GLV 2 A 1111 .75 AATAIE.

EX CS CS-19 LT-J R GR-2 1819B A-9 GLV 2 A

~12 1 ~7 ~TIVE EX CS CS-19 LT-IT ' GR-2

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 48 of 90 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 1819C B-10 GLV MAN 0 1111 ~7 ACTIVE EX CS CS-19 LT-J R GR-2 1819D B-9 GLV 1111 . 75 ACTIVE EX CS CS-19 LT-J R GR-2 1819E C-10 GLV 0 A 1111 . 75 ~ACT VE EX CS CS-19 LT-J R GR-2 1819F C-9 GLV MAN 2 A 12121 ~7 ACTIVE EX CS CS-19 LT-J R GR-2 1819G C-10 GLV 1111 .. 75 ACTIVE EX - CS CS-19 LT-J R GR-2 2825 E-8 GTV A 1221 . 75 ~PASS VE LT-J' GR-2 2825A F-8 BAV 2 A

~12 1 PASSIVE LT-J R GR-2

System: CONTAINMENT SPRAY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1261 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 49 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. xze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 2826 I-8 BAV MAN 2 A

~12 I ~7 ~PA I~VE LT-J R GR-2 2826A J-8 BAV MAN 2 A 111 1 RiSSIVE LT-J R GR-2 2829 E-9 GTV MAN 2 A 12121 ~7 %ESSIVE LT-J R VR-31 2830 I-9 GTV MAN 2 A 12121 ~7 VAASIVE LT-J R VR-31 2856 D-9 GTV MAN A 1111 ~7 PASSIVE LT-J R GR-2 2858 I-9 GTV MAN A

~11 .

~7 PAESTVE LT-J R GR-2 2863R H-10 REV SAV 1111 ~7 ACTIVE RT 10Y ADDED PER NRC GL 96"06

System: SAFETY INJECTION AND ACCUNULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 50 of 90 Rev: 1 Valve Coor. T~e Norm Safety Cate or Required Rel.Req Number PAID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 830A A-6 REV SAV 2 C

~12 2-2 1 AACTI AE RT 10Y 830B E-6 REV SAV 12122-2 1 ACTIVE RT 10Y

• 834A A-5 GLV AOV B

~1262- 1 PASSIVE PIT

• 834B E- 5 GLV AOV B 111 -2 1 TASSIVE PIT

• 835A C 4 GLV AOV B 12122-2 1 PASSIVE PIT

• 835B G-5 .GLV AOV B

~1K-2 1 FAAS.I.VE PIT 6

839A C-8 GLV AOV 2 B 11212- ~7 'PREXVE PIT

• 839B D-8 GLV AOV 1 B 111-2 MESTEE PIT

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL ate: 10/8/97 Page: 51 of 90 Rev: 1 Valve Number Coor.

PAID;

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

• 840A G-7 GLV AOV B

~12 2-2 ~7 PASSIVE PIT 840B H-7 GLV AOV B 11222- . 77.I EEEE IIVVEE PIT 841 C-7 GTV MOV 0 B 11212- 10 ACTIVE EX CS CS-33 ST-C CS CS-33 PIT CS 842A D-7 CV SAV 1 AC 11212- III ~CTIVE LT-X R CV-P Q CV-O 3R VR-8 CV-C R VR-8 842B G-7 CV SAV 1 AC 11E~ 111 EEETVE LT-X R CV-P 0 CV-0 3R VR-8 CV-C R VR-8

• 844A C-8 GLV AOV 2 B 12112- 1 PASSIVE PIT

• 844B G-8 GLV AOV 2 B 1221 1 VA I>~SI /E PIT

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 52 of 90 Rev: 1 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number K&&D. Size Actuator Pos Class ct Pas Tests Fre CSJ Remarks 846 A-6 GLV AOV 1112-1 1 ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 865

~1~

G-7 GTV 10 MOV 0 2 B AAGT AE EX CS CS-33 ST-C CS CS-33 PIT CS 867A D-7 CV SAV AC 11212 10 ACTIVE LT-X R GR-5 EVENT V PIV CV-P R VR-9 CV-0 3R VR-9 CV-C R VR-9 867B H-7 . CV SAV 1 AC 111~ 10 ACTIVE LT-X R GR-5 EVENT V PIV CV-P R VR-9 CV-0 3R VR-9 CV-C R VR-9 870A C-7 CV SAV 2 AC 12122-1 3 ACTIVE LT-J R GR-2 CV-P Q VR-11 CV-0 ~

.R VR-11 CV-C Q

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Pa e: 53 of 90 Rev: 1 Valve Number Coor.

~p& D.

~e Ezze Actuator Norm pos Safety class Cate or Act pas Required Tests Pre Rel.Req CSJ Remarks 870B E-7 CV SAV 2 AC 12f2-1 ~ACT VE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR- 11 CV-C Q 871A D-7 GTV MOV 2 B 12122-1 3 ACTIVE EX Q ST" C Q PIT R 871B E-7 GTV MOV 111-3 ACTIVE EX Q ST-C Q PIT R 872A C-2 CV SAV 1322-3 . 75 ACTIVE CV-0 Q CV-C Q 872B I-3 CV SAV C 333-2 ~7 ~AT VJ CV-0 Q CV-C Q 877A E-3 CV SAV 1 AC 11212 PASSIVE LT-X R GR-5 EVENT V PIV

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 54 of 90 Rev: 1 Valve Number Coor.

~pa D.

~e sz.ze Actuator Norm pos Safety class Cate o Act pas Required Tests pre Rel.Req CSJ Remarks 877B I-6 CV SAV AC 1112- 2 PASSIVE LT-X R GR-5 EVENT V PIV 878A E-3 GLV MOV 2 A 1222-2 2 PASSIPPE PIT R PIT DURING LT-X ONLY LT-X R GR-5 TECH SPEC PIV

• 878B D-4 GLV MOV 0 B 12122-2 2 PASSIVE PIT 878C I-5 GLV MOV A 2 ~PA SIVE PIT R PIT DURING LT-X ONLY LT-X R GR-5 TECH SPEC PIV

• '878D H-5 GLV MOV 2 B 12112- 2 MEEXUa PIT 878F

~1~E-3 CV 2

SAV 1 AC PASSIVE LT-X R GR-5 EVENT V PIV 878G D-5 CV SAV AC 1121 2 ~ATIVE LT-X R GR-5 EVENT V PIV CV-0 R VR<<10 CV-C R VR-10

I t

l S

II

~

P

INSERVICE TESTING PROGRAM ATTACHMENT B System: SAFETY INJECTION AND ACCUMULATORS Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL v

Valve Number Coor.

PaID.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 878H I-6 CV SAV AC 1121-2 2 PASSIVE LT"X R GR-5 EVENT V PIV 878J H-6 CV SAV 1 AC 12112 2 ACTIVE LT-X R GR-5 EVENT V PIV CV-0 R VR-10 CV-C R VR-10 879 G-5 GLV 2 A 12!22-1 . 75 EAEEIVE LT-J R GR-2 885A C-7 GLV MAN A 1211-1 ~7 ACTIVE EX Q LT-J R GR-2 885B F-8 GTV MAN 1211-1 ~7 ACTIVE EX

'I Q

LT-J R GR-2 887 H-8 REV SAV 2 C 1121 ~7 ~ATIVE RT 10Y 889A C-5 CV SAV 2 AC 1221-1 XCCTVE LT-J R GR-2 CVP.Q CV-0 R VR-11 VR- 11 CV-C Q

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 56 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PAID. xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 889B F-6 CV SAV 2 AC 312331 3 ACTIVE LT-J R GR-2 CV-P Q VR-11 CV-0 R VR-11 CV-C Q 891A B-3 CV SAV 2 C 12122-1 1. 5 ACTIVE CV-0 Q CV-C Q 891B D-5 CV SAV 12!22-1 1. 5 ACTIVE CV-0 Q CV-C Q 891C E-5 CV SAV 111-3 1. 5 ACTIVE CV-0 Q CV-C Q 1815A D-4 GTV MOV

~12 2-1 4 ACTIVE EX Q ST-0 Q PIT R 1815B D-3 GTV MOV 0

~12 2-1 4 CTIVE EX Q ST-0 Q PIT R

System: SAFETY INJECTION AND ACCUMULATORS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1262 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 57 of 90 Rev: 1 Valve Number Coor.

~PE D.

~e Size Actuator Norm Safety Pos Class Cate or Required Act Pas Tests Fre Rel.Req CSJ Remarks 1817 D-4 REV SAV 2 C 12122-1 . 75 ACTIVE RT 10Y 8623 A-3 CV SAV 2 AC 121222 1 ACTIVE LT-J R GR-2 CV-C Q 12406 B-7 GTV 2 A

~12 2-1 .75 PAEETVE LT-J R GR-2 12407 E-8 GTV 2 A

~12 2-1 ~7 VXS~SVE LT-J R GR-2

System: RCS OVERPRESSURE PROTECTION INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1263 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 58 of 90 Rev: 1 Valve Number Coor.

P&ID. P-ize e

Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 8606A B-4 CV SAV 2 AC 1323 1 ACTIVE LT-X R CV-C R VR-19 8606B G-4 CV SAV AC 1263 ACTIVE LT-X R CV-C R VR-19 8608A C-4 REV SAV C 3333 . 75 XCCTVE RT 10Y 8608B G-4 REV SAV C 1121 . 75 ACTIVE RT 10Y 8615A B-6 REV SAV C 1263 1 ~CT VE RT 10Y 8615B F-6 REV SAV 2 C 1263 1 ~ETTVE RT 10Y 8616A B-7 TWV SOV 1263 ~7 ACTIVE EX CS CS-11 ST-0 VR-15

INSERVICE TESTING PROGRAM ATTACHMENT B System: RCS OVERPRESSURE PROTECTION Dwg No: 33013-1263 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 59 of 90 Rev: 1 Valve Number Coor.

P&ID.

~e Sx.ze Actuator Norm Safety Pos Class Cate o Act Pas Required Tests Pre Rel.Req CSJ Remarks 8616B G-7 TWV SOV 2 B 1263 .75 31CTTVE EX CS CS-11 ST-0 VR-15 8619A C-9 TWV SOV B 12123 1 ACTIVE EX CS CS-11 ST-0 VR-15 ST-C VR-15 8619B G-9 TWV SOV B 1222 1 ACTIVE EX CS CS-11 ST-0 VR-15 ST-C VR.- 15 8630A C-9 CV SAV

~12 3 1 ACTIVE CV-0 CS CS-11 BY PORV TEST CV-C CS CS-11 8630B G-9 CV SAV C

~12 3 1 EETEV2 CS-11 CV-0 CS BY PORV TEST CV-C CS CS-11

System: CVCS LETDOWN INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1264 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 60 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PAID. xze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 123 E-9 GLV AOV 1 A

~AEETV LT-X 200A B-11 GLV AOV O,C 1 1264 2 ACTIVE EX CS CS-26 ST-C PIT CS R

CS-26 / GR-4 FS-C CS CS-26 LT-J R GR-2 LT-X R 200B B-10 GLV AOV O,C 1 1114 2 ACTIVE EX CS CS-26 ST-C PIT CS R

CS-'26

/ GR-4 FS-C CS CS-26 LT-J R GR-2 LT-X R 202 B-10 GLV AOV 1 A 1264 2 ~TIVE EX CS CS-26 ST-C PIT CS R

CS-26 / GR-4 FS-C CS CS-26 LT-J R GR-2 LT-X R 203 A-8 REV SAV AC 1264 2 ACTIVE LT-J GR-2 RT '0Y R

4 0 p

System: CVCS LETDOWN INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1264 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 61 of 90 Rev: 1 Valve Number Coor.

PAID.

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

• 310 C-9 GLV AOV 1 B 1114 ~7 ~ASSZVE PIT 371 B-7 GLV AOV

~12 4 2 A IVE CS-26 EX CS GR-4 ST-C CS CS-26 PIT R FS-C CS CS-26 LT-J R GR-2 702 A-10 CV SAV 2 C 1114 . 75 ACTIVE CV-0 CS CS-18

System: CVCS CHARGING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1265 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 62 of 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number ~P& D. 1ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 112B F-3 BFV AOV 1121 4 ACTIVE EX CS CS-25 ST-0 CS CS-25 PIT R FS-C CS CS-25 112C D-3 BFV AOV 0 12!21 4 ACTIVE EX CS CS-24 GR-4 ST-C CS CS-24 PIT R FS-0 CS CS-24 142 E-10 GLV AOV 0 2 B 2222-2 ACTIVE EX CS CS-23 ST-0 CS CS-23 PIT R FS-0 CS CS-23 257 A-4 REV SAV 2 C 1221-2 2 ACTIVE RT 10Y 268 F-3 BFV 2 B XiC~ 4 ACTIVE EX CS CS-24 270A F-3 GLV AOV 1121 - 1 ACTIVE EX ,.CS CS-21 GR-4 ST-C CS CS-21 PIT R

lk t I F

System: CVCS CHARGING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1265 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-.1999 INTERVAL Date: 10/8/97 Page: 63 of 90 Rev: 1 Valve Coor. e Norm Safety Cate o Required Rel.Req Nemher ~P& D. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 270B F-6 GLV AOV 0 111 -1 ACTIVE EX CS CS-21 GR-4 ST-C CS CS-21 PIT R 283 H-6 REV SAV 1121-2 . 75 ACTIVE RT 10Y 284 F-6 REV SAV 2 C 122-2 . 75 ~ATIVE RT 10Y 285 E-6 REV SAV

~12 5-2 ~7 ACTIVE 10Y RT 302C G-6 CV SAV 1121- 1 ACTIVE CV-0 Q NORMAL OPS SEAL FLOW 302D G-3 CV SAV 1111 2 ACTIVE NORMAL OPS SEAL FLOW 304A H-3 CV SAV AC 1265-1 ACTIVE LT-J R GR-2 CV-0 , Q NORMAL OPS SEAL FLOW CV-C CS CS-21

System: CVCS CHARGING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013"1265 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 64 of 90 Rev: 1 Valve Coor. ~Te Norm Safety Cate or Required Rel.Req Number PAID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 304B H-6 CV SAV 0 AC

~12 5-1 2 ACTIVE LT-J R GR-2 CV-0 Q NORMAL OPS SEAL FLOW CV-C CS CS-21 313 D-8 GTV MOV 0 22225-2 3 ACTIVE EX CS CS-22 ST-C CS CS-22 PIT R LT-J R GR-2 314 B-4 REV SAV 2 C

~12 5-1 2 ~ACT VE RT 10Y 358 F-3 BFV 2 B

~12 5-2 5 ACTIVE EX CS CS-25 370B B-2 . CV SAV 0 AC 1115- 3 2 ACT VE LT-J R GR-2 LT-X R CV-0 CS CS-23 CV-C CS CS-23 383B H-2 CV SAV AC

~12 5-1 ACTIVE LT-J GR-2 R

LT-X R CV-C CS CS-27

INSERVICE TESTING PROGRAM ATTACHMENT B System: CVCS CHARGING Dwg No: 33013-1265 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10 8 97 Pa e: 65 of 90 Valve Coor. ~T e Norm Safety Cate o Required Rel.Req Number VE.I.D. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 386 C-4 . GTV AOV 111-1 1 ACTIVE CS-22 EX CS ST-C PIT CS R

CS-22 / GR-4 FS-C CS CS-22 392A A-9 GLV AOV BC 1121-1 2 ACTIVE PIT RT VR-16 393 A-10 CV SAV C 1115-1 2 ACTIVE CV-0 CS CS-23 9315 A-9 CV SAV C 111-1 2 ACTIVE CV-0 CS-23 CS

System: RCDT INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1272 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 66 of 90 Valve Coor. +pe Norm Safety Cate or Required Rel.Req Number ~p& D. Saze Actuator Pos Class ct pas Tests Pre CSJ Remarks 1003A D-4 DIV AOV 2 A 1272-2 ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 1003B E-4 DIV AOV

~127 -2 ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 1655 B-2 GLV 0

~127 -2 ~7 ACTIVE EX Q LT-J R GR-2 1709G E-3 GTV 2, A

~17~ ~ . 75 PPPS IVE LT-J R GR-2 1713 A-3 CV SAV 2 AC

~127 -2 1 ~CTIVE LT-J R GR-2 CV-C CS CS-34

System: RCDT INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1272 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 67 of 90 Rev: 1 Valve Number Coor.

PAID.

~e Sx,ze Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 1721 D-3 DIV AOV 0 2 A

~1272- ~AT.KE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1722 D-3 DIV 1272-2 4 PA S VE LT-J R GR-2 1786 B-5 DIV AOV 0

~1272- 1 ~C~TVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1787 B-5 DIV AOV 2 A

~172-2 1 EEATZ 5 EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1789 B-5 DIV AOV 1117- . 75 ~CTHE EX Q ST-C Q PIT R FS-C ' Q LT-J GR-2

System: RCDT INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1272 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 68 of 90 Rev: 1 Valve Coor. Type Norm Safety Cate o Required Rel.Req Number ~P& D. Size Actuator Pos Class ct Pas Tests Fre CSJ Remarks 1793 A-3 DIV 2 A 12171 1 %ARETTE LT-J R GR-2

• 1811A D 7 GTV MAN 2 B 1272-2 ~ASS IVE CLASS BOUNDARY ID - NO TEST REQ

• 1811B E-7 GTV MAN 2 B 1127 1 i>ASS IVE CLASS BOUNDARY ID - NO TEST REQ

System: WASTE DISPOSAL - GAS

. INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1273 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL of Rev:

Date: 10/8/97 Page: 69 90 1 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number PaID. i2:e Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 14 I-3 GLV AOV C SSC B

~127 -2 ACTIVE EX Q PIT R FS-C Q

System: H2 RECOMBINERS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1275 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 70 of 90 Rev: 1 Valve Number Coor.

P&ID.

~e Size Actuator Norm Safety Pos Class Cate or ct Pas Required Tests Fre Rel.Req CSJ Remarks 1076A B-7 DIV 2 A 1275-1 1 PASSIVE LT-J R GR-2 1076B E"8 DIV 2 A 1275-1 1 PASSIVE LT-J R GR-2 1080A E-1 GTV 1171 1 1 VAASIIIE LT-J R GR-2 1084A D-7 DIV 111 -1 1 ASS VE LT-J R GR-2 1084B G-8 DIV 2 A

~175-I I PXS~IVE LT-J GR-2 R

• 8423A A-6 . CV SAV C 1275-2 1 XCTTV~

CV-0 R

• 8425A G-5 CV SAV 3 C 1275-2 2 AECT AE CV-0 R

• 8427A F-5 CV SAV 3 C

~ave-z ACTIAAE CV-O, R

System: H2 RECOMBINERS INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1275 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 71 of 90 Valve Coor. ~T e Norm Safety Cate or Required Rel.Req Number ~& E. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks

• 8433A D-5 CV SAV 3 C 1275-2 2 ~CTIVE CV-0 R

• 8435A C"5 CV SAV C 1121-2 . 75 ACTIVE CV-0 R 10205S1 B-7 GTV SOV

~127 -1 1 PASSIVE LT-J R GR-2 10209S1 D-7 GTV SOV 1275-1 1 PASSIVE LT-J R GR-2 10211Sl E-8 GTV SOV 2 A 12271 1 ~PAS IVE LT-J R GR-2 10213S1 G-8 GTV SOV 11171 I PASSIVE LT-J R GR-2 10214Sl C-1 GTV SOV 2 A 1275-1 1 TXSSIVE LT-J R GR-2 10215S1 E-1 GTV SOV 2 A ISI- 1 1 PPAETVE LT-J R GR-2

System: S/G BLOWDOWN INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1277 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 72 of 90 Valve Coor. +ye Norm Safety Cate or Required Rel.Req Number PAID. S~ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5735 A-4 GTV AOV 1277-1 .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 0 2 A 1277-1 .75 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J 5737 H-5 GTV AOV

~177-1 '

ACTIVE 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

~12 7-1 2 ~ACT VE EX Q ST-C Q PIT R FS-C Q LT-X R IN LIEU OF LT-J

System: NUCLEAR SAMPLING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1278 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 73 of 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number ~PG L~ xze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 921 G- 1 GTV SOV 2 A 1278 1 ~7 ACTTEEE 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

~7 1278-1 ACTAIAE 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 11271-1 .375 ACTIVE EX Q ST-0 Q GR-4 ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 924 I-2 GTV SOV 2 A

~178-1 ~75 AVT~Vi.

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

System: NUCLEAR SAMPLING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1278 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 74 of 90 Rev: 1 Valve Coor. T~e Norm Safety Cate or Required Rel.Req Number PAID. Size Actuator Pos Class ct Pas Tests Fre CSJ Remarks 951 E- 8 GLV AOV 1278-1 .375 A TIVE EX Q ST-C Q PIT R FS-C Q 951C E-8 CV SAV 1 C 13711 . 375 ~AT~E CV-0 CS CS-38 ADDED PER NRC GL 96-06 953 D-8 GLV AOV 1 B

~178-3 ACT.KE EX Q ST-C Q PIT R FS-C Q 953C D-8 CV SAV 1278-1 .375 ACTIVE CV-0 CS CS-38 ADDED PER NRC GL 96-06 955 B-8 GLV AOV 1 B 12171-3 XCTTVV EX Q ST-C Q PIT R FS-C Q 955C B-8 CV SAV

~178-3 .375 '.TI'TE CV-0 CS CS-38 ADDED PER NRC GL 96-06

System: NUCLEAR SAMPLING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1278 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 75 of 90 Rev: 1 Valve Number Coor.

~P6 D.

~e Size Actuator Norm Safety Pos Class Cate o ct Pas Required Tests Fre Rel.Req CSJ Remarks 956D B-9 GLV MAN 0 2 A 1278-1 .375 XCiiVa EX Q LT-J R GR-2 956 E D- 9 GLV 1278-1 .375 ACTIVE EX Q LT-J R GR-2 956F E-9 GLV O. 2 A 1278-1 .T77 XVPXUE EX Q LT-J R GR-2 959 C-3 GLV AOV 2 B 1278-2 .375 PPPszvE PIT 966A E-9 GLV AOV

~178-2 ~7 A TIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 966B D-9 GLV AOV 1278-1 .375 ACT.IVE EX Q ST-C Q PIT R'S-C

~

Q LT-J R GR-2

System: NUCLEAR SAMPLING INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1278 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 76 of 90 Rev: 1 Valve Coor. T~e Norm Safety Cate or Required Rel.Req Number PAID. Size Actuator Pos Class ct Pas Tests Fre CSJ Remarks 966C B-9 GTV AOV C 2 A

~ZZV -3. ~37 ~A:TF~TE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 7448 G-1 GTV 1278-1 .375 PASSIVE LT-J R GR-2 7452 H-2 GTV 2 A 1278-1 .375 ~PA STVE LT-J R GR-2 I-1 7456 1278-1 ~5 GTV MAN 2 A FASlSTFE LT-J R GR-2

System: POST ACC SAMP INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1279 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 77 of 90 Valve Coor. e Norm Safety Cate or Required Rel.Req Number ~aID. Faze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1723 E-2 DIV AOV 2 A

~17 9 ACTIVE EX Q ST"C Q PIT R FS-C Q LT-J R GR-2 1728 F-2 DIV AOV 0

~379 3 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2

System: CONTAINMENT HVAC & RECIRC INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1863 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 78 of 90 Rev: 1 Valve Coor. Type Norm Safety Cate or Required Rel.Req Number ~Pa D. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1554 C-5 DIV 2 A 111 .75 'PXEEXVE LT-J GR-2 R

1555 C-6 GTV MAN A 138 PA~SIZE LT-J R GR-2 1556 C-5 DIV 2 A 1133 . 75 ~PA SIVE LT-J R GR-2 1557 C-5 DIV 2 A 1181 . 75 PASSIVE LT-J R GR-2 1558 C-5 GTV MAN A 111 KAAETVE LT-J GR-2 R

1559 C-4 DIV 2 A 1183 . 75 SAASSI 8 LT-J R GR-2 1560 D-5 DIV A 1181 ~7 HEs&a LT-J R GR-2 1561 D- 5 GTV 1811 .5 .PASSIVE LT-J R GR-2

System: CONTAINMENT HVAC 6 RECIRC INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1863 V

GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 79 of 90 Valve Coor. +ye Norm Safety Cate or Required Rel.Req Number P&ID. Size Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1562 D-5 DIV 111 .75 PASSIVE LT-J R GR-2 1563 J-5 DIV MAN 2 A IS!83 ~7 PASSIVE LT-J GR-2 R

1564 J-6 GTV A 111 .5 ~PAS IVE LT-J GR-2 R

1565 J-6 DIV MAN 1ll13 ~7 PASSIVE LT-J R GR-2 1566 J-5 DIV MAN A 13183 ~7 PASSIVE LT-J R GR-2 1567 I-6 GTV A 111 PPPS IVE LT"J GR-2 R

1568 J-6 DIV 2 A 111 .75 ~ASSIVE LT-J R GR-2 1569 B-11 DIV PASSIVE LT-J R GR-2

System: CONTAINMENT HVAC & RECIRC INSERVICE TESTING PROGRAM .ATTACHMENT B Dwg No: 33013-1863 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 80 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number P&ID. xze Actuator Pos Class ct Pas Tests Fre CSJ Remarks 1570 B-11 GTV 2 A 1181 ~PA JiKE LT-J R GR-2 1571 B" 11 DIV 1181 . 777 PASSIVE LT-J R GR-2 1'572 B"12 DIV 2 A lll13 . 717 PAKSTV!

LT-J R GR-2 1573 B-12 GTV 2 A 133 .5 PARSEE LT-J R GR-2 1574 B-12 DIV MAN 2 A 1181 ~7 PPPslvE LT-J R GR-2

System: CONTAINMENT HVAC PURGE SUPPLY INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1865 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 81 of 90 Rev: 1 Valve Number Coor.

P~PPD.

~e Size Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 5869 F-9 BFV AOV C SSC 1181 48 ACTIVE EX R OOS WITH FLANGE INSTALLED ST-C R PIT R FS-C R 7445 H-7 BFV AOV O,C 2 1866 ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R . GR2 7478 H-8 ~ BFV AOV 0, C 2 A 111 6 ACTIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2

System: CONTAINMENT HVAC PURGE EXHAUST INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1866 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 82 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PaID. zze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 1596 I-10 GLV A 111 1 XCTT.'UE EX Q LT-J R GR-2 1597 I-9 DIV AOV 0 1B186 1 ~TIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 1598 . G-10 DIV AOV 2 A 1866 1 ~AT1VE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 G-10 DIV A 1599

~186, 1 AOV 2

~ATIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 5879 I-2 BFV AOV 2 B 1116 48 ~ATIVE EX R OOS WITH FLANGE INSALLED ST-C R PIT FSC'R R

System: AUX/INT BUILDING HVAC INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1870 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 83 of 90 Rev: 1 Valve Number Coor.

PAID.

~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 1870 ACTI E EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2 7971 G-4 BFV AOV 0, C 2 A 1870 ~ATIVE EX Q ST-C Q GR-4 PIT R FS-C Q LT-J R GR-2

System: CONTAINMENT VESSEL AIR TEST INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1882 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 84 of 90 Valve Number Coor.

E>~TD.

~e Sz.ze Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Fre Rel.Req CSJ Remarks 7443 E-10 - BFV MOV 12822 PASSIVE PIT R LT-J R GR-2 7444 J-5 BFV MOV 2 A 1882 PABETVE PIT R LT-J R GR-2

System: SERVICE AIR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1886 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 85 of 90 Rev: 1 Valve Number Coor.

~ps D.

~e szze Actuator Norm Safety Pos Class Cate or Act Pas Required Tests Pre Rel.Req CSJ Remarks 7141 C-3 GTV A 18811 2 PASSIVE LT-J R GR-2 7226 C-5 CV SAV AC 18818-2 2 ACTIVE LT-J R GR-2 CV-C CS CS-34

System: INSTRUMENT AIR INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1887/1893 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 86 of 90 Rev: 1 Valve Coor. Tyye Norm Safety Cate or Required Rel.Req Number P&ID. Bx.ze Actuator Pos Class Act Pas Tests Fre CSJ Remarks 5393 D-4 CV SAV 2 AC I BIB 7 I ~ACT VE LT-J R GR-2 CV-C R GR-3 5392 A-11 GTV AOV 0 2 A 221 ACATAE VR-12 EX R ST-C R VR-12 PIT R FS-C R VR- 12 LT-J R GR-2

System: PRIMARY WATER TREATMENT INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1908 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 87 of 90 Rev: 1 Valve Coor. e Norm Safety Cate or Required Rel.Req Number PAID. ize Actuator Pos Class Act Pas Tests Fre CSJ Remarks 8418 A-4 GLV AOV 111 -3 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 8419 A-5 CV SAV AC 1908-3 2 ACTIVE LT-J R GR-2 CV-C Q 8421R A-5 SAV 2 C

~1908-..REV 75 ACTIVE RT 10Y ADDED PER NRC GL 96-06

System: FIRE PROTECTION INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1989 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 88 of 90 Valve Number Coor.

VZ[D.

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

• 5133 C-8 CV SAV C SSC C 1119 10 ~ATIVE CV-0

• 5134 C-7 REV SAV C SSC C 111 9 ACTIVE RT 10Y

• 5135 H" 2 REV SAV C SSC C 111 9 ~CTTVE RT 10Y

• 5136 I-3 CV SAV C SSC 1911 10 ACTIVE

System: FIRE PROT-TB-TSC INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1990 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 89 of 90 Rev: 1 Valve Number Coor.

P&ID.

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

System: CONSTRUCTION FIRE SERV WATER INSERVICE TESTING PROGRAM ATTACHMENT B Dwg No: 33013-1991 GINNA STATION VALVE TESTING PROGRAM PLAN FOR THE 1990-1999 INTERVAL Date: 10/8/97 Page: 90 of 90 Rev: 1 Valve Number Coor.

P &>T.

~e Size Actuator Norm Safety Pos Class Cate o ct Pas Required Tests Fre Rel.Req CSJ Remarks 5129 D-7 GTV A

~11 2 FA.4~ S~VE LT-J R GR-2 9227 B-5 GTV AOV 1111 4 ACTIVE EX Q ST-C Q PIT R FS-C Q LT-J R GR-2 9229 C-5 CV SAV 2 AC 1991 . 4 ~ATTVE VR-32 LT-J R GR-2 CV-C Q 9230R C-5 REV SAV 119 ll 75 ACTIVE RT 10Y ADDED PER NRC GL 96-06

'0