ML092610435
| ML092610435 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/11/2009 |
| From: | Swift P Constellation Energy Group, Ginna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| WPLNRC-1002191 | |
| Download: ML092610435 (151) | |
Text
Paul Swift R.E. Ginna Nuclear Power Plant, LLC Manager, Nuclear Engineering Services 1503 Lake Road Ontario, New York 14519-9364 585.771.5208 585.771.3392 Fax Paul.swift@constellation.com 0
C01IMs600VaIon 1119rgy' Nuclear Generation Group September 11, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
R.E. Ginna Nuclear Power Plant Docket No. 50-244 Fifth Ten-Year Inservice Test Program for Safety-Related Pumps and Valves Pursuant to 10 CFR 50.55a(f)(5)(i), R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) has revised the pump and valve inservice testing (IST) programs for the fifth ten-year test interval that begins January 1, 2010. A copy of the program is included as Attachment (1). Enclosed in Attachment (1), pages 50 through 68, are necessary relief requests.
The relief requests are submitted under either the provisions of 10 CFR 50.55a(a)(3)(i) as an alternative that provides an acceptable level of quality and safety, 50.55a(a)(3)(ii) because compliance involves hardship or unusual difficulty without compensating increase in level of quality or safety, or the provisions of 10 CFR 50.55a(f)(5)(iii) because compliance with the code requirements is impractical.
The applicable 10 CFR 50.55a provision is identified in each relief request.
Relief requests PR-01 (PR-1), PR-02 (PR-3), GR-01 (GR-1), VR-01 (VR-3), VR-02 (VR-4), and VR-03 (VR-8) were previously approved for the Ginna fourth 10-year test interval. Relief requests GR-02 and GR-03 are new to the program.
Ginna LLC requests approval of the relief requests prior to the start of the fifth 10-year test interval, which will begin January 1, 2010. Since all previous IST Program commitments were reviewed and incorporated as necessary in the updated programs, all previous IST commitments are superseded by these fifth ten-year IST program submittals.
There are no regulatory commitments contained in this letter. Should you have questions regarding this matter, please contact Thomas Harding (585) 771-5219, or thomas.hardingirgconstellation.com.
Very truly yours, Paul M. Swift Ao4r (dPLAJ 26 I100.ý-I9
Attachment:
INSERVICE TESTING PROGRAM 5h TEN-YEAR INTERVAL Robert E.
Ginna Nuclear Power Plant cc:
S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC INSERVICE TESTING PROGRAM 5th TEN-YEAR INTERVAL Robert E. Ginna Nuclear Power Plant
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 1 of 74 INSERVICE TESTING PROGRAM 5th TEN-YEAR INTERVAL Robert E. Ginna Nuclear Power Plant Effective Date:
Prepared by:
Review by: _
Date:
Date:
Date:
Approved by:
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 2 of 74 Table of Contents
1.0 INTRODUCTION
3
2.0 REFERENCES
4 3.0 TERMS AND DEFINITIONS.......................................................................................
5 4.0 GENERAL REQUIREMENTS.........................................
5 5.0 PUMP TESTING PROGRAM.......................................................................................
6 5.1 S c o p e..................................................................................................................
6 5.2 Exemptions.....................................................................................................
7 5.3 Pump Groups.................................................................................................
7 5.4 Test Requirements...........................................................................................
7 5.5 Pump Testing Program Plan Description.........................................................
8 6.0.
VALVE TESTING PROGRAM....................................................................................
8 6.1 S c o p e..................................................................................................................
8 6.2 E xe m ptio ns...................................................................................................
.. 9 6.3 Test Requirements..........................................................................................
9 6.4 Valve Testinq Program Plan Description.....................................................
11 7.0 R E C O R D S....................................................................................................................
14 8.0 S Y S T E M IN D E X...........................................................................................................
15 9.0 COLD SHUTDOW N JUSTIFICATIONS....................................................................
16 10.0 REFUELING OUTAGE JUSTIFICATIONS................................................................
26 11.0 RELIEF REQUESTS 12.0 TECHNICAL JUSTIFICATIONS Attachment A: Pump Testing Program Plan Attachment B: Valve Testing Program Plan
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 3 of 74
1.0 INTRODUCTION
1.1 This document establishes and defines the Pump and Valve Inservice Testing Program for Ginna Station's fifth ten-year interval from January I, 2010 through December 31, 2019. 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 OM Code-2004 Edition, "Code for Operation and Maintenance of Nuclear Power Plants".
Program requirements for the fifth ten-year interval are developed in accordance with these guidelines.
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 Ginna Station 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 any redundant train is out of service.
Instead, equipment will be positioned to provide for safe plant operation.
Pumps and valves included in this program are those in systems or portions of systems (Section 8.0 - System Index) which are required to perform a specific function in shutting down the reactor to a safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident, as identified within Ginna Station's licensing basis.
1.3 Ginna Station is licensed for a safe shutdown condition of hot shutdown. As such, OM Code required testing does not apply to those components relied on for achieving and maintaining a cold shutdown condition.
1.4 In addition to those pumps and valves required to be tested by the Code, other "augmented" components are administratively included in the program from a good engineering and management practice standpoint.
The inclusion of components designated as "augmented" within the IST program has been discussed in NUREG-1482, Rev.1, Section 2.2, Generic Letter 89-04, NRC Staff Position II, "Scope of IST Programs", and Summary of Public Workshops Held in NRC Regions on Inspection Procedure 73756, Section 1, General Questions. These components are identified as "augmented" in the test tables and need not be tested to specific Code criteria.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 4 of 74
2.0 REFERENCES
2.1 ASME OM Code-2004 Edition, no Addenda, "Code for Operation and Maintenance of Nuclear Power Plants" (herein referred to as the Code or OM Code).
2.2 Nuclear Directive ND-IIT, Inservice Inspection and Testing.
2.3 Interface Procedure IP-IIT-2, Inservice Testing Program for Pumps and Valves.
2.4 Interface Procedure IP-IIT-3, Containment Leakage Rate Testing Program.
2.5 Ginna Station Technical Specifications.
2.6 Ginna Station Updated Final Safety Analysis Report (UFSAR).
2.7 NUREG-1482, Revision 1, Guidelines for Inservice Testing at Nuclear Power Plants.
2.8 NUREG-0821, Systematic Evaluation Program (SEP) topics.
2:9 Title 10 Code of Federal Regulations Part 50 Para. 50.55a, Codes and Standards.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 5 of 74 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.
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 Refueling - at least once per 18 months Biennially or every 2 years - at least once per 731 days 3.7 Group A Pumps - pumps that are operated continuously or routinely during normal operation, cold shutdown or refueling operation.
3.8 Group B Pumps - pumps in standby systems that are not operated routinely except for testing.
3.9 Vertical line shaft pumps - a vertically suspended pump where the pump driver and pump element are connected by a line shaft within an enclosed column.
3.10 Skid-mounted pumps and valves -
pumps and valves integral to or that support operation of major components, even though these pumps and valves may not be located directly on the skid. In general, these pumps and valves are supplied by the manufacturer of the major component.
3.11 Instrument loop - two or more instruments or components working together to provide a single output.
Per ASME OM Code Interpretation 04-07, pump suction and
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 6 of 74 discharge pressure instruments are not considered an instrument loop when used in conjunctionto determine differential pressure.
3.12 Instrument loop accuracy - accuracy of an instrument loop based on the square root of the sum of the squares of the inaccuracies of each instrument or component in the loop when considered separately. Alternatively, the allowable inaccuracy of an instrument loop may be based on the output for a known input into the instrument loop.
3.13 Plant operation - the conditions of startup, operation at power, hot standby, and reactor cooldown as defined by plant technical specifications.
3.14 Trending -
a comparison of current data to previous data obtained under similar conditions for the same equipment.
4.0 GENERAL REQUIREMENTS 4.1 Pump and valve Inservice testing shall be performed in accordance with the ASME OM Code-2004 to the extent practicable within limits of design, geometry and materials of construction of the components as follows:
Subsection ISTA -General Requirements Subsection ISTB -
Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants Subsection ISTC -
Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants Appendix I - Inservice Testing of Pressure relief Devices in Light-Water Reactor Nuclear Power Plants Appendix II - Check Valve Condition Monitoring Program 4.1.1 Additionally, ASME OM Code Cases that have been approved for use by the NRC per Regulatory Guide 1.192 and are adopted for use at Ginna Station (subject to additional NRC approval where required) are identified below. These Code Cases shall be used during the fifth 10-Year Interval IST Program implementation with all conditions, as applicable:
E Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants," Revision 0 (upon approval of Relief Request GR-02)
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 7 of 74 Code Case OMN-8, "Alternative Rules for Preservice and Inservice Testing of Power-Operated Valves That Are Used for System Control and Have a Safety Function per OM-10," Revision 0 (upon approval of Relief Request GR-03) 4.1.2 Where a Code test requirement is determined to be impractical, this Program Document identifies applicable Relief Requests, Cold Shutdown Justifications, Refueling Outage Justifications or Technical Position Justifications which describe the bases for the determination and alternative test methods and/or frequencies.
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 which are subject to NRC review and approval, in accordance with the guidance provided by Reference 2.9, should not be implemented prior to review and approval by the Nuclear Regulatory Commission.
4.4 This program and/or implementing procedures shall be revised as necessary following applicable changes to Technical Specifications or plant modifications.
4.5 IST Program requirements shall not supersede the requirements of Technical Specifications. Any identified conflicts between the requirements of the IST Program and Technical Specifications shall be rectified.
5.0 PUMP TESTING PROGRAM 5.1 Scope This Inservice Pump Testing Program includes all safety related centrifugal, vertical line shaft 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
- b.
shutdown the reactor to a safe shutdown condition
- c.
maintain the reactor in a safe shutdown condition
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 8 of 74 5.2 Exemptions 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.
- c.
Skid-mounted pumps that are tested as part of the major component and are justified by Ginna to be adequately tested. Skid-Mounted Pumps are pumps which are integral to or support operation of a parent pump or major component.
NUREG-1482, Rev.1, Section 3.4, "Skid-mounted Components and Component Subassemblies" provides further discussion pertaining to skid-mounted components.
5.3 Pump Groups NOTE:
Transitioning to the applicable edition of the ASME OM Code for the Fifth 10-Year IST Interval requires the grouping of pumps according to function as well as adopting the Comprehensive Pump Test.
The pump groupings and justification for the assigned group are provided in this section.
5.3.1 Group A Pumps The OM Code defines Group A pumps as those pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. Ginna considers the following pumps as being categorized as Group A. The justification does not necessarily consider all safety related functions.
Component Cooling Water Pumps, [PAC02A, 02B] - The component cooling water pumps perform the safety-related function of providing cooling water flow to certain essential equipment during post-accident conditions. A large break loss-of-coolant accident (LOCA) in conjunction with a loss of off-site power places the most severe demands on the CCW system. Under these conditions, the CCW pumps are capable of supplying the required accident cooling flow to those safety-related components dependent upon CCW for continued operability. During normal plant operation the CCW pumps provide cooling water to various nonessential heat loads.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 9 of 74 Charging Pumps, [PCH01A, 01B, 01C] -The charging pumps together with the charging system perform the following process functions during normal plant operation; 1) control reactor coolant inventory, chemistry conditions, activity level, and boron concentrations, 2) provide seal water injection flow to the reactor coolant pumps, 3) process reactor coolant effluent for reuse of boric acid and makeup water.
Safety significant functions of the charging pumps together with the charging system are to provide makeup and boration to the RCS via two credited flow paths.
During the safety significant function of makeup and boration the borated water supply source would be provided from the RWST. One charging pump alone can provide cold shutdown boration requirements immediately following reactor shutdown.
The charging pumps will be included in the IST Program scope as Augmented components since their only credited function is achieving cold shutdown. Ginna Station's safe shutdown condition is the Hot Shutdown condition; therefore, they do not meet the scoping/selection criteria specified in paragraph ISTA-1 100 of the OM Code. Since they are Augmented components the Comprehensive Pump Test will not be performed.
0 Motor Driven Auxiliary Feedwater Pumps, [PAF01A, 01B] - For worst case FSAR Chapter 15 events the MDAFW pumps are required to be capable of supplying AFW flow to the steam generators during a loss of normal feedwater flow or a steam line break (SLB) in conjunction with a loss of off-site power. During plant operation, the MDAFW pumps are briefly utilized during startup to maintain steam generator water level.
Residual Heat Removal Pumps, [PAC01A, 01B] - The RHR pumps perform the safety-related function of providing low head safety injection and recirculation flow to the RCS, and long term shutdown cooling during post-accident conditions.
During the recirculation phase of a small break LOCA, the RHR pumps have the capability of providing suction to the high head safety injection pumps via the RHR heat exchangers. During normal shutdown activities the RHR pumps, in conjunction with the RHR heat exchangers are utilized for decay heat removal from the RCS.
Spent Fuel Pool Recirculation Pumps, [PAC07A, 07B] - The spent fuel pool recirculation pump A performs the safety significant function of providing heat removal from the spent fuel pool by circulating fuel pool inventory through SFP heat exchanger A, allowing the residual heat to be transferred to the service water system. This function is required to limit the pool temperature during maximum normal heat load conditions associated with a refueling outage.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 10 of 74 The spent fuel pool recirculation pump B performs the safety-related function of providing heat removal from the spent fuel pool by circulating fuel pool inventory through SFP heat exchanger B, allowing the residual heat to be transferred to the service water system. The maximum safety basis or abnormal heat load assumed by design is that resulting from offloading a complete core.
Service Water Pumps, [PSW01A, 01B, 01C, 01D] - The service water (SW) pumps perform the safety-related function of heat removal from essential safety-related equipment during accident conditions and serve as a suction supply source for the SAFW pumps.
During normal plant operation the SW pumps provide cooling water flow to numerous nonessential heat loads.
5.3.2 Group B Pumps The OM Code defines Group B pumps as those pumps in standby systems that are not operated routinely except for testing. Ginna considers the following pumps as being categorized as Group B.
The justification does not necessarily consider all safety related functions.
Containment Spray Pumps, [PSI02A, 02B] - The containment spray pumps perform the safety-related function of providing a means for containment heat removal and pressure suppression in the event of a LOCA or steam line break inside containment. The CS system serves to limit peak containment pressure.
This function is accomplished by spraying relatively cool borated water from the RWST to inside the containment via the spray nozzles.
Suction supply to the containment spray pumps can also be provided from the RHR heat exchanger discharge when operating in the recirculation mode. The containment spray pumps also perform the safety-related function of removing fission products released into the containment atmosphere during a LOCA. This is accomplished by the addition of sodium hydroxide (NaOH) to the borated spray stream at the suction of the pumps. The pumps are not operated except during testing.
Diesel Generator Fuel Oil Transfer Pumps, [PDG02A, 02B] -The diesel generator fuel oil transfer pumps perform the safety-related function of transferring fuel oil from the storage tank to the day tank. This function ensures a continuous fuel supply in support of long term operation of the engine during accident conditions. The pumps are operated only during testing.
Turbine Driven Auxiliary Feedwater Pump, [PAF03] - For worst case FSAR Chapter 15 events the TDAFW pump is required to be capable of supplying AFW flow to the affected unit. Pump controls and associated valves receive their power from the vital 125 VDC supply source to ensure short term operability independent
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 11 of 74 of normal or emergency AC power satisfying beyond design basis station blackout requirements. The pump is operated only during testing.
Standby Auxiliary Feedwater Pumps, [PSF01A, 01B] - The SAFW pumps are required to be capable of supplying AFW flow to the steam generators in the event that the preferred AFW system has failed due to a high energy line break (HELB) in the intermediate building, a seismic event, or fire. The SAFW pumps have the same features as the MDAFW pumps with regard to functional capability and power supply separation. The pumps are started manually and will only start provided that the breaker for the associated MDAFW pump is open. The suction supply source is service water and the service water supply valve must be in the open position before the pumps will start. The pumps are operated only during testing.
Safety Injection Pumps, [PSI01A, 01B, 01C] - The SI pumps perform the safety-related function of providing high head safety injection and recirculation flow to the RCS, and long term shutdown cooling during post-LOCA conditions. In addition, the system accomplishes the safety related function of bringing the plant to a safe shutdown condition subsequent to a steam line break.
During the recirculation phase, the RHR pumps circulate containment sump inventory through the RHR heat exchangers to the SI pumps supply for return to the core.
SI recirculation would be required only if RCS pressure remained above the shutdown head of the RHR pumps. The pumps operate only during testing.
5.4 Test Requirements 5.4.1 Inservice pump tests shall be conducted in accordance with Subsection ISTB of the OM Code, unless specific relief is granted by the NRC.
5.4.2 When a Group A test is required a Comprehensive test may be substituted. When a Group B test is required a Group A test or Comprehensive test may be substituted. A Preservice test may be substituted for any Inservice test.
5.4.3 Group A and Group B pump tests shall be conducted nominally every three months during normal plant operation and the Comprehensive pump test conducted once every two years, except as follows:
- a.
For pumps in systems declared inoperable or not required to be operable, test schedules need not be followed. Within three months prior to returning a system to operable status, the affected pumps shall be tested and the test schedule followed. Pumps which can only be tested during plant operation shall be tested within one week following plant startup.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 12 of 74 5.4.4 Inservice pump test intervals may be extended by 25% to accommodate normal test schedules.
5.4.5 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 by the performance of a Comprehensive or Group A pump test. Deviations between the previous and new sets of reference values shall be identified and verified to represent acceptable pump operation.
5.4.6 The instrumentation requirements of Subsection ISTB of the OM Code shall be met.
5.4.7 All test data shall be analyzed after completion of a test. When data is recorded which exceeds the Required Action range, the pump shall immediately be declared inoperable.
5.5 Pump Testinq Progqram Plan Description 5.5:17 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.
Component - pump identification number.
- c.
PID - Piping and Instrumentation Diagram (P&ID) where the pump is located (Drawing Number 33013 series).
- d.
Coordinates (Coord) - P&ID coordinates.
- e.
Code Class -.designated safety class of the pump (SS = safety significant, NS =
non-safety).
- f.
Group - Assigned pump group (either A or B)
- g.
Test Parameters - these columns show applicable pump testing parameters that shall be measured. When a "Yes" is shown in a particular column, that parameter shall be measured or observed during Inservice pump testing in accordance with the Code.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 13 of 74 Measured Parameters include the following:
Pump Speed (if variable)
Differential Pressure Discharge Pressure Flow Rate Vibration (Peak Velocity)
Speed DP Disc Press Flow Vib
- h.
Frequency (Freq) - test frequency 5.5.2 Code Dev. - If alternate testing is planned or if a test is being waived, the applicable pump relief request (PR) number will be shown.
Changes to Attachment A shall be maintained with Revision Control by the IST Program Implementer.
VALVE TESTING PROGRAM 6.0; 6.1' Scope This 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
- b.
shutdown the reactor to a safe shutdown condition and maintain the safe shutdown condition
- c.
provide overpressure protection to a system, portion of a system or component which performs (a) or (b) above.
Exemptions 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.
6.2
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 14 of 74 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.
Skid-mounted Valves - valves that are tested as part of a major component and are justified to be adequately tested.
6.3 Test Requirements 6.3.1 Inservice valve tests shall be conducted in accordance with Subsection ISTC and Appendix I of the OM Code, unless specific relief is granted by the NRC.
6.3.2 Inservice valve tests shall be conducted nominally every three months during normal plant operation, except as follows:
- a.
For a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed.
Within 3 months prior to returning the system to operable status, exercising tests shall be conducted and test schedules followed.
- b.
Valves that operate in the course of plant operation at a frequency that would satisfy the exercising requirements of the Code need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the plant record at intervals no greater than specified in the Code.
6.3.3 Inservice valve test intervals may be extended by 25% to accommodate normal test schedules.
6.3.4 Reference values shall be determined from the results of Preservice testing or from the results of Inservice testing. These tests shall be performed under conditions as near as practicable to those expected during subsequent Inservice testing.
Reference values shall be established only when the valve is known to be operating acceptably.
6.3.5 When a valve or its control system has been replaced or repaired or has undergone maintenance that could affect its performance, and prior to declaring the valve operable, it shall be retested to demonstrate that the performance parameters which could be affected by the replacement, repair or maintenance are within acceptable limits. Deviations between the previous and new reference values shall be identified and analyzed. Verification that the new reference values represent acceptable valve operation shall be documented.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 15 of 74 6.3.6 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, it is not required to keep the plant in cold shutdown in order to complete all cold shutdown testing. If the time period since the last test for a particular valve is less than 3 months, then cold shutdown testing for that valve is not required. Any testing not completed at one cold shutdown due to outage duration, shall commence and continue as above during any subsequent cold shutdown that may occur before the next refueling outage to meet the specified testing frequency.
6.3.7 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.
6.3.8 All valve testing required to be performed during a refueling outage shall be completed prior to returning the plant to operation.
6.3.9 Containment Isolation Valves shall be leak tested in accordance with 10CFR50 Appendix J, Option B (LJ-C) and controlled in accordance with the Containment Leakage Rate Testing Program (Reference 2.4).
6.3.10 Those valves which perform both a containment-isolation function and a pressure isolation function shall be leak tested to both 10CFR50 Appendix J and OM Code requirements.
6.3.11 Relief Test (RT) - relief valves shall be tested in accordance with ASME OM Code Appendix I, to verify set pressure and seat tightness.
6.3.12 Exercising check valves to the full open position utilizing flow is acceptable if the maximum required accident flowrates are passed through the valves undergoing tests.
A valid full-stroke exercise by flow requires that the flow through the valve be known and recorded.
6.3.13 Where system design or operation prevents full stroke check valve exercising, the valve may be disassembled and manually exercised as an alternative. When a check valve is disassembled and manually exercised a partial stroke test shall be performed upon reassembly, if possible.
6.3.14 Valve test results, other than stroke timing, which do not meet the prescribed acceptance criteria shall result in the valve immediately being declared inoperable.
6.3.15 Valves with measured stroke times which do not meet acceptance criteria shall be immediately retested or declared inoperable. If the valve is retested and the second
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 16 of 74 set of data does not meet acceptance criteria, the data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable valve operation or the valve shall be declared inoperable. If the second set of data meets acceptance criteria, the cause of the initial deviation shall be analyzed and the results documented.
NOTE:
As an alternative to the requirements of paragraph ISTC-5120 of the ASME OM Code-2004 Edition, Code Case OMN-1 "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants" provides an alternative to MOV stroke time testing requirements.
6.3.16 Since valves included in OMN-1 are not required to follow the stroke time requirements of ISTC-5120, stroke timing to the position(s) required to fulfill their function(s) will only be performed during diagnostic testing. The stroke times during diagnostic testing will only be compared to a reference value and a limiting value of full-stroke time for trending purposes. Acceptable Range limits specified in ISTC-5122 are not required to be used.
6.3.17 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 the OM Code.
6.3.18 Check valve testing shall be demonstrated by performing both an open and closed test, commonly referred to as "bidirectional testing".
6.3.19 As an alternative to the requirements of paragraphs ISTC-3510, ISTC-3520, ISTC-3530, ISTC-3550, and ISTC-5221, Ginna may-establish a Check Valve Condition Monitoring (CVCM) Program per ISTC-5222. The purpose of this program is to both (a) improve check valve performance and to (b) optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select group of check valves. Ginna may implement this program on a valve or a group of similar valves basis.
6.3.20 All motor-operated valves, except for certain auxiliary feedwater valves have lock-in actuation circuits and do not permit partial stroke exercising.
6.3.21 Exercising of all Category A and B active manual valves will be performed at an interval of 2 years, provided that adverse conditions do not require more frequent testing. This testing frequency is in accordance with 10 CFR 50.55a(b)(3)(vi).
6.3.22 Pressure relief devices whose only overpressure protection function is to protect isolated safety related components, systems or portions of systems from fluid expansion caused by changes in fluid temperature, shall be designated as "thermal
G ST 6.4 6.4.1 INNA INSERVICE TESTING Revision 0 ATION PROGRAM Page 17 of 74 reliefs".
Testing or replacement of these devices in lieu of testing shall be in accordance with paragraph 1-1390 of Appendix I.
Valve Testing Program Plan Description Valves that are required to be tested for the program are identified in Attachment B -
Valve Testing Program Plan. The plan is organized as a table to provide the following information:
a)
System - each page of the valve plan contains a heading which identifies the plant system for valves on the page.
b)
Valve ID / Description - valve identification number and description.
c)
Class - designated safety class of the valve (SS = safety significant, NS = non-safety).
d)
Aug - Y or N for designation of augmented scope status of the valve.
e)
Cat - ASME category A, B, C, BC, or AC assigned to the valve.
f)
A/P - identification of the valve as ACTIVE - A or PASSIVE - P.
g)
Size - nominal size of the valve in inches
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 18 of 74 h)
Valve Type - valve design type as indicated by the following abbreviations:
Ball Valve BAV Butterfly Valve BFV Check Valve CV Diaphragm Valve DIV Gate Valve GTV Globe Valve GLV Nozzle check Valve NCV Relief Valve RV Thermal Relief Valve TRV Stop Check Valve SCV Three-way Valve TWV i)
Actuator Type -
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 j)
Drawing & Coord - P&ID Number (RG&E Drawing Number 33013 series) and location coordinates of the valve on the P&ID.
k)
Position: Normal / Safety / Fail-safe Normal - position of the valve during normal plant operation Safety - position of the valve during accident conditions Fail-safe - position valve moves to on loss of actuator power.
Positions indicated by the following:
0 - Open C - Closed Al - As-Is
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 19 of 74 I)
Required Test - required Inservice tests to be performed are indicated by the following:
BDT-C
- Bi-directional exercise test in non-safety close direction BDT-O
- Bi-directional exercise test in non-safety open direction CV-C
- Check Valve Exercise - Full closed CV-O
- Check Valve Exercise - Full open DI
- Disassembly and inspection per ISTC-5221(c)
DIAG
- MOV diagnostic test per Code Case OMN-1 EX
- Exercising test (for Category A or B valves)
FS (OC) - Fail Safe Test (0 = open, C = closed)
LJ-C
- Leak test per 10CFR50 Appendix J, Option B LT-X
- Leak test per OM Code LT-XT
- Leak test per Technical Specifications (PIVs)
- Position Indication Test RT
- Relief Valve Test ST (0,C) - Stroke Time (0 = open, C = closed) m)
Frequency - test frequency described by:
AD Administratively Directed - Augmented requirement Q
Quarterly, at least once every three months CS during cold shutdowns R
Refueling, once every 18 months 3R Once every three refueling outages 2Y Once every 2 years 5Y Relief valve 5 year interval for Safety Class 1 and Main Steam Safety Valves 10Y Relief valve 10 year interval for Safety Classes 2 and 3, excluding Main Steam Safety Valves CMP test frequency dictated by the Check Valve Condition Monitoring Program OMN1 -
ASME Code Case OMN-1 diagnostic test interval OPB Appendix J Option B, performance based interval for Containment Isolation Valves
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 20 of 74 n)
RR/CSJ/ROJ - identifies applicable Relief Request, Refueling Outage or Cold Shutdown Justification number, where:
CS = Cold Shutdown Justification ROJ = Refueling Outage Justification GR = Generic Relief Request VR
= Valve Relief Request TJ
= Technical Position Justification
- 0)
Comments - applicable pertinent clarification or additional information is provided or referenced.
6.4.2 Changes to Attachment B shall be maintained with Revision Control by the IST Program Implementer.
7.0 RECORDS Records of the Pump and Valve Inservice Testing Program shall be developed and maintained in accordance with criteria established by the Code as delineated by ND-liT, IP-IIT-2 and IP-IIT-3.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 21 of 74 8.0 SYSTEM INDEX SYSTEM Main Steam Main Feedwater Auxiliary Feedwater Standby Auxiliary Feedwater Diesel Generators Component Cooling Water Component Cooling Water Residual Heat Removal Residual Heat Removal Spent Fuel Pool Cooling Service Water Reactor Coolant Pressurizer Reactor Coolant Containment Spray Safety Injection & Accumulators RCS Overpressure Protection CVCS Letdown CVCS Charging Reactor Coolant Drain Tank Waste Disposal - Gas Hydrogen Recombiners Steam Generator Blowdown Nuclear Sampling Post Accident Sampling Containment HVAC, Recirculation Containment HVAC, Purge Supply Containment HVAC, Purge Exhaust Auxiliary/Intermediate Bldg HVAC Containment Vessel Air Test Service Air Instrument Air Instrument Air Primary Water Treatment - DI Water Fire Protection Plant Systems Fire Protection: Construction Fire Service Water Auxiliary Feedwater Lube Oil Skid PI&D Number 33013-1231 33013-1236-1,2 33013-1237 33013-1238 33013-1239-1,2 33013-1245 33013-1246-1,2 33013-1247 33013-1260 33013-1248 33013-1250-1,2,3 33013-1258 33013-1260 33013-1261 33013-1262-1,2 33013-1263 33013-1264 33013-1265-1,2 33013-1272-2 33013-1273-2 33013-1275-1,2 33013-1277-1 33013-1278-1,2 33013-1279 33013-1863 33013-1865 33013-1866 33013-1870 33013-1882 33013-1886-2 33013-1887 33013-1893 33013-1908-3 33013-1989 33013-1991 33013-2285
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 22 of 74 9.0 COLD SHUTDOWN JUSTIFICATIONS CS No.
Valve ID CS-1 590, 591,592, 593 CS-2 8616A, 8616B, 8619A, 8619B, 8620A, 8620B, 8630A, 8630B CS-3 700, 721 CS-4 701,720 CS-5 702 CS-6 710A,710B CS-07 112B, 357 CS-08 142, 370B, 393, 9315 CS-09 200A, 200B, 202, 371 CS-10 270A, 270B CS-11 386 CS-12 383B CS-13 749A, 749B CS-14 750A, 750B, 753A, 753B CS-15 951C, 953C, 955C CS-16 3516, 3517 CS-17 3518, 3519 CS-18 3992, 3993 CS-19 3994, 3995, 4269, 4270, 4271, 4272 CS-20 3994G, 3995G
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 23 of 74 COLD SHUTDOWN JUSTIFICATION - CS-01 System:
Valve(s):
Category:
Function:
Test Requirement:
Deferred Test Justification:
Alternate Test Frequency:
Reactor Coolant 590, 591,592, 593 B
Code Class:
2 These normally closed pilot operated solenoid valves are part of the RCS head vent system. The valves must be capable of opening to vent non-condensable gases from the reactor vessel head space during post-accident conditions.
This function supports post accident recovery by allowing the removal of gases from the reactor vessel head space which could inhibit adequate core cooling during natural circulation. The valves perform a safety function in the closed position to maintain pressure boundary integrity of the RCS.
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Periodic full or part-stroke exercising in the open and closed directions during normal plant operation could degrade this system by repeatedly challenging the downstream valves due to a phenomenon known as "burping." This phenomenon has been previously described in ASME report "Spurious Opening of Hydraulic-Assisted, Pilot-Operated Valves - An Investigation of the Phenomenon." The phenomenon involves a rapid pressure surge buildup at the valve inlet caused by opening the upstream valve in a series double isolation arrangement or closing a valve in a parallel redundant flow path isolation arrangement. The pressure surge is sufficient enough to lift the valve plug until a corresponding pressure increase in a control chamber above the pilot and disc can create enough downward differential pressure to close the valve. Failure of any one of these valves in the open direction would reduce the pressure boundary status from double-valve protection to single-valve-protection between the Reactor Coolant System (RCS) and the Containment building atmosphere.
Valve full stroke exercising shall be performed during cold shutdowns when RCS pressure has been reduced.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 24 of 74 System:
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Function:
COLD SHUTDOWN JUSTIFICATION - CS-02 Reactor Coolant 8616A, 8616B, 8619A, 8619B, 8620A, 8620B, 8630A, 8630B B and C Code Class:
3 (8620A/B are non-Code augmented valves)
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Solenoid-operated valves 8616A and 8616B are Overpressure Protection System (OPS) surge tank charging valves. Solenoid-operated valves 8619A, 8619B, 8620A and 8620B are nitrogen three way valves for the PORVs.
Valves 8630A and 8630B are the PORV actuating line check valves. All these valves must be capable of position change to support actuation of the Pressurizer power operated relief valves (PORV).
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be tested nominally every 3 months.
Full or partial exercising of these valves during power operation would actuate the power operated relief valves. Since the associated inlet block valves are not required to be Category A valves and their seat tightness is not credited in the licensing basis, actuation of the PORVs during power operation could cause unplanned pressure transients in the RCS resulting in a reactor trip.
Valve full stroke exercising shall be performed during cold shutdowns in conjunction with PORV exercising.
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COLD SHUTDOWN JUSTIFICATION - CS-03 Residual Heat Removal 700, 721 A
Code Class:
1 These normally closed motor operated valves are located in the RHR supply lines from the RCS loop hot legs. The valves must open for initiation of RHR shutdown cooling. The shutdown cooling mode of RHR is not required for accident mitigation or to achieve/maintain safe shutdown and is not considered safety related since Ginna is licensed as hot shutdown being safe shutdown. It is; however, considered a risk significant function and components supporting this function may be subject to testing. The valves perform a safety function in the closed position to isolate RCS pressure from the lower design pressure of the RHR system.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
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, thereby, preventing the inadvertent over-pressurization of the RHR system piping and components.
Valve full stroke exercising shall be performed during cold shutdowns when RCS pressure is below the valve interlock.
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COLD SHUTDOWN JUSTIFICATION - CS-04 Residual Heat Removal 701,720 A
Code Class:
1 These normally closed motor operated valves are located in the RHR supply lines from the RCS loop hot legs. The valves must open for initiation of RHR shutdown cooling. The shutdown cooling mode of RHR is not required for accident mitigation or to achieve/maintain safe shutdown and is not considered safety related since Ginna is licensed as hot shutdown being safe shutdown. It is; however, considered a risk significant function and components supporting this function may be subject to testing. The valves perform a safety function in the closed position to isolate RCS pressure from the lower design pressure of the RHR system and to maintain containment isolation.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-351 0, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Exercising these valves during power operation is impractical. Failure of one of these valves in the open position would reduce the system from double to single-valve-protection between the RCS and RHR systems. Leakage of the associated inboard valve could result in over-pressurization of RHR system piping and components or cause an inter-system LOCA.
Valve full stroke exercising shall be performed during cold shutdowns when RCS pressure is reduced to the point of allowing the valve to be safely opened.
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COLD SHUTDOWN JUSTIFICATION - CS-05 Residual Heat Removal 702 C
Code Class:
2 This normally closed check valve is located in a branch connection to CVCS letdown off the RHR low head safety injection (LHSI)/shutdown cooling header inside the primary containment. The valve must open to provide a pressure relief flow path between the LHSI/RHR piping and the letdown orifice outlet relief valve, 203. Overpressure protection is required to prevent over-pressurization of the lower pressure LHSI piping in the event of in-leakage from the high pressure RCS. Additionally, Ginna's response to GL 96-06 credits 702 with opening to prevent thermal over-pressurization of containment penetration P111 piping and components during post-LOCA conditions.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Full exercising this check valve during power operation would require isolating letdown which could cause perturbations in or result in a loss of Pressurizer level control possibly resulting in a reactor trip.
Valve full stroke exercising shall be performed during cold shutdowns when letdown is not required to be in service.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 28 of 74 System:
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COLD SHUTDOWN JUSTIFICATION - CS-06 Residual Heat Removal 710A, 710B C
Code Class:
2 These check valves are located at the discharge of RHR pumps. The valves must be capable of opening during post-accident low head safety injection and during the recirculation phase of safety injection. The check valves must be capable of closure if the adjacent train is out of service to prevent diversion of the in service pump's recirculation flow or to prevent diversion if train A and B are cross-tied.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Closure testing of valves during power operation is not practical since this would require cross-tying the RHR pumps discharge headers thus rendering both trains of RHR inoperable. In accordance with NUREG 1482, Rev.1, Section 3.1.2, entry into multiple LCOs to facilitate testing is to be avoided.
Valve full stroke exercising shall be performed during cold shutdowns when the system can be aligned to facilitate testing.
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COLD SHUTDOWN JUSTIFICATION - CS-07 Chemical and Volume Control 112B, 357 B and C Code Class:
2 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
112B is a normally closed air operated valve located in the RWST supply line to the charging pumps suction. The valve performs a safety significant function in the open position to align the RWST inventory to the charging pumps suction.
The RWST is designated as the emergency supply source of borated water for makeup and boration of the RCS. Likewise, 357 is a normally closed check valve located in the RWST supply line to the charging pumps suction. 357 performs a safety significant function in the open direction to provide a flow path for RWST inventory to the charging pumps suction.
Per ISTC-351 0, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be tested nominally every 3 months.
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.
Valve full stroke exercising shall be performed when transitioning to or during cold shutdowns when boron concentration is not a concern.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 30 of 74 System:
Valve(s):
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Function:
COLD SHUTDOWN JUSTIFICATION - CS-08 Chemical and Volume Control 142, 370B, 393, 9315 B, AC, and C Code Class:
1 and 2 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Normally open air operated valve (142) and check valve 370B are located in the charging header. The valves perform a safety significant function in the open position to provide a flow path for RCS makeup and boration when the charging pumps are aligned to receive suction from the RWST as the emergency makeup supply source of borated water. Additionally, 370B performs an open safety function for penetration over pressure protection to address GL 96-06 concerns and as a designated containment isolation valve must close for containment integrity post-LOCA. 393 and 9315 are normally closed Class 1 check valves located in the alternate charging line from the regenerative heat exchanger to the RCS Loop B hot leg. They perform a safety significant function in the open direction since this flow path is designated as the safety related flow path for the purpose of providing makeup and boration to the RCS when the suction of the charging pumps are aligned to the RWST.
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be tested nominally every 3 months.
Exercising these valves during power operation would isolate charging flow to the RCS which could result in loss of Pressurizer level control and a reactor trip.
In addition, exercising these valves during power operation may result in excessive thermal cycles to the regenerative heat exchanger potentially resulting in premature equipment failure and reduction in its expected service life.
Valve full stroke exercising shall be performed when transitioning to or during cold shutdowns when charging flow can be secured.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 31 of 74 System:
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COLD SHUTDOWN JUSTIFICATION - CS-09 Chemical and Volume Control 200A, 200B, 202, 371 A
Code Class:
1 and 2 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
200A, 200B and 202 are air operated valves located downstream of the letdown orifices. 371 is an air operated valve located in the normal letdown line from the RCS loop B to the non-regenerative heat exchanger. The valves perform a safety function in the closed position to maintain containment integrity during post-LOCA conditions. The valves are designated inboard containment isolation valves for penetrations P111 and P112.
Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Full or partial exercising of AOV 371 during power operation would interrupt or isolate letdown flow from the RCS which would result in loss of Pressurizer level control and, potentially, a reactor trip. Full or partial exercising of AOVs-200A, 200B or 202 during power operation could result in severe letdown flow perturbations that could potentially result in adverse Pressurizer level and RCS pressure transients.
Valve full stroke exercising shall be performed when transitioning to or during cold shutdowns when letdown flow can be secured.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 32 of 74 System:
Valve(s):
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COLD SHUTDOWN JUSTIFICATION - CS-10 Chemical and Volume Control 270A, 270B B
Code Class:
2 270A and 270B are air operated valves located in the seal water return lines from the RCP shaft seals. The valves perform a safety significant function in the closed position. Although the valves fail open, they are the only power operated valves located in the pressure class 2501 seal leak-off piping. Should a catastrophic leak occur at the RCP seal, the valves may be required to close to isolate the pressure class 151 piping and components associated with containment penetration P108 from RCS pressure, although this piping is also protected by a relief valve.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be tested nominally every 3 months.
Exercising these valves during power operation would interrupt flow to and from RCP seals which could result in RCP seal damage and require the plant to shut down.
Valve exercising shall be performed during cold shutdowns when RCP seal water flow can be interrupted.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 33 of 74 System:
Valve(s):
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Function:
COLD SHUTDOWN JUSTIFICATION - CS-i 1 Chemical and Volume Control 386 B
Code Class:
2 386 is an air operated valve located in the seal bypass line from RCP A and B.
386 is the only power operated valve located in the pressure class 2501 seal bypass piping. Should a catastrophic leak occur at either RCP seal while the seal bypass is in service, 386 may be required to close to isolate the pressure class 151 piping and components associated with containment penetration P108 from RCS pressure.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-351 0, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Exercising this valve during power operation would divert flow from the RCP seals which could result in RCP seal damage and require the plant to shut down.
Valve exercising shall be performed during cold shutdowns when RCP seal water flow can be interrupted.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 34 of 74 System:
Valve(s):
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Function:
COLD SHUTDOWN JUSTIFICATION - CS-12 Chemical and Volume Control 383B AC Code Class:
2 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
This check valve is located in the CVCS alternate charging line to the RCS loop B cold leg. 383B performs a safety function in both the open and closed directions. The valve must open for GL 96-06 concerns and as a designated containment isolation valve, it must be capable of closure on cessation or reversal of flow to maintain containment integrity.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Reverse flow exercising of this valve is impractical during power operation because this test would result in substantial radiation exposure to test personnel raising ALARA concerns. The valve is located inside containment and reverse exercising requires the use of temporary test equipment and an outside pressure source.
Valve exercising shall be performed during cold shutdowns.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 35 of 74 System:
Valve(s):
Category:
Function:
COLD SHUTDOWN JUSTIFICATION - CS-13 Component Cooling Water 749A, 749B A
Code Class:
2 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
These motor operated valves are located in the CCW supply lines to the reactor coolant pumps. As designated containment isolation valves, their closure capability may be required during post accident conditions to maintain containment integrity.
Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Full or partial stroking of 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.
Valve exercising shall be performed in transition to or during cold shutdowns when the RCPs can be removed from service.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 36 of 74 System:
Valve(s):
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COLD SHUTDOWN JUSTIFICATION - CS-14 Component Cooling Water 750A, 750B, 753A, 753B C
Code Class:
2 These check valves are located inside containment in the cooling water supply lines to the RCP thermal barrier coolers. The cooling coils of the thermal barriers are part of the RCS pressure boundary. A rupture in the RCP thermal barrier cooling coils would result in the release of reactor coolant to the attached CCW piping. Closure of these valves minimizes the low pressure CCW closed system piping exposed to RCS pressure.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Reverse flow exercising of these valves during operation at power would require isolation of CCW flow to the thermal barriers. This could result in damage to an operating reactor coolant pump and a reactor trip. Additionally, reverse exercising these check valves requires entry into containment and the installation of temporary test equipment.
Valve exercising shall be performed during cold shutdowns when the RCPs can be removed from service.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 37 of 74 System:
Valve(s):
Category:
Function:
COLD SHUTDOWN JUSTIFICATION - CS-15 Plant Sampling 951C, 953C, 955C C
Code Class:
1 Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
These check valves serve as thermal overpressure protection devices for containment penetration piping and components. The valves were installed to satisfy GL 96-06 concerns.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Exercising these check valves quarterly requires entry into Containment inside the missile barrier to connect test equipment, perform the test and disconnect test equipment. Under power operating conditions, this area is a high radiation area and not readily accessible. Since the personnel safety risks and ALARA concerns far outweigh the benefit achieved with a quarterly test, testing of these check valves will be performed during cold shutdowns.
Valve exercising shall be performed during cold shutdowns.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 38 of 74 System:
Valve(s):
Category:
Function:
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
COLD SHUTDOWN JUSTIFICATION - CS-16 Main Steam 3516, 3517 B
Code Class:
2 These air operated check valves are located in the main steam headers and serve as the main steam isolation valves (MSIV). The valves perform a safety function in the closed direction to prevent the unrestricted release of steam from the steam generator during a steam line break (SLB) and to protect the integrity of the unaffected steam generator for decay heat removal. Additionally, as designated containment isolation valves, they must also be capable of closure to maintain containment integrity.
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Exercising these valves during normal operation isolates one line of steam flow to the turbine. Isolation of a main steam header would cause a severe pressure transient in the associated main steam line possibly resulting in a plant trip.
Additionally, closure of an MSIV, at power, could potentially result in challenging the set point of the main-steam relief valves causing inadvertent lifting. Reducing power level to perform testing without causing a transient would significantly impact plant operations and power production.
Valve exercising shall be performed during cold shutdowns when the main steam headers can be isolated.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 39 of 74 System:
Valve(s):
Category:
Function:
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
COLD SHUTDOWN JUSTIFICATION - CS-17 Main Steam 3518, 3519 C
Code Class:
3 These check valves are located downstream of MSIVs. The valves perform a safety function in the closed direction. A steam line rupture downstream of the non-return valves would require valve closure to prevent unrestricted blow-down of the unaffected steam generator. This function prevents the addition of large amounts of mass and energy to containment which could compromise containment integrity and protects the integrity of the unaffected steam generator so it may be used for decay heat removal.
Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Exercising of these valves to the closed position is not possible without isolating the main steam header. Isolation of a main steam header would cause a severe pressure transient in the associated main steam line possibly resulting in a plant trip. Reducing power level to perform testing without causing a transient would significantly impact plant operations and power production.
These valves will be verified to be capable of closing during normal plant shutdown to cold shutdown, following closure of the main steam isolation valves.
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.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 40 of 74 System:
Valve(s):
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COLD SHUTDOWN JUSTIFICATION - CS-18 Main Feedwater 3992, 3993 C
Code Class:
2 These check valves are located outside containment in the normal feedwater flow path to steam generators. The valves perform a safety function in the closed direction to prevent the diversion of AFW flow from the steam generator to the non-safety-related feedwater piping. Also, subsequent to feedwater isolation during a SGTR or MSLB, closure of this check valve on reversal of flow serves to isolate the faulted steam generator. Additionally, as designated containment isolation valves, they may be required to close for containment integrity.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Exercising the feedwater injection check valves in the reverse direction is impracticable quarterly during power operation due to the necessity of isolating normal feedwater flow to the associated steam generator. Isolation of feedwater flow during normal operation would cause a loss of steam generator level control potentially resulting in a plant trip.
Valve full stroke exercising shall be performed during cold shutdowns when the system can be aligned to facilitate testing.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 41 of 74 System:
Valve(s):
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COLD SHUTDOWN JUSTIFICATION - CS-19 Main Feedwater 3994, 3995, 4269, 4270, 4271, 4272 B
Code Class:
3 4269 and 4270 are located in the main feedwater supply headers to the steam generators and serve as main feedwater regulating valves (MFRV). 4271 and 4272 are located in the bypass lines around the MFRVs. 3994 and 3995 are located in the main feedwater headers to the steam generators and serve as the main feedwater isolation valves (MFIV). These six air operated valves perform a safety function in the closed position to isolate feedwater flow during a steam line break (SLB) or feedwater line break (FWLB). 3994 and 3995 provide redundant isolation of the feedwater header in conjunction with the upstream MFRVs and their bypass valves. Their closure capability is credited in the accident analysis for redundant isolation of feedwater.
Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Full or partial exercising of these valves during operation at power is impractical since closing the flow control valves or the isolation valves would isolate feedwater to the respective steam generator and opening the bypass valves would result in feedwater flow perturbations and potentially severe transients including loss of RCS heat sink, loss of steam generator level control and a reactor trip.
Valve testing will be performed during cold shutdown or in transition to hot shutdown when isolation of feedwater will not impact plant safety.
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 42 of 74 System:
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Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
COLD SHUTDOWN JUSTIFICATION - CS-20 Main Feedwater 3994G, 3995G C
Code Class:
3 These check valves are located in the instrument air supply lines to the actuating air accumulators for main feedwater isolation valves (MFIV). The valves perform a safety function in the closed direction. Subsequent to a loss of normal instrument air, closure of this check valve maintains pressure boundary integrity of the accumulator. The accumulator provides a backup actuating air supply to the MFIV which closes upon receipt of an SI signal.
Closure of the MFIV provides redundant isolation capability, in conjunction with the MFRVs and their bypass valves, of the feedwater header.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Closure testing of these check valves entails a pressure drop/decay test of the associated air accumulator. During power operation, check valve closure testing is impractical since an inadvertent loss of air pressure would result in the associated main feedwater isolation valve going closed (fails closed on loss of air pressure). Isolating feedwater to the respective steam generator would result in potentially severe transients including loss of steam generator level control, loss of RCS heat sink and a reactor trip.
Valve testing will be performed during cold shutdown or in transition to hot shutdown when main feedwater can be isolated.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 43 of 74 10.0REFUELING OUTAGE JUSTIFICATIONS ROJ No.
ROJ-01 ROJ-02 ROJ-03 ROJ-04 ROJ-05 ROJ-06 Valve ID 8606A, 8606B 697A 853A, 853B 878G, 878J 870A, 870B, 889A, 889B 5392
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 44 of 74 System(s):
Valve(s):
Category(s):
Function:
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
REFUELING OUTAGE JUSTIFICATION - ROJ-01 Reactor Coolant 8606A, 8606B AC Code Class:
3 These check valves are is located in the nitrogen supply lines to the RCS overpressure protection accumulators and serve as Class 3 to non-Code boundary barriers. The valves perform a safety function in the closed direction.
Closure capability maintains pressure boundary integrity of the accumulator by providing a barrier between the Class 3 and non-Code class portions of the system.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
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 operation at power and cold shutdowns. Leak testing requires an extended period of time where the low temperature overpressure protection system will be out of service.
Valve closure verification will be performed in conjunction with a seat leakage test conducted during refueling outages when the overpressure protection accumulators can be removed from service.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 45 of 74 REFUELING OUTAGE JUSTIFICATION - ROJ-02 System(s):
Valve(s):
Category(s):
Residual Heat Removal 697A C
Code Class:
2 Function:
Test
- Requirement(s)
'Deferred Test Justification:
Alternate Test Frequency:
This check valve is located in the outlet line from RHR heat exchanger "A". It performs a safety function in the open and closed directions. During post-accident low head safety injection and during the recirculation phase of safety injection this valve must pass safety injection flow to reactor vessel upper plenum to maintain sufficient core inventory. The check valve isolates the Train A and Train B recirculation flow paths from each other. Additionally, during post-accident system operation, this check valve would be required to close in the event that Train A became unavailable thereby, preventing diversion of Train B flow to an out of service Train A in lieu of being directed to the core.
Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Full stroke exercising this valve in the forward direction quarterly during power operation is not possible since the RCS is theonly available flow path for valve full flow exercising and the RHR pump has insufficient discharge head to overcome reactor pressure. Full stroke exercising this valve in the forward direction during cold shutdown is precluded by restrictions related to LTOP concerns.
Full stroke exercising in the forward direction shall be performed during refueling outages when sufficient expansion volume exists in the RCS to accommodate the required flow rate.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 46 of 74 REFUELING OUTAGE JUSTIFICATION - ROJ-03 System(s):
Valve(s):
Category(s):
Function:
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Residual Heat Removal 853A, 853B AC Code Class:
1 These check valves are located inside containment in the low head safety injection lines to the reactor vessel. The valves are the first of two valves that serve as the Class 1 to Class 2 boundary barrier. The valves perform a safety function in the open and closed directions. They must open to provide a flow path for injection flow to the reactor vessel upon a low head safety injection actuation and as PIVs, must close to isolate the attached upstream lower pressure RHR system piping from the RCS.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Full stroke exercising these valves in the forward direction quarterly during power operation is not possible due to insufficient RHR pump discharge head to overcome reactor pressure. Full stroke exercising these valves in the forward direction during cold shutdown is precluded by restrictions related to LTOP concerns. During power operation, there is no practical means to test valve closure due to system design. To perform a closure verification constitutes a leak test, which presents significant hardships during cold shutdown, such as the use of temporary test equipment inside containment, excessive radiation exposure to test personnel, and extended outage time.
Full stroke exercising in the forward direction shall be performed during refueling outages when sufficient expansion volume exists in the RCS to accommodate the required flow rate. Reverse flow exercising shall be performed at refueling during the performance of PIV seat leakage testing per TS 3.4.14.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 47 of 74 REFUELING OUTAGE JUSTIFICATION - ROJ-04 System(s):
Valve(s):
Category(s):
Function:
Test Requirement(s):
Deferred:,lest Justification:
Alternate Test Frequency:
Safety Injection 878G, 878J AC Code Class:
1 These check valves are located in the safety injection lines to the RCS cold legs from the SI pumps discharge. The valves perform a safety function in the open and closed directions. They must be capable of opening to provide a flow path to the RCS for high head safety injection. As PIVs the valves must be capable of closure to maintain the integrity of the RCS pressure boundary and to isolate RCS pressure from the lower pressure Sl piping and components.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Full stroke exercising these valves in the forward direction quarterly during power operation is not possible due to insufficient SI pump discharge head to overcome reactor pressure. Full stroke exercising these valves in the forward direction during cold shutdown is precluded by restrictions related to LTOP concerns. During power operation, there is no practical means to test valve closure due to system design. To perform a closure verification constitutes a leak test, which presents significant hardships during cold shutdown, such as the use of temporary test equipment inside containment, excessive radiation exposure to test personnel, and extended outage time.
Full stroke exercising in the forward direction shall be performed during refueling outages when sufficient expansion volume exists in the RCS to accommodate the required flow rate. Reverse exercising shall be performed at refueling during the performance of PIV seat leakage testing per TS 3.4.14.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 48 of 74 REFUELING OUTAGE JUSTIFICATION - ROJ-05 System(s):
Valve(s):
Category(s):
Function:
- Test, Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
Safety Injection 870A, 870B, 889A, 889B AC Code Class:
2 These check valves are located in the SI pumps discharge lines. The valves perform a safety function in the open and closed directions. They must be capable of opening to provide a flow path to the RCS subsequent to the SI pumps starting on receipt of a safety injection actuation signal. As designated containment isolation valves, they must be capable of closure on reversal of flow to maintain containment integrity of the closed system outside containment. The valves must also be capable of closure to ensure SI pump flow is properly directed to the RCS subsequent to a failure of an SI pump to start.
Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be tested nominally every 3 months.
Full stroke exercising these valves in the forward direction quarterly during power operation is not possible due to insufficient SI pump discharge head to overcome reactor pressure. Full stroke exercising these valves in the forward direction during cold shutdown is precluded by restrictions related to LTOP concerns.
Full stroke exercising in the forward direction shall be performed during refueling outages when sufficient expansion volume exists in the RCS to accommodate the required flow rate.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 49 of 74 REFUELING OUTAGE JUSTIFICATION - ROJ-06 System(s):
Valve(s):
Category(s):
Instrument Air 5392 A
Code Class:
2 Function:
Test Requirement(s):
Deferred Test Justification:
Alternate Test Frequency:
This air operated valve is located in the instrument air supply line to containment. As a designated containment isolation valve, 5392 performs a safety function in the closed position for containment isolation.
Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Stroking valve 5392 during operation and cold shutdown is impractical because it would interrupt instrument air to containment and be disruptive to those components inside containment that are dependent upon instrument air to accomplish a function. Loss of instrument air would cause all air-operated valves to be actuated to their fail-safe position. During power operation, this would lead to a reactor trip and, during cold shutdown, this would compromise plant operation due to the loss of various components used in maintaining the reactor in a cold shutdown condition. Additionally, the valve control circuitry does not provide for partial stroke capability.
This valve will be full-stroke exercised during refueling outages when valve closure will not impact downstream component operability.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 50 of 74 11.0 RELIEF REQUESTS Relief No.
PR-01 PR-02 GR-01 GR-02 GR-03 VR-01 VR-02 VR-03 D/G Fuel Oil Transfer System Flow Rate PAF01A, PAF01B, PSF01A, PSF01B RCPB Isolation Valves - Leak Testing Use of Code Case OMN-1 for MOVs Use of Code Case OMN-8 for Control Valves 4324, 4325, 4326 434, 435
.392A
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 51 of 74 10 CFR 50.55a Request Number:
PR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety ASME Code Component(s) Affected:
Component ID PDG02A PDG02B Class 3
3 Group B
B Description Diesel Fuel Oil Transfer Pump A Diesel Fuel Oil Transfer Pump B Component/System Function:
The Diesel Fuel Oil Transfer pumps are required to transfer fuel oil from the storage tank to the day tank. This function ensures a continuous fuel supply to support long term operation of the Diesel during accident conditions.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda
Applicable Code Requirement
ISTB-3550, "Flow Rate", states in part "When measuring flow rate a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate flow rate directly, then the record shall indicate the method used to reduce the data.
Reason for Request
There are no installed instruments on the diesel fuel oil transfer system that allow a direct measurement of transfer pump flow rate. 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.
Proposed Alternative and Basis for Use:
Flow rate will be determined by calculation of day tank level increase vs. time utilizing the accuracy documented in design analysis EWR 4526-ME-20.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 52 of 74 PR-01 (Cont.)
Precedents:
NRC Letter, "Requests for Relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI Requirements for the R.E. Ginna Nuclear Power Plant Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program (TAC No. MA7265)"
dated June 13, 2000, previously authorized this relief request as PR-1 for the fourth. 10-year interval,
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 53 of 74 10 CFR 50.55a Request Number:
PR-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety ASME Code Component(s) Affected:
Component ID Class Group Description PAF01A 3
A "A" Preferred Motor Driven AFW Pump PAF01 B 3
A "B" Preferred Motor Driven AFW Pump PSF01A 3
B "C" Standby Motor Driven AFW Pump PSF01 B 3
B "D" Standby Motor Driven AFW Pump Component/System Function:
The AFW pumps are required to be capable of supplying AFW flow to the steam generators during a loss of normal feedwater flow or a steam line break in conjunction with a loss of off-site power. This function maintains steam generator water level to provide a secondary heat sink for residual heat removal of the reactor coolant system.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda
Applicable Code Requirement
ISTB-3550, "Flow Rate", states in part "When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall indicate the method used to reduce the data."
For Group A pumps, ISTB-5121, "Group A Test Procedure", states "Group A tests shall be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph." Paragraphs ISTB-5121(b) and (c) and Table ISTB-3000-1 require flow rate to be determined.
For Group B pumps, ISTB-5122, "Group B Test Procedure", states "Group B tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph." Paragraph ISTB-5122 and Table ISTB-3000-1 require flow rate or differential pressure to be determined.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 54 of 74 PR-02 (Cont.)
Reason for Request
The AFW pumps each have a minimum flow path that can be utilized for the respective Group A and Group B pump tests. The minimum flow lines provide a fixed resistance flow path from the pump discharge to the condensate storage or test tank then back to the suction of each pump. However, the minimum flow lines are not provided with flow instrumentation.
Compliance with the Code is impractical because of design limitations in that a flow rate measuring device is not installed in the associated pump minimum flow recirculation line being employed as the pump test circuit. Costly major hardware modifications would be required to provide a permanent flow measuring device in each affected line. It has been estimated that the cost would exceed $60,000 annually to install and maintain temporary flow measuring devices or more than $300,000 to install permanent flow measuring devices into the minimum flow recirculation lines in order to meet the ASME OM Code requirements and support the quarterly testing of the four AFW pumps. Additionally, flow is not variable since an installed flow orifice establishes a 40 gpm flow rate when the pump is operated in the recirculation mode.
The performance of pump tests using a fixed resistance flow path is an acceptable alternative to the Code requirements per NUREG-1482, Rev.1 Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices". During the performance of quarterly pump testing, pump differential pressure will be measured and trended. This provides a reference value for differential pressure that can be duplicated during subsequent tests. This methodology provides for
- the.acquisition of repeatable differential pressure, which is an adequate means of monitoring for pump degradation.
Concerns identified in NRC Bulletin 88-04, "Potential Safety Related Pump Loss", with regard to minimum recirculation flow line sizing have been assessed and verified to not be of concern during pump testing.
Therefore the current testing protocol which has the potential for service water intrusion and requires a reactivity change, and the cost of installing either temporary or permanent flow instrumentation imposes an undue burden without a compensating increase in the level of quality or safety.
Proposed Alternative and Basis for Use:
Quarterly testing of the designated Group A AFW pumps (PAF01A, PAF01 B) will be performed on minimum flow recirculation measuring differential pressure across the pump and measuring vibration using ASME OM Code-2004, ISTB-5121 and NUREG-1482, Rev.1 Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices" for guidance.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 55 of 74 PR-02 (Cont.)
Proposed Alternative and Basis for Use: (Cont.)
Quarterly testing of the designated Group B Standby AFW pumps (PSF01A, PSF01 B) will be performed on minimum flow recirculation measuring differential pressure across the pump using ASME OM Code-2004, ISTB-5122 and NUREG-1482, Rev.1 Section 5.9,"Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices" for guidance.
The proposed alternative testing provides reasonable assurance that the AFW pumps will be operationally ready.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
NRC Letter, "R.E. Ginna Nuclear Power Plant - Relief Request No. PR-3 Regarding Testing of Auxiliary Feedwater Pumps (TAC No. MD0316)", dated July 19, 2006, previously authorized this relief request as'PR-3 for the fourth 10-year interval,
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 56 of 74 10 CFR 50.55a Request Number:
GR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety ASME Code Component(s) Affected:
See Attachment Component/System Function:
Provide reactor coolant system pressure boundary isolation.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda.
Applicable Code Requirement(s):
ISTC-3630, "Leakage Rate for Other Than Containment Isolation Valves".
Reason for Request
Leakage testing, including testing requirements is governed by plant Technical Specifications.
Testing criteria utilized meets the intent of the OM Code leak rate testing requirements. Per NUREG 1482, Rev.1, Section 4.1.1, testing of the pair of valves would be acceptable if the configuration does not require two valves and the safety analysis for such a configuration would credit either of the two valves. Since individual testing of two sets of check valves is not possible due to lack of test connections and since testing of these valves with their adjacent MOVs is specified adequately by Technical Specifications, it is impractical to perform separate leak rate tests. Plant Technical Specifications establish the maximum permissible leakage rates, test pressure requirements, test frequency requirements, and the required action if the leak rate limit is exceeded. Considering the time, cost, and radiation exposure to test personnel, it would be burdensome to perform leak rate testing in accordance with the OM Code and would not result in a compensating increase in the level of quality and safety.
Proposed Alternative and Basis for Use:
These valves will be leak rate tested in accordance with RCS Pressure Isolation Valve leak rate testing per Technical Specification 3.4.14. The proposed alternative testing will provide reasonable assurance of the valves' operational readiness.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 57 of 74 GR-01 (Cont.)
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
NRC Letter, "Requests for Relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI Requirements for the R.E. Ginna Nuclear Power Plant Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program (TAC No. MA7265)"
dated June 13, 2000, previously authorized this relief request as GR-1 for the fourth 10-year interval,
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 58 of 74 GR - 01 Attachment Valve System Category Safety Class 853A 853B 867A 867B 878G 878J 878A 878C 877A 877B 878F 878H RHR RHR Sl SI SI SI SI Sl SI SI SI SI A/C A/C A/C A/C A/C A/C A
A A/C A/C A/C A/C 11 1
1 1
1 2
2 1
1 1
1 Configuration[Type Single CV Single CV Event V CV Event V CV Event V CV Event V CV MOV MOV Event V CV Event V CV Event V CV Event V CV
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 59 of 74 10 CFR 50.55a Request Number:
GR-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-- Alternative Provides Acceptable Level of Quality and Safety --
ASME Code Component(s) Affected:
Certain Motor-Operated Valves in ASME Safety Class 1, 2, and 3 systems which are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. The valves are those that include the designation "OMNI" in the "Frequency" column of the Valve Tables.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda
Applicable Code Requirement
ISTA-3130(b) states: "Code Cases shall be applicable to the edition and addenda specified in the test plan." The edition and addenda specified in the test plan for the next Ten-Year Interval for the R.E.
Ginna Nuclear Power Plant is the ASME OM Code-2004 Edition.
Reason for Request
Code Case OMN-1 contains no applicability statement. The Code Case is included in the latest edition/addenda incorporated by reference in 10 CFR 50.55a(b)(3) which is the 2004 Edition with no Addenda. ASME Code Cases no longer have expiration dates; however, they still must be applicable to the Edition and Addenda of the Code specified for use in the test plan. Paragraph 10 CFR 50.55a(b)(6) references Regulatory Guide (RG) 1.192, which conditionally approves the use of Code Case OMN-1 "in lieu of the provisions for stroke-time testing in Subsection ISTC of the 1995 Edition up to and including the 2000 Addenda of the ASME OM Code". The 2004 Edition of the OM Code is not listed in RG 1.192.
Proposed Alternative and Basis for Use:
R.E. Ginna Nuclear Power Plant will apply the requirements of OMN-1 "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants," including the conditions specified in Table 2 of USNRC Regulatory Guide 1.192, in lieu of the provisions for motor-operated valve testing in Subsection ISTC of the 2004 Edition of the ASME OM Code.
Relief is requested pursuant to 10CFR50.55a(a)(3)(i) based on the proposed alternative providing an acceptable level of quality and safety.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 60 of 74 GR-02 (Cont.)
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
Similar relief requests were approved for the other Constellation Energy plants:
Calvert Cliffs Nuclear Power Station (CCNPS)
NRC Letter, "Calvert Cliffs Nuclear Power Plant, Unit Nos.- 1 and 2 - Relief Requests for the Fourth 10-Year Interval Inservice Testing, Program for Pumps and Valves (TAC NOS. MD5998, MD5999, MD6000, MD6001, MD6002, MD6003, MD6004, MD6005, MD6006, MD6007, MD6008, MD6009, MD6010, AND MD6011)", dated June 18, 2008 Nine Mile Point Nuclear Station (NMPNS)
NRC.Letter, "Nine Mile Point Nuclear Station - Safety Evaluation of Relief Requests for the Unit No. 1 Fourth 10-Year and Unit No. 2 Third 10-Year Pump and Valve Inservice Testing Program (TAC NOS.
MD9202 and MD9203)", dated December 29, 2008
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 61 of 74 10 CFR 50.55a Request Number:
GR-03 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-- Alternative Provides Acceptable Level of Quality and Safety --
ASME Code Component(s) Affected:
Certain control valves in ASME Safety Class 1, 2, and 3 systems which are required fail-safe to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. The valves are those that include the designation "OMN-8" in the "Comments" column of the Valve Tables.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda
Applicable Code Requirement
ISTA-3130(b) states: "Code Cases shall be applicable to the edition and addenda specified in the test plan." The edition and addenda specified in the test plan for the next 10-Year Interval for R.E. Ginna Nuclear Power Plant is the ASME OM Code-2004 Edition.
Reason for Request
Code Case OMN-8 provides an alternative to stroke time testing power-operated control valves that have only a fail-safe safety function. Code Case OMN-8 contains no applicability statement. It specifies alternative testing to certain requirements in ASME/ANSI OMa-1 988 Part 10 and OM Code-1995. The 2004 Edition of the OM Code is not listed. The Code Case is included in the latest edition/addenda incorporated by reference in 10 CFR 50.55a(b)(3) which is the 2004 Edition with no Addenda. ASME Code Cases no longer have expiration dates; however, they still must be applicable to the Edition and Addenda of the Code specified for use in the test plan.
Proposed Alternative and Basis for Use:
R.E. Ginna Nuclear Power Plant will apply the requirements of Code Case OMN-8 "Alternative Rules for Preservice and Inservice Testing of Power-Operated Valves That Are Used for System Control and Have a Safety Function per OM-1 0," in lieu of the provisions for power-operated control valve testing specified in paragraphs ISTC-5131, ISTC-5132, ISTC-5133(b), ISTC-5141, ISTC-5142 &
ISTC-5143(b), in Subsection ISTC of the 2004 Edition of the ASME OM Code. Paragraph 10 CFR 50.55a(b)(6) references Regulatory Guide (RG) 1.192, which approves the use of Code Case OMN-8 for Code Editions through the 2000 Addenda.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 62 of 74 GR-03 (Cont.)
Proposed Alternative and Basis for Use (Cont.):
Relief is requested pursuant to 10CFR 50.55a(a)(3)(i) based on the proposed alternative providing an acceptable level of quality and safety.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
Similar relief requests were approved for the other Constellation Energy plants:
Calvert Cliffs Nuclear Power Station (CCNPS)
NRC Letter, "NRC Letter, "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Relief Requests for the Fourth 10-Year Interval Inservice Testing Program for Pumps and Valves (TAC NOS. MD5998, MD5999, MD6000, MD6001, MD6002, MD6003, MD6004, MD6005, MD6006, MD6007, MD6008, MD6009,MD6010, AND MD6011)", dated June 18, 2008 Nine.Mile Point Nuclear Station (NMPNS)
NRC Letter, "Nine Mile Point Nuclear Station - Safety Evaluation of Relief Requests for the Unit No. 1 Fourth 10-Year and Unit No. 2 Third 10-Year Pump and Valve Inservice Testing Program (TAC NOS.
MD9202 and MD9203)", dated December 29, 2008
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 63 of 74 10 CFR 50.55a Request Number:
VR-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety ASME Code Component(s) Affected:
Component ID Class Category Description 4324 3
B TDAFW Pump SW Strainer Bypass SOV 4325 3
B MDAFW Pump A SW Strainer Bypass SOV 4326 3
B MDAFW Pump B SW Strainer Bypass SOV Component/System Function:
These service water valves open upon an auxiliary feedwater pump bearing cooling water supply high strainer differential pressure to provide cooling water to the driver's bearings.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda.
Applicable Code Requirement(s):
Stroke time of solenoid-operated valves shall be measured and evaluated per ISTC-5150.
Reason for Request
These are normally closed rapid acting valves that automatically actuate to the open position on high differential pressure across the supply strainer. Measurement of stroke times during manual actuation is not practical and would not produce consistent, meaningful or trendable test results. The valves are not provided with control switches to allow for conventional stroke timing methodology. Additionally, there is no remote valve position indication or other positive means to determine valve disc position.
Without concise methods of initiating valve movement or determining when the stroke is completed, it is difficult to obtain repeatable stroke time data to monitor for degradation. It would be necessary to disassemble the respective differential pressure switch in order to control actuation of these valves and as a result of this disassembly, stroke timing during power operation would require rendering these valves inoperable and entering an LCO from which prompt restoration would be impractical.
These valves are tested on a quarterly basis during auxiliary feedwater pump testing. This testing includes strainer cleaning, strainer isolation, high differential pressure simulation, verification of valve operation and flow observation. Failure of these valves to stroke in conjunction with a clogged strainer would result in a lack of pressure at the bearing cooler inlet and a high DP alarm, at which time an Operator would be dispatched to manually trip the respective valve.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 64 of 74 VR-01 (Cont.)
Reason for Request: (Cont.)
This quarterly verification, while not measuring stroke time or monitoring for degradation, does provide an indication that each solenoid valve is moving to its safety position by verifying disc movement and is consistent with the guidelines provided in NUREG-1482, Rev.1, Section 4.2.3.
Proposed Alternative and Basis for Use:
These valves will be stroke tested during associated auxiliary feedwater pump testing by closing the valve downstream of the strainer. Acceptable valve operation will be based on:
" Verifying locally that the valve has de-energized and tripped open.
" Verifying the presence of a steady stream of water from the affected floor drain funnel.
Verifying that the associated main control board annunciator alarms.
The proposed alternative testing will accurately reflect obturator position and will provide reasonable assurance of the valves' operational readiness.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
NRC Letter, "Requests for Relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI Requirements for the R.E. Ginna Nuclear Power Plant Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program (TAC No. MA7265)"
dated June 13, 2000, previously authorized this relief request as VR-3 for the fourth 10-year interval,
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 65 of 74 10 CFR 50.55a Request Number:
VR-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- Hardship or Unusual Difficulty without Compensating Increase in Level of Quality or Safety ASME Code Component(s) Affected:
Component ID Class Category Description 434 1
C Pressurizer Relief Valve 435 1
C Pressurizer Relief Valve Component/System Function:
Pressurizer Safety Relief valves provide over-pressurization protection for the reactor coolant system/Pressurizer.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda.
Applicable Code Requirement(s):
Appendix I, paragraph 1-731 0(f), Determination of operation and electrical characteristics of position indication shall be done after maintenance or set pressure adjustment for Class 1 safety valves.
Reason for Request
These valves are mechanical spring-actuated valves with an externally mounted LVDT stem position indicator. The position indicator must be removed in order to permit removal of the safety valves each refueling outage for shipment to an off-site vendor for set pressure testing. It would be necessary to intentionally challenge RCS pressure limits to actuate these safety valves in order to perform position indication testing prior to removal for set pressure testing. Also, if these safety valves were actuated for a position indication test following re-installation, they would again need to be retested to ensure the set pressure has not been adversely affected. This involves increased testing and unnecessary radiation exposure to test personnel and result in a hardship without a compensating increase in the level of quality and safety. In accordance with plant administrative procedures, channel checks for Pressurizer safety valve position indication are performed once per shift and validated by comparison with tailpipe temperature indication.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 66 of 74 VR-02 (Cont.)
Proposed Alternative and Basis for Use:
These valves will be simulated to actuate using existing station calibration procedures. The procedure utilizes movement of the valve's coil (up/down) and verifies position via an alarm in the Control Room. Calibration of these position indicators is governed by plant calibration procedures and is performed on a refueling basis. These procedures verify that the proper clearance is obtained to ensure obturator position is accurately represented and will provide reasonable assurance of valve operational readiness.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
NRC Letter, "R.E. Ginna Nuclear Power Plant - Inservice Testing Program Relief Requests VR-4 and VR-8, (TAC No. MC0639)" Date November 21, 2003, previously authorized this relief request as VR-4 for the fourth 10-year interval.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 67 of 74 10 CFR 50.55a Request Number:
VR- 03 Relief Request in Accordance with 10 CFR 50.55a(f)(5)(iii)
- Inservice Testing Impracticality ASME Code Component(s) Affected:
Component ID Class Category Description 392A 1
C Pressurizer Relief Valve Component/System Function:
This normally closed air operated valve is located in the alternate charging line from the regenerative heat exchanger to the RCS Loop B hot leg. This flow path is designated as the safety related flow path for the purpose of providing makeup and boration to the RCS when the suction of the charging pumps are aligned to the RWST. 392A serves as an isolation valve and a relief valve. The valve performs a safety function in its relieving position. Although 392A fails to the closed position on a loss of:actuating air or control power, it is designed to open at a differential pressure setpoint of 250 psid to allow sufficient charging flow to provide cold shutdown boration.
Applicable Code Edition and Addenda
ASME OM Code-2004 Edition, No Addenda.
Applicable Code Requirement(s):
Paragraph 1-7360(c) of Appendix I, requires that typical bench testing be performed on relief valves for set pressure determination.
Impracticality of Compliance:
This valve is a welded in-line air-operated valve that also performs a relief function at a specific differential pressure. The set-pressure determination listed in paragraph 1-7360(c) is impractical to perform on valve 392A since it cannot be removed from the system. Performance of Code required testing would require a system piping modification to facilitate removal of the valve from the system Burden Caused by Compliance:
To comply with Code testing requirements a system piping modification would be required to facilitate removal of the valve from the system.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 68 of 74 VR-03 (Cont.)
Proposed Alternative and Basis for Use:
Valve 392A will be tested in place each refueling outage by verifying that it will open and pass the required flow at design differential pressure. The proposed alternative testing provides reasonable assurance of the valve's operational readiness.
Duration of Proposed Alternative:
This relief request, upon approval, will be applied to the R.E. Ginna Nuclear Power Plant fifth 10-Year IST Interval.
Precedents:
NRC Letter, "R.E* Ginna Nuclear Power Plant - Inservice Testing Program Relief Requests VR-4 and VR-8, (TAC No. MC0639)" Date November 21, 2003, previously authorized this relief request as VR-8 for the fourth 10-year interval.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 69 of 74 12.0 TECHNICAL POSITION JUSTIFICATIONS TJ No.
TJ-01 TJ-02 TJ-03 TJ-04 TJ-05 TJ-06 Valve ID Flow Reference Value Tolerance 5933A, 5933B, 5934A, 5934B 5907, 5907A, 5908, 5908A Deferral Justification Test Window On-Line Maintenance 8616A, 8616B, 8619A, 8619B, 8620A, 8620B
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 70 of 74 Technical Position Justifications TJ-01 During performance of Inservice testing of program pumps, the guidance provided in NUREG-1482, Rev.1, Section 5.3 shall be followed whereas, a total tolerance of +/-2 percent, including the effect of instrument precision on accuracy, of the reference value for flow shall be utilized.
TJ-02 Solenoid-operated valves 5933A, 5933B, 5934A and 5934B open to provide starting air to the diesel generators. These are rapid acting solenoid valves whose design prohibits visual observance of stroking as there are no external indicators on these valves. Diesel start times are affected by valve stroke times. Measurement and evaluation of stroke times shall not be performed. Valve exercising is performed monthly in conjunction with diesel generator start testing. Per the guidance provided by NUREG 1482, Rev.1, Section 3.4 and as allowed by ISTC-1200, valve stroking parameters will be considered acceptable if the associated diesel generator start is acceptable. Additionally, diesel start and bus re-energization times are verified each refueling outage to be less than the Technical Specification acceptance criteria of 10 seconds.
TJ-03 Solenoid-operated valves 5907, 5907A, 5908 and 5908A open and close to direct fuel oil to Diesel Generator (D/G) day tanks or back to the diesel fuel oil storage tanks. These are rapid acting solenoid valves whose design prohibits visual observation of stroking as there are no external indicators on these valves. These valves are automatically actuated as necessary based upon diesel fuel oil day tank levels. These valves do not have control switches. Diesel generators are tested monthly (per Technical Specifications), during which these valves actuate for filling the fuel oil day tanks and for diesel fuel oil recirculation.
Measurement and evaluation of stroke time shall not be performed. These valves shall be exercised and fail safe tested at least quarterly during diesel generator testing. Per the guidance provided by NUREG 1482, Rev. 1, Section 3.4 and as allowed by ISTC-1200, valve stroking parameters will be considered acceptable based upon satisfactory actuation as demonstrated by adequate fuel oil delivery during the D/G tests.
TJ-04 Inservice Test (IST) Program components which are required to be tested during a refueling outage(RFO) may be tested in conjunction with plant "coast-down" (i.e. a period where a conscious deviation from normal operating temperature and power occurs in conjunction with reactor fuel depletion) as qualified below, or a planned load reduction (e.g. reduction in turbine load via a selected downward ramp rate) intended to take the plant from Mode 1, power operation, to an offline condition, and ultimately to Mode 6, refueling.
The period where the load reduction is accomplished via plant coast-down potentially can encompass a period of weeks before the actual start of an RFO. The existing regulatory guidance for allowing deferral of testing to an RFO is based on the impracticality of being able to perform the test on a quarterly basis. Performing test which have been deferred to an RFO weeks in advance of the RFO is not in keeping with the spirit of the deferral latitude.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 71 of 74 As such, testing being performed to satisfy various IST program deferrals, while in plant coast-down, should only take place when the projected end of the coast down window is 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> or less. Five working days affords adequate time to accomplish the anticipated limited test scope and is not considered excessive when compared to the intent of the Code deferral allowance.
All IST components required to be tested during an RFO shall have their prescribed test satisfactorily completed and demonstrated operable prior to resumption of power operation and before exceeding the associated Technical Specification-Mode of applicability, unless specifically stated otherwise in the Technical Specifications.
TJ-05 The advent of on-line plant maintenance to perform work on safety related components and systems outside of the traditional refueling outage(RFO) time frame, is designed to maximize component/system availability while favorably impacting RFO duration and the associated corporate financial impact. The practice of doing on-line maintenance represents a departure from the norm where the bulk of the maintenance was performed while engaged in an RFO. As such, the Inservice Test Program, which is directed by the ASME Code which does not take into account on-line maintenance practices, can experience implementation issues when on-line preventative maintenance or corrective maintenance is performed.
Typically, a number of Inservice Test Program components can't meet Code based quarterly test frequency due to the practicality of performing the testing. System alignments, operating conditions (pressure, flow, temperature, etc.) and other such restrictions often render the testing impracticable. The Code allows the affected testing to be deferred to a lower plant MODE, from MODE 5, cold shutdown to MODE 6, Refueling. The understanding between the Licensee and the NRC is that such testing will take place in the highest MODE deemed practicable by the Licensee with the assumption that sufficient basis to justify the deferred MODE exists. Contrary to what occurred in the past, the NRC is no longer required to approve such deferrals. As such, along with the deferral comes the expectation that testing can and should only be performed when in the applicable deferred MODE unless extenuating circumstances exist. Performance of on-line maintenance and the need to
.demonstrate post-maintenance operability for the component/system worked on clearly is an example of an extenuating circumstance given its prevalent implementation and widespread acceptance throughout the nuclear industry.
Inservice Test Program components which have had their associated Code required tests deferred from the normal "during operation at power" time frame, wither to cold shutdown (using a Cold Shutdown Justification (CSJ) or Refueling Shutdown (using a Refueling Outage Justification (ROJ)), may revert back to. the at power time frame, on a limited basis, to accomplish post-maintenance operability testing (PMOT) following performance of on-line maintenance provided that:
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 72 of 74 A) The testing that will occur during power operation will not expose plant personnel to unsafe working conditions nor place components or systems in alignments adverse to plant safety.
AND B) One or more of the following maintenance scope activities are desired and serves to justify the performance of deferred testing at the normal at power time frame:
- 1) Corrective on-line maintenance is desired to be performed on the component to restore the component to the operable condition and testing required to demonstrate component/system post-maintenance operability is contained in the surveillance test(s) used to satisfy the associated IST Program Code requirements.
- 2) Preventative on-line maintenance is desired to be performed on the component to lessen or eliminate RFO time frame system/component unavailability (e.g. performing the maintenance in a plant MODE that poses a lesser or no adverse risk probability to plant safety) and the testing required to demonstrate component/system post-maintenance operability is contained in the surveillance test(s) used to satisfy the associated IST Program
.Code requirements.
- The relaxation of the associated CSJ or ROJ is only to be exercised on a limited basis.
Limited is defined as not more than once per 18 months (All Ginna Technical Specification surveillance requirements which tie performance to a fuel cycle frequency, utilize an 18 month fuel cycle duration) unless additional documented justification is provided in advance of the proposed maintenance. The IST Program Owner and Site Implementer must review and concur with such justification before the proposed maintenance can proceed.
TJ-06 Solenoid-operated valves 8616A, 8616B, 8619A, 8619B, 8620A and 8620B open (8620A/B close) to provide nitrogen to cycle the power operated relief valves (PORVs) which provide RCS overpressure protection. These solenoid valves are totally enclosed and have no externally visible indication of valve position. Since these valves function to admit nitrogen to the Pressurizer PORVs to open, it can be indirectly verified that each valve has actuated by monitoring the operation of the PORVs. Measuring the stroke times of a PORV provides indication of solenoid-operated valve degradation since any significant increase in solenoid valve stroke time would result in longer PORV stroke times and may result in the PORV.
exceeding its stroke time limit. Per the guidance provided by NUREG 1482, Rev.1, Section 3.4 and as allowed by ISTC-1200, valve stroking parameters will be considered acceptable if the associated PORV cycling is acceptable.
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 73 of 74 Table 1 PUMP AND VALVE TEST PROGRAM PLAN TABLE OF ACRONYMS VALVE TYPE BAV - Ball Valve BFV - Butterfly Valve CV - Check Valve DIV - Diaphragm GTV - Gate Valve GLV - Globe Valve NCV - Nozzle check Valve RV - Relief Valve TRV - Thermal Relief SCV - Stop Check Valve TVWV - Three-way Valve ACTUATOR MOV - Motor AOV - Air SOV - Solenoid MAN - Manual HYD - Hydraulic SAV - Self Actuated NORMAL POSITION 0 - Open C - Closed Al - As-Is REQUIRED TESTS BDT-C - Bi-directional exercise closed BDT-O - Bi-directional exercise open CPT - Biennial Comprehensive Pump Test CV-C - Check Valve Exercise - Full closed CV-O - Check Valve Exercise - Full open DI - Disassembly and inspection DIAG - OMN-1 MOV diagnostic test EX - Exercise test (Category A or B valves)
FS (O,C) - Fail Safe (0 - open, C = closed)
Group A Pump Test - Quarterly Test Group B Pump Test - Quarterly Test LJ-C - Leak test per 1 OCFR50 App J Opt B LT-X - Leak test per OM Code LT-XT - Leak test per Tech Specs (PIVs)
PIT - Position Indication Test RT - Relief Valve Test ST (O,C) - Stroke Time (0 = open, C = closed)
TEST FREQUENCY 40 mo - 40 months per Tech Specs 6 mo -
6 months Q
- Quarterly CS
- Cold Shutdown OC
- Operating Cycle (18 months)
R
- Refueling - not to exceed 18 months 3R
- Once every 3 refueling outages 2Y
- At least once every 2 years per OM Code 5Y
- At least once every five years 10Y - At least once every ten years CMP -
test frequency dictated by the Check Valve Condition Monitoring Program OMN1-Code Case OMN-1 diagnostic test interval OPB - Option B, performance based interval AD
- Administratively directed, augmented requirement SAFETY CLASS 1
2 3
NC - non class SSC - safety significant
GINNA INSERVICE TESTING Revision 0 STATION PROGRAM Page 74 of 74 Table 1 (Cont.)
PUMP AND VALVE TEST PROGRAM PLAN TABLE OF ACRONYMS DEFERRAL JUSTIFICATIONS GR
- Generic Relief Request PR
- Pump Relief Request VR
- Valve Relief Request CS
- Cold Shutdown Justifications ROJ - Refueling Outage Justifications TJ
- Technical Justifications ASME CATEGORY A
B C
AC BC MEASURE PUMP TEST PARAMETERS N - Pump Speed P - Discharge Pressure (Positive Displacement)
Pd - Differential Pressure (Centrifugal)
Q Flow Rate V
- Vibration Peak Velocity
Revision: 0 Consteilation Energy (Ginna)
Valve Table AFW - A UXILIAR Y FEED WA TER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 3996 3
N BC A
5 SCV MOV 1237 (1-6)
C O/C Al CV-O 2Y CVCMP EX Q
TDAFW PUMP DISCHARGE VLV MOV-3996 PIT 2Y ST-C Q
ST-O Q
3998 3
N C
A 5
CV SAV 1237 (1-8)
C O/C NA CV-C CMP CVCMP CV-O 2Y TURBINE DRIVEN AUX FW PUMP DISCHARGE CHECK VLV 4000A 3
N B
A 3
GLV MOV 1237 (D-7)
C O/C Al EX Q
PIT 2Y AUXILIARY FEEDWATER CROSSOVER MOTOR OPERATED STOP CHECK VALVE ST-C 0
ST-0 Q
4000B 3
N B
A 3
GLV MOV 1237 (D-8)
C O/C Al EX Q
PIT 2Y AUXILIARY FEEDWATER CROSSOVER MOTOR OPERATED STOP CHECK VALVE ST-C Q
ST-O Q
4000C 2
N C
A 3
CV SAV 1237 (B-10)
C O/C NA CV-C CMP CVCMP CV-O 2Y AUX FW PUMP A DISCHARGE CHECK VALVE 4000D 2
N C
A 3
CV SAV 1237 (E-10)
C O/C NA CV-C CMP CVCMP CV-O 2Y AUX FW PUMP B DISCHARGE CHECK VALVE 4003 2
N C
A 3
CV SAV 1237 (I-11)
C O/C NA CV-C CMP CVCMP CV-O 2Y TURBINE DRIVEN AUX FW PUMP DISCHARGE CHECH VLV TO STEAM GENERATOR A 4004 2
N C
A 3
CV SAV 1237 (J-10)
C O/C NA CV-C CMP CVCMP CV-O 2Y TURBINE DRIVEN AUX FW PUMP DISCHARGE CHECH VLV TO STEAM GENERATOR B 4007 3
N B
A 3
GLV MOV 1237 (B-8) 0 O/C Al DIAG OMN1 EX 18M MDAFW PUMP A DISCHARGE VALVE MOV-4007 4008 3
N B
A 3
GLV MOV 1237 (E-8) 0 O/C Al DIAG OMN1 EX 18M MDAFW PUMP B DISCHARGE VLV MOV-4008 4009 3
N C
A 3
CV SAV 1237 (B-5) 0 O/C NA CV-C CMP CVCMP CV-O 2Y AUX FW PUMP A DISCHARGE CHECK VLV Page 1 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table AFW - AUXILIARY FEED WATER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4010 3
N C
A 3
CV SAV 1237 (E-5) 0 O/C NA CV-C CMP CVCMP CV-O 2Y AUX FW PUMP B DISCHARGE CHECK VLV 4013 3
N B
A 4
GTV MOV 1237 (1-2)
C 0
Al DIAG OMN1 EX R
TURBINE DRIVEN AUX FW PUMP SW SUCTION VLV MOV-4013 4014 3
N C
A 4
CV SAV 1237 (H-2)
C O/C NA CV-C 2Y CVCMP CV-O 2Y SUCTION CHECK VLV TO TURBINE DRIVEN AUX FW PUMP 4016 3
N C
A 4
CV SAV 1237 (E-2)
C O/C NA CV-C 2Y CVCMP CV-O 2Y SUCTION CHECK VLV TO AUX FW PUMP B 4017 3
N C
A 4
CV SAV 1237 (B-2)
C O/C NA CV-C 2Y CVCMP CV-O 2Y SUCTION CHECK VLV TO AUX FW PUMP A 4020 3
N C
A
.75 RV SAV 1237 (1-3)
C O/C NA RT ly TURBINE DRIVEN AUX FW PUMP SUCTION RELIEF VLV 4021 3
N C
A
.75 RV AUX FW PUMP A SUCTION RELIEF VLV 4022 3
N C
A
.75 RV AUX FW PUMP B SUCTION RELIEF VLV 4023 3
N C
A 1.5 CV TURBINE DRIVEN AUX FW PUMP RECIRCULATION CHECK VLV 4027 3
N B
A 4
GTV SW SUCTION MOV FOR PAF01A (MDAFW PUMP A) 4028 3
N B
A 4
GTV SW SUCTION MOV FOR PAFOIB (MDAFW PUMP B)
SAV SAV SAV MOV MOV 1237 (B-2) 1237 (E-3) 1237 (1-5) 1237 (C-3) 1237 (D-3)
C C
C C
C O/C O/C 0
0 0
NA NA NA Al A]
RT RT CV-C CV-0 DIAG EX DIAG EX lay lay 0Q OMN1 R
OMN1 R
4083 3
N C
A 1
CV SAV 1237 (H-3)
O/C C
BDT-O R
CV-C CS CONDENSATE PUMP INLET CHECK VLV TO AUX FW PUMPS 4098 3
N -
B A
4 GTV MAN 1237(1-2)
C 0
NA EX 2Y SW INLET ISOL VLV TO TURBINE DRIVEN AUX FW PUMP Page 2 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table AFW - AUXILIARY FEEDWA TER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
AlP Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4291 3
N B
A 1.5 GTV AOV 1237 (H-5) 0 O/C 0
EX 0
FS-O Q
TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRCULATION AIR OPERATED VAL VE PIT 2Y ST-O Q
4297 3
N B
A 3
GLV AOV 1237 (1-10) 0 0
0 EX 0
Code Case OMN-8 FS-O 0
CONTROL VALVE ON PAF03 (TDAFW PUMP) DISCHARGE TO EMS01B (SG A)
PIT 2Y 4298 3
N B
A 3
GLV AOV 1237 (J-8)
O O
O EX Q
Code Case OMN-8 FS-O Q
CONTROL VALVE ON PAF03 (TDAFW PUMP) DISCHARGE TO EMS01B (SG B)
PIT 2Y 4304 3
N B
A 1
GTV AOV 1237 (C-6)
C O/C 0
EX Q
FS-O 0
MDAFW PUMP A RECIRC VLV AOV-4304 PIT 2Y ST-O Q
4304A 3
N C
A 1
CV SAV 1237 (C-6)
C 0
NA CV-P CMP CVCMP DI CMP MDAFW PUMP A RECIRC CHECK 4310 3
N B
A 1
GTV AOV 1237 (E-6)
C O/C 0
EX 0
FS-O Q
MDAFW PUMP B RECIRC VLV AOV-4310 PIT 2Y ST-O 0
4310A 3
N C
A 1
CV SAV 1237 (E-6)
C 0
NA CV-P CMP CVCMP DI CMP MDAFW PUMP B RECIRC CHECK 4324 3
N B
A
.75 GTV SOV 1237 (J-3)
C 0
0 EX 0
FS-O Q
TURBINE DRIVEN AUX FW PUMP SW STRAINER BYPASS SOV ST-O VR - 01 4325 3
N B
A
.5 DIV SOV 1237 (C-4)
C 0
0 EX Q
FS-O Q
AUX FW PUMP A SW STRAINER BYPASS SOV ST-O VR - 01 4326 3
N B
A
.5 DIV SOV 1237 (F-3)
C 0
0 EX Q
FS-O Q
AUX FW PUMP B SW STRAINER BYPASS SOV ST-O VR - 01 4344 3
N B
A 4
GTV MAN 1237 (E-3)
C 0
NA EX 2Y SW INLET ISOL VLV TO AUX FW PUMP B Page 3 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table AFW-AUXILIARY FEEDWATER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4345 3
N B
A 4
GTV MAN 1237 (C-3)
C 0
EX 2Y SW INLET ISOL VLV TO AUX FW PUMP A 4480 3
N A
A 1.5 GTV AOV 1237 (B-6)
C C
C EX Q
FS-C Q
BYPASS VALVE ON AUXILIARY FEEDWATER TO EMS01A (STEAM GENERATOR A)
4481 3
N A
A 1.5 GTV AOV 1237 (F-6)
C C
C EX Q
FS-C Q
BYPASS VALVE ON AUXILIARY FEEDWATER TO EMS01B (STEAM GENERATOR B)
Page 4 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CCW - COMPONENT COOLING WATER Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A.P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments I Notes 17 3
N B
A 1
GLV AOV 1245 (A-3) 0 C
C EX Q
FS-C Q
CCW SURGE TANK VENT RCV-017 PIT 2Y ST-C Q
651 3
N C
A 2
RV SAV 1245 (A-3)
C O/C NA RT 2Y VACUUM BREAKER FOR TAC01 (CCW SURGE TANK)RELIEF V.
723A 3
N C
A 8
NCV SAV 1245 (D-6)
O/C O/C NA CV-C Q
CV-O Q
NOZZLE CHECK VALVE FOR COMPONENT COOLING WATER PUMP A DISCHARGE 723B 3
N C
A 8
NCV SAV 1245 (E-6)
O/C O/C NA CV-C Q
CV-O 0
NOZZLE CHECK VALVE FOR COMPONENT COOLING WATER PUMP B DISCHARGE 732 3
N C
A 3
RV SAV 1245 (A-3)
C O/C NA RT 10Y CCW SURGE TANK RELIEF VLV TO WASTE HOLDUP TANK 738A 3
N B
A 10 GTV MOV 1245 (F-3)
C 0
NA DIAG OMN1 High Risk MOV per OMN-1 EX Q
MOTOR OPERATED BLOCK VALVE FOR COMPONENT COOLING WATER SUPPLY TO EAC02A (RESIDUAL HEAT REMOVAL HEAT EXCHANGER A) 738B 3
N B
A 10 GTV MOV 1245 (H-4)
C 0
NA DIAG OMN1 High Risk MOV per OMN-1 EX Q
MOTOR OPERATED BLOCK VALVE FOR COMPONENT COOLING WATER SUPPLY TO EAC02B (RESIDUAL HEAT REMOVAL HEAT EXCHANGERB) 740A 3
N C
A 1
TRV SAV 1245 (G-3)
C 0
NA RT 10Y RHR HX A CCW OUTLET RELIEF VLV 740B 3
N C
A 1
TRV SAV 1245(1-3)
C 0
NA RT 1Y RHR HX B CCW OUTLET RELIEF VLV 743 2
N AC A
2 CV SAV 1246-1 (C-6) 0 C
NA BDT-O Normal Ops CVCMP CV-C OPB CCW INLET INNER CHECK VLV TO EXCESS LETDOWN HX (IN CNMT)
LJ-C OPB 744 2
N C
A
.75 TRV SAV 1246-1 (C-7)
C O/C NA RT 10Y CCW OUTLET RELIEF VALVE FOR ECH03 (EXCESS LETDOWN HEAT EXCHANGER)
Page 5 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CCW - COMPONENT COOLING WATER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 745 2
N A
A 2
GLV AOV 1246-1 (B-6) 0 C
C EX Q
FS-C Q
EXCESS LETDOWN HX CCW OUTLET CNMT ISOL AOV-745 LT-X 2Y PIT 2Y ST-C Q
749A 2
N A
A 3
GTV MOV 1246-1 (B-5) 0 C
Al EX CS CS - 13 LT-X 2Y CCW TO RCP A ISOL VLV MOV-749A PIT 2Y ST-C CS CS - 13 749B 2
N A
A 3
GTV MOV 1246-1 (B-4) 0 C
Al EX CS CS - 13 LT-X 2Y CCW TO RCP B ISOL VLV MOV-749B PIT 2Y ST-C CS CS - 13 750A 2
N C
A 4
CV RCP A CCW INLET CHECK VLV (IN CNMT) 750B 2
N C
A 4
CV RCP B CCW INLET CHECK VLV (IN CNMT) 753A 2
N C
A 1.5 CV CCW SUPPLY CHECK VALVE TO RCP "A" THERMAL BARRIER 753B 2
N C
A 1.5 CV CCW SUPPLY CHECK VALVE TO RCP "B" THERMAL BARRIER 755A 2
N C
A
.75 RV RCP A THERMAL BARRIER CCW OUTLET RELIEF VLV (IN CNMT) 755B 2
N C
A
.75 RV RCP B THERMAL BARRIER CCW OUTLET RELIEF VLV (IN CNMT) 758A 2
N C
A 2
RV RCP A CCW OUTLET RELIEF VLV (IN CNMT) 758B 2
N C
A 2
RV RCP B CCW OUTLET RELIEF VLV (IN CNMT)
SAV SAV SAV SAV SAV SAV SAV SAV 1246-1 (C-5) 1246-1 (C-3) 1246-1 (F-5) 1246-1 (F-2) 1246-1 (G-6) 1246-1 (G-3) 1246-1 (H-5) 1246-1 (H-2)
C C
C C
O/C O/C O/C O/C NA NA NA NA NA NA NA NA BDT-O CV-C BDT-O CV-C BDT-O CV-C BDT-O CV-C RT RT RT RT Normal Ops CS Normal Ops CS Normal Ops CS Normal Ops CS 10Y 10Y 10Y 10Y CS - 14 CS - 14 CS - 14 CS - 14 Page 6 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CCW - COMPONENT COOLING WATER Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 759A 2
N A
A 3
GTV MOV 1246-1 (1-5) 0 C
Al DIAG OMN1 EX CS CCW FROM RCP A ISOL VLV MOV-759A LT-X 2Y 759B 2
N A
A 3
GTV MOV 1246-1 (1-2) 0 C
Al DIAG OMN1 EX CS CCW FROM RCP B ISOL VLV MOV-759B LT-X 2Y 766 3
N C
A
.75 TRV SAV 1246-2 (G-8)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR ECH04 (SEAL WATER HEAT EXCHANGER) 770 3
N C
A
.75 TRV SAV 1245 (F-7)
C 0
NA RT 10Y CCW INLET RELIEF VALVE FOR SAMPLE HEAT EXCHANGERS 774A 3
N C
A
.75 TRV SAV 1246-2 (D-5)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR EWD01 B (WASTE GAS COMP RESSOR B SEAL WATER HEAT EXCHANGER) 774B 3
N C
A
.75 TRV SAV 1246-2 (C-3)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR ECH07 (BORIC ACID EVAPORATOR CONDENSER) 774C 3
N C
A
.75 TRV SAV 1246-2 (B-4)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR ECH01 (BORIC ACID EVAPORATOR DISTILLATE COOLER) 774D 3
N C
A
.75 TRV SAV 1246-2 (C-8)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR EWD01A (WASTE GAS COMP RESSOR A SEAL WATER HEAT EXCHANGER) 776 3
N C
A
.75 TRV SAV 1246-2 (H-9)
C 0
NA RT 10Y CCW OUTLET RELIEF VALVE FOR NON REGENERATIVE HEAT EXCHANGER 813 2
N A
A 6
GTV MOV 1246-1 (B-8) 0 C
Al DIAG OMN1 EX 18M CCW TO Rx SUPPORT COOLERS ISOL VLV MOV-813 LT-X 2Y 814 2
N A
A 6
GTV MOV 1246-1 (I-8) 0 C
Al DIAG OMN1 EX 18M CCW FROM Rx SUPPORT CLRS ISOL VLV MOV-814 LT-X 2Y 817 3
Y B
NA 8
GTV MOV 1246-1 (A-4) 0 NA Al EX R
PIT 2Y CCW TO CNMT ISOL VLV MOV-817 ST-C R
Page 7 of 64
Revision: 0 Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 818 2
N C
A
.75 TRV CCW OUTLET RELIEF VALVE FOR REACTOR SUPPORT COOLE Constellation Energy (Ginna)
Valve Table CCW - COMPONENT COOLING WATER Actuator Drawing Position --------
Required Type
& Coord Normal Safety Fail-Safe Test SAV 1246-1 (H-8)
C O/C NA RT ERS Unit 1 Frequency RR/CSJ/ROJ Comments / Notes 10Y 823 3
Y B
P 2
GTV MOV 1245 (D-2)
C C
Al PIT 2Y RMW TO CCW SURGE TANK MOV-823 Page 8 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CFSW - CONSTRUCTION FIRE SERV WATER Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test Free MAN 1991 (D-7)
C C
NA LJ-C C
Unit 1 Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 5129 2
N A
P 2
GTV FIREWATER/SW SUPPLY TO CMNT DURING CONSTRUCTION C uency RR/CSJ/ROJ Comments / Notes
)PB
)NLY Page 9 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table CHPE - CONTAINMENT HVAC PURGE EXHAUST Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 1596 2
N A
A 1
GLV MAN 1866(1-10) 0 C
NA EX 2Y LJ-C OPB INLET BLOCK VLV TO AOV 1597 (CNMT AIR SAMPLE INLET) 1597 2
N A
A 1
DIV AOV 1866(1-9) 0 C
C EX Q
FS-C Q
CNMT AIR SAMPLE ISOL VLV AOV-1597 LJ-C OPB PIT 2Y ST-C Q
1598 2
N A
A 1
DIV AOV 1866 (G-10) 0 C
C EX Q
FS-C Q
CONTAINMENT AIR SAMPLE ISOL VLV AOV-1598 LJ-C OPB PIT 2Y ST-C 0
1599 2
N A
A 1
DIV AOV 1866 (G-10) 0 C
C EX Q
FS-C Q
CONTAINMENT AIR SAMPLE ISOL VLV AOV-1599 LJ-C OPB PIT 2Y ST-C Q
5879 2
N B
A 48 BFV AOV 1866 (1-2)
C C
C EX R
CONTAINMENT PURGE EXHAUST VLV AOV-5879 PIT 2Y ST-C R
7970 2
N A
A 6
BFV AOV 1870 (G-2)
OC C
C EX Q
FS-C Q
CONTAINMENT MINI PURGE EXHAUST VALVE INSIDE LJ-C OPB PIT 2Y ST-C 0
7971 2
N A
A 6
BFV AOV 1870 (G-4)
OC C
C EX Q
FS-C 0
CONTAINMENT MINI PURGE EXHAUST VALVE OUTSIDE LJ-C OPB PIT 2Y ST-C Q
Page 10 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table CHPS - CONTAINMENT HVAC PURGE SUPPLY Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P. Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments ! Notes 5869 SSC N
B A
48 BFV AOV 1865 (F-10)
C C
C EX R
CONTAINMENT PURGE SUPPLY AIR OPERATED VALVE PIT 2Y ST-C R
7445 2
N A
A 6
BFV AOV 1865 (H-7)
OC C
C EX Q
FS-C Q
CNMT MINI PURGE SUPPLY VLV OUTSIDE AOV-7445 U-C OPB PIT 2Y ST-C Q
7478 2
N A
A 6
BFV AOV 1865 (H-8)
OC C
C EX Q
FS-C Q
CNMT MINI PURGE SUPPLY VLV OUTSIDE AOV-7478 LJ-C OPB PIT 2Y ST-C Q
Page 11 of 64
Revision: 0 Valve ID Valve ActuE Description Class Aug. Cat.
A/P Size Type Typ 1557
- 2.
N A
P
.75 DIV MA!
A RECIRC FAN AIR SAMPLE LINE PRI ISOL, PENET-305 1558 2
N A
P
.5 GTV MA!
A RECIRC FAN AIR SAMPLE LINE VENT, PENET-305 1559 2
N A
P
.75 DIV MAr A REIRC FAN AIR SAMPLE LINE SEC [SOL, PENET-305 1560 2
N A
P
.75 DIV MA!
A & B RECIRC FAN AIR SAMPLE RETURN LINE PRI ISOL, PENET-305 1561 2
N A
P
.5 GTV
- MA!
A & B RECIRC FAN AIR SAMPLE RETURN LINE VENT, PENET-305 1562 2
N A
P
.75 DIV MAt A & B RECIRC FAN AIR SAMPLE RETURN LINE SEC ISOL, PENET-305 1572 2
N A
P
.75 DIV MAr C RECIRC FAN AIR SAMPLE RETURN LINE PRI ISOL, PENET-124 1573 2
N A
P
.5 GTV MA!'
C RECIRC FAN AIR SAMPLE RETURN LINE VENT, PENET-124 1574 2
N A
P
.75 DIV MAr C RECIRC FAN AIR SAMPLE RETURN SEC fSOL, PENET-124 Constellation Energy (Ginna)
Valve Table CHR - CONTAINMENT HVAC & RECIRC ator Drawing Position........
Required e
& Coord Normal Safety Fail-Safe Test q
1863 (C-5)
C C
NA LJ-C N
1863 (C-5)
C C
NA LJ-C A
1863 (C-4)
C C
NA LJ-C N
1863 (D-5)
C C
NA LJ-C Q
1863 (D-5)
C C
NA L-C q
1863 (D-5)
C C
NA LU-C q
1863 (B-12)
C C
NA LJ-C N
1863 (B-12)
C C
NA LJ-C q
1863 (B-12)
C C
NA LJ-C Unit 1 Ik Frequency RR/CSJ/ROJ Comments / Notes OPB OPB OPB OPB OPB OPB OPB OPB OPB Page 12of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table CS - CONTAINMENT SPRAY Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 1802 2
N C
A
.75 RV SAV 1261 (F-3)
C 0
NA RT 10Y SPRAY ADDITIVE TANK RELIEF VLV TO ATMOSPHERE 1819A 2
N A
A
.75 GLV MAN 1261 (A-10) 0 O/C NA INSTR ISOL VLV TO PT-945 (CNMT PRESS) 1819B 2
N A
A
.75 GLV MAN 1261 (A-9) 0 O/C NA INSTR ISOL VLV TO PT-946 (CNMT PRESS) 1819C 2
N A
A
.75 GLV MAN 1261 (B-10) 0 O/C NA INSTR ISOL VLV TO PT-947 (CNMT PRESS) 1819D 2
N A
A
.75 GLV MAN 1261 (B-9) 0 O/C NA INSTR ISOL VLV TO PT-948 (CNMT PRESS) 1819E 2
N A
A
.75 GLV MAN 1261 (C-10) 0 O/C NA INSTR ISOL VLV TO PT-949 (CNMT PRESS) 1819F 2
N A
A
.75 GLV MAN 1261 (C-9) 0 O/C NA INSTR ISOL VLV TO PT-950 (CNMT PRESS) 1819G 2
N A
A
.75 GLV MAN 1261 (C-10) 0 O/C NA INSTR ISOL VLV TO PT-944 (CNMT PRESS) 2825 2
N A
P
.75 GTV MAN 1261 (E-8)
C C
NA CONTAINMENT SPRAY PUMP A DISCHARGE INNER DRAIN VLV 2825A 2
N A
P
.5 BAV MAN 1261 (F-8)
C C
NA CONTAINMENT SPRAY PUMP A DISCHARGE OUTER DRAIN VLV 2826 2
N A
P
.75 GTV MAN 1261 (1-8)
C C
NA CONTAINMENT SPRAY PUMP B DISCHARGE INNER DRAIN VLV 2826A 2
N A
P
.5 BAV MAN 1261 (J-8)
C C
NA CONTAINMENT SPRAY PUMP B DISCHARGE OUTER DRAIN VLV 2856 2
N A
P
.75 GTV MAN 1261 (D-9)
C C
NA INSTR ISOL VLV TO PI-933A & 2780 (CNMT SPRAY PMP A DISCH)
EX LJ-C EX LJ-C EX LJ-C EX LJ-C EX LJ-C EX LJ-C EX LJ-C LJ-C LJ-C LJ-C LJ-C LJ-C 2Y OPB 2Y OPB 2Y OPB 2Y OPB 2Y OPB 2Y OPB 2Y OPB OPB OPB OPB OPB OPB Page 13of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CS - CONTAINMENT SPRAY Unit 1 Valve ID Valve Actuator Drawing Description Class Aug. Cat.
A/P Size Type Type
& Coord 2858 2
N A
P
.75 GTV MAN 1261 (1-9)
INSTR ISOL VLV TO PI-933B & 2779 (CNMT SPRAY PMP B DISCH) 2863R 2
N C
A
.75 TRV SAV 1261 (H-10)
CHARCOAL FILTER DOUSING HEADER RELIEF VALVE 836A 2
N B
A 2
CNMT SPRAY NAOH ADDITION AOV-836A 836B 2
N B
A 2
CNMT SPRAY NAOH ADDITION AOV-836B 845C 3
N C
A 2
RV SAV 1261 (F-4)
CONTAINMENT SPRAY ADDITIVE TANK VACUUM BREAKER-RELIEF VALVE 845D 3
N C
A 2
RV SAV 1261 (F-4)
CONTAINMENT SPRAY ADDITIVE TANK VACUUM BREAKER-RELIEF VALVE 847A 2
N C
A 2
CV SAV 1261 (G-5)
SPRAY ADDITIVE TANK OUTLET CHECK VLV TO CNMT SPRAY EDUCTOR A 847B 2
N C
A 2
CV SAV 1261 (H-5)
SPRAY ADDITIVE TANK OUTLET CHECK VLV TO CNMT SPRAY EDUCTOR B 860A 2
N A
A 6
GTV MOV 1261 (E-7)
CONTAINMENT SPRAY PUMP A MOTOR OPERATED DISCHARGE VALVE 860B 2
N A
A 6
GTV MOV 1261 (E-7)
CONTAINMENT SPRAY PUMP A DISCHARGE ISOLATION MOTOR OPERATED VALVE 860C 2
N A
A 6
GTV MOV 1261 (1-7)
CONTAINMENT SPRAY PUMP B DISCHARGE ISOLATION MOTOR OPERATED VALVE 860D 2
N A
A 6
GTV MOV 1261 (1-7)
CONTAINMENT SPRAY PUMP B MOTOR OPERATED DISCHARGE ISOLATION VALVE Position -------- Required Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes C
C NA LJ-C OPB C
C NA RT 10Y Added per NRC GL 96-06 0
0 0
0 0/C 0/C 0/C O/C O/C O/C 0
0 NA NA NA NA Al Al Al Al EX FS-O ST-0 EX FS-O ST-0 RT RT CV-C CV-0 CV-C CV-O DIAG EX LT-X DIAG EX LT-X DIAG EX LT-X DIAG EX LT-X Q
Q Q
2Y 2Y Q
0 Q
Q OMN1 18M 2Y OMN1 18M 2Y OMN1 18M 2Y OMN1 18M 2Y Page 14 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CS - CONTAINMENT SPRAY Unit 1 Valve ID Valve Actuator Drawing Valve ID Valve Actuator Drawing Description Class Aug.
Cat.
A/P Size Type Type
& Coord Nor 861 2
N C
A
.75 RV SAV 1261 (J-2)
C CONTAINMENT SPRAY PUMPS SUCTION RELIEF VLV 862A 2
N AC A
6 CV SAV 1261 (E-8)
C CONTAINMENT SPRAY PUMP A DISCHARGE CHECK VLV 862B 2
N AC A
6 CV SAV 1261 (1-8)
C CONTAINMENT SPRAY PUMP B DISCHARGE CHECK VLV 864A 2
N A
P
.75 GLV MAN 1261 (E-8)
C INLET ISOL VLV TO FI-933 (CNMT SPRAY PMP A FLOW)
'864B 2
N A
P
.75 GLV MAN 1261 (H-8)
C INLET ISOL VLV TO FI-933 (CNMT SPRAY PMP B FLOW) 869A 2
N A
P
.75 GLV MAN 1261 (E-9)
C INSTR ROOT VLV TO PI-933A & 2780 (CNMT SPRAY PMP A DISCH) 869B 2
N A
P
.75 GLV MAN 1261 (1-9)
C INSTR ROOT VLV TO PI-933B & 2779 (CNMT SPRAY PMP B DISCH) 875A 2
N B
P 2
GLV MOV 1261 (F-9)
C UPPER CNMT SPRAY CHARCOAL FILTER DOUSING MOTOR OPERATED VALVE 875B 2
N B
P 2
GLV MOV 1261 (G-9)
C UPPER CNMT SPRAY CHARCOAL FILTER DOUSING MOV-875B 876A 2
N B
P 2
GLV MOV 1261 (H-9)
C LOWER CONTAINMENT SPRAY CHARCOAL FILTER DOUSING MOTOR OPERATED VALVE 876B 2
N B
P 2
GLV MOV 1261 (G-9)
C LOWER CNMT SPRAY CHARCOAL FILTER DOUSING MOV-876B 896A 2
N A
A 10 GTV MOV 1261 (C-2) 0 Position -------- Required nal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes O/C NA RT 10Y O/C NA CV-C Q
CV-O 0
LJ-C OPB O/C NA CV-C Q
CV-O Q
LJ-C OPB C
C C
C C
C C
C NA NA NA NA Al Al Al Al LJ-C LJ-C LJ-C LJ-C PIT PIT PIT PIT OPB OPB OPB OPB 2Y 2Y 2Y 2Y O/C Al DIAG OMNI EX CS RWST OUTLET TO CNMT SPRAY & SAFETY INJECTION PUMPS MOV-896A LT-X 2Y Page 15of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CS - CONTAINMENT SPRAY Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test 896B 2
N A
A 10 GTV MOV 1261 (D-2) 0 O/C Al DIAG EX RWST OUTLET TO CNMT SPRAY & SAFETY INJECTION PUMPS MOV-896B LT-X 897 2
N A
A 2
GLV MOV 1261 (C-7) 0 O/C Al DIAG EX SAFETY INJECTION RECIRC TO RWST MOV-897 LT-X 898 2
N A
A 2
GLV MOV 1261 (C-7) 0 O/C Al DIAG EX SAFETY INJECTION RECIRC TO RWST MOV-898 LT-X Unit 1 Frequency RR/CSJ/ROJ Comments / Notes OMN1 CS 2Y OMN1 CS 2Y OMN1 CS 2Y Page 16of 64
Revision: 0 Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 7443 2
N A
P 6
BFV CONTAINMENT LEAK TEST ISOL VLV MOV-7443 7444 2
N A
P 6
BFV CONTAINMENT LEAK TEST MOTOR OPERATED VALVE Constellation Energy (Ginna)
Valve Table CVAT - CONTAINMENT VESSEL AIR TEST Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test F
MAN 1882 (E-10)
C C
NA LJ-C MAN 1882 (1-5)
C C
NA U-C Unit 1 requency RR/CSJ/ROJ Comments / Notes OPB OPB Page 17of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CVCS - CVCS CHARGING Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 112B 2
Y B
A 4
BFV AOV 1265-2 (F-3)
C 0
C EX CS CS - 07 PIT 2Y EMERG MAKEUP RWST TO CHARGING PUMP LCV-1 12B ST-O CS CS - 07 112C SSC Y
B A
4 BFV AOV 1265-2 (D-3) 0 C
0 EX CS PIT 2Y VCT OUTLET VLV LCV-12C ST-C CS 142 2
Y B
A 2
GLV AOV 1265-2 (E-10) 0 0
0 EX CS CS - 08 FS-O CS CS - 08 CHARGING FLOW TO REGEN HX HCV-142 PIT 2Y ST-O CS CS - 08 257 SSC Y C
A 2
RV SAV 1265-2 (A-4)
C O/C NA RT 10Y VCT RELIEF VALVE TO HOLDUP TANKS 268 SSC Y
B A
4 BFV MAN 1265-2 (F-3) 0 O/C NA EX 2Y VCT SUCTION ISOL VLV TO CHARGING PUMP B & C 270A 2
Y B
A 2
GLV AOV 1265-1 (F-3) 0 C
0 EX CS CS - 10 PIT 2Y RCP A SEAL OUTLET VLV AOV-270A ST-C CS CS - 10 270B 2
Y B
A 2
GLV AOV 1265-1 (F-6) 0 C
0 EX CS CS - 10 PIT 2Y RCP B SEAL OUTLET VLV AOV 270B ST-C CS CS - 10 283 2
N C
A
.75 RV SAV 1265-2 (H-6)
C O/C NA RT 10Y CHARGING PUMP C DISCHARGE RELIEF VLV TO VCT 284 2
N C
A
.75 RV SAV 1265-2 (F-6)
C O/C NA RT 10Y CHARGING PUMP B DISCHARGE RELIEF VLV TO VCT 285 2
N C
A
.75 RV SAV 1265-2 (E-6)
C O/C NA RT 10Y CHARGING PUMP A DISCHARGE RELIEF VLV TO VCT 302C 1
Y C
A 2
CV SAV 1265-1 (G-6) 0 0
NA BDT-C R
CV-O Normal Ops RCP B SEAL INJECTION INLET CHECK VLV 302D 1
Y C
A 2
CV SAV 1265-1 (G-3) 0 0
NA BDT-C R
CV-O Normal Ops RCP A SEAL INJECTION INLET CHECK VLV Page 18of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CVCS - CVCS CHARGING Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 304A 1
N AC A
2 CV SAV 1265-1 (H-3) 0 O/C NA CV-C OPB CVCMP RCP A SEAL INJECTION INLET CHECK VALVE 304B 1
N AC A
2 CV SAV 1265-1 (H-6)
RCP B SEAL INJECTION INLET CHECK VLV 313 2
N A
A 3
GTV MOV 1265-2 (D-8)
SEAL OR EXCESS LETDOWN RETURN ISOLATION MOTOR OPERATED VALVE TEST 314 2
N C
A 2
RV SAV 1265-1 (B-4)
SEAL WATER RETURN RELIEF VLV TO PRT 357 2
Y C
A 4
CV SAV 1261 (B-3)
RWST SUCTION CHECK VLV TO CHARGING PUMPS 358 2
Y B
A 4
BFV MAN 1265-2 (F-3)
RWST MAKEUP AOV BYPASS VLV TO CHARGING PUMPS SUCTION k.,V-U.
U2 LJ-C OPB 0
O/C NA CV-C OPB CVCMP 0
C C
C C
0 0
O/C Al NA NA NA CV-O LJ-C DIAG EX LJ-C RT BDT-C CV-O EX Q
OPB OMN1 CS OPB lOY CS CS 2Y CS - 07 370B 1
N AC A
2 CV SAV 1265-1 (B-2) 0 O/C NA CV-C CS CS - 08 CV-O CS CS - 08 CHARGING PUMP DISCH CHECK VLV TO REGEN HX'S LJ-C OPB LT-X 2Y 383B 2
N AC A
2 CV SAV 1265-1 (H-2)
C C
NA BDT-O CS CS - 12 CV-C CS CS - 12 ALTERNATE CHARGING LINE INLET CHECK VLV TO LOOP A COLD LEG LJ-C OPB LT-X 2Y 386 2
N B
A 1
GTV AOV 1265-1 (C-4)
C C
C EX CS CS - 11 FS-C CS CS - 11 RCP A & B SEAL BYPASS AOV-386 PIT 2Y ST-C CS CS - 11 392A 2
N BC A
2 GLV AOV 1265-1 (A-9)
C 0
VR - 03 CHARGING VLV RHX TO LOOP B HOT AOV-392A 393 1
Y C
A 2
CV SAV 1265-1 (A-10)
C 0
NA BDT-C CS CV-0 CS CS - 08 CHARGING LINE INLET CHECK VLV TO LOOP B HOT LEG (IMB)
Page 19 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table CVCS - CVCS CHARGING Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 9315 1
Y C
A 2
CV SAV 1265-1 (A-9)
C 0
NA BDT-C CS CV-O CS CS - 08 CHARGING LINE INLET CHECK VLV TO LOOP B HOT LEG (RCS,IMB)
Page 20 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table CVL - CVCS LETDOWN Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 123 1
N A
, P
.75 GLV AOV 1264 (E-9)
C C
C LT-X 2Y EXCESS LETDOWN HX FLOW CONTROL HCV-123 200A 1
N A
A 2
GLV AOV 1264 (B-11)
O/C C
C EX CS CS - 09 FS-C CS CS - 09 LTDN ORIFICE AOV-200A LJ-C OPB LT-X 2Y PIT 2Y ST-C CS CS - 09 200B 1
N A
A 2
GLV AOV 1264 (B-10)
O/C C
C EX CS CS - 09 FS-C CS CS - 09 LTDN ORIFICE AOV-200B LJ-C OPB LT-X 2Y PIT 2Y ST-C CS CS - 09 202 1
N A
A 2
GLV AOV 1264 (B-10)
C C
C EX CS CS - 09 FS-C CS CS - 09 LTDN ORIFICE AOV-202 LJ-C OPB LT-X 2Y PIT 2Y ST-C CS CS - 09 203 2
N AC A
2 RV SAV 1264 (A-8)
C O/C NA LJ-C OPB RT 10Y LOOP B LETDOWN TO NON-REGENERATIVE HEAT EXCHANGER RELIEF VALVE TO PRESSURIZER RELIEF TANK 310 1
Y B
P
.75 GLV AOV 1264 (C-9)
C C
C PIT 2Y EXCESS LTDN LOOP A COLD TO HX AOV-31 0 371 2
N A
A 2
GLV AOV 1264 (B-7) 0 C
C EX CS CS - 09 FS-C CS CS - 09 LETDOWN ISOL VLV RHR TO NRHX AOV-371 LJ-C OPB PIT 2Y ST-C CS CS - 09 702 2
N C
A
.75 CV SAV 1264 (A-10)
C 0
NA BDT-C Normal Ops CV-O CS CS - 05 RHR LETDOWN INLET CHECK VLV TO NRHX (OVER PRESS PROTECTION)
Page 21 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table EDG - EMERGENCY DIESEL GENERATOR Unit 1 Valve ID Valve Actuator Drawing Position........
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 12398G 3
N B
A 1
GTV MAN 1239-1 (E-3) 0 O/C NA EX 2Y A D/G FUEL OIL SOLENOID RECIRC ISOLATION VALVE 12399G 3
N B
A 1
GTV MAN 1239-2 (E-8) 0 O/C NA EX 2Y B-D/G FUEL OIL SOLENOID RECIRC ISOL VLV 5907 3
.N B
A 1
GTV SOV 1239-1 (E-3) 0 O/C C
EX Q
FS-C Q
TJ-03 D/G A FUEL OIL SOV TO DAY TANK ST-C Q
ST-O Q
5907A 3
N B
A
.75 GTV SOV 1239-1 (E-3)
C O/C 0
EX Q
FS-O Q
TJ-03 D/G A FUEL OIL TRANSFER PUMP SOLENOID OPERATED RECIRC VLV ST-C Q
ST-O Q
5908 3
N B
A 1
GTV SOV 1239-2 (E-9) 0 O/C C
EX Q
FS-C Q
TJ-03 D/G B FUEL OIL SOLENOID VLV TO DAY TANK ST-C Q
ST-O 0
5908A 3
N B
A
.75 GTV SOV 1239-2 (E-9)
C O/C 0
EX Q
FS-O 0
TJ-03 D/G B FUEL OIL TRANSFER PUMP RECIRCULATION SOV ST-C Q
ST-0 0
5923 3
N C
A
.375 RV SAV 1239-1 (A-2)
C O/C NA RT 10Y D/G A FUEL OIL BOOSTER PUMP DISCHARGE RELIEF VLV (TO DAY TK) 5924 3
N C
A
.375 RV SAV 1239-2 (A-10)
C O/C NA RT 10Y D/G B FUEL OIL BOOSTER PUMP DISCHARGE RELIEF VLV (TO DAY TK) 5933A 3
N B
A 1.5 GTV SOV 1239-1 (G-11)
C 0
Al EX Q
ST-0 0
TJ-02 D/G A STARTING AIR SOV 5933B 3
N B
A 1.5 GTV SOV 1239-1 (F-11)
C 0
Al EX Q
ST-O Q
TJ-02 D/G A STARTING AIR SOV 5934A 3
N B
A 1.5 GTV SOV 1239-2 (C-2)
C 0
Al EX 0
ST-0 Q
TJ-02 D/G B STARTING AIR SOV Page 22 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table EDG - EMERGENCY DIESEL GENERATOR Unit 1 Valve ID Valve Actuator Drawing Description Class Aug. Cat.
A/P Size Type Type
& Coord
......... Position -------- Required Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments I Notes C
0 Al EX Q
ST-O Q
TJ-02 5934B 3
N B
A 1.5 GTV SOV 1239-2 (B-2)
D/G B STARTING AIR SOV 5937 3
N B
A 1
GLV MAN 1239-1 (E-3)
DIG A FUEL OIL SOV BYPASS VLV (TO DAY TK) 5938 3
N B
A 1
GLV MAN 1239-2 (E-8)
D/G B FUEL OIL SOLENOID VLV 5908 BYPASS VLV (TO DAY TK) 5941A 3
N C
A
.75 CV SAV 1239-1 (F-i)
DISCHARGE CHECK VALVE FOR CDG01A (D/G A STARTING AIR COMPRESSOR) 5942A 3
N C
A
.75 CV SAV 1239-2 (F-1 1)
D/G B STARTING AIR COMPRESSOR DISCHARGE CHECK VLV 5943A 3
N C
A
.75 RV SAV 1239-1 (F-i)
DISCHARGE RELIEF VALVE FOR CDG01A (D/G A STARTING AIR COMPRESSOR) 5944A 3
N C
A
.75 RV SAV 1239-2 (F-11)
D/G B STARTING AIR COMPRESSOR DISCHARGE RELIEF VLV 5947B 3
N C
A
.75 RV SAV 1239-1 (F-i)
RELIEF VALVE FOR TDG03A (D/G A STARTING AIR RECEIVER Al) 5947C 3
N C
A
.75 RV SAV 1239-1 (G-1)
RELIEF VALVE FOR TDG03B (D/G A STARTING AIR RECEIVER A2) 5948B 3
N C
A
.75 RV SAV 1239-2 (G-10)
D/G B STARTING AIR RECEIVER B2 RELIEF VLV 5948C 3
N C
A
.75 RV SAV 1239-2 (F-10)
D/G B STARTING AIR RECIEVER B1 RELIEF VLV 5955 3
N C
A 3
CV SAV 1239-1 (I-1)
O/C O/C C
C O/C O/C O/C O/C O/C O/C O/C NA NA NA NA NA NA NA NA NA NA NA EX EX BDT-0 CV-C BDT-0 CV-C RT RT RT RT RT RT CV-C CV-O 2Y 2Y Q
Q 0
Q 10Y loY 10Y 10Y 10Y 10Y Q
Q D/G A FUEL OIL TRANSFER PUMP SUCTION CHECK VLV 5956 3
N C
A 3
CV SAV 1239-2 (1-10)
C O/C NA CV-C Q
CV-0 Q
D/G B FUEL OIL TRANSFER PUMP SUCTION CHECK VLV Page 23 of 64
Revision: 0 Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 5959 3
N C
A 1.5 RV D/G A FUEL OIL TRANSFER PUMP DISCHARGE RELIEF VLV 5960 3
N C
A 1.5 RV D/G B FUEL OIL TRANSFER PUMP DISCHARGE RELIEF VLV 5960A 3
N C
A 1.5 CV D/G A FUEL OIL DAY TANK CHECK VLV TO STORAGE TANK A 5960B 3
N C
A 1.5 CV D/G B FUEL OIL DAY TANK CHECK VLV TO STORAGE TANK B 5989 3
N C
A 2.5 RV D/G A LUBE OIL RELIEF VLV 5990 3
N C
A 2.5 RV D/G B LUBE OIL RELIEF VLV Constellation Energy (Ginna)
Valve Table EDG - EMERGENCY DIESEL GENERATOR Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes SAV 1239-1 (G-3)
C O/C NA RT lay SAV 1239-2 (G-8)
C O/C NA RT lay SAV 1239-1 (C-1)
C O/C NA DI CMP CVCMP SAV 1239-2 (C-11)
C O/C NA DI CMP CVCMP SAV 1239-1 (C-3)
C O/C NA RT lay SAV 1239-2 (C-9)
C O/C NA RT lay Unit 1 Page 24 of 64
Revision: 0 Valve ID Valve Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 9227 2
N A
P 4
BAV CONTAINMENT FIRE HOSE SUPPLY AIR OPERATED VALVE 9229 2
N AC A
4 CV CNMT HOSE REEL SUPPLY CHECK VLV (IN CNMT) 9230R 2
N C
A
.75 TRV CONTAINMENT FIRE HEADER THERMAL RELIEF VALVE Actuator Type MAN SAV Constellation Energy (Ginna)
Valve Table FP - FIRE PROTECTION Drawing Position -------- Requ
& Coord Normal Safety Fail-Safe Tes 1991 (B-5)
C C
NA LJ-1991 (C-5)
C O/C NA CV CV LJ-i red st C
-C
-O C
Unit 1 Frequency RR/CSJ/ROJ Comments / Notes OPB OPB CVCMP R
OPB SAV 1991 (C-5)
C 0
NA RT 10Y Added per NRC GL 96-06 Page 25 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table HREC - H2 RECOMBINERS Unit 1 Valve ID Valve Actuator Drawing Description Class Aug.
Cat.
A/P Size Type Type
& Coord Norm Position -------- Required al Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes C
NA LJ-C OPB 10205S1 2
N A
P 1
GTV SOV 1275-1 (B-7)
C H2 PILOT LINE SOLENOID OPERATED ISOL VLV TO RECOMBINER A 10209St 2
N A
P 1
GTV SOV 1275-1 (D-7)
C H2 MAIN FUEL LINE SOLENOID OPERATED ISOL VLV TO RECOMBINER A 10211S1 2
N A
P 1
GTV SOV 1275-1 (E-8)
C H2 PILOT LINE SOLENOID OPERATED ISOL VLV TO RECOMBINER B 10213S1 2
N A
P 1
GTV SOV 1275-1 (G-8)
C HYDROGEN MAIN FUEL LINE TO RECOMBINER B ISOLATION SOLENOID OPERATED VALVE 10214S1 2
N A
P 1
GTV SOV 1275-1 (C-1)
C 02 LINE A SOL OPERATED ISOL VLV TO CNMT VENT DUCT (CNMT ISOL) 10215S1 2
N A
P 1
GTV SOV 1275-1 (E-1)
C 02 LINE B SOL OPERATED ISOL VLV TO CNMT VENT DUCT (CNMT ISOL) 1076A 2
N A
P 1
DIV MAN 1275-1 (B-7)
C HYDROGEN RECOMBINER A PILOT BURNER ISOL VLV (MANUAL CNMT ISOL) 1076B 2
N A
P 1
DIV MAN 1275-1 (E-8)
C HYDROGEN RECOMBINER B PILOT BURNER ISOL VLV (MANUAL CNMT ISOL) 1080A 2
N A
P 1
GTV MAN 1275-1 (E-1)
C 02 ISOL VLV TO CNMT VENT DUCT 1084A 2
N A
P 1
DIV MAN 1275-1 (D-7)
C NA NA NA NA NA NA NA NA NA LJ-C LJ-C LJ-C LJ-C LJ-C L-C LJ-C LJ-C LJ-C OPB OPB OPB OPB OPB OPB OPB OPB OPB HYDROGEN RECOMBINER A MAIN FUEL ISOL VLV (MANUAL CNMT ISOL) 1084B 2
N A
P 1
DIV MAN 1275-1 (G-8)
C C
NA LJ-C OPB HYDROGEN RECOMBINER B MAIN FUEL ISOL VLV (MANUAL CNMT ISOL)
Page 26 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table IA - INSTRUMENTAIR Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 5392 2
N A
A 2
GTV AOV 1893 (A-11) o C
C EX R
ROJ - 06 FS-C R
ROJ - 06 INSTR AIR TO CONTAINMENT ISOL AOV-5392 LJ-C OPB PIT 2Y ST-C R
ROJ - 06 5393 2
N AC A
2 CV SAV 1887 (D-4) 0 C
NA BDT-O Normal Ops CVCMP CV-C OPB IA INLET CHECK VLV TO CONTAINMENT (IN CNMT)
LJ-C OPB Page 27 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table MFW - MAIN FEEDWA TER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A!P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 3992 2
N C
A 14 CV SAV 1236-2 (J-3) 0 C
NA BDT-O Normal Ops CV-C CS CS - 18 S/G B FW INLET CHECK VLV 3993 2
N C
A 14 CV SAV 1236-2 (A-3) 0 C
NA BDT-O Normal Ops CV-C CS CS - 18 S/G A FW INLET CHECK VLV 3994 3
N B
A 14 GLV AOV 1236-2 (J-3) 0 C
C EX CS CS - 19 PIT 2Y MAIN FW INLET BLOCK VLV TO S/G B ST-C CS CS - 19 3994G 3
N C
A
.75 CV SAV 1236-3 (1-7)
C C
NA BDT-O CS CV-C CS CS - 20 MFIV ACCUMULATOR CHECK VALVE 3994K 3
N C
A
.75 RV SAV 1236-3 (G-8)
C O/C NA RT 10Y MFIV ACCUMULATOR RELIEF VALVE 3995 3
N B
A 14 GLV AOV 1236-2 (A-3) 0 C
C EX CS CS - 19 PIT 2Y MAIN FW INLET BLOCK VLV TO S/G A ST-C CS CS - 19 3995G 3
N C
A
.75 CV SAV 1236-3 (E-7)
C C
NA BDT-O CS CV-C CS CS - 20 MFIV ACCUMULATOR CHECK VALVE 3995K 3
N C
A
.75 RV SAV 1236-3 (C-8)
C O/C NA RT 10Y MFIV ACCUMULATOR RELIEF VALVE 4269 3
N B
A 12 GLV AOV 1236-2 (D-3) 0 C
C EX CS CS - 19 FS-C CS CS - 19 MAIN FW CONTROL AOV TO S/G A PIT 2Y ST-C CS CS - 19 4270 3
N B
A 12 GLV AOV 1236-2 (G-3) 0 C
C EX CS CS - 19 FS-C CS CS - 19 MAIN FW CONTROL AOV TO S/G B PIT 2Y ST-C CS CS - 19 4271 3
N B
A 4
GLV AOV 1236-2 (D-3)
C C
C EX CS CS - 19 FS-C CS CS - 19 FW BYPASS CONTROL AOV 4271 TO S/G A AOV PIT 2Y ST-C CS CS - 19 Page 28 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table MFW - MAIN FEED WA TER Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4272 3
N B
A 4
C C
C EX CS CS - 19 FS-C CS CS - 19 FW BYPASS CONTROL AOV 4272 TO S/G B AOV PIT 2Y ST-C CS CS - 19 Page 29 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table MS - MAIN STEAM Unit 1 Valve ID Valve Actuator Drawing
......... Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 3410 2
N B
A 6
GTV AOV 1231 (1-5)
C O/C C
EX CS FS-C CS STEAM GENERATOR B ATMOSPHERIC RELIEF VALVE PIT 2Y 3411 2
N B
A 6
GTV AOV 1231 (C-5)
STEAM GENERATOR B ATMOSPHERIC RELIEF VALVE 3412A 2
N B
A
.5 GLV MAN 1231 (G-6)
S/G B MS LOOP HEADER INNER SAMPLE ISOL VLV 3413A 2
N B
A
.5 GLV MAN 1231 (B-6)
S/G A MS LOOP HEADER INNER SAMPLE ISOL VLV 3504A 2
N B
A 6
GTV MOV 1231 (F-4)
MOV FOR SG B MAIN STEAM SUPPLY TO PAF03 (TURBINE DRIVEN AFW PUMP) 3504B 3
N C
A 6
CV SAV 1231 (E-4)
CHECK VALVE FOR SG B MAIN STEAM TO PAF03 (TURBINE DRIVEN AFW PUMP) 3505A 2
N B
A 6
GTV MOV 1231 (B-4)
MOV FOR SG A MAIN STEAM SUPPLY TO PAF03 (TURBINE DRIVEN AFW PUMP) 3505B 3
N C
A 6
CV SAV 1231 (D-4)
CHECK VALVE FOR SG A MAIN STEAM TO PAF03 (TURBINE DRIVEN AFW PUMP) 3506 2
N B
A 6
GTV MAN 1231 (H-4)
S/G B MS INLET BLOCK VLV TO ARV 3410 3507 2
N B
A 6
GTV MAN 1231 (C-4)
S/G A MS INLET BLOCK VLV TO ARV 3411 3508 2
N C
A 6
RV SAV 1231 (G-5)
S/G B MS SAFETY VLV 3509 2
N C
A 6
RV SAV 1231 (A-5)
S/G A MS SAFETY VLV 3510 2
N C
A 6
RV SAV 1231 (G-6)
S/G B MS SAFETY VLV C
O/C C
C O/C O/C O/C O/C O/C O/C O/C O/C O/C NA NA Al NA Al NA NA NA NA NA NA EX EX DIAG EX CV-C CV-0 DIAG EX CV-C CV-0 EX EX RT RT RT 2Y 2Y OMN1 18M Q
2Y OMN1 18M 0
2Y 2Y 2Y 5Y 5Y 5Y CVCMP CVCMP Radiography Radiography Page 30 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table MS - MAIN STEAM Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 3511 2
N C
A 6
RV SAV 1231 (A-6)
C O/C NA RT 5Y S/G A MS SAFETY VLV 3512 2
N C
S/G B MS SAFETY VLV 3513 2
N C
S/G A MS SAFETY VLV 3514 2
N C
S/G B MS SAFETY VLV 3515 2
N C
S/G A MS SAFETY VLV 3516 2
N B
A 6
A 6
A 6
A 6
A 30 RV RV RV RV SAV 1231 (G-7)
SAV 1231 (A-7)
SAV 1231 (G-8)
SAV 1231 (A-7)
AOV 1231 (G-10)
C C
C C
O/C O/C O/C O/C C
NA NA NA NA C
RT RT RT RT BDT-O 5Y 5Y 5Y 5Y Normal Ops CV 0
EX CS CS - 16 MSIV B AOV-3516 FS-C CS CS - 16 PIT 2Y ST-C CS CS - 16 3517 2
N B
A 30 CV AOV 1231 (A-11) 0 C
C BDT-0 Normal Ops EX CS CS - 16 MSIV A AOV-3517 FS-C CS CS - 16 PIT 2Y ST-C CS CS - 16 3518 3
N C
A 30 CV SAV 1231 (G-10).
0 C
NA BDT-0 Normal Ops CV-C CS CS - 17 S/G B MAIN STEAM CHECK VLV 3519 3
N C
A 30 CV SAV 1231 (A-11) 0 C
NA BDT-0 Normal Ops CV-C CS CS - 17 S/G A MAIN STEAM CHECK VLV 3520 2
N B
A 2
GLV MAN 1231 (F-10) 0 C
NA EX 2Y INLET ISOL VLV TO S/G B DRAIN/TRAPS 3521 2
N B
A 2
GLV MAN 1231 (B-11) 0 C
NA EX 2Y INLET ISOL VLV TO S/G A DRAIN/TRAPS Page 31 of 64
Revision: 0 Cons Valve ID Valve Actuator Drawing Valve ID Valve Actuator Drawing Description Class Aug.
Cat.
A/P Size Type Type
& Coord 3652 3
N B
A 3
GTV HYD 1231 (D-2)
TURBINE DRIVEN AUX FW PUMP TRIP THROTTLE VALVE 3668 2
N B
A 1
GLV MAN 1231 (G-9)
S/G B MS INLET BLOCK VLV TO TEMPERATURE COMPENSATED SUPPORTS 3669 2
N B
A 1
GLV MAN 1231 (B-9)
S/G A MS INLET BLOCK VLV TO TEMPERATURE COMPENSATED SUPPORTS tellation Energy (Ginna)
Valve Table MS - MAIN STEAM Position --------
Requ Normal Safety Fail-Safe Tes O
O/C Al E
O C
NA E
O C
NA E
Unit 1 ired t
x x
X Frequency RR/CSJ/ROJ Comments / Notes Q
skid-mounted 2Y 2Y Page 32 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table NS - NUCLEAR SAMPLING Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test 7448 2
N A
P
.375 GTV MAN 1278-1 (G-1)
C C
NA LJ-C CONTAINMENT H2 MONITOR A SAMPLE INLET LINE TEST CONN ISOL VLV 7452 2
N A
P
.375 GTV MAN 1278-1 (H-2)
C C
NA LJ-C CONTAINMENT H2 MONITORS SAMPLE RETURN LINE TEST CONN ISOL VLV 7456 2
N A
P
.375 GTV MAN 1278-1 (I-1)
C C
NA LJ-C CONTAINMENT H2 MONITOR B SAMPLE INLET LINE TEST CONN ISOL VLV 921 2
N A
A
.375 GTV SOV 1278-1 (G-1)
C C
C EX FS-C H2 MONITOR A INLET ISOLATION VLV SOV-921 LJ-C PIT ST-C ST-O 922 2
N A
A
.375 GTV SOV 1278-1 (H-2)
C C
C EX FS-C H2 MONITOR A RETURN ISOL VLV SOV-922 LJ-C PIT ST-C ST-O 923 2
N A
A
.375 GTV SOV 1278-1 (J-1)
C C
C EX FS-C H2 MONITOR B INLET ISOLATION VLV SOV-923 LJ-C PIT ST-C ST-O 924 2
N A
A
.375 GTV SOV 1278-1 (1-2)
C C
C EX FS-C H2 MONITOR B RETURN ISOL VLV SOV-924 LJ-C PIT ST-C ST-O 951 1
Y B
NA
.375 GLV AOV 1278-1 (E-8)
C NA C
EX FS-C PRESSURIZER STEAM SPACE SAMPLE ISOL AOV PIT Unit 1 Frequency RR/CSJ/ROJ Comments / Notes OPB OPB OPB Q
0 OPB 2Y Q
Q Q
0 OPB 2Y 0
Q Q
Q OPB 2Y Q
Q Q
Q OPB 2Y Q
Q Q
Q 2Y Page 33 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table NS - NUCLEAR SAMPLING Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 951C 1
N C
A
.375 CV SAV 1278-1 (E-8)
C 0
NA BDT-C CS Added per NRC GL 96-06 CV-O CS CS - 15 AOV-951 BYPASS CHECK VALVE 953 1
Y B
NA
.375 GLV AOV 1278-1 (D-8)
C NA C
EX Q
FS-C Q
PRESSURIZER LIQUID SPACE SAMPLE ISOL AOV PIT 2Y 953C 1
N C
A
.375 CV SAV 1278-1 (D-8)
C 0
NA BDT-C CS Added per NRC GL 96-06 CV-O CS CS - 15 AOV-953 BYPASS CHECK VALVE 955 1
Y B
NA
.5 GLV AOV 1278-1 (B-8)
C NA C
EX Q
FS-C Q
LOOP B HOT LEG SAMPLE ISOL AOV PIT 2Y 955C 1
N C
A
.375 CV SAV 1278-1 (B-8)
C 0
NA BDT-C CS Added per NRC GL 96-06 CV-O CS CS - 15 AOV-955 BYPASS CHECK VALVE 956D 2
N A
A
.375 GLV MAN 1278-1 (B-9) 0 C
NA EX 2Y LJ-C OPB INLET BLOCK VLV TO AOV 966C (LOOP B HOT LEG SAMPLE CNMT ISOL) 956E 2
N A
A
.375 GLV MAN, 1278-1 (D-9) 0 C
NA EX 2Y LJ-C OPB INLET BLOCK VLV TO AOV 966B (PRZR LIQUID SAMPLE CNMT ISOL) 956F 2
N A
A
.375 GLV MAN 1278-1 (E-9) 0 C
NA EX 2Y LJ-C OPB INLET BLOCK VLV TO AOV 966A (PRZR STEAM SAMPLE CNMT [SOL) 959 2
N B
P
.375 GLV AOV 1278-2 (C-3)
C C
C PIT 2Y RHR LOOP SAMPLE ISOL AOV 966A 2
N A
A
.375 GLV AOV 1278-1 (E-9)
C C
C EX 0
FS-C Q
PRESSURIZER STEAM SPACE SAMPLE CONTAINMENT ISOLATION AIR OPERATED VALVE LJ-C OPB PIT 2Y ST-C 0
966B 2
N A
A
.375 GLV AOV 1278-1 (D-9)
C C
C EX Q
FS-C Q
PRESSURIZER LIQUIDSPACE SAMPLE CONTAINMENT ISOL AOV LJ-C OPB PIT 2Y ST-C Q
Page 34 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table NS - NUCLEAR SAMPLING Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 966C 2
N A
A
.375 GTV AOV 1278-1 (B-9)
C C
C EX Q
FS-C Q
LOOP B HOT LEG SAMPLE CONTAINMENT ISOL AOV LJ-C OPB PIT 2Y ST-C Q
Page 35 of 64
Revision: 0 Cons PA tellation Energy (Ginna)
Valve Table S-POST ACC SAMP
......... Position --------
Requ Normal Safety Fail-Safe Tes O
C C
E Unit 1 Valve ID Valve Actuator Drawing Description Class Aug.
Cat.
A/P Size Type Type
& Coord 1723 2
N A
A 3
DIV AOV 1279 (E-2)
CONTAINMENT SUMP A SAMPLE PUMP DISCHARGE ISOL VLV TO PASS WHUT ired t
X FS-C LJ-C PIT ST-C Frequency RR/CSJ/ROJ Comments / Notes Q
Q OPB 2Y Q
1728 2
N A
A 3
DIV AOV 1279 (F-2) 0 C
C EX Q
FS-C Q
CONTAINMENT SUMP A SAMPLE PUMP DISCHARGE ISOL VLV TO PASS WHUT LJ-C OPB PIT 2Y ST-C Q
Page 36 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table PWT - PRIMARY WATER TREATMENT Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 8418 2
N A
A 2
GLV AOV 1908-3 (A-4)
C C
C EX 0
FS-C Q
CONTAINMENT DEMIN WATER ISOL VLV AOV-8418 LJ-C OPB PIT 2Y ST-C Q
8419 2
N AC A
2 CV SAV 1908-3 (A-5)
C O/C NA CV-C OPB CVCMP CV-O CMP CONDENSATE OR DI WATER INLET CHECK VLV TO CONTAINMENT (IN CNMT)
LJ-C OPB 8421R 2
N C
A
.25 TRV SAV 1908-3 (A-5)
C 0
NA RT 1oy Added per NRC GL 96-06 PENETRATION P324 THERMAL RELIEF Page 37 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table Unit 1 RCDT - REACTOR COOLANT DRAIN TANK Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 1003A 2
N A
A 3
DIV AOV 1272-2 (D-4) 0 C
C EX Q
FS-C Q
RCDT OUTLET [SOL VALVE AOV-1003A LJ-C OPB PIT 2Y ST-C Q
1003B 2
N A
A 3
DIV AOV 1272-2 (E-4) 0 C
C EX Q
FS-C 0
RCDT OUTLET ISOL VALVE AOV-1003B LJ-C OPB PIT 2Y ST-C Q
1655 2
N A
A
.375 GLV MAN 1272-2 (B-2) 0 C
C EX 2Y LJ-C OPB RCDT OUTLET ISOL VLV TO GAS ANALYZER 1709G 2
N A
P
.75 GTV MAN 1272-2 (E-3)
C C
NA LJ-C OPB RCDT OUTLET LINE DRAIN VLV 1713 2
N AC P
1 CV SAV 1272-2 (A-3)
C C
NA LJ-C OPB N2 INLET CHECK VLV TO RCDT 1721 2
N A
A 3
DIV AOV 1272-2 (D-3) 0 C
C EX 0
FS-C Q
RCDT OUTLET ISOL VALVE AOV-1721 LJ-C OPB PIT 2Y ST-C Q
1722 2
N A
P 4
DIV MAN 1272-2 (D-3)
C C
NA LJ-C OPB REFUELING CANAL DRAIN ISOL VLV TO RCDT PMP 1786 2
N A
A 1
DIV AOV 1272-2 (B-5) 0 C
C EX Q
FS-C Q
PRT RCDT ISOL TO VENT HEADER ISOL VALVE AOV-1786 LJ-C OPB PIT 2Y ST-C Q
1787 2
N A
A 1
DIV AOV 1272-2 (B-5) 0 C
C EX Q
FS-C Q
PRT RCDT ISOL TO VENT HEADER ISOL VALVE AOV-1787 LJ-C OPB PIT 2Y ST-C Q
Page 38 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RCDT - REACTOR COOLANT DRAIN TANK Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 1789 2
N A
A
.75 DIV AOV 1272-2 (B-5) 0 C
C EX Q
FS-C Q
RCDT OUTLET ISOL AOV TO GAS ANALYZER LJ-C OPB PIT 2Y ST-C Q
1793 2
N A
P 1
DIV MAN 1272-2 (A-3)
C C
NA LJ-C OPB N2 INLET ISOL VLV TO RCDT Page 39 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RCP - REACTOR COOLANT PRZR Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 430 1
N B
A 3
GLV AOV 1258 (B-8)
C O/C C
EX CS FS-C CS PRESSURIZER POWER OPERATED RELIEF VALVE PIT 2Y ST-C CS ST-O CS 431C 1
N B
A 3
GLV AOV 1258 (C-8)
C O/C C
EX CS FS-C CS PRESSURIZER POWER OPERATED RELIEF VALVE PIT 2Y ST-C CS ST-O CS 434 1
N C
A 4
RV SAV 1258 (A-9)
C O/C NA PIT 2Y VR - 02
- RT R
PRESSURIZER RELIEF VLV TO PRESSURIZER RELIEF TANK 435 1
N C
A 4
RV SAV 1258 (C-9)
PRESSURIZER RELIEF VLV TO PRESSURIZER RELIEF TANK 508 2
N A
A 2
DIV AOV 1258 (F-7)
C C
C EX Q
FS-C Q
RMW TO CNMT ISOL VLV AOV-508 LJ-C OPB PIT 2Y ST-C Q
515 1
N B
A 3
GTV MOV 1258 (C-8) 0 O/C Al DIAG OMN1 EX 18M PRZR PORV BLOCK VLV MOV-515 516 1
N B
A 3
GTV MOV 1258 (B-8) 0 O/C Al DIAG OMN1 EX 18M PRZR PORV BLOCK VLV MOV-516 528 2
N AC A
2 CV SAV 1258 (E-9)
C C
NA BDT-O Normal Ops CVCMP CV-C OPB N2 INLET CHECK VLV TO PRESSURIZER RELIEF TANK LJ-C OPB 529 2
N AC A
2 CV SAV 1258 (F-9)
C O/C NA CV-C OPB CVCMP CV-0 Q
RMW PUMP DISCHARGE CHECK VLV TO PRT (IN CNMT)
LJ-C OPB Page 40 of 64
Revision: 0 Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 539 2
N A
A
.375 GLV PRT SAMPLE ISOL AOV TO GAS ANALYZER (CNMT ISOL)
Constellation Energy (Ginna)
Valve Table RCP - REACTOR COOLANT PRZR Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test AOV 1258 (E-7)
C C
C EX FS-C LJ-C PIT ST-C MAN 1258 (E-8) 0 C
NA EX LJ-C MAN 1258 (E-8)
LC C
NA LJ-C CNMT)
SAV 1258 (F-9)
C 0
NA RT ND PRT V-548 Unit 1 546 2
N A
A
.375 GLV PRT SAMPLE ISOL VLV TO GAS ANALYZER (OUTSIDE CNMT) 547 2
N A
P
.75 GLV N2 INLET ISOL VLV TO PRESSURIZER RELIEF TANK (OUTSIDE 568R 2
N C
A
.75 TRV THERMAL RELIEF FOR PIPING BETWEEN RMW DISCH V-508 AI Frequency RR/CSJ/ROJ Comments / Notes Q
0 OPB 2Y 0
2Y OPB OPB 10Y Added per NRC GL 96-06 I
Page 41 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table Unit 1 RCS - REACTOR COOLANT SYSTEM Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 590 2
N B
A GLV SOV 1260 (J-5)
C O/C C
EX CS CS - 01 FS-C CS CS - 01 REACTOR HEAD VENT OUTER SOLENOID OPERATED VALVE PIT 2Y ST-C CS CS - 01 ST-O CS CS - 01 591 2
N B
A 1
GLV SOV 1260 (J-5)
C O/C C
EX CS CS - 01 FS-C CS CS - 01 REACTOR HEAD VENT OUTER SOLENOID OPERATED VALVE PIT 2Y ST-C CS CS - 01 ST-O CS CS - 01 592 2
N B
A 1
GLV SOV 1260 (J-5)
C O/C C
EX CS CS - 01 FS-C CS CS - 01 REACTOR HEAD VENT INNER SOLENOID OPERATED VALVE PIT 2Y ST-C CS CS - 01 ST-O CS CS - 01 593 2
N B
A 1
GLV SOV 1260 (J-5)
C O/C C
EX CS CS - 01 FS-C CS CS - 01 REACTOR HEAD VENT INNER SOLENOID OPERATED VALVE PIT 2Y ST-C CS CS - 01 ST-O CS CS - 01 Page 42 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RCSOP - RCS OVERPRESSURE PROTECTION Unit 1 Valve ID Valve Description Class Aug. Cat.
A/P Size Type 8606A 3
N AC A
1 CV NITROGEN ACCUMULATOR A INLET CHECK VLV 8606B 3
N AC A
1 CV NITROGEN ACCUMULATOR B INLET CHECK VLV 8608A 3
N C
A
.75 RV NITROGEN ACCUMULATOR A RELIEF VLV 8608B 3
N C
A
.75 RV NITROGEN ACCUMULATOR B RELIEF VLV 8615A 3
N C
A 1
RV N2 INLET TO N2 SURGE TANK A RELIEF VLV (A TRAIN) 8615B 3
N C
A 1
RV N2 INLET TO N2 SURGE TANK B RELIEF VLV (B TRAIN) 8616A 3
N B
A
.75 TWV ACCUM TO SURGE TANK VLV SOV-8616A 8616B 3
N B
A
.75 TWV ACCUM TO SURGE TANK VLV SOV-8616B 8619A 3
NW B A
1 TWV N2 ARMING VLV SOV-8619A 8619B 3
N B
A 1
TWV N2 ARMING VLV SOV-8619B 8620A NC Y
B A
.75 TWV IA SOV TO PCV 430 (PORV ACTUATION A TRAIN) 86208 NC Y
B A
.75 TWV IA SOV TO PCV 431C (PORV ACTUATION B TRAIN)
Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes SAV 1263 (B-4)
C C
NA BDT-O Q
CV-C R
ROJ - 01 LT-X 2Y SAV SAV SAV SAV SAV SOV SOV SOV SOV SOV SOV 1263 (G-4) 1263 (C-4) 1263 (G-4) 1263 (B-6) 1263 (F-6) 1263 (B-7) 1263 (G-7) 1263 (C-9) 1263 (G-9) 1263 (C-10) 1263 (H-10)
C O/C O/C O/C O/C 0
0 O/C O/C C
C NA NA NA NA NA Al Al Al Al Al A[
BDT-O CV-C LT-X RT RT RT RT EX ST-O EX ST-O EX ST-C ST-O EX ST-C ST-O EX ST-C EX ST-C Q
R 2Y 10Y lay 10Y 10Y CS CS CS CS CS CS CS CS CS CS CS CS CS CS ROJ - 01 CS - 02 CS - 02 CS - 02 CS - 02 CS - 02 CS - 02 TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation Page 43 of 64
Revision: 0 Valve ID V
Description Class Aug.
Cat.
A/P Size I
8630A 3
N C
A 1
NITROGEN INLET CHECK VLV TO PVC 430 (A TRAIN) 8630B 3
N C
A 1
NITROGEN INLET CHECK VLV TO PCV 431C (B TRAIN) valve rype CV CV Constellation Energy (Ginna)
Valve Table RCSOP - RCS OVERPRESSURE PROTECTION Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ SAV 1263 (C-9) 0 O/C NA CV-C CS CS - 02 CV-O CS CS - 02 SAV 1263 (G-9) 0 O/C NA CV-C CS CS - 02 CV-O CS CS - 02 Unit 1 Comments / Notes TJ Satisfied by PORV actuation TJ Satisfied by PORV actuation Page 44 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RHR - RESIDUAL HEAT REMOVAL Unit 1 Valve ID Valve Actuator Drawing Positio Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety F 1813A 2
N A
P 6
GTV MOV 1247 (E-3)
C C
REACTOR COOLANT DRAIN TANK PUMP SUCTION FROM CONTAINMENT SUMP B MOTOR OPERATED VALVE 1813B 2
N A
P 6
GTV MOV 1247 (B-4)
C C
REACTOR COOLANT DRAIN TANK PUMP SUCTION FROM CONTAINMENT SUMP B MOTOR OPERATED VALVE 624 2
Y B
P 8
BFV AOV 1247 (J-7) 0 0
RHR HEAT EXCHANGER B FLOW CONTROL 625 2
Y B
P 8
BFV AOV 1247(1-8) 0 0
RHR HEAT EXCHANGER A FLOW CONTROL 626 2
Y B
A 6
BFV AOV 1247 (H-7)
C C
RHR HEAT EXCHANGER BYPASS 686G 2
N C
A 0.25 TRV SAV 1247 (D-8)
C 0
RHR PUMP A RECIRC LINE UPSTREAM RELIEF VALVE 686H 2
N C
A 0.25 TRV SAV 1247 (C-8)
C 0
RHR PUMP B RECIRC LINE UPSTREAM RELIEF VALVE 6861 2
N C
A 0.25 TRV SAV 1247 (D-8)
C 0
RHR PUMP A RECIRC LINE DOWNSTREAM RELIEF VALVE 686J 2
N C
A 0.25 TRV SAV 1247 (C-8)
C 0
RHR PUMP B RECIRC LINE DOWNSTREAM RELIEF VALVE 697A 2
N C
A 8
CV SAV 1247 (F-9)
C O/C RHR HEAT EXCHANGER A OUTLET CHECK VLV 697B 2
N C
A 8
CV SAV 1247 (B-9)
C O/C RHR HEAT EXCHANGER B OUTLET CHECK VLV 700 1
N A
A 10 GTV MOV 1247 (G-l)
C O/C RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-700 n --------
Required
0 C
NA NA NA NA NA NA Al EX EX EX FS-C RT RT RT RT CV-C CV-O CV-C CV-O EX LT-X PIT ST-O Q
Q 10Y 10Y 10Y 10Y 0
R Q
Q CS 2Y 2Y CS Code Case OMN-8 Added per PCR 2008-0015 Added per PCR 2008-0015 Added per PCR 2008-0015 Added per PCR 2008-0015 ROJ - 02 CS - 03 CS - 03 Page 45 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RHR - RESIDUAL HEAT REMOVAL Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 701 1
N A
A 10 GTV MOV 1247 (G-2)
C O/C Al EX CS CS - 04 LT-X 2Y RHR PUMP SUCTION FROM LOOP A HOT LEG MOV-701 PIT 2Y ST-O CS CS - 04 704A 2
N B
A 10 GTV MOV 1247 (D-4) 0 O/C Al DIAG OMN1 EX 18M RESIDUAL HEAT REMOVAL PUMP A SUCTION MOTOR OPERATED VALVE 704B 2
N B
A 10 GTV MOV 1247 (C-4) 0 O/C Al DIAG OMN1 EX 18M RESIDUAL HEAT REMOVAL PUMP B SUCTION MOTOR OPERATED VALVE 710A 2
N C
A 8
CV SAV 1247 (F-6)
C O/C NA CV-C CS CS - 06 CV-O Q
RHR PUMP A DISCHARGE CHECK VLV 710B 2
N C
A 8
CV SAV 1247 (B-6)
C O/C NA CV-C CS CS - 06 CV-O Q
RHR PUMP B DISCHARGE CHECK VLV 720 1
N A
A 10 GTV MOV 1247(1-2)
C O/C Al EX CS CS - 04 LT-X 2Y RHR PUMP DISCHARGE TO LOOP B COLD LEG MOV-720 PIT 2Y ST-O CS CS - 04 721 1
N A
A 10 GTV MOV 1247(1-1)
C O/C Al EX CS CS - 03 LT-X 2Y RHR PUMP DISCHARGE TO LOOP B COLD LEG MOV-721 PIT 2Y ST-O CS CS - 03 850A 2
N B
A 10 GTV MOV 1247 (F-4)
C O/C Al DIAG OMN1 EX 18M RHR PUMP SUCTION FROM CNMT SUMP B MOV-850A 850B 2
N B
A 10 GTV MOV 1247 (B-4)
C O/C Al DIAG OMN1 EX 18M RHR PUMP MOTOR OPERATED SUCTION FROM CNMT SUMP B 851A 2
Y B
P 10 GTV MOV 1247(B-1)
O O
PIT 2Y RHR PUMP MOTOR OPERATED SUCTION FROM CNMT SUMP B
.851B 2
Y B
P 10 GTV MOV 1247 (B-2)
O O
PIT 2Y RHR PUMP MOTOR OPERATED SUCTION FROM CNMT SUMP B Page 46 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table RHR - RESIDUAL HEAT REMOVAL Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 852A 1
N A
A 6
GTV MOV 1260 (F-4)
C O/C Al DIAG OMN1 EX CS RHR PUMP DISCHARGE TO REACTOR VESSEL DELUGE MOV-852A LT-X 2Y 852B 1
N A
A 6
GTV MOV 1260 (F-4)
C O/C Al DIAG OMN1 EX CS RHR PUMP DISCHARGE TO REACTOR VESSEL DELUGE MOV-852B LT-X 2Y 853A 1
N AC A
6 CV SAV 1260 (F-5)
C O/C NA CV-C R
ROJ - 03 CV-O R
ROJ - 03 RHR INLET CHECK VLV TO REACTOR VESSEL CORE DELUGE LT-XT R
GR-01 853B 1
N AC A
6 CV SAV 1260 (F-5)
C O/C NA CV-C R
ROJ - 03 CV-O R
ROJ - 03 RHR INLET CHECK VLV TO REACTOR VESSEL CORE DELUGE LT-XT R
GR-01 854 2
N C
A 10 CV SAV 1247 (G-4)
C O/C NA CV-C CMP CVCMP CV-0 R
RWST SUCTION CHECK VLV TO RHR PUMPS 856 2
N B
A 10 GTV MOV 1247 (G-5) 0 O/C Al DIAG OMN1 EX CS RHR PUMP MOTOR OPERATED SUCTION FROM RWST 857A 2
N B
A 6
GTV MOV 1247 (C-11)
C O/C Al DIAG OMN1 EX 18M RHR PUMP DISCHARGE MOTOR OPERATED VALVE TO SAFETY INJECTION PUMP SUCTION 857B 2
N B
A 6
GTV MOV 1247 (B-11)
C O/C Al DIAG OMN1 EX 18M RHR PUMP MOTOR OPERATED DISCHARGE TO SAFETY INJECTION PUMP SUCTION 857C 2
N B
A 6
GTV MOV 1247 (B-11)
C O/C Al DIAG OMN1 EX 18M RHR PUMP MOTOR OPERATED DISCHARGE TO SAFETY INJECTION PUMP SUCTION Page 47 of 64
Revision: 0 Valve ID Valve Description Class Aug.
Cat.
ATP Size Type 7141 2
N A
P 2
GTV SA MIDDLE ISOL VLV TO CONTAINMENT (INTER BLDG) 7226 2
N AC P
2 CV SERVICE AIR TO CONTAINMENT CHECK VALVE Constellation Energy (Ginna)
Valve Table SA - SERVICE AIR Actuator Drawing
Position --------
Requ Type
&.Coord Normal Safety Fail-Safe Tes MAN 1886-2 (C-3)
C C
LJ SAV 1886-2 (C-5)
C C
NA LJ Unit 1 ired st
-C Frequency RR/CSJ/ROJ Comments / Notes OPB OPB
-C Page 48 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SAFW - STANDBY AUXILIARY FEEDWA TER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 9629A 3
N B
A 4
GTV MOV 1238 (B-3)
C 0
Al DIAG OMN1 High Risk MOV per OMN-1 EX 0
SAFW PUMP C SUCTION VLV MOV-9629A 9629B 3
N B
A 4
GTV MOV 1238 (1-3)
C 0
SAFW PUMP D SUCTION VLV MOV-9629B 9700A 3
N C
A 3
CV SAV 1238 (B-6)
C O/C SAFW PUMP C DISCHARGE CHECK VALVE 9700B 3
N C
A 3
CV SAV 1238 (1-6)
C O/C SAFW PUMP D DISCHARGE CHECK VALVE 9701A 3
N B
A 3
GLV MOV 1238 (B-7) 0 0
SAFW PUMP C DISCHARGE VLV MOV-9701A 9701B 3
N B
A 3
GLV MOV 1238 (1-7) 0 0
SAFW PUMP D DISCHARGE VLV MOV-9701B 9703A 3
N B
A 3
GLV MOV 1238 (F-8)
C O/C STANDBY AUX FW PUMP CROSSOVER VLV MOV-9703A 9703B 3
N B
A 3
GLV MOV 1238 (F-8)
C O/C STANDBY AUX FW PUMP CROSSOVER VLV MOV-9703B 9704A 2
N BC A
3 SCV MOV 1238 (B-9)
C O/C STANDBY AUXILIARY FEEDWATER PUMP C MOTOR OPERATED STOP CHECK ISOLATION VALVE 9704B 2
N BC A
3 SCV MOV 1238 (1-9)
C O/C STANDBY AUX FW PUMP D ISOL VLV MOV-9704B 9705A 2
N C
A 3
CV SAV 1238 (B-10)
C O/C SAFW PUMP C DISC CHECK VALVE TO SG "A" 9705B 2
N C
A 3
CV SAV 1238 (1-10)
C O/C SAFW PUMP D DISC CHECK VALVE TO SG "B" Al NA NA Al Al Al Al Al DIAG EX CV-C CV-0 CV-C CV-0 DIAG EX DIAG EX DIAG EX DIAG EX CV-C CV-O DIAG EX OMNI CMP 2Y CMP 2Y OMN1 Q
OMN1 Q
OMN1 18M OMN1 18M CMP 2Y OMN1 R
High Risk MOV per OMN-1 CVCMP CVCMP High Risk MOV per OMN-1 High Risk MOV per OMN-1 CVCMP Al CV-C CMP CVCMP CV-0 2Y DIAG OMN1 EX R
NA CV-C CMP CVCMP CV-0 2Y NA CV-C CMP CVCMP CV-0 2Y Page 49 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table SAFW - STANDBY AUXILIARY FEEDWA TER Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
AJP Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 9707A 3
Y B
A 4
GTV MAN 1238 (E-4)
C 0
NA EX 2Y-AD SAFW PUMP CNDST TEST TANK ISOL VLV TO STANDBY AUX FW PUMP C 9707B 3
Y B
A 4
GTV MAN 1238 (H-4)
C 0
NA EX 2Y-AD SAFW PUMP CNDST TEST TANK ISOL VLV TO STANDBY AUX FW PUMP D 9708A 3
Y C
A 4
CV SAV 1238 (D-4)
C 0
NA CV-O 2Y-AD SAFW PUMP CNDST TEST TANK CHECK VLV TO STANDBY AUX FW PUMP C 9708B 3
Y C
A 4
CV SAV 1238 (H-4)
C 0
NA CV-O 2Y-AD SAFW PUMP CNDST TEST TANK CHECK VLV TO STANDBY AUX FW PUMP D 9709A 3
N C
A 1
RV SAV 1238 (B-3)
C O/C NA RT 10Y STANDBY AUX FW PUMP C SUCTION LINE RELIEF VLV 9709B 3
N C
A 1
RV SAV 1238 (1-3)
C O/C NA RT 10Y STANDBY AUX FW PUMP D SUCTION LINE RELIEF VLV 9710A 3
N B
A 1.5 GLV AOV 1238 (C-7)
C O/C 0
EX Q
FS-O Q
STANDBY AUX FW PUMP C RECIRCULATION VLV AOV-9710A PIT 2Y ST-C Q
ST-O Q
9710B 3
N B
A 1.5 GLV AOV 1238 (H-7)
C O/C 0
EX Q
FS-O Q
STANDBY AUX FW PUMP D RECIRCULATION VLV AOV-9710B PIT 2Y ST-C Q
ST-O Q
9721A 3
N C
A
.5 CV SAV 1238 (C-3)
C O/C NA CV-C Q
CV-O Q
CONDENSATE PRESSURIZATION CHECK VALVE TO SAFW PUMP "C" 9721B 3
N C
A
.5 CV SAV 1238 (G-3)
C O/C NA CV-C 0
CV-O Q
CONDENSATE PRESSURIZATION CHECK VALVE TO SAFW PUMP "d" 9728 SSC Y
B A
6 TWV MAN 1238 (G-4) 0 C
NA EX R-AD TCDO1 (STANDBY AFW PUMP CONDENSATE TEST TANK) OUTLET BLOCK VALVE (3 WAY VALVE)
Page 50 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SAFW - STANDBY AUXILIARY FEEDWA TER Actuator Drawing Position --------
Required Type
& Coord Normal Safety Fail-Safe Test Fr MOV 1238 (1-8) 0 O/C Al DIAG EX Unit 1 Valve ID Valve Valve ID Valve Description Class Aug.
Cat.
A/P Size Type 9746 3
N B
A 3
GTV EMERGENCY DISCHARGE MOV FOR PAF01B (SAFW PUMP D) equency RR/CSJ/ROJ Comments / Notes OMN1 Q
Page 51 of 64
Revision: 0 SF Valve ID Valve Actuator Valve ID Valve Actuator Description Class Aug.
Cat.
A/P Size Type Type 782 3
N B
A 4
GTV MAN 1
LOW SUCTION ISOL VLV TO SPENT FUEL POOL RECIRC PUMPS (ALT) 8152 2
N A
P 1
GTV MAN 1
PRESSURE TEST VALVE TO DOUBLE O-RING BLIND FLANGE SAC05 8614 3
N B
A 4
GTV MAN 1
SPENT FUEL POOL HEAT EXCHANGER A OUTLET ISOL VLV 8654 3
N B
A 6
GTV MAN 1
SUCTION BLOCK VLV TO SPENT FUEL POOL RECIRC PUMP A 8655 SSC N
C A
4 CV SAV 1
SPENT FUEL POOL RECIRC PUMP A DISCHARGE CHECK VLV 8657 3
Y B
A 8
GTV MAN SUCTION BLOCK VLV TO SPENT FUEL POOL RECIRC PUMP B 8658 3
N C
A 6
CV SAV SPENT FUEL POOL RECIRC PUMP B DISCHARGE CHECK VLV 8663 3
Y B
A 8
GTV MAN SPENT FUEL POOL HEAT EXCHANGER B OUTLET BLOCK VLV 8667 3
N B
A 6
GTV MAN ISOLATION GATE VALVE FROM SFP PUMP B TO SFP HEAT EXCHANGER B Constellation Energy (Ginna)
Valve Table PC - SPENT FUEL POOL COOL Drawing Position -------- Requ
& Coord Normal Safety Fail-Safe Tes 248 (D-1)
C 0
NA E
248 (C-5)
C C
NA LJ-248 (H-8) 0 O/C NA E
E:
248 (H-2) 0 O/C NA E
E; 248 (H-4)
C O/C NA CV CV 1248 (1-2) 0 O/C NA E
1248 (1-4)
C O/C NA CV CV 1248 (1-9) 0 O/C NA E
1248 (1-5)
C 0
NA E
Unit 1 ING ired t
X
-C X
X X
X
-C
-0 X
.C
-0 X
X Frequency RR/CSJ/ROJ Comments / Notes 2Y OPB 2Y 2Y 2Y 2Y Q
0 2Y-Q Q
2Y 2Y Page 52 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SGBD - S/G BLOWDOWN Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments ! Notes 5735 2
N A
A
.75 GTV AOV 1277-1 (A-4) 0 C
C EX 0
FS-C Q
STEAM GENERATOR A BLOWDOWN SAMPLE AIR OPERATED ISOLATION VALVE LT-X 2Y PIT 2Y ST-C 0
5736 2
N A
A
.75 GTV AOV 1277-1 (F-4) 0 C
C EX Q
FS-C Q
STEAM GEN B BLOWDOWN SAMPLE ISOL VLV AOV-5736 LT-X 2Y PIT 2Y ST-C Q
5737 2
N A
A 2
GTV AOV 1277-1 (H-5) 0 C
C EX Q
FS-C Q
STEAM GENERATOR B BLOWDOWN ISOLATION AIR OPERATED VALVE LT-X 2Y PIT 2Y ST-C Q
5738 2
N A
A 2
GTV AOV 1277-1 (C-5) 0 C
C EX Q
FS-C Q
STEAM GEN A BLOWDOWN ISOL VLV AOV-5738 LT-X 2Y PIT 2Y ST-C Q
Page 53 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SI - SAFETY INJECTION AND A CCUMULA TORS Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 12406 2
N A
P
.75 GTV MAN 1262-1 (B-7)
C C
NA LJ-C OPB INSTR ISOL VLV TO PI-922A (SI PMP A DISCH) 12407 2
N A
P
.75 GTV MAN 1262-1 (E-8)
C C
NA LJ-C OPB INSTR ISOL VLV TO PI-923A (SI PMP B DISCH) 1815A 2
N B
A 4
GTV MOV 1262-1 (D-4) 0 0
Al EX Q
PIT 2Y SI PUMP C SUCTION VALVE ST-O Q
1815B 2
N B
A 4
GTV MOV 1262-1 (D-3) 0 0
Al EX Q
PIT 2Y SI PUMP C SUCTION VALVE ST-O Q
1817 2
N C
A
.75 RV SAV 1262-1 (D-4)
C O/C NA RT ly SI PUMP C SUCTION RELIEF VLV TO CNMT SPRAY PUMP DISCHARGE 2817C 2
N A
P
.75 BAV MAN 1262-1 (F-7)
C C
NA LJ-C OPB SI ACCUMULATOR MAKEUP PUMP DISCHARGE ISOLATION VALVE 2817J 2
N AC P
.75 CV SAV 1262-1 (G-7)
C C
NA LJ-C OPB SI ACCUMULATOR MAKEUP PUMP DISCHARGE CHECK VALVE 830A 2
N C
A 1
RV SAV 1262-2 (A-6)
C O/C NA RT ly LOOP B ACCUMULATOR A RELIEF VLV 830B 2
N C
A 1
RV SAV 1262-2 (E-6)
C O/C NA RT lay LOOP A ACCUMULATOR B RELIEF VLV 834A 2
N B
P 1
GLV AOV 1262-2 (A-5)
C C
C PIT 2Y SI ACCUMULATOR A N2 AIR OPERATED FILL/VENT VALVE 834B 2
N B
P 1
GLV AOV 1262-2 (E-5)
C C
C PIT 2Y SI ACCUMULATOR B AIR OPERATED NITROGEN FILL/VENT VALVE 835A 2
N B
P 1
GLV AOV 1262-2 (C-4)
C C
C PIT 2Y SI ACCUMULATOR A AIR OPERATED FILL VALVE 835B 2
N B
P 1
GLV AOV 1262-2 (G-5)
C C
C PIT 2Y SI ACCUMULATOR B AIR OPERATED FILL VALVE Page 54 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table Unit 1 SI - SAFETY INJECTION AND ACCUMULATORS Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 839A 2
N B
P
.75 GLV AOV 1262-2 (C-8)
C C
C PIT 2Y SI ACCUMULATOR A TEST VALVE AOV-839A 839B 1
N B
P
.75 GLV AOV 1262-2 (D-8)
C C
C PIT 2Y SI LINE LOOP B TEST VALVE AOV-839B 840A 2
N B
P
.75 GLV AOV 1262-2 (G-7)
C C
C PIT 2Y SI ACCUMULATOR B TEST VALVE AOV-840A 840B 1
N B
P
.75 GLV AOV 1262-2 (H-7)
C C
C PIT 2Y SI LINE LOOP B TEST VALVE AOV-840B 841 2
N B
A 10 GTV MOV 1262-2 (C-7) 0 O/C Al DIAG OMN1 EX CS SI ACCUMULATOR A DISCH TO LOOP B MOV-841 842A 1
N AC A
10 CV SAV 1262-2 (D-7)
C O/C NA CV-C CMP CVCMP CV-O 6M-AD LOOP B ACCUMULATOR A DUMP LINE CHECK VLV CV-O 3R LT-X 2Y 842B 1
N AC A
10 CV SAV 1262-2 (G-7)
C O/C NA CV-C CMP CVCMP CV-O 6M-AD LOOP A ACCUMULATOR B DUMP LINE CHECK VLV CV-O 3R LT-X 2Y 844A 2
N B
P 1
GLV AOV 126ý-2 (C-8)
C C
C PIT 2Y SI ACCUMULATOR A DRAIN VALVE AOV-844A 844B 2
N B
P 1
GLV AOV 1262-2 (G-8)
C C
C PIT 2Y SI ACCUMULATOR B DRAIN VALVE AOV-844B 846 2
N A
A 1
GLV AOV 1262-1 (A-6)
C C
C EX Q
FS-C Q
ACCUM N2 SUPPLY ISOL VALVE AOV-846 LJ-C OPB PIT 2Y ST-C Q
8623 2
N AC A
1 CV SAV 1262-2 (A-3)
C C
NA BDT-O Normal Ops CVCMP CV-C OPB N2 INLET CHECK VLV TO ACCUMULATORS A & B LJ-C OPB Page 55 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table S1 - SAFETY INJECTION AND ACCUMULA TORS Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments /Notes 865 2
N B
A 10 GTV MOV 1262-2 (G-7) 0 O/C Al DIAG OMN1 EX CS SI ACCUMULATOR B DISCHARGE TO LOOP A MOTOR OPERATED VALV E 867A 1
N AC A
10 CV SAV 1262-2 (D-7)
C O/C NA CV-C R
CVCMP CV-O R
SI PUMP DISCHARGE AND ACCUMULATOR TANK A CHECK VALVE TO LOOP B COLD LEG CV-O 3R LT-XT R
GR-01 867B 1
N AC A
10 CV SAV 1262-2 (H-7)
C O/C NA CV-C R
CVCMP CV-O R
SI PUMP DISCHARGE AND ACCUMULATOR TANK B CHECK VALVE TO LOOP A COLD LEG CV-O 3R LT-XT R
GR-01 870A 2
N AC A
3 CV SAV 1262-1 (C-7)
C O/C CV-C Q
CV-O R
ROJ - 05 SI PUMP C DISCHARGE CHECK VLV TO LOOP B COLD LEG LJ-C OPB 870B 2
N AC A
3 CV SAV 1262-1 (E-7)
C O/C CV-C Q
CV-O R
ROJ - 05 SI PUMP C DISCHARGE CHECK VLV TO LOOP A COLD LEG LJ-C OPB 871A 2
N B
A 3
GTV MOV 1262-1 (D-7) 0 O/C Al DIAG OMN1 EX 18M SI PUMP C DISCHARGE TO LOOP B MOV-871A 871B 2
N B
A 3
GTV MOV 1262-1 (E-7) 0 O/C Al DIAG OMN1 EX 18M SI PUMP C DISCHARGE TO LOOP A MOV-871 B 872A 2
N C
A
.75 CV SAV 1262-2 (C-2)
C 0
NA CV-C Q
CV-O Q
SI PUMP A TEST LINE CHECK VLV (IN CNMT) 872B 2
N C
A
.75 CV SAV 1262-2 (1-3)
C 0
NA CV-C Q
CV-0 0
SI PUMP B TEST LINE CHECK VLV (IN CNMT) 877A 1
N AC P
2 CV SAV 1262-2 (E-3)
C C
NA LT-XT 40 MO GR -01 SI PUMP A DISCHARGE CHECK VLV TO LOOP B HOT LEG 877B 1
N AC P
2 CV SAV 1262-2 (1-6)"
C C
NA LT-XT 40 MO GR - 01 SI PUMP B DISCHARGE CHECK VLV TO LOOP A HOT LEG 878A 2
N A -
P 2
GLV MOV 1262-2 (E-3)
C C
Al LT-XT 40 MO GR -01 PIT 2Y SI PUMP A DISCHARGE TO LOOP B HOT LEG MOV-878A Page 56 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SI - SAFETY INJECTION AND ACCUMULA TORS Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 878B 2
N B
P 2
GLV MOV 1262-2 (D-4) 0 0
Al PIT 2Y SI PUMP A DISCHARGE TO LOOP B COLD LEG MOTOR OPERATED VA LVE 878C 2
N A
P 2
GLV MOV 1262-2 (1-5)
C C
Al LT-XT 40 MO GR-01 PIT 2Y SI PUMP B DISCHARGE TO LOOP A HOT LEG MOV-878C 878D 2
N B
P 2
GLV MOV 1262-2 (H-5) 0 0
Al PIT 2Y SI PUMP B DISCHARGE TO LOOP A COLD LEG MOV-878D 878F 1
N AC P
2 CV SAV 1262-2 (E-3)
C C
NA LT-XT 40 MO GR -01 SI PUMP A DISCHARGE CHECK VLV TO LOOP B HOT LEG 878G 1
N AC A
2 CV SAV 1262-2 (D-5)
C O/C NA CV-C R
ROJ - 04 CV-O R
ROJ - 04 SI PUMP A DISCHARGE CHECK VLV TO LOOP B COLD LEG LT-XT R
GR-01 878H 1
N AC P
2 CV SAV 1262-2 (1-6)
C C
NA LT-XT R
GR-01 SI PUMP B DISCHARGE CHECK VLV TO LOOP A HOT LEG 878J 1
N AC A
2 CV SAV 1262-2 (H-6)
C O/C NA CV-C R
ROJ - 04 CV-O R
ROJ - 04 SI PUMP B DISCHARGE CHECK VLV TO LOOP A COLD LEG LT-XT R
GR-01 879 2
N A
P
.75 GLV MAN 1262-1 (G-5)
C C
NA LJ-C OPB INLET ISOL VLV TO TEST FLOW INDICATORS FI-929 & FI-929A 885A 2
N A
A
.75 GLV MAN 1262-1 (C-7) 0 OC NA EX 2Y LJ-C OPB INSTR ROOT VLV TO PT-922 & PI-922A (SI PMP A DISCH) 885B 2
N A
A
.75 GTV MAN 1262-1 (F-8) 0 OC NA EX 2Y LJ-C OPB INSTR ROOT VLV TO PT-923 & PI-923A (SI PMP B DISCH) 887 2
N C
A
.75 TRV SAV 1262-2 (H-8)
C OC NA RT ly LOOP A ACCUMULATOR B TEST LINE RELIEF VLV TO PRT (IN CNMT) 889A 2
N AC A
3 CV SAV 1262-1 (C-5)
C O/C NA CV-C Q
CV-O R
ROJ - 05 SI PUMP A DISCHARGE CHECK VLV LJ-C OPB Page 57 of 64
Revision: 0 Valve ID Valve Valve ID Description Class Aug.
Cat.
A/P Size 889B 2
N AC A
3 SI PUMP B DISCHARGE CHECK VLV 891A 2
N C
A 1.5 SI PUMP A RECIRC LINE CHECK VLV TO RWST 8911B 2
N C
A 1.5 SI PUMP C RECIRC LINE CHECK VLV TO RWST 891C 2
N C
A 1.5 SI PUMP B RECIRC LINE CHECK VLV TO RWST Valve Type CV Constellation Energy (Ginna)
Valve Table SI - SAFETY INJECTION AND ACCUMULATORS Actuator Drawing Position -------- Required Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes SAV 1262-1 (F-6)
C 0/C NA CV-C Q
CV-O R
ROJ - 05 LJ-C OPB SAV 1262-1 (B-3)
C O/C NA CV-C Q
CV-O Q
SAV 1262-1 (D-5)
C O/C NA CV-C Q
CV-0 Q
SAV 1262-1 (E-5)
C O/C NA CV-C 0
CV-0 Q
Unit 1 CV CV CV Page 58 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SW - SERVICE WATER Unit 1 Valve ID Valve Actuator Drawing
......... Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4561 3
N B
A 14 BFV AOV 1250-3 (G-9) 0 0
0 EX Q
FS-O Q
CONTAINMENT COOLERS SW OUTLET FLOW CONTROL AOV ST-0 Q
4562 3
N B
A 14 BFV AOV 1250-3 (G-10)
C 0
0 EX Q
FS-0 0
AIR OPERATED BYPASS OF VALVE 4561 (CONTAINMENT FAN COOLERS SW OUTLET FLOW CONTROL ST-0 0
AOV) 4601 3
N C
A 14 NCV SAV 1250-1 (D-2)
O/C O/C NA CV-C R
CV-C 0
NOZZLE CHECK VALVE FOR SERVICE WATER PUMP "A" DISCHARGE CV-O Q
4602 3
N C
A 14 NCV SAV 1250-1 (E-2)
NOZZLE CHECK VALVE FOR SERVICE WATER PUMP "B" DISCHARGE 4603 3
N C
A 14 NCV SAV 1250-1 (F-2)
NOZZLE CHECK VALVE FOR SERVICE WATER PUMP "C" DISCHARGE 4604 3
N C
A 14 NCV SAV 1250-1 (G-2)
NOZZLE CHECK VALVE FOR SERVICE WATER PUMP "D" DISCHARGE 4609 3
N B
A 8
BFV MOV 1250-1 (C-2)
SCREENHOUSE SW ISOL VLV MOV-4609 4613 3
N B
A 10 BFV MOV 1250-1 (D-6)
TURBINE BUILDING SERVICE WATER ISOLATION MOTOR OPERATED VALVE 4614 3
N B
A 10 BFV MOV 1250-3 (H-2)
TURBINE BUILDING SERVICE WATER ISOLATION MOTOR OPERATED VALVE 4615 3
N B
A 20 GTV MOV 1250-1 (J-9)
AUX BLDG SW ISOL VLV MOV-4615 4616 3
N B
A 20 GTV MOV 1250-1 (A-9)
AUX BLDG SW ISO VLV MOV-4616 4619C 3
N B
A 12 GTV MAN 1250-2 (F-6)
CCW HX A REDUNDANT SW OUTLET ISOL VLV O/C O/C O/C 0
0 0
0 0
C O/C O/C O/C C
C C
O/C O/C 0
NA NA NA Al Al Al Al Al NA CV-C CV-C CV-0 CV-C CV-C CV-0 CV-C CV-C CV-0 DIAG EX DIAG EX DIAG EX DIAG EX DIAG EX EX Q
R Q
R Q
Q R
0 OMN1 18M OMN1 18M OMN1 18M OMN1 18M OMN1 1 8M 2Y Page 59 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SW-SERVICE WATER Unit 1 Valve ID Valve Actuator Drawing Position --------
Required Description Class Aug.
Cat.
AJP Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4620B 3
N B
A 12 GTV MAN 1250-2 (E-6)
C 0
NA EX 2Y CCW HX B REDUNDANT SW OUTLET ISOL MOV 4622 3
Y B
A 6
GLV MAN 1250-2 (H-8) 0 O/C NA EX 3R-AD SFP HX A SW OUTLET ISOL VLV 4622A 3
Y B
A 6
GTV MAN 1250-2 (H-7)
C 0
NA EX 2Y SFP HX A REDUNDANT SW OUTLET ISOL VLV 4629 2
N A
A 8
BFV MAN 1250-3 (B-7) 0 O/C NA EX 2Y LT-X 2Y SERVICE WATER OUTLET BLOCK VALVE FOR ACA01A, ACA01 E, ACA01 F (CONTAINME NT RECIRCULATING FAN A COOLERS) & ACA10 (CNMT RECIRC FAN A MTR CLR) 4630 2
N A
A 8
BFV MAN 1250-3 (C-7) 0 O/C NA EX 2Y LT-X 2Y SERVICE WATER OUTLET BLOCK VALVE FOR ACA01B, ACA01G, ACA01H (CONTAINME NT RECIRCULATING FAN B COOLERS) & ACA07 (CNMT RECIRC FAN B MTR CLR) 4635 2
N B
A 8
BFV MAN 1250-3 (D-7) 0 C
NA EX 2Y SW INLET BLOCK VLV TO REACTOR COMPARTMENT COOLER B 4636 2
N A
A 2.5 BFV MAN 1250-3 (F-7) 0 C
NA EX 2Y LT-X 2Y REACTOR COMPARTMENT COOLER B SW OUTLET BLOCK VLV 4643 2
N A
A 8
BFV MAN 1250-3 (G-7) 0 O/C NA EX 2Y LT-X 2Y SERVICE WATER OUTLET BLOCK VALVE FOR ACA01C, ACA01J, ACA01K, (CONTAINM ENT RECIRCULATING FAN C COOLERS) & ACA08 (CNMT RECIRC FAN C MTR CLR) 4644 2
N A
A 8
BFV MAN 1250-3 (H-7) 0 O/C NA EX 2Y LT-X 2Y SERVICE WATER OUTLET BLOCK VALVE FOR ACA01 D, ACA01 L, ACA01 M, (CONTAINM ENT RECIRCULATING FAN D COOLERS) & ACA09 (CNMT RECIRC FAN D MTR CLR) 4653 3
N C
A
.75 TRV SAV 1250.2 (F-6)
C 0
NA RT 10Y CCW HX A SW OUTLET RELIEF VLV 4654 3
N C
A
.75 TRV SAV 1250-2 (D-6)
C 0
NA RT 10Y CCW HX B SW OUTLET RELIEF VLV 4655 2
N AC A
.75 RV SAV 1250-3 (A-7)
C O/C NA LT-X 2Y RT 10Y CONTAINMENT RECIRC FAN A COOLER SW OUTLET RELIEF VLV Page 60 of 64
Revision: 0 Constellation Energy (Ginna)
Unit 1 Valve Table SW - SER VICE WATER Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4656 2
N AC A
.75 RV SAV 1250-3 (C-7)
C O/C NA LT-X 2Y RT 10Y CONTAINMENT RECIRC FAN B COOLER SW OUTLET RELIEF VLV 4657 3
Y C
A
.75 TRV SAV 1250-2 (H-8)
C SFP HX A SW OUTLET RELIEF VLV 4658 2
N AC A
.75 RV SAV 1250-3 (E-7)
C REACTOR COMPARTMENT COOLER B SW OUTLET RELIEF VLV 4659 2
N AC A
.75 RV SAV 1250-3 (G-7)
C CONTAINMENT RECIRC FAN C COOLER SW OUTLET RELIEF VLV 4660 2
N AC A
.75 RV SAV 1250-3 (H-7)
C CONTAINMENT RECIRC FAN D COOLER SW OUTLET RELIEF VLV 4663 3
N B
A 6
GTV MOV 1250-3 (1-3) 0 AIR CONDITIONING SERVICE WATER MOTOR OPERATED ISOLATION VALVE 4664 3
N B
A 10 GTV MOV 1250-3 (H-2) 0 TURBINE BLDG SW ISOL VLV MOV-4664 4670 3
N B
A 10 GTV MOV 1250-1 (D-5) 0 TURBINE BLDG SW ISOL VLV MOV-4670 4717 3
N C
A
.75 TRV SAV 1250-1 (D-7)
C D/G A HX'S SW OUTLET RELIEF VLV 4718 3
N C
A
.75 TRV SAV 1250-1 (H-5)
C D/G B HX'S SW OUTLET RELIEF VLV 4733 3
N B
A 6
BFV MOV 1250-3 (1-3) 0 AIR CONDITIONING SW ISOL VLV MOV-4733 4734 3
N B
A 14 BFV MOV 1250-2 (E-3) 0 AUXILIARY BUILDING SERVICE WATER ISOLATION MOTOR OPERATED VALVE 4735 3
N B
A 18 BFV MOV 1250-2 (B-2) 0 AUXILIARY BUILDING SERVICE WATER ISOLATION MOTOR OPERATED VALVE O/C NA RT LT-X RT LT-X RT LT-X RT DIAG EX DIAG EX DIAG EX RT RT DIAG EX DIAG EX DIAG EX 10Y 2Y 10Y 2Y 10Y 2Y 10Y OMNI 18M OMN1 18M OMNI 18M 10Y 10Y OMNI 18M OMNI 18M OMNI 18M C
Al O/C Al Page 61 of 64 Page 61 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SW - SERVICE WATER Unit 1 Valve ID Valve Actuator Drawing Position -------- Required Description Class Aug.
Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Test Frequency RR/CSJ/ROJ Comments / Notes 4739B 3
N B
A 3
GTV MAN 1250-1 (B-11)
C 0
NA EX 2Y AUX BLDG MOTOR COOLERS SW OUTLET ISOL VLV (REDUNDANT) 4757 2
N B
A 8
BFV MAN SW INLET BLOCK VLV TO REACTOR COMPARTMENT COOLER A 4758 2
N A
A 2.5 BFV MAN REACTOR COMPARTMENT COOLER A SW OUTLET BLOCK VLV 4759 2
N AC A
.75 RV SAV REACTOR COMPARTMENT COOLER A SW OUTLET RELIEF VLV 4770 3
Y C
A
.75 TRV SAV CNMT PENETRATION COOLER SW OUTLET RELIEF VLV 4770A 3
N C
A
.75 TRV SAV RHR PUMP COOLING FAN A SW OUTLET RELIEF VLV 4770B 3
N C
A
.75 TRV SAV RHR PUMP COOLING FAN B SW OUTLET RELIEF VLV 4770F 3
Y C
A
.75 TRV SAV CHARGING PUMP ROOM COOLER A SW OUTLET RELIEF VLV 4770G 3
Y C
A
.75 TRV SAV CHARGING PUMP ROOM COOLER B SW OUTLET RELIEF VLV 4780 3
N B
A 8
BFV MOV SCREEN HOUSE SW ISOL VLV MOV-4780 8681 3
N C
A
.75 TRV SAV SFP HX B SW OUTLET RELIEF VLV 8689 3
Y B
A 10 BFV MAN 1250'3 (E-7) 1250-3 (D-7) 1250-3 (D-7) 1250-1 (H-10) 1250-1 (E-10) 1250-1 (D-10) 1250-1 (E-10) 1250-1 (F-10) 1250-1 (C-2) 1250-2 (C-8)
C C
O/C 0
0 0
0 0
C 0
NA NA NA NA NA NA NA NA Al NA EX EX LT-X LT-X RT RT RT RT RT RT DIAG EX RT 2Y 2Y 2Y 2Y 10Y laY 10Y 10Y 10Y 10Y OMNI 18M 10Y 1250-2 (E-9) 0 O/C NA EX 3R-AD SFP HX B SW OUTLET ISOL VLV 9627A 3
N C
A 4
CV SAV 1250-2 (A-6)
C O/C NA CV-P CMP CVCMP DI CMP SW INLET CHECK VLV TO STANDBY AUX FW PUMP ROOM Page 62 of 64
Revision: 0 Constellation Energy (Ginna)
Valve Table SW-SERVICE WATER Valve ID Valve Actuator Drawing
......... Position -------- Requ Description Class Aug. Cat.
A/P Size Type Type
& Coord Normal Safety Fail-Safe Tes 9627B 3
N C
A 4
CV SAV 1250-2 (B-6)
C O/C NA CV D
SW INLET CHECK VLV TO STANDBY AUX FW PUMP ROOM 9632A 3
N B
A 1.5 GTV AOV 1250-2 (E-9)
C 0
0 E
FS-SAFW PUMP ROOM COOLING UNIT A SW OUTLET FLOW CONTROL AOV ST-9632B 3
N B
A 1.5 GTV AOV 1250-2 (E-10)
C 0
0 E
FS-SAFW PUMP ROOM COOLING UNIT B SW OUTLET FLOW CONTROL AOV ST-9634B 3
N B
A 2
GLV MAN 1250-2 (F-10)
C 0
NA E
SAFW PUMP ROOM CLG UNITS A & B SW ISOL VLV TO RETURN HDR Unit 1 i red
- t
-P x
0 0
Frequency RR/CSJ/ROJ Comments / Notes CMP CVCMP CMP Q
Q Q
Q Q
2Y K
- 0 0
Page 63 of 64
Revision: 0 Constellati6n Efiergy (Ginna)
Valve Table WDG - WASTE DISPOSAL - GA Drawing Position -------- Requ
& Coord Normal Safety Fail-Safe Tes 1273-2 (1-3)
C C
C E
Unit 1 Valve ID Valve Actuator Description Class Aug.
Cat.
A/P Size Type Type 14 SSC Y
B A
2 GLV AOV GAS DECAY TANK RELEASE AOV TO PLANT VENT VIA CHARCOAL FILTEI S
ired t
-C T
Frequency RR/CSJ/ROJ Comments / Notes Q
Q 2Y R
FS PI Page 64 of 64
Constellation Energy (Ginna)
Pump Matrix SYSTEM: AFW - AUXILIARY FEEDWATER Test Parameters Code Disc.
I Code Component PID(Coord)
Class Group Press DP Flow VIB Speedi Freg Dev.
Comments PAF01 A 1237 (B-5) 3 A
No Yes No Yes No Q
PR - 02 Relief is for flow rate measurement AUXILIARY FEEDWATER PUMP A No Yes Yes Yes No 2Y PAF01 B 1237 (E-5) 3 A
No Yes No Yes No Q
PR - 02 Relief is for flow rate measurement AUXILIARY FEEDWATER PUMP B No Yes Yes Yes No 2Y PAF03 1237 (1-5) 3 B
No Yes Yes No Yes Q
TURBINE DRIVEN AUXILIARY FEEDWATER PUMP No Yes Yes Yes Yes 2Y 1
Constellation Energy (Ginna)
Pump Matrix SYSTEM: CCW - COMPONENT COOLING WATER Test Parameters Code Disc.
Code Component PID(Coord)
Class Group Press DP Flow VIB Speedl Freg Dev.
Comments PAC02A 1245 (D-5) 3 A
No Yes Yes Yes No Q
COMPONENT COOLING WATER PUMP A No Yes Yes Yes No 2Y PAC02B 1245 (E-5) 3 A
No Yes Yes Yes No Q
COMPONENT COOLING WATER PUMP B No Yes Yes Yes No 2Y 2
Constellation Energy (Ginna)
Pump Matrix SYSTEM: CS - CONTAINMENT SPRAY Test Parameters Code Disc.
I Code Component PID(Coord)
Class Group Press DP Flow VIB Speedi Freg Dev.
Comments PSI02A 1261 (E-3) 2 B
No Yes Yes No No Q
CONTAINMENT SPRAY PUMP A No Yes Yes Yes No 2Y PSI02B 1261 (1-3) 2 B
No Yes Yes No No Q
CONTAINMENT SPRAY PUMP B No Yes Yes Yes No 2Y 3
Constellation Energy (Ginna)
Pump Matrix SYSTEM: CVCS - CVCS CHARGING Component PCH01A CHARGING PUMP A PCH01B CHARGING PUMP B PCHO1C CHARGING PUMP C PID(Coord) 1265-2 (E-5) 1265-2 (G-5) 1265-2 (H-5)
Code Class 2
2 2
Group A
A A
Disc.
Press Yes Yes Yes Test Parameters DP Flow VIB No Yes Yes No Yes Yes No Yes Yes Speeds Yes Yes Yes Code Freg Dev.
Q Comments Augmented Component Augmented Component Augmented Component Q
4
Constellation Energy (Ginna)
Pump Matrix SYSTEM: EDG - EMERGENCY DIESEL GENERATOR Test Parameters Code Disc.
S
]
Code Component PID(Coord)
Class Group IPress DP Flow VIB Speed Freg Dev.
Comments PDG02A 1239-1 (1-3) 3 B
Yes No Yes No No Q
PR - 01 Relief is for flow rate measurement DIESEL GENERATOR A FUEL OIL TRANSFER PUMP Yes No Yes Yes No 2Y PDG02B 1239-2 (1-9) 3 B
Yes No Yes No No Q
PR - 01 Relief is for flow rate measurement DIESEL GENERATOR B FUEL OIL TRANSFER PUMP Yes No Yes Yes No 2Y 5
Constellation Energy (Ginna)
Pump Matrix SYSTEM: RHR - RESIDUAL HEAT REMOVAL Test Parameters Code Disc.
i Code Component PID(Coord)
Class Group Press DP Flow VIB Speedi Freg Dev.
Comments PAC01A 1247 (F-5) 2 A
No Yes Yes Yes No Q
RESIDUAL HEAT REMOVAL PUMP A No Yes Yes Yes No 2Y PAC01B 1247 (B-5) 2 A
No Yes Yes Yes No Q
RESIDUAL HEAT REMOVAL PUMP B No Yes Yes Yes No 2Y 6
Constellation Energy (Ginna)
Pump Matrix SYSTEM: SAFW - STANDBY AUXILIARY FEEDWATER Code r
Component PID(Coord)
Class Group PSF01A 1238 (B-5) 3 B
STANDBY AUXILIARY FEEDWATER PUMP C PSFO1B 1238 (1-5) 3 B
STANDBY AUXILIARY FEEDWATER PUMP D Disc.
Press No No No No Test Parameters DP Flow VIB Yes No No Yes Yes Yes Yes No No Yes Yes Yes SpeedN No No No No Freg Q
2Y Q
2Y Code Dev.
Comments PR - 02 Relief is for flow rate measurement PR - 02 Relief is for flow rate measurement 7
Constellation Energy (Ginna)
Pump Matrix SYSTEM: SFPC - SPENT FUEL POOL COOLING Test Parameters Code Disc.
Code Component PID(Coord)
Class Group Press DP Flow VIB Speed Freg Dev.
Comments PAC07A 1248 (H-3)
SSC A
No Yes Yes Yes No Q
Augmented Component SPENT FUEL POOL RECIRCULATION PUMP A PAC07B 1248 (1-3) 3 A
No Yes Yes Yes No Q
SPENT FUEL POOL RECIRCULATION PUMP B No Yes Yes Yes No 2Y 8
Constellation Energy (Ginna)
Pump Matrix SYSTEM: SI - SAFETY INJECTION AND ACCUMULATORS Test Parameters Code Disc.
I Code Component PID(Coord)
Class Group Press DP Flow VIB Speedi Freg Dev.
Comments PSI01A 1262-1 (C-4) 2 B
No Yes Yes No No 0
SAFETY INJECTION PUMP A No Yes Yes Yes No 2Y PSI01B 1262-1 (F-4) 2 B
No Yes Yes No No Q
SAFETY INJECTION PUMP B No Yes Yes Yes No 2Y PSI01C 1262-1 (D-4) 2 B
No Yes Yes No No Q
SAFETY INJECTION PUMP C No Yes Yes Yes No 2Y 9
Constellation Energy (Ginna)
Pump Matrix SYSTEM: SW - SERVICE WATER Test Parameters Code Disc.
Code Component PID(Coord)
Class Group Press DP Flow VIB Speed Freg Dev.
Comments PSWO1A 1250-1 (D-2) 3 A
No Yes Yes Yes No 0
SERVICE WATER PUMP A No Yes Yes Yes No 2Y PSWO1B 1250-1 (E-2) 3 A
No Yes Yes Yes No Q
SERVICE WATER PUMP B No Yes Yes Yes No 2Y PSWO1C 1250-1 (F-2) 3 A
No Yes Yes Yes No Q
SERVICE WATER PUMP C No Yes Yes Yes No 2Y PSWO1D 1250-1 (G-2) 3 A
No Yes Yes Yes No Q
SERVICE WATER PUMP D No Yes Yes Yes No 2Y 10