ML20094J242
| ML20094J242 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/13/1995 |
| From: | Clint Jones POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20094J238 | List: |
| References | |
| PROC-950913, NUDOCS 9511150192 | |
| Download: ML20094J242 (150) | |
Text
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l JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES SECOND INTERVAL ,
Revision 9 Effective Date blh-Ob Prepared by: Date: S-hl-C. Jones /ISTEQineer Reviewed by: Date: f- /2 "
A.'Giverson/ System Eng. Support Lead Approved by: d Date: 9 - /J - 96 F. Edler/ Tech. Services Dept. Manager Authorized
'for use by: /
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Date: 9/ lJ/ f' -
/ / l H.' Salmon / Site Executive Officer ' '
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9511150192 951102 )
PDR ADOCK 05000333 P PDR t .. n- )
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 1 i
Table of Contents ;
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- 1. INTRODUCTION....................................... .. 3
- 2. APPLICABLE DOCUMENTS..... ............................ 3 )
- 3. INSERVICE TESTING PROGRAM FOR PUMPS................... 4 I l
- 4. INSERVICE TESTING PROGRAM FOR VALVES.................. 5 '
- 5. SYSTEMS SUBJECT TO TESTING............................ 7 1
l APPENDIX A - PUMP TESTING PROGRAM.......................... 8 I s
APPENDIX B - VALVE TESTING PROGRAM........................ 35 APPENDIX C -
SUMMARY
OF CHANGES.......................... 148 O
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t NEW YORK POWER AUTHORITY l L JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l
1.0 INTRODUCTION
Revision 9 of the James A. FitzPatrick ASME Inservice Testing i i (IST) Program will be in effect through the end of the second I interval unless changed and re-issued for reasons other than ;
the routine update required at the start of the third interval per 10 CFR 50.55a (f) . The third inspection interval begins in l September of 1996, reflecting a 14 extension approved by the NRC in a letter from J.E. Menning to W.J. Cahill on 10/26/94.
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l This document outlines the IST Program for J.A. Fitzpatrick '
l based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition, through Winter 1981 Addenda (the Code). References in this document to "IWP" or "IWV" correspond to Subsections IWP and IWV, respectively, of the Code, unless otherwise noted.
2.0 APPLICABLE DOCUMENTS This IST Program Plan was developed per the requirements of the following documents:
e Title 10, Code of Federal Regulations, Part 50 e Final Safety Analysis Report, J.A. Fitzpatrick Nuclear l Power Plant
/~ e b] e J.A. FitzPatrick Technical Specifications ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through Winter 1981 Addenda, e NRC Safety Evaluation by the Office of Nuclear Reactor Regulation related to the Inservice Testing Program Relief Requests Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant Docket No. 50-333, Dated January 8, 1992.
e Safety Evaluation for Inservice Testing (IST) Program Relief Requests, James A. FitzPatrick Nuclear Power Plant, Dated July 28, 1992.
Other documents used for guidance in the development of the IST Program are listed below:
e NRC Regulatory Guide 1.26, " Quality Group Classifications and Standards for Water , Steam , and Radioactive-Waste-Contaminating Components of Nuclear Power Plants" e Standard Review Plan NUREG 0800, Section 3.9.6,
" Inservice Testing of Pumps and Valves" e NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" p) e NRC Minutes of the Public Meetings on Generic Letter 89-04 Rev. No. 9 Page 3 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l [) 3.0 INSERVICE TESTING PROGRAM FOR PUMPS L ,/
3.1 Code Compliance This IST Program for pumps is based on the requirements of Subsection IWP of the Code and any Code interpretations. Where these requirements have been determined'to be impractical, conformance would cause unreasonable hardship without any compensating increase ;
in safety, or an alternative test provides an acceptable i level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a (g) (iii) .
3.2 Allowable Ranoes of Test Ouantities 1
The allowable ranges for test parameters as specified in I Table IWP-3100-2 will be used for all measurements of l pressure, flow, and vibration except as provided for in I specific relief requests approved by the NRC. In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP-3100-2. l p 3.3 Testino Intervals LJ \
The test frequency for pumps included in the IST Program )
will be as set forth in 1WP-3400. A band of 125 percent of the test interval may be applied to a test schedule as !
allowed by the J.A Fitzpatrick Technical Specifications j to provide for operational flexibility.
3.4 Pumo Procram Table Appendix A lists those pumps included in the IST Program with references to parameters to be measured and applicable requests for relief. -
3.5 Relief Recuests for Pump Testing Appendix A includes relief requests related to pump testing.
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l NEW YORK POWER AUTHORITY
! JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES t
! bj 4.0 INSERVICE TESTING PROGRAM FOR VAIdFag 4.1 Code Comoliance i
This IST Program for valves is based on the requirements of Subsection IWV of the code and any Code interpretations or additional requirements imposed by Generic Letter 89-04. Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of
'10 CFR- 50. 55a (g) (iii) and Generic Letter 89-04.
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4.2 Testina Intervals The test frequency for valves included in the IST Program 3 will be as set forth in IWV-3400, IWV-3500 and related i relief requests. A band of 125 percent of the test 1 interval may be applied to a test schedule as allowed by the J. A. Fitzpatrick Technical Specifications to provide l for operational flexibility. Where quarterly testing of valves is impractical or otherwise undesirable, testing p
y may be permitted by performed during cold shutdown periods as IWV-3412 (a) . Justifications for this deferred testing are provided in Appendix B with j elaboration of J. A. Fitzpatrick plant policy set forth in !
l Relief Request NOTE V51.
l l 4.3 Stroke Time Acceptance Criteria i
l The acceptance criteria for the stroke times of power-
! operated valves will be as set forth in IWV-3410 and l- using the guidance of Generic Letter 89-04, 4.4 Check Valve Testina Full-stroke exercising of check valves to the open position using system flow requires that a test be ,
performed whereby the predicted full accident condition i flowrate through the valve be verified and measured. Any i deviation to this requirement must satisfy the requirements of Generic Letter 89-04, Position 1.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
- [D 4.5 Valve Procram Table U
Appendix B lists those valves included in the IST Program ,
with references to required testing, respective test l intervals, applicable requests for relief and cold :
shutdown justifications.
4.6 Relief Recuests for Valve Testina l
Appendix B includes all relief requests and cold shutdown ;
justifications related to valve testing. l l
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NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM-FOR PUMPS AND VALVES i I
5.0 SYSTEMS SUBJECT TO TESTING DRAWING i SYSTEM # SYSTEM NAME #
01-125 Standby Gas Treatment FM-48A l 02-2 Reactor Water Recirculation' FM-26A 02-3 Nuclear Boiler Instrumentation FM-47A 03 Control Rod Drive FM-27B 07 Neutron Tip Monitors FM-119A 10 Residual Heat Removal FM-20A FM-20B 11 Standby Liquid Control FM-21A 12 Reactor Water Cleanup FM-24A 13 Reactor Core Isolation Cooling FM-22A 14 Core Spray FM-23A 15 Reactor Building Closed Loop FM-15A Cooling FM-15B 16-1 Leak Rate Analyzer FM-49A 19 Fuel Pool Cooling FM-19A 20 Radioactive Waste FM-17A 23 High Pressure Cooling injection FM-25A 27 Containment Atmosphere Dilution FM-18A i FM-18B FM-18D ,
i 29 Main Steam FM-29A i 34 Feedwater FM-34A 1
39 Breathing, Instrument & Service FM-39C i Air 46 Service & Emergency Service Water FM-46A FM-46B 66 Reactor Building Service Water FB-10H 70 Control Room Service & Chill Water FB-35E O
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NEW YORK POWER AUTHORITY JAMES ~A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES O APPENDIX A l
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l PUMP TESTING PROGRAM O ,
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES t
t APPENDIX A v- '
PUMP TESTING PROGRAM 4 t
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Table of Contents .
Pump Table Explanation ....................................... 10 Pump Table.................................................... 11 Relief Requests............................................... 12 I
NOTE P1: WITHDRAWN......................................... 12 NOTE P2: RHRSW and Emergency. Service Water................. 13 NOTE P3: WITHDRAWN ........................................ 14 NOTE P4: WITHDRAWN ........................................ 14 NOTE PS: RHRSW and Emergency Service Water................. 15 NOTE P6: WITHDRAWN......................................... 16 NOTE P7: Standby Liquid Control............................ 17 NOTE P8 WITHDRAWN......................................... 18 NOTE P9: RHRSW and Emergency Service Water................. 19 g NOTE P10: WITHDRAWN......................................... 20 J NOTE P11: Core Spray........................................ 21 NOTE P12: Standby Liquid _ Control............................ 23 NOTE P13: Standby Liquid Control............................ 24
. NOTE P14: Generic - Bearing Temperature Measurements........ 28 NOTE P15: WITHDRAWN......................................... 30 NOTE P16: Generic - Suction Pressure Measurement............ 31 NOTE P17: Generic - Digital Instruments..................... 33 NOTE P18: WITHDRAWN ........................................ 34 O
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Rev. No. 9 Page 9 of 150
NEW YORK POWER AUTHORITY-
' JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES O y APPENDIX A PUMP TABLE EXPLANATION Summary of Information Provided The Pump Table provides the following information:
- Individual pump identifier
- Test' type -
" Design" refers to tests where design or substantial flowrate is achieved. -
- The drawing on which the pump appears
- Drawin{)
Speed coordinates
- Inlet pressure (')
- Flow rate (3)
- Vibration amplitude ")
- Observation of lube oil level ()
- Test interval
- Bearing temperature ()
() These parameters .are each addressed with either- an "X" indicating - the parameter is . measured, an "X" with a note
'hy v
number indicating the parameter 'is measured but with some-
-exception to the Code, or by a note number indicating relief is requested to eliminate measurement of the parameter. A blank indicates that measurement of the reapective parameter is not applicable.
Pumo Relief Recuests Notes PXX refer to relief requests for the Pump Testing Program.
Each pump request for relief provides the following information:
- System
- Individual pump identifier
- ISI Classification
- Safety Function
- . Code test requirement for which relief is requested
- Basis for relief
- Proposed alternate testing d
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YORK P O 1/ E R -AUTHORITY JAMES A FITEPATRICK NUCLEAR : POWER PLANT INSERVICE TESTINO PROGRAM F0R PUMPS AND VALVES PUMP TABLE DRAWING DWG Ihum! DIFFERENTIAL FICW VIBRATION BEARING LUBE OIL -
PUMP ID TEST TYPE NtMBER INSPECTION CO-CR SPEED PRESSURE PRESSURE RATE AMPLITUDE TEMPERATURE LEVEL FREQUENCY
.__....__... ....___...__._...............__......___................__.....___...............__.........._.......__...___..................__....../
10P-1A DESIGN fM-20B PRESSURE.....__ ..................
B-6 X P2 X X P17 X P9 P14 PS 1 - QUARTERLY 10P-1B DESIGN FM-2'0B B-5 X P2 .X X P17 X P9 P14 PS a- 1 - QUARTERLY 10P-1C DESIGN FM-208 C-6 X P2 X X Pl? I P9 P14 PS 1 - QUARTERLY
, 10P-1D DESIGN FM-20B C-5 X P2 I I P17 X P9 P14 PS 1 - QUARTERLY 10P-3A DESIGN FM-20A B-7 I P16 X X P17 1 P14 X 1 - QUARTERLY 10P-3B DESIGN FN-20A B.3 I P16 X X P17 X P14 X 1 - QUARTERLY .-
10P-3C DESIGN FM-20A C-7 X P16 I X P17 X P14 X 1 - QUARTERLY 10P-3D DESIGN FM-20A C-3 X P16 K X P17 X P14 X 1 - QUARTERLY 11P-2A DESIGN FM-21A D-4 I P12 X X P7 X P13 P14 X 1 - QUARTERLY i
.X P12 X X P7 I P13 P14 X 1'. QUARTERLY [
14P-1A DESIGN FM-23A C-8 I I P11 X P17 X P17 X P14 X 1 - QUARTERLY ,
14 P-1B DESIGN IM-23A C-3 X P11 X P17 X P17 X P14 I 1 - QUARTERLY ;
23P-1B DESIGN EN-25A E-5 I Pl? X X P17 X P14 X 1 - QUARTERLY -
23P-1M DESIGN FM-25A E-4 X P17 X X P17 X P17 I P14 X 1 - QUARTERLY- ,
46P-2A DESIGN FM-4 6B D-8 I P2- X X Pl? X P9 P14 PS 1 - QUARTERLY 46P-23 DESIGN PM-46A C-8 I P2 X X P17 I P9 P14 PS 1 - QUARTERLY i it l
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NEM YORK PO ER AUTHORITY ,
JAMES A FITEPATRICK ' NUCLEAR P.O N E R PLANT 1NSERVICE TESTING- PROGRAM F0R PUMPS AND VALVES
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t PUMP TABLE DRAWING DWG ' INLET DIFFERENTIAL FI.CW VIBRATION BEARING- LUBE OIL INSPECTION- ,
PUMP ID . TEST TYPE NUMBER CO-OR EFEED PRESSURE PRESSURE RATE AMPLI711DE - TEMPERATURE LEVEL / PRESSURE FREQUENCY ^f 10P.1A DESIGN FM-20B B-6 I P2 X X P17 I P9 P14: P5 1 - QUARTERLY. '
10P-1B , DESIGN F?t-20B B-5 K P2- X X P17 X P9 P14 PS 1 - QUARTERLY '
'f 10P-1C DESIGN PM-20B C-6 I P2 X X P17 ' X P9 - - P14 PS 1 -. QUARTERLY 10P-1D DESIGN FM-20B C-5 X P2 I X P17 X P9 P14 PS 1 - QUARTERLY 10P-3A DESIGN fM-20A B-7 X P16 X X P17 I P14 X 1 - QUARTERLY i
10P-3B DESIGN FM-20A B-3 I P16 X X P17 X . P14 . I 1 . QUARTERLY '
f 10P-3C.' DESIGN PM-20A C-7 I P16 X X P17 X P14 X 1 . QUARTERLY 10P-3D DESIGN PM-JOA C-3 I P16 I- X P17 'X P14 X 1 . QUARTERLY I
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-11P-2A DESIGN FM-21A D-4 X P12 X X P7 X P13 P14 I. 1 . QUARTERLY. I 11P-2B DESIGN FM-21A B-4 X P12 X X P7 - X P13 - P14 X 1 - QUARTERLY 14P-1A DESIGN FM-23A C-9 K P11 X P17 X P17 K ' P14 ' 'X 1 - QUARTERLY 14P-1B DESIGN FM-23A C-3 X P11- X P17 X P17 X P14 X 1 - QUARTERLY
, 23P-1B DESIGN FM-25A E-5 X P17 K X P17 .X ' P14 X 1 - QUARTERLY' 23P-1M DESIGN FM-25A E X P17 X X P17 X P17 X P14 X '1 - QUARTERLY t
46P-2A DESIGN FM-46B D-8 X P2 X X P17 X P9 P14 P5 '1 - QUARTERLY I
46P-2B DESIGN FM-46A C-8 I P2 X X P17 K P9 P14 PS 1 - QUARTERLY. ,
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT i
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES !
APPENDIX A Pumo Relief Recuests i
NOTE P1 This relief request has been withdrawn. l O
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A
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U Pumo Relief Reauests i
NOTE P3 This-relief request has been withdrawn.
NOTE P4 This relief request has been withdrawn.
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'NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A i 8 J
- Pumo Relief Reauests NOTE P5 -
SYSTEMS: RHR Service Water j Emergency Service Water 1 PUMPS: RHRSW 10P-1A, B, C, D ESW 46P-2A, B
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CLASS: 3 FUNCTION: Provide emergency cooling water from intake bay to various emergency heat exchangers and back-up~
injection points.
TEST REQUIREMENT: IWP-3100 and Table IWP-3100-1 require observation of proper lubrication level or pressure.
BASIS FOR RELIEF: These pumps are of a vertical submerged open line i shaft design. The pump bearings are water '
lubricated and the lube oil observation cannot be
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NJ performed.
ALTERNATE TEST: Other Code required parameters being measured will detect degradation of the mechanical condition of the pumps.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A
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Pumo Relief Recuests l
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NOTE P6 This relief request has been withdrawn. ,
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' NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING' PROGRAM FOR PUMPS AND VALVES APPENDIX A O .
Pumo Relief Recruests NOTE P7 I
SYSTEM: Standby Liquid Control (SLC)
PUMPS: SLC 11P-2A, B CLASS: 2 l I
FUNCTION: These pumps inject borated water into the reactor l vessel as an alternate means for negative !
reactivity addition and reactor shutdown.
TEST REQUIREMENT: IWP-3500 specifies that a pump shall be run for at least five minutes under stable conditions before recording the required test data.
IWP-4600 specifies that flowrate shall be measured using a rate or quantity meter installed in the pump test circuit.
BASIS FOR RELIEF: The SLC test loop is not equipped with flow (O) instrumentation and the only practical means of determining flowrate is to monitor the change of level in a test tank from which water is being !
pumped. The installed test tank has a capacity !
of only 210 gallons and is not capable of l accommodating 5 minutes of pump operation at '
rated conditions (2 50 gpm).
l ALTERNATE TESTING: The flowrate of the SLC pumps will be determined '
by measuring the change in water level in the test tank during a period of pump operation at the reference discharge pressure over a period of at least two (2) minutes.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES ,
APPENDIX A O .
Pumo Relief Recuests NOTE P8 This relief request has been withdrawn. !
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT-INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A i O Pumo Relief Recuests NOTE P9 ,
h SYSTEMS: RHR Service Water (RHRSW)
Emergency Service Water (ESW)
PUMPS: RHRSW 10P-1A, B, C, D ESW 46P-2A, B !
CLASS: 3 FUNCTION: Provide emergency cooling water from'the intake l bay to various emergency heat exchangers and I backup injection points. '
TEST REQUIREMENT: IWP-4510 requires that, on a pump coupled to the driver, vibration measurements shall be taken on the bearing housing near the coupling.
BASIS FOR RELIEF: These pumps are of a vertical submerged open- ;
n line shaft design with the ' pump bearings V submerged and inaccessible below the floor slab. J' The bearing / seal housing near the upper coupling, which is accessible, is in a confined area in close proximity to the rotating shaft and coupling. Access to this area for vibration monitoring is considered to present an unacceptable personnel safety hazard during pump operation.
ASME/ ANSI OMa-1988, Part 6, " Operation and Maintenance of Nuclear Power Plants", Paragraph 4.6.4 (b) identifies the access problem associated with measuring vibration of vertical line shaft pumps and directs that measurements be taken on the upper motor bearing housing in three orthogonal directions. This Standard considers measuring in this manner an acceptable method for monitoring vibration.
ALTERNATE TESTING: Vibration measurements on these pumps will be taken on the upper motor bearing housing per ASME/ ANSI OMa-1988, Part 6, " Operation and Maintenance of Nuclear Power Plants", Paragraph
- 4. 6. 4 (b) . In addition, vibration measurements will comply with the applicable requirements of O' Paragraphs 4.3, 4.4, 4.5, 4.6.1, 4.6.4, 5.1, 5.2 and 6.1 of that standard. '
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NEW YORK POWER AUTHORITY '
JAMES A. FITZPATRICK' NUCLEAR POWER' PLANT l i
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A O ,
b Pumo Relief Recuests NOTE P10 This relief request has been withdrawn.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PR') GRAM FOR PUMPS AND VALVES APPENDIX A Pumo Relief Recuests NOTE Pil SYSTEM: Core Spray PUMPS: 14P-1A,B CLASS: 2 FUNCTION: Pump cooling water from the suppression pool to the reactor in the event of a LOCA.
TEST REQUIREMENT: Per IWP-4120, the full-scale range of - the pump '
inlet pressure instrument shall be three times the reference value or less.
BASIS FOR RELIEF: The installed core spray pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating conditions. The full-scale range, 60 psig, is sufficient for a post-accident condition when the q torus is at the maximum accident pressure. This, Q however, exceeds the range- limit for inlet pressure under the test condition (approx. 5 psig).
Suction pressure measurements serve two functions. First, they provide assurance that the prescribed NPSH requirements for the pumps i are meti. Secondly, they are used for determining j pump differential pressure. !
1 The installed gauges are calibrated to within 12%
accuracy (FS), thus the maximum variation in measured suction pressure due to inaccuracy would be 21.2 psi. This is considered to be suitable for determining that adequate NPSH is available for proper pump operation.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
.,r' APPENDIX A Pumo Relief Recuests NOTE Pil (cont.)
Pump discharge pressure during testing is i typically 300 psig. which results in a calculated differential pressure of approximately 295 psid.
Given the accuracy of the discharge pressure measurement of 2.5 psi, the resultant maximum variation in calculated differential pressure will be 3.7 psi. or 1.25%. This is consistent with the requirements of Table IWP-4110-1 that I only requires that instrument accuracy be better than 2% of full scale.
ALTERNATE TESTING: Use existing vendor supplied inlet pressure indicators (as described above) for testing of the core spray pumps. (See Relief Request NOTE P16)
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A ,
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Pumo Relief Recuests 1 i
NOTE P12 !
SYSTEM: Standby Liquid Control (SLC)
PUMPS: 11P-2 A, B CLASS: 2 FUNCTION: These pumps inject borated water into the reactor vessel as an alternate, means for negative reactivity addition and reactor shutdown.
TEST REQUIREMENT: Per IWP-4120, the full-scale range of the pump inlet pressure instrument shall be three times 1
the reference value or less.
BASIS FOR RELIEF: The pump inlet pressure indicators are designed to provide adequate inlet pressure indication when pumping from the SLC storage tank. These instruments have a range of 0-30 psig and are C) calibrated to within i2%-accuracy. Thus, there
\d is a potential for a variation of 20.6 psi due to instrument accuracy. Since the SLC pumps are of the reciprocating positive displacement type, pump flowrate is not sensitive to pump differential pressure. In addition, the typical pump inlet pressure-(approx. 1 psi) is less than 0.1% of the developed differential pressure (1279 psid). A variation of io.6 psi in the inlet pressure will not significantly affect pump parameters.
ALTERNATE TESTING: Use existing vendor supplied inlet pressure indicators for the SLC pump flow test. (See Relief Request NOTE P16)
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NFW YORK POWER AUTHORITY JAMES A. ITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A O
Pumo Relief Recuests '
NOTE P13 SYSTEM: Standby Liquid Control (SLC)
PUMPS: 11P-2A,B CLASS: 2 FUNCTION: These pumps inject borated water into the reactor vessel as an alternate means for negative 1 reactivity addition and reactor shutdown. I 1
TEST REQUIREMENT: Per IWP-4520(b), vibration measurement instruments shall have a frequency response range ' i from one half minimum to at least manmum pump i shaft rotational speed. I BASIS FOR RELIEF: The nominal speed of the SLC pumps is 520 RPM which correlates to a rotational frequency of l 8.67 Hz. IWP-4520 (b) requires vibration l instrumentation be accurate to ist full scale )
V() over a range of 4.33-8.67 Hz for these pumps.
The Authority has purchased new instruments for use during surveillance testing with certified l
accuracy of iS% full scale over a range of 5-2000 i Hz. Calibration is verified accurate using a l system test methodology over a range of 6-500 Hz in units of displacement (Mils Pk-Pk) and 6-1000 Hz. in units of both velocity (IPS Pk) and ;
acceleration (g's Pk). The system test verification is limited by the' capability of the calibration shaker system to accurately sustain vibration at meaningful amplitudes outside the '
tested frequencies. The certified calibration 15% range is arrived at through addition of individual transducer and meter inaccuracies over the stated frequency range.
The instrument lower frequency response limits are a result of high-pass filters installed to eliminate low-frequency elements associated with the input signal from entering the process of '
single and double integration. These filters prevent low frequency electronic noise in from g distorting readings in the resultant units (IPS, Mils). As a side effect, any actual vibration
(] occurring at low frequencies is filtered out.
Rev. No. 9 Page 24 of 150
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
,. APPENDIX A' Pumo Relief Recuests NOTE P13 (cont.) This is a necessary trade-off, as 1 mv of electronic noise at 4.33 Hz translates to - 20.86 Mils Pk-Pk with the accelerometer used with these 4 instruments.
The Authority has extensively researched this issue concerning Code compliance and intent, and strongly feels that, for these pumps, procurement of equipment capable of meeting the Code required accuracy is impractical with little or no benefit. Instrumentation capable of meeting the Code for these pumps is cumbersome, difficult to operate, prone to human error, costly to purchase and expensive to calibrate. The number of vendors that supply instrumentation accurate at these frequencies is limited, and there are even fewer qualified vendors capable of performing the required calibration services. Most standard.
qualified calibration laboratories provide calibration services only to a minimum of 10 Hz.
In addition to the impracticability of procuring the instruments, the Authority feels that the ;
instruments presently used are adequate to assess the condition of.these pumps. The manufacturer of these pumps, Union Pump Co., Battle Creek,
)
Michigan, has stated that these pumps, being of a simplified reciprocating design, have no failure mechanisms that would be revealed at frequencies less than shaft speed. Union Pump has stated that all failure modes of this pump resulting in increasing vibration will be manifested at shaft speed frequency or harmonics In light of the information provided by
?
thereof. ;
, Union Pump, monitoring sub-synchronous vibration for these pumps is not needed, but super-
- synchronous readings will provide meaningful
- information in the detection of imminent machinery faults.
A search of the INPO NPRDS database has revealed only one failure reported for pumps of this or similar design whose discovery mentioned increased vibration levels. The cited cause of the failure was improper end play set leading to
, g bearing failure. Feilures of this type would
' g normally be detected at running (shaft) speed frequency, harmonics thereof, or non-harmonic Rev. No. 9 Page 25 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
-INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A Pumo Relief Recuests i
NOTE P13 (cont.) super-synchronous bearing defect frequencies. It should also be noted that these are standby pumps !
which are normally operated only during pump and i valve testing. In the unlikely event this system is required to fulfill its design function, only {
one of the two redundant pumps need operate for a period of 23 to 125 minutes.
1 In addition to vibration monitoring performed for the IST Program, these pumps are included in the Authority's Rotating Equipment Monitoring Program. Vibration spectral data is periodically collected and analyzed for the pump and gear motors in addition to those required by the Code.
The equipment used by the Rotating Equipment j Program is certified accurate i 5% over a i frequency range 5-2000 Hz and is also limited by l high-pass integrating filters, but allows for ;
discrete frequency analysis and trending using FFTs. Vendor specifications state that this
/~}
b equipment should provide fairly accurate data down to 2 Hz in units of acceleration (g's Pk)
(using the raw transducer signal - negating the need for integration) . Study of low-frequency spectra taken in g's Pk with these instruments has revealed no distinct sub-synchronous peaks above the noise floor acceleration signal In light of their rigorous testing and limited design run time, it is not likely that a minor mechanical fault would prevent these pumps from fulfilling their design function and unlikely that development of a major fault would go unnoticed.
In conclusion, the Authority feels that the use of high quality, commercially available vibration monitoring equipment calibrated to be at least accurate i 5% full scale over a range of 6 Hz to 500 Hz (nominal shaft speed - 8.67 Hz) is an appropriate method of monitoring the mechanical condition of the SLC pumps. Such instruments will provide meaningful and useful measurements over the frequency range in which pump faults will develop and manifest. This meets the intent 7 of the Code and certainly will neither adversely t impact system reliability nor the health and b safety of the general public. In addition, it Rev. No. 9 Page 26 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLAITT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVER APPENDIX A O
PumD Relief Recuests i
NOTE P13 (cont.) relieves the Authority of the burden and expense involved in the procurement, calibration, training and certification associated with obtaining new ;
equipment which is simply not needed to !
adequately assess the condition of the subject t
pumps.
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-ALTERNATE TESTING: The vibration measurements will be taken using
. instrumentation accurate i 5% full scale over a
- frequency range of 6 Hz to 500 Hz. The data will
{ be evaluated per IWP-3200.
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-[O Pumo Relief Reauests NOTE P14 SYSTEMS: Various PUMPS: All pumps in Program
' CLASS: 2 and 3 FUNCTION: Various TEST REQUIREMENT: IWP-3300 and _IWP-4310 requires that the temperature of all centrifugal pump bearings outside the main flowpath and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the~ bearings.
BASIS FOR RELIEF: The data associated with bearing temperatures taken at one-year intervals provides little statistical basis for determining the incremental Os degradation of a bearing or any meaningful trending information or correlation.
In many cases pump bearings are_ water-cooled and thus, bearing temperature is a function-of the temperature of the cooling medium, which can vary considerably.
Vibration measurements are a significantly more reliable indication of pump bearing degradation i than are temperature measurements. All pumps in i the program are subjected to vibration !
measurements in accordance with IWP-4500. 1 Although excessive bearing temperature is an indication of an imminent or existing bearing l failure, it is highly unlikely that such a j condition would go unnoticed during routine j surveillance testing since it would manifest :
itself in other obvious indications such as i audible noise, unusual vibration, increased motor I current, etc.
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Rev. No. 9 page 28 of 150
, NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l
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Pumo Relief Recuests r
NOTE P14 (cont.)
Any potential gain from taking bearing l temperature measurements, which in most cases would be done locally using portable instrumentation, cannot offset the cost in terms of dilution of operator effort, distraction of operators from other primary duties, excessive operating periods for standby pumps, and l
. unnecessary personnel radiation exposure.
ALTERNATE TESTING: Vibration monitoring will be performed in' accordance with IWP-4500. Such vibration monitoring will provide adequate monitoring and evaluation of the material condition of the pump bearings.
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l INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A i
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Pumo Relief Recuests ;
NOTE P15 This relief request has been withdrawn.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A Pumo Relief Recuests NOTE P16 SYSTEMS: Various PUMPS: Various CLASS: Various FUNCTION: This is a generic relief request.
TEST REQUIREMENT: Per IWP-4210, if the presence or absence of liquid.in a gage line could produce a difference of more than 0.25% in the indicated value of~the measured pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the static correction used.
BASIS FOR RELIEF: When this requirement is applied to the measurement of pump suction pressure where measured pressures are at relative low levels, O the 0.25% limit is overly restrictive and oftentimes results in complicated venting procedures and unnecessary health physics risks associated with handling and disposal of radioactive contaminated water with no ,
commensurate gain or improvement of test j reliability. j Normally, the only quantitative use of suction pressure measurements, where significant accuracy ,
is required, is in determining pump differential i pressure or head. In most cases the pump j discharge pressure exceeds the suction pressure by at least a factor of five (5). This being the case, a 0.25% error introduced into the suction pressure measurement results in an error of 0.05%
in the differential pressure calculation. This is insignificant in light of the potential 6%
error allowance applied to both the suction and discharge pressure instruments (Ref IWP-4110).
V Rev. No. 9 Page 31 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 1
I APPENDIX A i
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l Pumo Relief Recuests I
NOTE P36 (cont.)
ALTERNATE TESTING: If the presence or absence of liquid in a gage line used for sensing pump suction pressure could produce a difference of more than 0.25% in the calculated value of the pump differential pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the static correction used.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A O ;
Pumo Relief Recuests i I
l NOTE P17 '
SYSTEMS: Various
-PUMPS: This is a generic relief request.
CLASS: Various i
FUNCTION: Various ,
TEST. REQUIRE!'.ENT: IWP-4120 requires that the full-scale range of each instrument shall be three time the reference '
value or less. '
BASIS FOR RELIEF: In several instances instruments used to measure
! pump parameters use digital readouts. Although these instruments are highly accurate and I
suitable for use, they are virtually unlimited in range and thus'do not meet the code requirement.
l f ASME/ ANSI OM-1987, Part 6, Paragraph 4.6.1.2 allows the use of digital instruments with limiting provisions.
ALTERNATE TESTING: Digital instruments may be used during pump.
testing provided that the reference value shall not exceed 70% of the calibrated . range of the instrument.
Digital instruments shall have an accuracy of 12 percent (15 percent for vibration) over the !
calibrated range of the instrument.
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, APPENDIX A i i Pumo Relief Recuests I
l NOTE P18 This relief request has been withdrawn. j
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NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT i INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 1
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VALVE TESTING PROGRAM i
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NEW YORK POWER AUTHORITY j JAMES A. FITZPATRICK NUCLEAR POWER PLANT '
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES s APPENDIX B
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l VALVE TESTING PROGRAM I Table of Contents f Valve Table Explanation....................................... 39 i
l Valve Symbols............................. ................... 42 Valve Types................................................. 42 Valve Actuator Types........................................ 42 l Test Method................................................. 43 l Test Frequency.............................................. 43 ]
. Valve Table................................................... 44 Cold Shutdown Justification................................... 97 i CS1: Reactor Water Recirculation........................... 97
! CS2: Residual Heat Removal................................. 97 CS3: Residual Heat Removal................................. 98 CS4: Reactor Building Closed Loop Cooling.................. 98 CS5: Reactor Building Closed Loop Cooling.................. 98 CS6: HPCI.................................................. 99 T CS7: Control Rod Drive Hydraulics.......................... 99
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CS8: DELETED. ............................................. 99 CS9: Feedwater............................................. 99 CS10: Containment Vent and Purge........................... 100 CS11: DELETED.............................................. 100 CS12: Main Steam........................................... 100 CS13: Main Steam........................................... 100 CS14: DELETED.............................................. 101 CS15: DELETED.............................................. 101 CS16: High Pressure Coolant Injection...................... 101 CS17: Reactor Coolant Isolation Cooling.................... 101 !
CS18: Reactor Coolant Isolation Cooling.................... 102 RELIEF REQUESTS.............................................. 103 i
NOTE V1: Reactor Water Recirculation...................... 103 ,
NOTE V2: Control Rod Drive................................ 104 '
NOTE V3: WITHDRAWN........................................ 105 l NOTE V4: WITHDRAWN........................................ 105 l NOTE V5: Standby Liquid Control........................... 106 NOTE V6: Reactor Core Isolation Cooling................... 107 l NOTE V7: WITHDRAWN........................................ 108 !
NOTE V8: WITHDRAWN........................................ 108 NOTE V9: HPCI............................................. 109 NOTE V10: WITHDRAWN........................................ 109
, NOTE Vil: WITHDRAWN........................................ 109 l
NOTE V12: Feedwater........................................ 110 NOTE V13: WITHDRAWN........................................ 111 Rev. No. 9 Page 36 of 150 t
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1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
, INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES '
1 APPENDIX B N/
VALVE TESTING PROGRAM i
l Table of Contents 1 i Relief Requests (Cont'd) !
NOTE V14: Instrument Air................................... 111 NOTE V15: W I THD RAWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 -
NOTE V16: WITHDRAWN........................................ 111 NOTE V17: HPCI............................................. 112 NOTE V18: WITHDRAWN........................................ 113 NOTE V19: Containment Isolation............................ 114 NOTE V20: WITHDRAWN........................................ 116 NOTE V21: WITHDRAWN........................................ 116 NOTE V22: HPCI............................................. 116 [
NOTE V23: WITHDRAWN........................................ 117 NOTE V24: WITHDRAWN........................................ 117 NOTE V25: WITHDRAWN........................................ 117 NOTE V26: WITHDRAWN........................................ 117 NOTE V27: ADS and Main Steam............................... 118 NOTE V28: Excess Flow Checks............................... 120 NOTE V29: Fast Acting Valves............................... 122 NOTE V30: WITHDRAWN........................................ 124
{N x NOTE V31: WITHDRAWN........................................ 124 NOTE V32: Residual Heat Removal............................ 125 NOTE V33: WITHDRAWN........................................ 127 NOTE V34: HPCI............................................. 127 NOTE V35: HPCI.............................................. 129 NOTE V36: WITHDRAWN........................................ 130 NOTE V37: WITHDRAWN........................................ 130 NOTE V38: WITHDRAWN........................................ 130 NOTE V39: WITHDRAWN........................................ 130 NOTE V40: WITHDRAWN........................................ 130 NOTE V41: WITHDRAWN........................................ 130 NOTE V42: WITHDRAWN........................................ 130 NOTE V43: WITHDRAWN........................................ 130 NOTE V44: WITHDRAWN........................................ 130 NOTE V45: WITHDRAWN........................................ 130 NOTE V46: Containment Isolation Valves..................... 131 NOTE V47: High Pressure Coolant Injection.................. 133 NOTE V48: Containment Atmospheric Dilution................. 134 NOTE V49: Emergency Service Water.......................... 135 NOTE V50: Traversing Incore Probe.......................... 136 NOTE V51: Generic - Cold Shutdown Testing.................. 137 NOTE V52: WITHDRAWN........................................ 139 NOTE V53: WITHDRAWN........................................ 139 b
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, NEW YORK POWER AUTHORITY !
JAMES A. FITZPATRICK NUCLEAR POWER PLANT ;
M INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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VALVE TESTING PROGRAM Table of Contents Relief Requests (Cont #d)'
NOTE V54: HPCI............................................. 139 NOTE V55: Core Spray....................................... 140 '
NOTE V56: Residual Heat Removal............................ 141 NOTE V57: Core Spray....................................... 142 '
NOTE V58: Automatic Depressurization....................... 144 NOTE V59: Main Steam....................................... 145 NOTE V60: Residual Heat Removal............................
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NEW YORK POWER AUTHORITY JAMES A.'FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPEND 1X B VALVE TABLE-EXPLANATION Summary of Information Provided The Valve Table is sorted by system number then drawing number and provides the following information:
Individual valve identifier
- Drawing coordinatesSection XI ISI Classification Section XI IWV category
- Nominal size
- Valve type
- Actuator type Section XI test required Relief request (RR) / cold shutdown (CS) justification Alternate test
- Remarks I
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Rev. No. 9 Page 39 of 150
'NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES I
f APPENDIX B '
Cold Shutdown Justification Notes CSXX refer to cold shutdown justifications which provide the justification for testing affected components at cold shutdown instead i of every three months. (Refer-to Relief Request NOTE VS1) The Cold l Shutdown Justifications provide the following information:
]
- ' System
- - Individual valve identifier :
- l Section XI category
- Safety function
- Justification O
Rev. No. 9 Page 40 of 150
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests Notes VXX refer to Relief Requests for the Valve Testing Program. The Valve Relief Requests' provide the following information:
- System '
- Individual valve identifier
- Section XI category
- ISI Classification
- Safety Function Test requirement from which relief is requested
- Basis for relief
- Alternate testing l
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NEW YORK POWER AUTHORITY '
JAMES A. FITZPATRICK NUCLEAR POWER PLANT !
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l l
,m APPENDIX B k,)
s l VALVE SYMBOLS 1
Valve Tvoes 3W Three-way valve i AN Angle valve i BF Butterfly valve BK Ball check l BL Ball valve i CK Swing check l GA Gate valve GL Globe valve LK Lift check NK Non-return check ,
PG Plug valve i RL Relief valve SC Stop check i SK Spring check '
TK Testable check 1 WK Wafer Check XP Explosive valve I
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Valve Actuator Tvoes AO Air operator EH Electro-hydraulic HO Hydraulic operator MA Manual operator MO Motor operator PA Pilot actuated SA Self actuated SO Solenoid operator SP Spring operator SQ Squib actuator b
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT -
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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Test Method 1
l TS Stroke time measured during valve exercising .IWV-3413 TM. Stroke time measured during valve exercising IWV-3413 FS Full stroke exercise IWV-3412 FC- Fail-safe to close position IWV-3415 FO Fail-safe to open position IWV-3415
-PE Partial stroke exercise IWV-3412 LK Leak test IWV-3420 LJ Leak test per 10CFR50 Appendix J Type C RL Relief valve test IWV-3512 PI Remote position indication verification IWV-3300 DA Disassemble and inspect per relief request SP Special test (Refer to relief request)
XP ' Explosively actuated valve test IWV-3610 FF Forward flow check valve test IWV-3522
, RF Check valve closure test IWV-3522 PF Partial flow check valve test MS Manual stroke test (non-intrusive) IWV-3522 ME Exercising check valves using manual operator- IWV-3522 l
Test Frecuency
-1 Quarterly -5 2 Years
-2 Cold Shutdown -6 Special Test per Relief Request !
-3 Refueling -7 Monthly
-4 IWV-3511/3610' i l
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I AUTHORITY JAMES A. FITEPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM POR PUMPS AND VALVES VALVE TABLE STSTEM: Standby Gas Treatment . SYSTEM ID: 01-125
- DRANING: FM-4 8A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 01-125MOV-100A C-6 2 B 4.00 BF 10 TM-1 PI-3 01-125Mov-100s F-6 2 B 4.00 BF MO 1N-1 PI-3 01-125MOV-11 G-8 2 B 24.00 BF MO TM-1 PI-3 01-125MOV-12 F-8 2 B 24.00 BF MO TN-1 PI-3 01-125MOV-14A D-7 2 B 24.00 BF MO TM-1 PI-3 01-125Mov-14B E-7 2 B 24.00 BF MO TM-1 PI-3 01-125MOV-15A D-3 2 B 24.00 BF MO TN-1 FI-3 01-125MOV-15B F-3 2 B 24.00 BF MO TM-1 PI-3 REV. NO: 9 PAGE 44 OF 150 L_
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PO2ER AUTHORITY V
JAMES A. FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Automatic Depressurization System . SYSTEM ID: 02 DRAWING: FM-29A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 02RV-1 H-7 2 C 3.00 CK SA MS-2 V58 02RV-10 G-7 2 C 3.00 CK SA MS-2 V58 02RV-11 G-7 2 C 3.00 CK SA MS-2 V58 02RV-2 H-7 2 C 3.00 CK SA MS-2 V58 02RV-3 H-7 2 C 3.00 CK SA MS-2 V58 02RV-4 H-7 2 C 3.00 CK SA MS-2 V58 02KV-5 H-7 2 C 3.00 CK SA MS-2 V58 02RV-6 H-7 2 C 3.00 CK SA MS-2 V58 02RV-7 H-7 2 C 3.00 CK SA MS-2 V58 02RV-71A G-6 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71B G-6 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71C G-6 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71D F-6 1 BC 6.00 RL SA , AO FS-1 V27 FS-3 RL-4 '
02RV-71E F-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71F F-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71G G-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 REV. NO: 9 PAGE 45 CF 150
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(_ NEW YORK (V
POWER AUTHORITY U
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JAMES A. FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Aut N tic Depressurization System - SYSTEM ID: 02 DRAWING: FM-29A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. KI TEST RR / CS AL7ERNATE TEST REMARKS 02RV-71H G-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4
- 02RV-71J G-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71K G-6 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-71L G-7 1 BC 6.00 RL SA AO FS-1 V27 FS-3 RL-4 02RV-8 G-7 2 C 3.00 CK SA MS-2 V58 02RV-9 G-7 2 C 3.00 CK SA MS-2 V58 02VB-1 H-8 2 C 10. fj 0 CK SA MS-2 VS8 02VB-10 G-8 2 C 10.00 CK SA MS-2 V58 02VB-11 G-8 2 C 10.00 CK SA MS-2 VS8 02VB-2 H-8 2 C 10.00 CK SA MS-2 V58 02VB-3 H-8 2 C 10.00 CK SA MS-2 V58 02VB-4 H-8 2 C 10.00 CK SA MS-2 V58 02VB-S H-8 2 C 10.00 CK SA MS-2 V58 02VB-6 H-8 2 C 10.00 CK SA MS-2 V58 02VB-7 H-8 2 C 10.00 CK SA MS-2 V58 02VB-8 G-8 2 C 10.00 CK SA MS-2 V58 l
l 02VB-9 G-8 2 C 10.00 CK SA MS-2 V58 REV. NO: 9 PAGE 46 OF 150
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JAMES A F I T 2 P A T R I'C K NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Water Recirculation - SYSTEM ID: 02-2 DRAWING: FM-26A t VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TCST REMARKS 02-2AOV-39 E-4 1 A 0.75 GA AO 'IM- 1 FC-1 PI-3 IJ-3 02-2AOV-40 F-2 1 A 0.75 GA AO Dt-1 FC-1 PI-3 IJ-3 02-2EFV-PS-128A B-6 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS F1OW LK-3 02-2EFV-PS-128B B-6 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-2EFV-PT-24A C-3 1 AC 1.00 EK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-2EFV-PT-24B C-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2EFV-PT-25A C-3 1 AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-2EFV-PT-25B C-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-2RWR-13A C-3 1 AC 0.75 SK SA RF-1 V1 IJ-3 IJ-3 02-2RWR-13B C-8 1 AC 0.75 SK SA RF-1 V1 IJ-3 IJ-3 02-2SOV-001 D-3 1 A 0.75 GL SO 'IM- 1 V29 FC-1 PI-3 IJ-3 i
REV. NO: 9 PAGE 47 OF 150
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NEW YORK P d el)E RAUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Water Recirculation . SYSTEM ID: 02-2 DRANING: FM-26A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNA TEST REP 8 ARKS
...............................................................................................................................TE 02-2SOV-002 D-8 1 A 0.75 GL SO 'IM - 1 V29 FC-1 PI.3 IJ-3 022EW1DPT111A E-3 1 AC 1.00 BK SA LK-1 V28 LK.3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFVIDPT111B E-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV1FT110A F-3 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 022EFV1FT110C D-3 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 022EFVIFT110E F-7 1 AC 1.00 BK SA LK-1 V28 LK.3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV1FT110G D-8 1 AC 1.00 BK SA LK-1 v28 LK.3 VALVE ISOLATES ON EXCESS FION LK-3 022EFV2DPT111A E-3 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2DPT111B E-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2FT110A F-3 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 022EW2FT110C D-3 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2FT110E F-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS F10W LK-3 REV. NO: 9 FAGE 48 OF 150
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VALVE TABLE SYSTEM: Reactor Water Recirculation - SYSTEM ID: 02-2 DRAWING: IN-26A!
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VEVE TYPE ACIVATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 022EFY2FT110G D-8 1 AC 1.00 BK SA I.K-1 V28 LK-3 VALVE ISOIATES ON EXCESS FLOW LK.3 02MOV-53A C-3 1 B 28.00 GA MO TM-2 CS1 FI-3 02MOV-53B C-7 1 B 28.00 GA MO TM-2 CS1 PI-3 1
REY. NO: 9 PAGE 49 OF 150 I
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JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Nuclear Boiler Vessel Instruments - SYSTEM ID: 02-3 DRAWINGr IN-47A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SEC1'. XI TEST RR / CS ALTERNATE TEST REMARKS 02-3EFV-11 F-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-13A E-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-13B E-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3ETV-15A E-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-15B E-4 1- AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-15N B-1 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-17A D-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-17B D-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIcW LK-3 02-3EFV-19A D-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 '
02-3EFV-19B D-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FION LK-3 02-3EFV-21A H-5 1 AC f.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-21B C-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-21C C-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 REV. NO: 9 FAGE 50 OF 150
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\ l V NEW YORK P6VER AUTHORITY V JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Nuclear Boiler vessel Instruments - SYSTEM ID: 02-3 DRAMING: FM-47A VEVE ID DWG CO-OR CLASS VEVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 02-3EFV-21D H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02 3EFV-23 F-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-23A H-S 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFv-23B D-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02 3EFV-23C D-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VEVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-23D H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VEVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-25 C-7 1 AC 1.00 BK SA LK-1 V28 LK.3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31A H-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-31B H-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-31C H-S 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-31D H-S 1 AC 1.00 BK SA LK-1 V28 LK-3 VEVE ISOIATES ON EXCESS FLOW LK-3 02-3EFV-31E D-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VEVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31F H-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 REV. NO: 9 PACE 51 OF 150
NEW YORK PO ER AUTHORITY JAMES A. FITZPATRICK NUCLEAR- POWER- PLANT fNSERVICE TESTINO PROGRAM FOR PUMPS AND VALVES-VALVE. TABLE-SYSTEMr Nuclear Boiler Vessel Instruments - SYSTEM ID: 02-3 DRAWING: m-47A VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMNtKS
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02-3EFV-31G H-S 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-31H H-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-31J H-4 1 AC 1.00 BK' SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FI4W LK-3 02-3EFV-31K H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-31L H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FIDW LK-3 02-3EPV-31M D-4 1 AC 1.00 BK SA - LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FI4W LK-3 02-3EFV-31N H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW LK-3 02-3EFV-31P H-4 1 AC 1.00 BK SA LK V28 LK-3 VALVE ISOLATES ON EXCESS FIEW LK-3 02-3EFV-31R H-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31S H-4 1 AC 1.00 BK SA LK-1 V28 .LK-3 VALV8 ISOIATES ON EXCESS FLOW LK-3 02-3EFV-33 B-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISO!ATES ON EXCESS FLOW LK-3 REV. NO: 9 PAGE 52 OF 150 -
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AUTHORITY JAMES A. FITZPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Control Rod Drive - SYSTEM ID: 03 DRANING: FM-27B VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 03AOV-126 C-4 2 B 1.00 GA AO 'IM-1 V2 FS-6 FO-1 V2 FO-6 03AOV-127 D-4 2 B 1.00 GA AO TM-1 V2 FS-6 FO-1 V2 FO-6 03AOV-32 H-4 2 B 1.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-33 F-4 2 B 2.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC PC-1 PI-3 03AOV-34 H-4 2 B 1.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-35 F-4 2 B 2.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-36 H-6 2 B 1.00 GA AO TS-1 '
TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-37 F-6 2 B 2.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-38 H-6 2 B 1.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 03AOV-39 F-6 2 B 2.00 GA AO TS-1 TECH SPEC STROKE TIME LIMIT-30 SEC FC-1 PI-3 REV. NO: 9 PAGE 53 OF 150
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JAMES A E ITZPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Control Rod Drive - SYSTEM ID: 03 DRAWING: EM-27B VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACIUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 03HCU-114 D-4 2 C 0.75 BK SA FF-1 V2 FF.6 03HCU-115 C-4 2 C 0.75 BK SA RF.2 CS7 03HCU-138 C-4 2 C 0.75 BK SA RF-1 REVERSE FLOW TESTED VIA ROD MOTION REV. NO: 9 PAGE 54 OF 150
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JAMES A . FITEPATRICK NUCLEAR POW 3R PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALYE TABLE SYSTEM: Traveling In-Core Probe . SYSTEM ID: 07 DRANING: PM-119A VALVE ID DNG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 07EV-104A F-5 2 D 0.37 XP SQ XP-4 07EV-104B F-4 2 D 0.37 XP SQ XP-4 07EV-104C F-4 2 D 0.37 XP SQ XP-4 07SOV-104A F-5 2 A 0.37 BL SO W-1 V50 FC-1 PI-3 Im7 - 3 07SOV-104B F-4 2 A 0.37 BL SO 1N-1 V50 FC-1 PI-3 LJ-3 07SOV-104C F-4 2 A 0.37 BL SO TM-1 V50 FC-1 PI-3 I.73 REV. NO: 9 PAGE 55 OF 150
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I JAMES A. FITEPATRICK NUCLEAR. POWER PLANT I
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ZNSERVICE 7ESTINO PROGRAM F0R P U M'P S AND VALVES VALVE TABLE SYSTEM: Residual Heat Removal - SYSTEM ID: 10'
'DRANING m-2 0A )
VAI.M ID DMG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS c
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10AOV-68A F-6 1 AC 24.00 TK SA A0 FF-2 V60 - DA-6 PENDING EVALUATION PER V60 ,
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10A0V-68B F-5 1 AC 24.00 TK SA AO - FF-2 V60 DA-6 PENDING EVALUATION PER V60 p RF-2 CS2 LK-3 10MOV-13A C-6 i 2 B 20.00 GA MO TM-1 PI-3 P
, 10Mov-138 C-4 2 B 20.00 GA MO TM-1 i
PI-3 .
10MOV-13C C-6 2 B 20.00 GA i MO TM-1
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$ 10MOV-13D C-5 2 B 20.00 GA MO TM-1 f
PI I 10Mov-15A C-6 2 B 20.00 GA MO TM-1 !
PI-3 s
10MOV-15B C-4 2 B 20.00 GA MO TM-1 I i
PI-3 ~
t 10Mov-15C C-6 2 B 20.00 GA MO TM-1 PI-3 1
10MOV-15D C-4 .2 B 20.00 CA MO TM-1 PI-3
- h 10MOV-16A D-8 2 B 4.00 CA 983 TM-1
PI-3 k
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PAGE 56 OF 150 '
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\/ AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALYE TABLE SYSTEM: Residual Heat Pemoval - SYSTEM ID: 10 DRAMING FM-20Al VALVE ID IMG CD-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. KI TEST RR / CS ALTERNATE TEST REMARKS 10MOV-17 D-5 1 A 20.00 GA MO TS-2 CS3 LK-3 SATISFIED BY IJ-3 PER EVALUATION TM-2 CS3 .
PI-3 LK-3 IJ-3 10MOV-18 E-5 1 A 20.00 GA MO TS-2 CS3 LK-3 SATISFIED BY LJ-3 PER EVALUATION I TM-2 CS3 PI-3 LK-3 IJ-3 10MOV-25A F-8 1 A 24.00 GA MO TS-1 LK-3 SATISFIED BY IJ-3 PER EVALUATION TM-1 PI-3 LK-3 IJ-3 10MOV-25B F-3 1 A 24.00 GA MO TS-1 LK-3 SATISFIED BY IJ-3 PER EVALUATION TM-1 PI-3 LK-3 IJ-3 10MOV-26A G-7 2 A 10.00 GA MO TS-1 TM-1 PI-3 IJ-3 V19 10MOV-26B G-4 2 A 10.00 GA MO TS-1 TM-1 PI-3 IJ-3 v19 10MOV-27A F-8 1 A 18.00 AN MO TS-1 1M-1 PI-3 IJ-3 REV. NO: 9 PAGE 57 OF 150
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J P tr/E R A U T H O ll1 I T Y JAMES A FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE- TABLE SYSTEM: Residual Heat Removal - SYSTEM ID: 10 DRAWING: FN-20A VALVE ID DMG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS i 10MOV-27B F-3 1 A 18.00 AN MO TS-1 1 TM-1 PI-3 M-3 10Mov-31A G-6 2 A 10.00 GL MO TS-1 TM-1 PI-3 M-3 V19 10MOV-31B G-5 2 A 10.00 GL MO TS-1 TM-1 PI-3 M- 3 V19 10POV- 34 A E-7 2 B 14.00 GL MO TS-1 TM-1 i PI-3 10MOV-34B E-3 2 B 14.00 GL MO TS-1 TM-1 PI-3 10MOV-38A E-7 2 A 4.00 GL MO TS-1 TM-1 PI-3 M- 3 V19 '
10MOV-38B E-4 2 A 4.00 GL MO TS-1 TM-1 PI-3 M-3 V19 10MOV-39A E-8 2 A 16.00 GL PC I
TM-1 PI-3 M-3 V19 REV. NO: 9 PAGE 58 CF 150 ,
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NEW YORK POuER AUTHORITT JAMES A. FITZPATRICK NUCLEAR POMER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Residual Heat Removal - SYSTEM ID: 10 DRANING: fM-20A VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 10MOV-39B E-3 2 A 16.00 GL MO TM-1 PI.3 LJ-3 V19 10MOV-66A D-8 2 B 20.00 GL MO TM-1 PI-3 10MOV-66B D-3 2 B 20.00 GL MO TM-1 PI-3 10RHR-262 H-3 2 C 4.00 CK SA RF-1 10RHR-277 G-8 2 C 4.00 CK SA RF.1 10RHR-42A C-8 2 C 16.00 CK St FF-1 RF-1 10RHR-42B C-3 2 C 16.00 CK SA FF-1 RF-1 10RHR-42C C-8 2 C 16.00 CK SA FF-1 RF-1 10RHR-42D C-3 2 C 16.00 CK SA FF-1 RF-1 10RHR-52A G-6 2 A 2.00 GA MA LJ-3 Vig 10R10t-52B G-5 2 A 2.00 GA MA IJ-3 V19 10RHR-64A C-8 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 10RHR-649 C-3 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 REV. NO: 9 PAGE 59 OF 150 t
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JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM POR PUMPS AND V I ' " ". S VALVE TABLE STSTEM: Residual Heat Removal - SYSTEM ID: 10 DRAWING: FM-20A VALVE ID DNG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 10RHR-64C D-8 2 C 3.00 CK SA PF-1 V32 RF-1 i DA-6 10RHR-64D D-3 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 10RHR-95A C-8 2 C 0.75 SK SA RF-1 V56 RF-3 10RHR-959 B-5 2 C 0.75 SK SA RF-1 V56 RF_3 10SV-35A E-8 2 C 1.00 RL SA RL-4 10SV-35B E-3 2 C 1.00 RL SA RL-4 10SV-40 D-5 2 C 1.00 RL SA RL-4 REV. NO: 9 PAGE 60 OF 150
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\b*/ N E tt YORK P 6 '# E R AUTHORITY v' JAMES A FIT 2 PATRICK ElUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Residual Heat Removal - SYSTEM IDr 10 DRANING: FM-20B' VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACITJATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 10MOV-89A D-6 3 B 16.00 GA MO TM-1 PI.3 10MOV-89B E-5 3 B 16.00 GA MO TM-1 PI.3 10RHR-14A B-7 3 C 12.00 CK SA FF-1 RF-1 10RHR-14B B-4 3 C 12.00 CK SA FF-1 RF-1 10RHR-14C C-7 3 C 12.00 CK SA FF-1 RF-1 10MHR-14D C-4 3 C 12.00 CK SA FF.1
- RF-1 10SOV-101A B-6 3 B 0.75 GL SO TM-1 FO-1 FF-3 10SOV-101B B-5 3 B 0.75 GL SO TM-1 N1 FF-3 10SOV-101C C-6 3 B 0.75 GL SO TM-1 FO-1 FF-3 10SOV-101D C-5 3 B O.75 GL SO TM-1 FO-1 FF-3 REY. NOr 9 PAGE 61 OF 150 1
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i FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEMS Standby Liquid Control . SYSTEM ID: 11 DRAWING: IN-21A ,
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 11EV-14A D-6 1 D 1.50 XP SQ IP-4 11EV-14 B B-6 1 D 1.50 XP SQ IP-4 11SLC-16 C-7 1 AC 1.50 CK SA FF-1 V5 FF-3 RF-1 V5 IJ-3 IJ-3 11SLC-17 D-7 1 AC '1.50 SK SA FF-1 V5 FF-3 RF-1 V5 IJ-3 LJ-3 11SLC-43A D-6 2 C 1.50 SK SA FF-1 RF-1 11SLC-43B B-6 2 C 1.50 SK SA FF-1 RF-1 11SV-39A D-4 2 C 1.00 RL SA RL-4 11SV-39B C-4 2 C 1.00 RL SA RL-4 I
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NEW Y O R Ir P d%^I R AUTHORITY JAMES A. FITZPATRICK_ NUCLEAR POWER PLANT INSERVICE TESTINO PROGRAM F0R -PUMPS AND VALVES VALVE TABLE 6 I
ETSTEM: Reactor Water Clean Up System - SYSTEM ID: 12 DRAWING: FN-24A; 7 VALVE ID DNG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 12MOV-15 E-e 1 A 6.00 GA IC TS-1 i PI-3 f
IJ-3 12MOV.18 E.7 1 A 6.00 GA MO TS-1 PI-3 IJ-3 12MOV-69 H-7 1 A 4.00 GA PC TS-1 I PI-3 LJ.3 V19
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k V N E ff 7ORK POWER AUTHORITY JAMES A. 'FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM POR PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Core Isolation Cooling - SYSTEM ID: 13 DRAWING: m-22A, VALVE ID DWG CO-OR CLASS VALVE CATEGORT SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 13EFV-01A G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIOf LK-3 13EFV-01B G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIOf LK-3 13EFV-02A G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 13EFV-02B F-7 1 A0 1.00 BK SA LK-1 V28 LK_3 VALVE ISOLATES ON EXCESS FION LK-3 13MOV-15 F-7 1 A 3.00 GA MO TS-1 PI-3 IJ-3 V19 13MOV-16 P-7 1 A 3.00 GA MO TS-1 PI-3 IJ-3 V19 13MOV-21 F-5 1 A 4.00 GA MO TM-1 PI-3 IJ-3 V19 13MOV-27 E-5 2 B 2.00 GL MO TS-1 PI-3 13MOV-41 D-7 2 B 6.00 GA MO TM-1 FI-3 13RCIC-37 E-6 2 C 1.50 CK SA FF-2 CS17 13RCIC-38 E-6 2 C 1.50 CK SA FF-2 CS17 13RCIC-4 D-6 2 AC 8.00 LK SA RF-1 V6 IJ-3 12-3 REV. NO: 9 PAGE 64 OF 150
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Core Isolation Cooling - SYSTEM ID: 13 DRAWING: IN-22A VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACIUATOR TYPE SECT. XI TEST ~ RR / CS. ALTERNATE TEST REMARKS
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_ _ _ _ _ . . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ _ _ _ __ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . _ . . _ _ _________.m_____.
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NEU TORK P O'V E R AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Core Spray - SYSTEM ID: 14 3 DRAWING: FM-23A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS
.........._.................................................................................................... 1..............................................................
14AOV-13A F-6 1 AC 10.00 TK SA AO PE-2 V57 RF-2 FF-3 LK-3 PI-3 14AOV-13B F-5 1 AC 10.00 TK SA AO PE-2 V57 RF-2 FF-3 LK-3 PI-3 14 CSP-10A D-8 2 C 12.00 CK SA FF-1 14 CSP-10B D-3 2 C 12.00 CK SA FF-1 14 CSP-62 A E-7 2 C 1.00 SK SA RF-1 RF-3 14 CSP-62 B E-3 2 C 1.00 SK SA RF-1 RF-3 14 CSP-76A F-7 2 C 2.00 SK SA RF-1 14 CSP-76B F-4 2 C 2.00 SK SA RF-1 14EFV-31A E-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FICM LK-3 14EFv-31B E-4 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FLON LK-3 14MOV-11A F-7 1 A 10.00 GA MO TM-1 PI-3 IJ-3 14MOV-11B F-4 1 A 10.00 GA MO IN-1 PI-3 IJ-3 REV. NO: 9 PAGE 66 OF 150
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JAMES :A. FITZPATRICK NUCLEAR POWER PLANT
-1NSERVICE TESTING. PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Core Spray - SYSTEM ID: 14' DIUuf1NG: fM-23A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE . SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 14MOV-12A F-6 1 A 10.00 GA MO *IM-1 LK-3 SATISFIED BY M-3 PER EVALUATION PI-3 LK M-3 14MOV-12B F-4 1 A 10.00 GA MO TM-1 LK-3 SATISFIED BY M-3 PER EVALUATION PI-3
'LK-3 M-3 14MOV-26A F-7 2 B 8.00 GL. MO TS-1 PI-3 14MOV-26B F-3 2 B 8.00 GL MO 'TS-1 PI-3 14MOV-5A ' E-7 2 B 3.00 GA MO TM-1 PI-3 14t43V-5B E-3 2 B 3.00 GA MO TM-1 PI-3 14Mov-7A C-6 2 B 16.00 GA MO TM-1 PI-3 14MOV-7B C-4 2 B 16.00 GA MO TM-1 PI-3 14SV-20A E-8 2 C 1.50- RL SA RL-4 14SV-20B D-2 2 C 1.50 RL SA RL-4 REV. NO 9 PAGE 67 OF 150
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' VALVE TABLE SYSTEM: Reactor Building Closed Icop Cooling - SYSTEM ID: 15 DRANING: FM-15A VALVE ID DtfG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REPGRKS 15MOV-175A C-2 3 B 6.00 GA MO TM-1 PI.3 15MOV-175B C-2 3 B 6,00 GA MO W-1 PI.3
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AUTHORITY 7 JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Building Closed Icop Cooling - SYSTEM ID: 15 DRANING: FM-15B VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACI'JATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 15AOV-130A C-7 3 A 6.00 GL AO TM-2 CSS PE-7 PI-3 14-3 15AOV-130B D-5 3 A 4.00 GL AO TM-2 CSS PE-7 PI-3 IJ-3 15AOV-131A E-7 3 A 4.00 GL AO 1N-2 CS5 PE-7 PI-3 IJ-3 15AOV-131B E-4 3 A 4.00 GL AO TM-2 CSS PE-7 PI-3 IJ-3 15AOV-132A F-5 3 A 4.00 GL AO TM-2 CS4 PE-7 PI-3 IJ-3 15AOV-132B F-7 3 A 4.00 GL AO 1N-2 CS4 PE-7 PI-3 IJ-3 15AOV-133A F-5 3 A 4.00 GL AO TM-2 CS4 PE-7 PI-3 IJ-3 15AOV-133B F-7 3 A 4.00 GL AO TM-2 CS4 PE-7 PI-3 IJ-3 REV. NO: 9 PAGE69OF150l
S [g 'N NEW YORK P O 13 E R AUTHORITY JAMES A FITZPATR ICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Building Closed Loop Cooling - SYSTEM ID: 15 DRAWINor FM-15B VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 15AOV-134A C-6 3 A 1.50 GL AO Df-2 CSS PE-7 PI-3 IJ-3 15RBC-35A D-4 3 C 1.50 SK SA RF-1 15RBC-25B D-8 3 C 1.50 SK SA RF-1 15RBC 35C D-3 3 C 1.50 SK SA RF-1 15RBC-35D E-9 3 C 1.50 SK c:A RF-1 15RBC-39A P -4 3 C 1.50 SK SA RF-1 15RBC-38B F-3 3 C 1.50 SK SA RF-1 15RBC-61 F-7 3 C 1.00 SK SA RF-1 REV. NO: 9 PAGE 70 OF 150
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JAMES A. FITEPATRICK NUCLEAR PCWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS' AND VALVES VALVE TABLE SYSTEM: Leak Rate Analyzer - SYSTEM ID: 16-1 DRANING: FM-49A VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACIUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 16-1AOV-101A D-7 2 A 0.37 GA AO m-1 V29 FC-1 ,
PI-3 IJ-3 V19 16-1AOV-101B E-7 2 A 0.37 GA AO M-1 V29 FC-1 PI-3 IJ-3 V19 16-1AOV-102A D-7 2 A 0.37 CA AO W-1 V29 FC-1 PI-3 IJ-3 V19 16-1AOV-102B C-7 2 A 0.37 GA AO TM-1 V29 FC-1 PI-3 IJ-3 vi9 i
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SYSTEM: Fuel Pool Cooling - SYSTEM ID: 19 DRANING: IN-19Ai VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACRfATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 19VB-1A G-5 3 C 1.50 RL SA RL-4 i 19VB-1B G-5 3 C 1.50 RL SA RL-4 t
J REV. NO: 9 PAGE 72 OF 150
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JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE 7ESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: High Pressure Coolant Injection - SYSTEM ID: 23 DRAWING: FM-25A:
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (1N) VALVE TYPE ACTtJATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 23AOV-39 B-5 2 B 1.00 GA AO 1M-1 V29 FC-1 .
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23AOV-42 G-2 2 B 1.00 GA AO TM-1 V29 FC-1 PI-3 23EFV-01A G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FICW LK-3 23EFV-01B G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FION LK-3 23EFV-02A G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 23EFV-02B G-7 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FION LK-3 23HOV-1 F-3 2 B 10.00 GL HO TM-1 V29 PI-3 23HPI-12 C-6 2 AC 16.00 LK SA FF-1 RF-1 V34 LJ-3 LJ-3 23HPI-13 C-7 2 C 2.00 SC SA MA FF-1 V35 DA-3 RF-2 CS16 23HPI-130 C-5 2 C 2.00 SK SA FF-1 V54 DA-3 PF-1 23HPI-18 F-7 1 C 14.00 CK SA ME-2 CS6 23HPI-32 G-5 2 C 16.00 CK SA FF-1 REV. NO: 9 PAGE 74 OF 150
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VALVE TABLE SYSTEM: High Pressure Coolant Injection' - SYSTEM ID: 23 DRAlf1NG: FM-25A VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS
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23HPI 402 E-7 .2 C 2.00 CK SA FF-2 V17 RF-2 V17 23HPI-403 E-7 2 C 2.00 CK SA FF-2 V17 RF-2 V17 23HPI-56 C-6 2 C 2.00 SK SA FF-1 V22 _DA-3 23HPI-61 B-7 2 C 16.00 CK SA FF-1 V9 DA 6
.PF-3 23HPI-62' F-4 2 C 4.00 CK SA FF-1 V47 DA-6 23HPI-65 C-6 2 AC 20.00 LK SA FF-1 RF*1 V34 IJ-3 IJ-3 23M3V-14 F-3 2 9 10.00 GA MO TM-1 PI-3 23MOV-15 F-7 1 A 10.00 GA MO TS-1 1M-1
-PI-3 IJ-3 V19 23MOV-16 F-7 1 A 10.00 GA . MO TS-1 1M-1 PI-3 IJ-3 V19 23MOV-17 G-5 2 B 16.00 GA MO TM-1 PI-3 22MOV-19 F-6 1 A 14.00 GA 90 1M-1 PI IJ-3 V19 REY. NO: 9 PAGE 75 OF 150
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JAMES A PITZPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM POR PUMPS 7. N D VALVES VALVE TABLE SYSTEM: High Pressure Coolant Injection - SYSTEM ID 23 DRAWING: FM-25A VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE AC'IUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 23MOV-20 F-6 2 B 14.00 GA MO m-1 PI-3 23MOV-21 G-6 2 B 8.00 GL MO TM-1 PI-3 23MOV-25 F-5 2 B 4.00 GL MO TS-1 TM-1 PI-3 23MOV-57 F-5 2 B 16.00 GA MO TM-1 PI-3 23MOV-58 C-7 2 B 16.00 GA MO TM-1 PI.3 23MOV-60 P-7 1 A 1.00 GL MO TS-1 PI-3 IJ-3 V19 23SV-34 F-6 2 C 1.00 RL SA RL-4 REY. NO: 9 PAGE 76 OF 150
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' VALVE- TABLE-SYSTDE: Containment Atmosphere Dilution - SYSTEM ID 27 DRANING 176-18A VALVE ID -DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE EECT. XI TEST RR / CS ALTERNATE TEST _,REMARRS' 27A0V-126A G-5 2 -- B 2.00 GL . AO 17t-1 V29 PI-3 27A07 1269 E-5 2 B 1.00 GL AO TM-1 V29 PI-3 27A0V-128A G-4 2 B 1.50 GL AO TM-1 V29 PI-3 27A0V-128B E-4 2 B 1.50 GL AO TM-1 V29 PI-3 27A0V-129A F-4 2 B 1.00 GL AO TM-1 V29 PI-3 27ACV-129H F-4 2 B 1.00 GL AO TM-1 V29 PI-3
'27 CAD-19A G-6 2 C 2.00 CK TA FF-1 27 CAD-19B C-6 2 C 2.00 CK SA FF-1 27SV-115A G-4 2 C 0.50 RL SA RL-4 275V-115B E-4 2 C 0.50 RL SA RL-4 27SV-118A G-5 2 C 0.50 RL . SA RL-4 275V-118B C-6 2 C 0.50 RL SA RL-4 REY. NO: 9 PAGE 77 OF 150
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NEW YORE P O V it R AUTHORITY JAMES A. FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTINO PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Containment Atmosphere Dilution - SYSTEM ID: 27 DRAWING: m-ISB .
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27A0V-101A C-6 2 A 20.00 BF AO m-1 FC-1 PI-3 I7-3 V19 27A0V-101B C-6 2 A 20.00 BF AO m-1 FC-1 PI-3 1.7- 3 V19 27A0V-111 C-2 2 A 24.00 BF AO TS-2 CS10 FC-2 CS10 PI-3 1.7-3 V19 27A0V-112 C-3 2 A 24.00 BF AO TS-2 CS10 FC-2 CS10 PI-3 1.7-3 V19 27A0V-113 D-B 2 A 24.00 BF AO TS-2 CS10 FC-2 CS10 PI-3 1.7-3 V19 27AOV-114 D-8 2 A 24.00 BF AO TS-2 CS10 FC-2 CS10 PI-3 1.7- 3 V19 27A0V-115 C-2 2 A 20.00 BF AO TS-2 CS10 FC-2 CS10 PI-3 1.7- 3 V19 27A0V-116 C-3 2 A 20.00 BP AO TS-2 CS10 FC-2 CS10 PI-3 IJ-3 V19 REV. NO: 9 FAGE 78 OF 150
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JAMES A. FITEPATRICK NUCLEAR 5 INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Cbntainment Atmosphere Dilution . SYSTEM ID: 27 DRAWING: EM-18B VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST RD'ARKS 27AOV-117 B-8 2 A 20.00 BF AO TS-1 FC-1 i PI-3 1.7- 3 V19
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27AOV-118 B-8 2 A 20.00 BF AO TS-1 FC-1 PI-3 I
1.7-3 V19 27AOV-131A C-4 2 A 1.50 GA AO TS-1 TM-1 I FC-1 PI.3 LJ-3 V19 27AOV-131B C-3 2 A 1.50 GA AO TS-1 TN-1 FC-1 PI-3 LJ-3 V19 27AOV-132A C-4 2 A 1.50 GA AO TS-1 1N-1 FC-1 PI-3 1.7-3 V19 27AOV-132B C-3 2 A 1.50 GA AO TS-1 TM-1 FC-1 PI-3 1.7-3 V19 27 CAD-67 C-4 2 AC 1.50 SK SA FF-1 RF-1 LJ-3 V19 REV. NO: 9 PAGE 79 OF 150
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N E 18 YORK P Olf'E R AUTHORITY JAMES A PITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE ? ABLE SYSTEM: Containment Atmosphere Dilution - SYSTEM ID: 27 DRAWING: m-18B VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYN ACTUA7OR fYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27 CAD-68 C-4 2 AC 1.50 SK SA FF-1 RF-1 LJ-3 V19 27 CAD-69 C-3 2 AC 1.50 SK SA FF-1 RF-1 LJ-3 V19 27 CAD-70 C-3 2 AC 1.50 SK SA FF-1 RF-1 Ia7- 3 V19 27MOV-113 C-8 2 A 3.00 BF MO TS-1 TM-1 PI-3 LJ-3 V19 27MOV-117 B-8 2 A 3.00 BF MO TS-1 2-1 PI-3 1.7-3 V19 27MOV-121 H-B 2 B 6.00 BF MO W-1 PI.3 27MOV-122 C-8 2 A 3.00 GL MO TS-1 m-1 PI-3 LJ.3 V19 27MOV-123 B-8 2 A 3.00 GL MO TS-1 TM-1 PI-3 LJ-3 V19 27SOV-125A F-5 2 A 1.00 GL SO m-1 V29 FC-1 PI-3 LJ-3 REV. NO: 9 PAGE 80 OF 150
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VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS- ALTERNATE TEST REMARKS 27SOV-125B F-4 2 A 1.00 GL SO TM-1 V29 FC-1 PI-3 LJ-3 27SOV-125C F-5 2 A 1.00 GL SO 1M-1 V29 FC-1 PI-3 1.7- 3 i
27SOV-125D F-4 2 A 1.00 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-135A E-5 2 A 1.00 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-135B F-5 2 A 1.00 GL SO TM-1 V29 FC-1 t PI-3 IJ-3 i i
27SOV-135C E-5 2 A 1.00 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-135D F-5 2 A 1.00 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27VB-1 C-6 2 AC 30.00 CK SA . M2-1 LK-3 V48 PI-3 REY. NO: 9 PAGE 81 OF 150
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JAMES A_ FITEPATRICK NUCLEAR ' POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Containment Atmosphere Dilution - SYSTEM ID: 27 DRAWING: FM-18B VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27VB-2 C-6 2 AC 30.00 CK SA ME-1 LK-3 V48 PI-3 27VB-3 C-6 2 AC 30.00 CK SA ME-1 LK-3 V48 PI-3 27VB-4 C-6 2 AC 30.00 CK SA ME-1 LK-3 V48 PI-3 27VB-5 C-6 2 AC 30.00 CK SA ME-1 LK-3 V48 PI-3 27VB-6 C-6 2 AC 20.00 CK SA ME-1 Im7 - 3 V19 PI-3 27VB-7 C-6 2 AC 20.00 CK SA ME-1 1.7- 3 Vi>
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- SYSTEM: Contairtment Atmosphere Dilution - SYSTEM ID: 27 DRAWING: FM-18D!
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT XI TEST RR / CS ALTERRATE TEST FDtARKS 27SOV-119El C-7 2 A 0.37 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-119E2 C-6 5 A 0.37 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27sOV-119F1 D-4 2 A 0.37 GL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-119F2 D-4 2 A 0.37 GI. 50 TM-1 V29 FC-1 PI-3 IJ-3 27SOV-120E1 F-6 2 A 0.37 GL SO IM-1 V29 FC-1 PI-3 LJ-3 27SOV-120E2 F-6 2 A C.37 CL SO TM-1 V29 FC-1 PI-3 IJ-3 27SOV-120F1 G-4 2 A d.37 GL SO TM-1 V29 FC-1 PI-3 IJ-3 2750V-120F2 G-4 2 A 0.37 GL SO 1M-1 V29 FC-1 PI-3 Ins .
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JAMES A. FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Cbntainment Atmosphere Dilution - SYSTEM ID: 27 DRAWINGr FM-18D.
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 27SOV-122E1 F-6 2 A 0.37 GL SO TM-1 V29 FC-1 PI.3 M-3 27SOV-122E2 F-6 2 A 0.37 GL SO 1M-1 V29 FC.1 PI-3 M-3 27SOV-122F1 G-4 2 A 0.37 GL SO 1M-1 V29 FC-1 PI.3 M.3 27SOV-122F2 G-4 2 A 0.37 GL SO IN-1 V29 FC-1 PI-3 M-3 27SOV-123E1 E-6 2 A 0.37 GL SO TM-1 V29 FC-1 PI-3 M-3 27SOV-123E2 E-6 2 A 0.37 GL SO TM-1 V29 FC-1 PI-3 M-3 27SOV-123F1 F-4 2 A 0.37 GL SO IM-1 V29 FC-1 PI-3 M-3 27SOV-123F2 F-4 2 A 0.37 GL SO IM-1 V29 FC-1 PI-3 U-3 REV. NO: 9 PAGE 84 OF 150
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FC-1 PI-3 LJ-3 27SOV-124F1 C-3 2 A 0.37 CL SO TM-1 V29 FC-1 PI_3 ,
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27*JOV-141 E-6 2 A 1.00 GL SO 1M-1 V29-PO-1 PI-3 LJ-3 27SOV-145 G-5 2 A 1.00 GL SO TM-1 V29 FO-1 PI-3 IJ-3 I
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,U k NEN YORK P O VE R AUTHORITY JAMES A FITZPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE STSTEP8: Main Steam - SYSTEM ID: 29 DRAWING: EM-29A VALVE ID DWG CO-OR CLASS VALVE CATEOORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 29AOV-80A E-5 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 V59 PI-3 IJ-3 V19 29AOV-80B D-5 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CICSE TIME 3-5 SEC FC-2 V59 PI-3 IJ-3 V19 29AOV-80C D-5 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CIDSE TIME 3-5 SEC FC-2 V59 PI-3 IJ-3 vi9 29AOV-80D D-5 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 V59 PI-3 IJ-3 V19 297.OV-86A G-4 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 CS12 PI-3 IJ-3 V19 29AOV-86B F-4 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CICSE TIME 3-5 SEC FC-2 CS12 PI-3 IJ-3 V19 29AOV-86C E-4 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CICSE TIME 3-5 SEC FC-2 CS12 PI-3 IJ-3 V19 29AOV-86D D-4 1 A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CIDSE TIME 3-5 SEC FC-2 CS12 PI-3 LJ-3 V19 REV. NO: 9 PAGE 87 OF 150
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POWER' AUTHORITY JAMES- A. FITZPATRICK ' NUCLEAR. POWER PLANT ,
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES f L
VALVE TABLE ;
j .i SYSTEM: Main Steam - SYSTEM ID: 29 t DRANING: FM-29A:
?. I t
! VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE AC'IUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST.. REMARKS .
..........................____.............___.___..__..................___......_____.__.......___.___......................................._____.........__......_......_i 1
29EFV-30A F-5 1- AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EICESS FIDW LK-3 i d t t
i 29EFV-30B F-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIbet f ,
LK-3 29EFV-30C F-5 1 AC 1.00 BK SA LK-1 V28 LK-3. VALVE ISOIATES ON EXCESS FIDW LK-3 -!
29EFV-30D F-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FICIf 5
LK-3 "
x 29EFV-34A F-8 1 AC 1.00 BK SA LK-1 V2 8 ' LK-3 VALVE ISOIATES ON EXCESS FLOts !
LK-3
?
29EFV-34B F-8 1 AC 1.00 BK SA LK-1 V28 'LK-3' VALVE ISOLATES ON EXCESS FLOW LK-3 ,
i l 29EFV-34C F-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES CN EXCESS FLOW l
LK-3 i 6
i 29EFV-34D F-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS F14W [
LK-3 I
'. LK-3 i .
29EFV-53B E-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOIATES ON EXCESS FLOW ,
i LK-3 29EFV-53C E-8 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FIDW
! 'LK-3' .
t
, - LL 29EFV-53D E-B 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW L L
LK-3
}
a 29EFV-54A E-5 1 AC . 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FICW L
j LK-3 f
I REV. NO: 9 PAGE 88 OF 150 l
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POWER AUTHORITY V
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM POR PUMPS AND VALVES VALVE TABLE SYSTEM: Main Steam - SYSTEM ID: 29 DRAWING: FM-29A.
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE AC'ItJATOR TYPE SECT. II TEST RR / CS ALTERNATE TEST REMARKS 29EFV-54B E-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS F14W LK-3 29EPT-54C E-5 1 AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 29EFV-54D E-5 1 AC !.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 29MOV-200A C-3 2 B 1.00 GL MO W-1 PI-3 29MOV-200B B-3 2 B 1.00 GL MO TM-1 PI-3 2SMOV-201A C-3 2 B 1.00 GL MO W-1 PI-3 29MOV-201B B-3 2 B 1.00 GL MO M-1 PI-3 2SMOV-202A C-3 2 B 1.00 GL MO W-1 PI-3 l 29MOV-202B B-3 2 B 1.00 GL MO W-1 PI-3 2SMOV-203A H-3 2 B 1.00 GL MO TM-2 CS13 PI-3 i 29MOV-203B H-3 2 B 1.00 GL MO TM-2 CS13 PI-3 29MOV-204A C-3 2 B 1.00 GL MO 2-1 PI-3 29MOV-2049 B-3 2 B 1.00 GL MO N-1 PI-3 I
REY. NO: 9 PAGE 89 OF 150
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% N NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTINO PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Main Steam - SYSTEM ID: 29 DRAWING: FM-29A,'
VALVE ID DWG CO-OR CIASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 29MOV-74 C-6 1 A 3.00 G.T MO TS-1 PI.3 1.7-3 29MOV-77 C-5 1 A 3.00 GA MO TS-1 PI-3 1.7-3 I
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i REV, NO: 9 FAGE 90 OF 150 .
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P tl V E R AUTHORITY V a J A ll E S A. FITZPATRICK NUCLEAR P O N E R' PLANT
- INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM
- Feedwater System . SYSTEM ID: 34 DRAMING: IN.34A' VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 34fMS-28A E-7 1 AC 18.00 CK SA RF-1 V12 LJ-3 IJ-3 34FWS-28B F-7 1 AC 18.00 CK SA FF-1 RF-1 V12 LJ-3 .
IJ-3 34NRV-111A E-7 1 AC 18.00 NK SA AO RF-2 CS9 IJ-3 V19 34NRV-111B F-7 1 AC 18.00 NK SA AO RF-2 CS9 IJ-3 V19 ,
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REY. NO: 9 PAGE 91 OF 150 l 1
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[f~sv\ NEW YORK POWER ks% AUTHORITY v
JAMES A FITZPATRICK NUCLEAR PONER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Instrument Air System - SYSTEM ID: 39 DRAWING: FM-39C VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 39IAS-22 E-5 2 AC 2.00 CK SA FF-2 V14 RF-1 IJ-3 391AS-29 F.3 2 AC 1.00 CK SA FF-2 V14 RF-1 IJ-3 t
REV. NO: 9 PAGE 92 OF 150 i
_ ___ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ___________._____m _ _ _ _ _ _
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/D N/ NEW YORK P'& V E R AUTHORITY %d' JAMES A PITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTINO PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Service Water - SYSTEM ID: 46 DRAWIltG: FB-10H VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 46SMS-60A C-5 3 C 4.00 CK SA RF-1 46SWS-60B C-5 3 C 4.00 CK SA RF-1 3
66PCV-101 D-3 3 8 3.00 GL AO FO-1 66TCV-107E C-4 3 B 2.50 GL AO FO-1 66TCV-107F C-7 3 B 2.50 GL AO FO-1 1
i REV. NO: 9 :
PAGE 93 OF 150 t
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YORK P U +/E R AUTHORITY JAMES A. FITEPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROCRAh FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Emergency Service Water - SYSTEM ID: 46 DRAWING: FB-35E VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACITJATOR TYPE SECY. XI TEST RR / CS ALTERNATE TEST REMARKS 46 (70) ESN-101 G-6 3 B 4.00 GA MA FS-1 V49 FS-3 46(70)ESW-102 C-6 3 B 4.00 GA MA FS-1 V49 FS-3 46(70)ESW-103 F-6 3 B 4.00 GA MA FS-1 V49 FS-3 46(70)ESW-104 C-6 3 B 4.00 GA MA FS-1 V49 FS-3 4S(70)SWS-101 H-8 3 C 6.00 CK SA RF-1 46(70)SWS-102 H-8 3 C 6.00 CK SA RF-1 46(70)SMS-13 G-4 3 B 6.00 GL MA FS-1 46(70)SWS-14 E-4 3 B 6.00 GL MA FS-1 70TCV-120A F-7 3 B 2.00 3W AO FO-1 70TCV-120B C-6 3 B 2.00 3W AO FO- 1 70TCV-121A F-6 3 B 2.00 3W AO FO-1 70TCV-121B C-7 3 B 2.00 3W AO FO-1 70NAC-12A F-6 3 B 4.00 GA MA FS-1 70'ZAC-12B C-6 3 8 4.00 GA MA FS-1 70NI.C-5A F-2 3 8 4.00 GA MA FS-1 70WAC-5B D-2 ? B (.00 GA MA FS-1 REV. NO: 9 PAGE 94 OF 150
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V h x .. V NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TEST 1NO PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEM: Emergency Service Water - SYSTEM ID: 46 DRAWING; FM-46A ;
VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACIUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 46ESW-19A B-6 3 C 2.00 SK SA FF.1 46ESW-20B B-8 3 C ,
2.00 SK SA FF-1 46ESW-21B B-8 3 C 2.00 SK SA FF-1 46ES2-22A B-7 3 C 2.00 SK SA FF-1 46STS-67A B-6 3 C 3.00 CK SA RF-1 4GSWS-67B B-7 3 C 3.00 CK SA RF-1 46 SUS-68 B-6 3 C 3.00 CK SA RF-1 46SWS-69 B-8 3 C 3.00 CK SA RF-1 67PCV-101 D-2 3 B 2.50 GL AO FO.1 RW. NO: 9 PAGE 95 OF 150
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P O'M E R AUTHORITY L]
JAMES A FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE .
SYSTEM: Emergency Service Water - SYSTEM IDr 46 DRAWING: IN-4 6B VALVE ID DWG CO-OL CLASS VALVE CATEGORY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 46ES3-13A E-3 3 C 3.00 CK SA FF-1 4 6ES;3-13 B C-2 3 C 3.00 CK SA FF-1 46ESW-1A E-7 3 C 12.00 CK SA FF-1 45ESW-1B D-7 3 C 12.00 CK SA FF-1 46ES3-40A E-S 3 C 1.00 CK SA RF-1 4 6ES3-4 0B E-4 3 C 1.00 CK SA RF-1 46ES'-7A E-S 3 C 6.00 CK SA FF-1 f
46ESW-7B E-S 3 C 6.00 CK SA FF-1 46ESW-9A E-4 3 C 8.00 CK SA FF-1 46EST-9B D-4 3 C 8.00 CK SA FF-1 46MOV-101A E-6 3 B 10.00 GA MO 'IN - 1 PI-3 46MOV-101B D-6 3 B 10.00 GA MO TM-1 PI-3 46MOV-102A E-6 3 B 8.00 GA MO TM-1 PI-3 46MOV-102B D-6 3 B 8.00 GA MO TM-1 PI-3 REV. NO:. 9 PAGE 96 OF 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Cold Shutdown Justifications
- 1. SYSTEM: REACTOR WATER RECIRCULATION (RWR)
COMPONENTS: 02MOV-53A, B CATEGORY: B SKFETY FUNCTION: These valves close, on low reactor pressure to isolate the faulted loop coincident with initiation of the RHR System in the LPCI mode, to prevent diversion of LPCI flow.
JUSTIFICATION: In order to exercise these valves, the respective recirculation pump must'be secured.
Securing either pump- (single loop operation) is limited by Technical Specification requirements and is not prudent. Single loop operation also requires a reduction in power.
- 2. SYSTEM: RESIDUAL HEAT REMOVAL COMPONENTS: 10AOV-68A, B CATEGORY: A,C s
SAFETY FUNCTION: These valves open to provide flowpaths for LPCI and core spray injection to the reactor vessel.
They close for pressure isolation from the reactor vessel.
JUSTIFICATION: With the reactor at operating pressure, the RHR pumps cannot develop sufficient discharge pres-sure to open these valves. The installed air operators are designed to open these valves at zero differential pressure which is not practical ;
with the reactor at operating pressure.
Therefore, these valves cannot be full or part-stroke exercised during normal. plant operation.
Since there is no position indication for these ;
valves, closure verification must be done by backflow testing. Such testing during plant operation is impractical due to personnel safety concerns related to the potential release of radioactive steam at high pressure.
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,g Rev. No. 9 Page 97 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
{ INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
,p APPENDIX B Cold Shutdown Justifications
- 3. SYSTEM: RESIDUAL HEAT REMOVAL COMPONENTS: 10MOV-17 and 10MOV-18 CATEGDRY: A 1
SAFETY FUNCTION: These valves remain closed to protect the RHR System piping and components from over- i pressurization during plant operation and !
inadvertent drain down events while in cold shutdown. They also perform a containment isolation function.
JUSTIFICATION: With the reactor pressure greater than 75 psig, these valves are prevented from opening by an l
electrical interlock. l
- 4. SYSTEM: REACTOR BUILDING CLOSED LOOP COOLING COMPONENTS: 15AOV-132A, B; 15AOV-133A, B CATEGORY: A
~
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_. SAFETY FUNCTION: These valves close to provide containment x isolation.
JUSTIFICATION: During normal plant operation, these valves must remain open to provide cooling water to the ,
recirculation pump motor and seal coolers. l Closing these valves would result in damage to '
the recirculation pumps.
- 5. SYSTEM: REACTOR BUILDING CLOSED LOOP COOLING COMPONENTS: 15AOV-130A, B; 15AOV-131A, B; 15AOV-134A CATEGORY: A SAFETY FUNCTION: These valves close to provide containment isolation. I JUSTIFICATION: During plant operation, these valves must remain open to provide cooling water to the Drywell coolers and Drywell equipment drain sump cooler.
Closing these valves during operation could cause a spike in Drywell pressure due to the loss of cooling water flow which may result a reactor scram and plant shutdown.
Rev. No. 9 Page 98 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B I
v}
- 6. SYSTEM: HIGH PRESSURE COOLANT INJECTION COMPONENT: 23HPI-18 CATEGORY: C SAFETY FUNCTION: This valve opens to provide a flowpath for the HPCI system injection to the reactor vessel. l JUSTIFICATION: With the reactor at operating pressure, the HPCI i pump can develop sufficient discharge pressure to open this valve, however HPCI injection of cold j water to the reactor vessel during critical l operation could result in an undesirable l reactivity excursion and thermal transient to the piping components. During plant operation the differential pressure developed across the valve l disc could be in excess of 1000 psid - precluding !
manual manipulation of the valve. Therefore, I these valves cannot be exercised during normal l plant operation.
l fT 7. SYSTEM: CONTROL ROD DRIVE HYDRAULICS Y )
COMPONENTS: 03HCU-115 (Typical for 137 HCUs) CATEGORY: C SAFETY FUNCTION: These valves close on initiation of a scram to prevent diversion of scram drive water flow into a depressurized charging header.
JUSTIFICATION: Exercising these valves during operation would require depressurization of the charging header with the potential for a loss of scram function.
- 8. DELETED
- 9. SYSTEM: FEEDWATER COMPONENTS: 34NRV-111A,B CATEGORY: A,C SAFETY FUNCTION: These valves close to provide containment isolation and to prevent diversion of HPCI flow into the feedwater system.
JUSTIFICATION: Exercising these valves during operation would 7s require isolation of feedwater flow to the
(
\ ') reactor vessel. This not prudent nor practical without a plant shutdown.
Rev. No. 9 Page 99 of 150
.NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- I N S E R V I C E T E S T I N G P R O G R A M F O R P U M P S A N D V A_ M E R l
l i e APPENDIX B O
- 10. SYSTEM: CONTAINMENT VENT & PURGE COMPONENTS: 27AOV-111, 112, 113, 114, 115, 116 CATEGORY: A 1
SAFETY FUNCTION: These valves close to provide a containment {
isolation function.
JUSTIFICATION: Due to NRC concerns that these valves will not !
close under Design Basis Accident conditions, I they will not be opened whenever primary l containment is required except for safety-related I reasons. For this reason these valves will be tested at cold shutdown when primary containment is not required.
- 11. DELETED p
- 12. SYSTEM: MAIN STEAM COMPONENTS: 29AOV-86A, B, C, D CATEGORY: A SAFETY FUNCTION: These valves close to provide containment isolation.
JUSTIFICATION: Performance of the fail close test for the MSIVs requires entry into the Steam Tunnel. This cannot be done during normal operation.
- 13. SYSTEM: MAIN STEAM COMPONENTS: 29MOV-203A, B CATEGORY: B SAFETY FUNCTION: These valves open to provide flowpaths for post-accident MSIV packing leak-off to the standby gas treatment system.
JUSTIFICATION: Opening these valves during power operation could subject downstream piping to pressures in excess of its 150 psi design pressure.
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Rev. No. 9 Page 100 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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- 14. DELETED
- 15. DELETED
- 16. SYSTEM: HIGH PRESSURE COOLANT INJECTION COMPONENT: 23HPI-13 SAFETY FUNCTION: This valve opens to allow condensate drainage from the steam exhaust piping to the suppression chamber. It closes for containment isolation.
JUSTIFICATION: Closure verification for this valve is accomplished by performing a back flow test where the drain line is isolated from the-steam exhaust line and the torus is vented to atmosphere.
Placing the HPIC system and containment in this configuration during plant operation is undesirable and could adversely affect the
S plant's response in the event of an accident. ;
G
- 17. SYSTEM: REACTOR COOLANT ISOLATION COOLING l COMPONENT: 13RCIC-37 and 13RCIC-38 SAFETY FUNCTION: These valves open to eliminate any differential pressure that could force water from the suppression chamber into the RCIC steam exhaust piping when the suppression chamber pressure is greater than atmospheric.
JUSTIFICATION: Verifying proper operation of these valves involves a test that requires isolation of the vacuum breakers for an extended period of time.
During this test the RCIC System is considered to be inoperable. Due to operational concerns associated with the plant's response to possible transients without an operable RCIC system, it is considered to be imprudent to test these valves while the plant is operational.
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%J Rev. No. 9 Page 101 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B V
- 18. SYSTEM: REACTOR COOLANT ISOLATION COOLING COMPONENT: 13RCIC-7 SAFETY FUNCTION: This valve opens to allow condensate drainage from the steam exhaust piping to the suppression chamber. It closes for containment isolation.
JUSTIFICATION: Closure verification for this valve is accomplished by performing a back flow test where the drain line is isolated from the steam exhaust -
line. Placing the RCIC system in this configuration during plant operation is undesirable- and could adversely' affect the plant's response in the event of a transient.
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I Rev. No. 9 Page 102 of 150
NEW YORK POWER AUTHORITY' JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests NOTE V1 SYSTEM: Reactor Water; Recirculation (RWR)
VALVES: 02-2RWR-13A, B CATEGORY: A,C CLASS: 1 ,
- FUNCTION: These' recirculation pump seal. water injection valves close to provide containment isolation.
TEST REQUIREMENT: Per IWV-3521, exercise valves closed every three ,
months. -
BASIS FOR RELIEF: To test during normal operations or cold shutdown !
requires securing the RWR pumps and entering q containment to check the valves closed via a back-
_h leakage test. Testing therefore impossible and, during operation -is during cold shutdown, ;
performing back-leakage tests would place an undue i burden on the plant staff.
ALTERNATE TESTING: During each refuel outage, these normally ' open <
valves will be verified to close during leak '
testing performed per 10CFR50, Appendix J.
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Rev. No. 9 Page 103 of 150 i
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l APPENDIX B Valve Relief Recuests NOTE V2 SYSTEM: Control Rod Drive (CRD)
VALVES: 03AOV-126 03HCU-114 03AOV-127
, CATEGORY: B C l CLASS: 2 2 FUNCTION: During a reactor scram, 03AOV-126 and -127 receive a signal to open and thus allow the scram charging water flow from the HCU accumulators to the CRD mechanism and the scram discharge water flow from the CRD mechanism to the scram discharge volumes.
Check valve 03HCU-114 is located downstream of 03AOV-127, and opens to permit scram discharge flow.
TEST REQUIREMENT: Per IWV-3411, . exercise these valves for operability ph every three months.
Per IWV-3413 (b) , the stroke time of all power-operated valves shall be measured.
BASIS FOR RELIEF: Exercising these valves quarterly during power .
operations would result in rapid insertion of i control rods. This is undesirable because of subjecting the reactor core to rapid reactivity transients The AOVs are fast-acting valves with full-stroke time within a fraction of a second and are not equipped with indication of both open and close position. Direct measurement of full stroke time is impractical.
ALTERNATE TESTING: These valves will be tested in accordance with the JAF Technical Specification scram time test requirements as follows: l e 10% of all operable control rods shall be j scram time tested every 16 weeks (TS Section 1 4.3.C.2) v I Rev. No. 9 Page 104 of 150 l
NEW YORK POWER AUTHORITY JAMES A.'FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
-f APPENDIX B Valve Relief Recuests NOTE V2 (cont'd.)
e All operable control rods shall be scram time tested after each refueling outage with reactor pressure above 950 psig (TS Section 4.3.C.1).
In all cases the measured scram time will be evaluated. A satisfactory scram time test verifies l
- proper operation of these valves. '
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l NOTE V3 This relief request has been withdrawn.
I NOTE V4 This relief request has been withdrawn.
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Rev. No. 9 Page 105 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests NOTE V5 i
SYSTEM: Standby Liquid Control (SLC)
VALVES: 11SLC-16 11SLC-17 CATEGORY: A,C
' CLASS: 1 FUNCTION: These valves prohibit backflow from the reactor ,
vessel to the SLC System and provide for l containment isolation. They open to permit SLC System flow to the reactor vessel.
TEST REQUIREMENT: Per IWV-3521, exercise valves every three months.
BASIS FOR RELIEF: Full or partial-stroke exercising these valves
( requires that flow be established through the subject check valves. The only practical means of initiating flow through these valves requires actuation of the SLC system and pumping from the SLC Tank to the reactor vessel. This would introduce boron into the reactor vessel resulting l in unacceptable reactivity and chemistry transients. l Testing during cold. shutdown would i result in chemistry transients and undue burden on the plant staff with respect to maintenance of the SLC Pump explosive valves.
l ALTERNATE TESTING: Once during each operating cycle (normally a refuel outage) and as required by Technical Specifications, the valves shall be cycled open by injecting water into the reactor vessel by use of the Standby Liquid Control pumps.
Following the exercise test as described above, the valves will be verified to close by means of a :
leakrate test performed per 10CFR50, Appendix J.
O Rev. No. 9 Page 106 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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Valve Relief Reauests NOTE V6 SYSTEM: Reactor Core Isolation Cooling VALVES: 13RCIC-04 13RCIC-05 i CATEGORY: A,C ;
CLASS: 2 !
l 1
FUNCTION: These valves close to provide containment i isolation. i l
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TEST REQUIREMENT: Per IWV-3521, exercise these valves closed every i three months. i BASIS FOR RELIEF: These valves are exercised open during RCIC surveillance testing performed periodically during
[) plant operations in accordance with the JAF
'N_ / Technical Specifications. Since there is no provision on either of these valves that provides ;
position indication of the disc, valve closure must be verified by backflow or leakage testing. j In order to verify valve closure by the backflow technique, the RCIC exhaust line must be isolated l for the duration of the test causing the RCIC System to be inoperable. The potential safety impact of voluntarily placing the RCIC System in an inoperable status during plant operation at power is considered to be imprudent and unwarranted in relation to any apparent gain in system reliability derived from the closure verification. In addition, the valves are located approximately twenty (20) feet from the floor necessitating erection of a large scaffold in the vicinity of the RCIC pump. This also is considered to be undesirable from the aspect of potential damage to RCIC System components should the scaffold be subjected to structural failure.
V Rev. No. 9 Page 107 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j'
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
( APPENDIX B V
Valve Relief Recuests NOTE V6 (cont'd.) I Based on the foregoing discussion, testing of these valves during plant operation at power is considered to be impractical. During cold shutdowns, erection of the scaffold in addition to other activities related to test performance would place an extreme burden on the plant staff and would likely result in unwarranted extensions to all forced outages with the added negative impact on plant performance and availability.
Verifying closure' of these valves during each refuel outage will provide sufficient assurance that the valves will continue to be operable with respect to their capability to close.
ALTERNATE TESTING: At each refueling outage, these valves will be verified to close in conjunction with leak testing performed per 10CFR50, Appendix J.
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v NOTE V7 This relief request has been withdrawn.
NOTE V8 This relief request has been withdrawn.
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O Rev. No. 9 Page 108 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests NOTE V9 SYSTEM: High Pressure Coolant Injection (HPCI)
VALVE: 23HPI-61 CATEGORY: C CLASS: 2 FUNCTION: This valve opens to provide a flowpath from the suppression chamber to the suction of the HPCI booster pump.
TEST REQUIREMENT: Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF: The only practical method available to full flow exercise this valve is to pump water from the sup-pression pool into the reactor vessel or the Di Condensate Storage Tank. Due to the lack of V suitable water quality in the suppression pool, neither of these options is practical.
ALTERNATE TESTING: This valve will be partial-flow tested once per operating cycle.
At least once every six (6) years this valve will.
be disassembled, inspected, and verified to be operable.
NOTE V10 This relief request has been withdrawn.
NOTE Vil This relief request has been withdrawn.
Rev. No. 9 Page 109 of 150
NEW YORK POWER AUTHORITY I JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l
APPENDIX B
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C/ 1 Valve Relief Recuests I
NOTE V12 SYSTEM: Feedwater System VALVES: 34FWS-28A, B l
CATEGORY: A,C l CLASS: 1 FUNCTION: These valves close for containment isolation upon l cessation of feedwater flow during accident I conditions.
TEST REQUIREMENT: Per IWV-3521, exercise these valves closed every j three months. 1 l
BASIS FOR RELIEF: There are no position indicators on these valves or other means to verify closure, thus, the only l practical means of verifying closure is to perform i (3 a backflow or leakage test. Performing such a test !
() requires entry into the containment vessel and I extensive system preparations, including draining of the main feedwater piping from the outlet of the ;
sixth point feedwater heaters to the reactor vessel I isolation valves (approximately 2000 gallons per line). Furthermore, testing of 34FWS-28B requires I shutdown of the cleanup system. It is estimated that testing of either of these valves would require up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and demand significant staff l resources. l During plant operation at power, these valves cannot be closed without precipitating a plant shutdown.
Verifying closure of these valves during each i refuel outage will provide sufficient assurance i that the valves continue to be operable with respect to their capability to close.
l ALTERNATE TESTING: At each refueling outage, these valves will be l verified to close in conjunction with leak testing performed per 10CFR50, Appendix J. l
,Ch, L.j' Rev. No. 9 Page 110 of 150 l 1
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR-POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES ,
APPENDIX B O
i Valve Relief Recuests NOTE V13 This relief request has been withdrawn.
NOTE Vl_4_4 SYSTEM: Instrument Air i
VALVES: 39IAS-22 39IAS-29 CATEGORY: A,C CLASS: 2 FUNCTION: These valves open to provide nitrogen to the MSIV's and the SRV accumulators inside the containment.
I They close for containment isolation.
TEST REQUIREMENTS: Per IWV-3521, exercise these valves open every three months.
l BASIS FOR RELIEF: Exercising these valves (open) is performed by t
charging the bleed-down header following MSIV testing. During plant operation at power, this is impractical since closure of the MSIV's would cause j a plant trip. Also, performing such a test requires entry into the containment vessel and local manipulation of test connections located inside the drywell. During plant operation at power and, on occasion, while in the cold shutdown ;
mode, the containment atmosphere is maintained in a '
nitrogen-inerted condition. During such periods, entry into the containment is not practical due to personnel safety concerns.
ALTERNATE TESTING: These valves will be exercised (open) during cold shutdown periods when the containment is de-inerted consistent with the requirements of IWV-3522 and l the provisions of Note V51.
NOTE V15 This relief request has been withdrawn.
NOTE V16 This relief request has been withdrawn.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
()
Valve Relief Reauests NOTE V17 SYSTEM: High Pressure Coolant Injection I
VALVES: 23HPI-402 23HPI-403 CATEGORY: C j 1
CLASS: 2 FUNCTION: These valves open to eliminate any differential pressure that could force water from the suppression chamber into the HPCI exhaust piping :
when the suppression chamber pressure is greater I than atmospheric. They .ose to prevent HPCI l exhaust steam from entering the suppression chamber air space, thus bypassing the quenching action of the suppression pool.
('., TEST REQUIREMENTS: Per IWV-3521, exercise these valves open and closed (j every three months.
BASIS FOR RELIEF: There are no position indicators on these valves or I other means for verifying valve closure, thus the only practical means of verifying closure is to perform a backflow or leakage test. Since the i valves are installed in series with no intermediate i test tap, verifying that each individual valve l closes is not practical.
In order to perform the cpecified safety function in the closed direction, only one valve of the pair needs to close. Thus, verifying that either valve closes is adequate to demonstrate reliable ;
operation of the pair. i Operation of the HPCI pump turbine itself does not prove operability of these valves and special testing is required. This testing necessitates isolation of the vacuum breaker piping which, in turn, results in the inoperability of the HPCI System for the duration of the test. Due to the importance of the HPCI system function and the lack of a redundant HPCI train, it is not considered prudent to perform this testing during
/,,) operation at power.
plant
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Rev. No. 9 Page 112 of 150
NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT '
INSERVICE TESTING PROGRAM FOR PUMPS A_Mn VALVES i
APPENDIX B '
Valve Relief Reauests 1 f l :
NOTE V17 (cont' Q f l r ALTERNATE TESTING: These valves will be exercised open and the pair (at least one valve) will be verified to close during cold shutdown periods per IWV-3522. Should the closure test of both valves fail, then corrective action will be applied to both valves prior to returning the system to operability.
NOTE V18 This relief request is withdrawn.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B G
V .
L Valve Relief Recuests NOTE V19 l SYSTEM: Containment Isolation Valves VALVES: See Valve List Attached !
CATEGORY: A !
CLASS: See-Valve List Attached FUNCTION: Containment Isolation.
A TEST REQUIREMENT: Per IWV-3426, measure individual containment isolation valves leak rates.
BASIS FOR RELIEF: By original plant design, these valves are tested i in established groupings to determine a penetration leak rate. The Appendix J, Type C LLRT test methodology has been reviewed and addressed in p Section 3.7 of the Technical Specifications.
ALTERNATE TESTING: Test these containment isolation valves by the original design groupings. -
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l NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
,es APPENDIX B ;
I Valve Relief Reauests !
l NOTE V19 (cont.)
VALVE ID CLASS VALVE ID CLASS 10MOV-26A,B 2 27AOV-113 2 1 10MOV-31A,B 2 27AOV-114 2 10MOV-38A,B 2 27AOV-115 2 10MOV-39A,B 2 27AOV-116 2
{
10RHR-52A,B 2 27AOV _17 2 4 12MOV-69 1 27AOV-118 2 )
13MOV-15 1 27AOV-131A,B 2 13MOV-16 1 27AOV-132A,B 2 13MOV-21 1 27 CAD-67,68,69,70 2 e-'g 27MOV-113 2
\s /' 27MOV-117 2 16-1A0V-101A,B 2 27MOV-122 2 16-1AOV-102A,B 2 27MOV-123 2 23MOV-15 1 27VB-6 2 23MOV-16 1 27VB-7 2 23MOV-19 1 29AOV-80A,B,C,D 1 23MOV-60 1 29AOV-86A,B,C,D 1 27AOV-101A,B 2 34NRV-111A,B 1 27AOV-111 2 27AOV-112 2 O
I Rev. No. 9 Page 115 of 150 ,
NEW YORK POWER' AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l INSERVICE TESTING' PROGRAM FOR PUMPS AND VALVES APPENDIX B I Valve Relief Recuests NOTE V20 This relief request has been withdrawn.
NOTE V21 This relief request has been withdrawn.
NOTE V22 i SYSTEM: High Pressure Coolant Injection VALVE: 23HPI-56 l
CATEGORY: C CLASS: 2 FUNCTION: Opens to permit HPCI turbine condensate to drain to the suppression chamber.
TEST REQUIREMENTS: Per IWV-3521, exercise this valve open every A three months.
N BASIS FOR RELIEF: There is no means for exercising this valve to the open position where positive indication of acceptable valve performance is verified.
ALTERNATE TESTING: In accordance with Generic Letter 89-04 Position 2, at least once during each operating cycle (normally a refuel outage) the valve will be disassembled, inspected, and verified to be operable.
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NEW YORK POWER AUTHORITY JAMES A._FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4
- APPENDIX B
! Valve Relief Recuests i 1 l NOTE V23 This relief request has been withdrawn.
i f
j NOTE V24 This relief request has been withdrawn.
NOTE V25 This relief request has been withdrawn.
i NOTE V26 This relief request has been withdrawn.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES p APPENDIX B
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Valve Relief Recuests NOTE V27 SYSTEM: A'utomatic Depressurization (ADS)/ Main Steam VALVES: 02RV-71A,B,C,D,E,F,G,H,J,K and L CATEGORY: B,C CLASS: 1 FUNCTION: All these valves are required to open when actuated by manual switch to relieve reactor pressure during an accident or transient condition. Valves 02RV-71A,B,C,D,E,G, and H open upon receipt of ADS actuation signal.
TEST REQUIREMENT: Per IWV-3411 and 3413 (b) , exercise and measure the stroke time every three months.
BASIS FOR RELIEF: These valves are fast-acting valves and do not have O position indication. Therefore, stroke time cannot
~b be effectively measured.
When testing these valves, a reactor pressure of at least 50 psig is needed for opening by the pilot '
assembly and a minimum reactor pressure of 940 psig j is specified to minimize potential damage to the i pilot valve and disc surfaces. Testing at each j start-up from a cold shutdown condition would produce additional stress cycles which may lead to a low cycle fatigue failure.
ALTERNATE TESTING: Following each refuel outage or once each operating cycle with reactor pressure at least 940 psig, I these valves will be exercised in accordance with i the operational test r equirements set forth in the '
JAP Technical Specifications. SRV tailpipe temperature and acoustic monitors will be used to verify valve opening. Additionally, in accordance with Technical Specification requirements, the pilot assembly for each SRV will be bench tested at least once every two operating cycles. The bench testing includes "as-found" setpoint, leakage and pilot disc sticking tests.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
, APPENDIX B Valve Relief Recuests NOTE V27 (cont.)
In addition to the pilot assembly bench testing, -
refurbishment is performed, if necessary, in accordance with the valve manufacturer's procedure including inspection of the pilot valve stem labyrinth seal area. This program of testing, ;
inspections, and maintenance is performed in- ,
accordance with the related BWROG recommendations '
to monitor and resolve setpoint drift problems. '
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE _S_
m APPENDIX B Valve Relief Recuests NOTE V28 SYSTEM: Various VALVES: Excess Flow Check Valves' (Attached)
CATEGORY: A,C CLASS: 1 FUNCTION: These valves close to isolate the respective instrument lines in the event of a pipe break downstream of the valves.
TEST REQUIREMENT: Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF: Testing these valves requires isolation of their associated safety-related instrument which could place the plant in an unsafe condition. In O addition, the induced hydraulic transients V resulting from establishing flow and subsequent valve closure would most likely result in an engineered safety feature actuation. During such testing, radiation doses to test personnel would be high due to the location of these valves and effluence of reactor water during the test. These valves have proven to be highly reliable and testing at the Code-required frequency would not significantly increase the reliability of these valves.
ALTERNATE TESTING: Exercise these valves closed for operability once each operating cycle.
v Rev. No. 9 Page 120 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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Valve Relief Recuests NOTE V28 (cont.) !
EXCESS FLOW CHECK VALVES 02-2EFV-PS-128A,B 02-3EFV-11 02-3EFV-23 02-2EFV-PT-24A,B 02-3EFV-13A,B 02-3EFV-25 02-2EFV-PT-25A,B 02-3EFV-15A,B 02-3EFV-31A,B,C,D 02-2EFV1-DPT-111A,B 02-3EFV-15N 02-3EFV-31E,F,G,H 02-2EFV1-FT-110A,C,E,G 02-3EFV-17A,B 02-3EFV-31J,K,L,M 02-2EFV2-DPT-111A,B 02-3EFV-19A,B 02-3EFV-31N,P,R,S 02-2EFV2-FT-110A,C,E,G 02-3EFV-21A,B,C,D 02-3EFV-33 02-3EFV-23A,B,C,D 13EFV-01A,B 14EFV-31A,B 13EFV-02A,B 23EFV-01A,B 29EFV-30A,B,C,D 29EFV-53A,B,C,D 23EFV-02A,B 29EFV-34A,B,C,D 29EFV-54A,B,C,D O
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O Rev. No. 9 Page 121 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVEE
- p. APPENDIX B Valve Relief Recuests
-NOTE V29 SYSTEM: Various VALVES: Fast Acting Valves (Attached)
CATEGORY: See Valve List on Next Page CLASS: See Valve List on Next Page FUNCTION: See Valve List on Next Page TEST REQUIREMENT: Valve stroke time shall be evaluated and test intervals changed with respect to corrective action requirements of IWV-3417 (a) .
BASIS FOR RELIEF: The measured stroke times of these valves are consistently well below two (2) seconds and can vary significantly due to circumstances unrelated to the condition of the valves. Two reasons for
(~ these variations are inconsistency of operator
\
reaction times and changes in system parameters.
Because of this, trending the stroke times of these fast acting valves will provide inaccurate, and sometimes misleading indication of valve degradation.
ALTERNATE TESTING: In accordance with Generic Letter 89-04, Position 6, if the measured stroke time is greater than the maximum limiting stroke time of 2 seconds, corrective action per IWV-3417(b) will be taken.
Test records will verify satisfactory stroke time is achieved but, need not require recording of the actual measured stroke time.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B v
Valve Relief Recuests NOTE V29 (cont.)
VALVE ID CATEGORY CLASS' FUNCTION 02-2SOV-001 A 1 Close 02-2SOV-002 A 1 Close 16-1AOV-101A, B A 2 Close 16-1AOV-102A, B A 2 Close 20AOV-83 A 2 Close 20AOV-95 A 2 Close 23HOV-1 B 2 Close 23AOV-39 B 2 Close 23AOV-42 B 2 Close 27SOV-119E1, E2, F1, F2 A 2 Close
, 27SOV-120E1, E2, F1, F2 A 2 Close Os 27SOV-122E1, E2, F1, F2 A 2 Close 27SOV-123E1, E2, F1, F2 A 2 Close 27SOV-124E1, E2, F1, F2 A 2 Close 27SOV-125A, B, C, D A 2 Close 27SOV-135A, B, C, D A 2 Close 27SOV-141 A 2 Open, Close 27SOV-145 A 2 Open, Close 27AOV-126A, B B 2 Open, Close 27AOV-128A, B B 2 Open, Close 27AOV-129A, B B 2 Open, Close Note: Function is the direction in which the valve is considered to be fast acting, s 2 seconds.
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Rev. No. 9 Page 123 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests J
NOTE V30 This relief request has been withdrawn.
NOTE V31 This relief request has been withdrawn.
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NEW YORK POWER AUTHORITY' JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
- p. APPENDIX B I \
Valve Relief Recuests NOTE V32 i
l SYSTEM: Residual Heat Removal (RHR)
VALVES: 10RHR-64A, B, C, D CATEGORY: C l CLASS: 2 FUNCTION: These valves open . on forward flow to provide minimum flow protection for the RHR pumps and close on reverse flow to prevent diversion of flow through an idle parallel pump.
TEST REQUIREMENT: Per IWV-3521, exercise these valves open every three months.
BASIS FOR RELIEF: These valves are exercised open every three months by flow during pump testing. However, quantitative
' . O_ flow measurement as a means of verifying these valves open has been determined to be impractical.
There is no installed flow instrumentation in the minimum flow line thus attempts at flow measurements are being made by strap on ultrasonic flow meters. Due to the minimum flow line configuration and operating conditions, there is a high amount of cavitation / turbulence in the line causing the ultrasonic flow meter to go into fault.
Attempts have been made at different locations and with different size' transducers, and faults still occur.
This test method requires the RHR pumps to be operated repeatedly (three to four times) at minimum flow conditions for the maximum time period (5 minutes) allowed by procedure. Running at this condition is undesirable, particularly for a test method that frequently does not yield meaningful results.. NRC Information Notice 89-08 documented concerns about pump damage caused by operating at low flow conditions. When this test is performed with no flow measurements being taken, the time p spent at minimum pump flow is short.
V Rev. No. 9 Page 125 of 150 u
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
. APPENDIX B Valve Relief Reauests FOTE V32 (cont.)
In addition, this testing must be performed in a radiation area which has caused increased exposure to personnel while multiple test attempts and l transducer repositioning are accomplished. It is '
concluded that continued efforts with this method are not practical.
l l
Attempts were made to distinguish the check valve opening impact on the valve bonnet using a seismic vibration probe. Meaningful results could not be ,
i obtained again due to the high background noise and vibration associated with a pump start at minimum ,
l flow. .
The method of using process flow and pressure instrumentation in the main line to infer the flow in the minimum flow line was investigated.
However, the small flow rate through the minimum
,rN flow line in comparison with the main line flow
() would not be discernable within t.he accuracy of the process instrumentation.
ALTERNATE TESTING: These valves will continue to be exercised open during quarterly pump testing without flow measurement.
Also, in accordance with Generic Letter 89-04 Position 2, at least once each operating cycle (normally a refuel outage) at least one (1) valve will be disassembled, inspected, and verified to be operable. The acceptance criteria as stated in the GL is provided in the maintenance procedure used for check valve disassembly. If any valve is found to be inoperable, the remaining valves will be disassembled and inspected prior to startup. The inspection schedule will be such that all four (4) valves in the group are inspected at least once every six (6) years.
(y b
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l i
APPENDIX B i O l Valve Relief Recuests I i
l NOTE V33 This relief request has been withdrawn.
NOTE V34 SYSTEM: High Pressure. Coolant Injection VALVES: 23HPI-12 i 23HPI-65 l CATEGORY: A,C ;
1 CLASS: 2 l
FUNCTION: These valves open to provide a flowpath from the .
HPCI turbine exhaust to the suppression pool. They close to provide containment isolation.
TEST REQUIREMENTS: Per IWV-3521, exercise these valves closed every ;
three months. j BASIS FOR RELIEF: These valves are exercised open quarterly during HPCI surveillance testing performed during plant operation in accordance with the JAF Technical i Specifications. Since there is no disc position indication on either of these valves, closure must be verified by backflow or leakage testing.
In order to verify valve closure by the backflow technique, the HPCI exhaust line must be isolated for the duration of the test, causing the HPCI System to be inoperable. The potential safety impact of voluntarily placing the HPCI System in an inoperable status during plant operation at power i
is considered to be imprudent and unwarranted in relation to any apparent gain in system reliability derived from the closure verification. In addition, the valves are loccted approximately twenty (20) feet from the floor, necessitating erection of a large scaffold in the vicinity of the HPCI pump. This also is considered to be undesirable from the aspect of potential damage to HPCI System components should the scaffold be subjected to structural failure.
i O I Rev. No. 9 Page 127 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR' POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B O
Valve Relief Recuests NOTE V34 (cont.)
Based on the foregoing discussion, testing of these valves during plant operation at power is considered to be impractical. During cold shutdowns, erection of the scaffold in addition to other activities related to test performance would ;
place an extreme burden on the plant staff and i would likely result in unwarranted extensions to all forced outages with the added negative impact on plant performance and availability.
Verifying closure of these valves during each-refuel outage will provide sufficient assurance that the valves will continue to be operable with respect to their capability to close.
ALTERNATE TESTING: At each refuel outage, these valves will be verified to close in conjunction with leak testing performed per 10CFR50, Appendix J.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B v
Valve Relief Recuests NOTE V35 SYSTEM: High Pressure Coolant Injection
-VALVE: 23HPI-13 CATEGORY: C CLASS: 2 FUNCTION: This valve opens to permit HPCI turbine condensate to drain to the suppression chamber.
TEST REQUIREMENTS: Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF: There is no position indicator on this valve or any other means to verify the valve opens.
,Q ALTERNATE TESTING: In accordance with Generic Letter 89-04 Position 2, at least once each operating cycle (normally a
'(,,) refuel outage) the valve will be disassembled, inspected, and verified to be operable.
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Rev. No. 9 Page 129 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES i
,-,- APPENDIX B
\
Valve Relief Recuests NOTE V36 This relief request has been withdrawn.
. NOTE V37 This relief request has been withdrawn.
l NOTE V38 This relief request has been withdrawn. ,
l NOTE V39 This relief request has been withdrawn. '
I NOTE V40 This relief request has been withdrawn. l l
NOTE V41 This relief request has been withdrawn.
NOTE V42 This relief request has been withdrawn.
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(_) NOTE V43 This relief request has been withdrawn.
NOTE V44 This relief request has been withdrawn. i l
NOTE V45 This relief request has been withdrawn.
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v Rev. No. 9 Page 130 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
_ APPENDIX B v
Valve Relief Recuests NOTE V46 SYSTEM: Various VALVES: Containment Isolation Valves (26 inches Nominal Pipe Size)
CATEGORY: A and A,C CLASS: 1 or 2 FUNCTION: These valves close to provide containment isolation.
TEST REQUIREMENTS: Per IWV-3427 (b) , seat leakage rate shall be trended and corrective action taken.
BASIS FOR RELIEF: Based on input from many utilities and NRC staff review of testing data at some plants, the NRC determined that the usefulness of IWV-3427(b) does not justify the burden of complying with the Os requirements of- IWV-3427 (b) .
'l ALTERNATE TESTING: In accordance with Generic Letter'89-04, Position l 10, these valves are provided with leak rate limits specified in accordance with IWV-3426 and will be repaired or replaced whenever seat. leakages exceed established limits. ;
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NEW YORK POWER AUTHORITY '
JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES i
\
APPENDIX B s
("^E.
\~s -
- Valve Relief Recuests l
NOTE V46 (cont.)
VALVE ID VALVE ID
, 10MOV-26A,B 27AOV-101A,B 1 1
4 10MOV-27A,B 27AOV-111 10MOV-31A,B 27AOV-112 a
12MOV-18 27AOV-115 13RCIC-4 27AOV-116 I 13RCIC-5 27AOV-117
V 15AOV-130A 27VB-6 15RBC-24A 27VB-7 ,
23HPI-12 29AOV-80A,B,C,D 23HPI-65 29AOV-86A,B,C,D 23MOV-15 34FWS-28A,B 23MOV-16 34NRV-111A,B 23MOV-19 46ESW-16B l
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Rev. No. 9 Page 132 of 150 1
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests NOTE V47 SYSTEM: High Pressure Coolant Injection VALVES: 23HPI-62 CATEGORY: C CLASS: 2 FUNCTION: This valve opens to provide a-flowpath for minimum flow from the HPCI main pump.
TEST REQUIREMENTS: Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF: Due to the configuration of the minimum flow motor operated valve control logic, fully developed flow cannot be achieved through this check valve.
Additionally, full-stroke exercising cannot be verified with existing instrumentation, and s therefore cannot be performed.
ALTERNATE TESTING: In accordance with Generic Letter 89-04 Position 2, the valve will be disassembled and inspected each operating cycle (normally a refuel outage).
Rev. No. 9 Page 133 of 150
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
,_ APPENDIX B Valve Relief Recuests NOTE V48 SYSTEM: Containment Atmospheric Dilution (CAD)
VALVES: 27VB-1 thru 5 CATEGORY: A,C CLASS: 2
' FUNCTION: These valves open to relieve vacuum from the suppression chamber to the drywell if differential pressure between them should exceed 0.5 psid. They close to prevent bypass flow from the drywell to the suppression chamber without the quenching action of the suppression pool.
TEST REQUIREMENTS: Per IWV-3424 and IWV-3426, measure individual valve ;
leakrates for valves.
p(j . Per IWV-3427 (b) , seat leakage rate shall be trended and corrective action taken. ;
BASIS FOR RELIEF: The configuration of the vacuum breaker lines precludes measuring individual valve leakrates.
In accordance with JAF Technical Specifications, Section 4.7.A.S.d, these valves are leak tested each cycle (normally during refueling outages) as a group with other elements of the containment vessels in conjunction with an integrated drywell/ suppression chamber bypass leakage test.
This test method may be subjected to significant variations associated with other contributing factors involved with the difficulty of performing the test rather than indication of valve degradation. As such, the usefulness of applying IWV-3427(b) would not justify the burden and i uncertainties associated with the performance of this test.
I ALTERNATE TESTING: These valves will be tested together and '
appropriate acceptance criteria established in accordance with JAF Technical Specifications, ;
Section 4.7.A.5.d. !
O Rev. No. 9 Page 134 of 150 m
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B i
.l Valve Relief Recuests i
NOTE V49 SYSTEM: Emergency Service Water VALVES: 46 (70) ESW-101 thru 104 CATEGORY: B .
1 CLASS: 3 FUNCTION: These valves are manually opened to provide ESW flow to Control and Relay Room air handlers to ensure continued cooling in the event the normal chilled water system is rendered inoperable.
TEST REQUIREMENTS: Per IWV-3411, exercise these valves open every three months.
BASIS FOR RELIEF: These valves provide isolation between the raw ESW System and the glycol / water mixture in the chilled water system. Opening ' these valves will cause
{V) contamination of the glycol / water solution. l i
ALTERNATE TESTING: These valves will be' exercised during each reactor i refueling outage. j l
Rev. No. 9 Page 135 of 150
NEW YORK' POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B f '
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Valve Relief Recuestj NOTE V50 SYSTEM: Traversing In-Core Probe (TIP)
VALVES: 07SOV-104A, B, C CATEGORY: A CLASS: 2 FUNCTION: These valves close to provide containment isolation.
TEST REQUIREMENTS: Per IWV-3413 (b) , measure - the . full stroke time of the valve.
BASIS FOR RELIEF: The computer control system for TIP system includes a provision for measuring valve cycle ~ time (opened and closed) and not closure time alone. The sequence opens the subject. valve (stroke < 2 (3 seconds), maintains it energized for 10 seconds
() (including the opening stroke), and de-energizes the valve solenoid allowing the valve to stroke closed (< 2 seconds). The total elapsed valve cycle time is specified to be s 12 seconds.
ALTERNATE TESTING: The overall cycle time (opened and closed) for these valves will be measured and evaluated per IWV-3413 and IWV-3417.
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l Rev. No. 9 Page 136 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
-Q Valve Relief Recuests NOTE V51 SYSTEM: Various VALVES: All valves tested during cold shutdown conditions.
CATEGORY: Various CLASS: Various FUNCTION: Various TEST REQUIREMENT: Valves shall be exercised ... unless such operation is not practical during plant operation. If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during ' plant operation and full stroke exercised during cold shutdowns. Full stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on
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a frequency determined by the intervals between shutdowns as follows:
For intervals of 3 months or longer - exercise during each shutdown. (IWV-3412 and-IWV-3522)
BASIS FOR RELIEF: In many instances testing of all valves designated for testing during cold shutdown cannot be completed due to the brevity of an outage or the lack of plant conditions needed for testing specific valves. It has been the policy of the NRC that if testing commences in a reasonable time and reasonable efforts are made to test all valves, then outage extension is not required when the only reason is to provide the opportunity for completion of valve testing.
ASME/ ANSI OMa-1987, Operation and Maintenance of Nuclear Power Plants, Part 10 (Paragraphs 4.2.1.2 and 4.3.2.2) recognizes this issue and allows deferred testing as set forth below.
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Rev. No. 9 Page 137 of 150 m a
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPEND 1X B
,V Valve Relief Recuests NOTE VS1 (cont.)
ALTERNATS TESTING: For those valves designated to be exercised or-tested during cold shutdown, . exercising shall i commence as soon as practical after the plant i reaches a stable cold shutdown condition as defined i by the applicable Technical Specification but no l
later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown. ;
The 48-hour requirement need not apply if all l valves are-tested during an outage. Valve testing 1 need not be performed more often than once every :
three (3) months except as provided for in IWV-3417(a). Completion of all valve testing during a cold shutdown outage is not required if the length j of the shutdown period is insufficient to complete 4 all testing. Testing not completed prior to i
startup will be rescheduled for the next cold shutdown in a sequence such that the test schedule does not omit nor favor certain valves or groups of ,
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,v Rev. No. 9 Page 138 of 150
NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT t INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES p APPENDIX B l
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Valve Relief Recuests NOTE V52 This relief request has been withdrawn. !
i NOTE V53 This relief request has been withdrawn.
NOTE V54 SYSTEM: High Pressure Coolant Injection VALVE: 23HPI-130 !
i CATEGORY: C CLASS: 2 FUNCTION: This valve opens to provide a flowpath for cooling water circulation through the HPCI turbine lube oil cooler.
l TEST REQUIREMENTS: Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF: This valve has no means of determining disc position or flowrate and, thus there is no mechanism for verifying full accident flow and nor ,
full-stroke of this valve. Satisfactory operation of the HPCI turbine during quarterly testing verifies adequate operation of valve and cooling system.
ALTERNATE TESTING: In accordance with Generic Letter 89'04 Position 2, at least once during each operating cycle (normally a refuel outage) the valve will be disassembled, inspected, and verified to be operable.
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Rev. No. 9 Page 139 of 150
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NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER-PLANT '
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVER 1
1-p APPENDIX B i i GI Valve Relief Recuests 1~
NOTE V55 This relief request has been withdrawn.
l NOTE V56 i
SYSTEM: Residual Heat Removal
. VALVES: 10RHR-95A,B '
CATEGORY: C l- CLASS: 2 1
FUNCTION: These valves close to prevent reverse flow from the i Torus.
TEST REQUIREMENTS: Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF: These are simple check valves with no means of
'N determining disc position without performing a backleakage test. Performing such a test, would-require setting up a hydrostatic pump in a high !
radiation area. l 1
During cold shutdown, the system lineup changes and effort involved with testing would constitute an unreasonable burden on the plant staff.
l ALTERNATE TESTING: During each refuel outage these valves will be l verified to close during a hydrostatic leakrate ;
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
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\s' Valve Relief Recuests NOTE V57 l l
l SYSTEM: Core Spray l
VALVES: 14AOV-13A,B CATEGORY: A,C 1
CLASS: 1 l FUNCTION: These valves open to provide flowpaths from the Core Spray System to the reactor vessel. They close for pressure isolation protection of the low pressure core spray piping.
TEST REQUIREMENTS: Per IWV-3521, exercise these valves open every three months.
BASIS FOR RELIEF: There is no mechanism by which these valves can be full-stroke exercised without injecting water from l
(~} the core spray pumps to the reactor vessel.
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During plant operation, the core spray pumps cannot produce sufficient discharge pressure to overcome reactor vessel pressure and provide flow into the vessel. The installed air operators are capable of exercising the valves, providing there is no differential pressure across the valve seat; obviously this is not the case.
During cold shutdown, injecting into the reactor vessel requires a major effort to establish the prerequisite conditions and realignment of the Core Spray System to allow supplying water from the CST.
Torus water cannot be used since it does not meet the chemistry requirements for reactor grade make-up. It is estimated that such a test would take about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform and would result in a significant burden on the plant operating staff. In addition, there is a potential for overfilling the reactor vessel and flooding the main steam lines.
This could adversely affect the performance of the main steam safety / relief valves (SRV's) since there is cause to believe that a contributing factor to the historically poor performance of the SRV's is water contamination of the operators.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES v' APPENDIX B Valve Relief Recuests l
i NOTE V57 (cont.)
l The installed check valve operators are capable of exercising the valves through their full stroke; however, the sizing of the operators does not satisfy the criteria set forth in IWV-3522 (b) .
ALTERNATE TESTING: During cold shutdown, each'of these valves will be I exercised using the installed operators.
l Each of these valves will be full-stroke exercised during each refuel outage by injecting full accident flow into the reactor vessel.
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Rev. No. 9 Page 142 of 150 l
I NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Recuests NOTE V58 i
SYSTEM: Automatic Depressurization VALVES: 02RV-1 thru 02RV-11 02VB-1 thru 02VB-11 CATEGORY: C '
CLASS: 2 FUNCTION: These valves remain closed to prevent steam from an open safety / relief valve (SRV) from entering the ,
drywell. They open following closure of an SRV to 1 preveit the formation of a water column within the downcomer that could cause torus damage during subsequent lifting of the same SRV.
TEST REQUIREMENTS: Per IWV-3521, exercise these valves open and closed .
every three months.
BASIS FOR RELIEF: Exercising these valves require local manipulation of each valve and thus entry into the containment.
During plant operation at power, and on occasion while in cold shutdown, the containment atmosphere is maintained in a nitrogen-inerted condition.
During such periods, entry into the containment is not practical due to personnel safety concerns.
ALTERNATE TESTING: These valves will be exercised during cold shutdowns when the containment is de-inerted consistent with the requirements of IWV-3522 and the provisions of Note V51.
Rev. No. 9 Page 143 of 150 m
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM-FOR PUMPS AND VALVES
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Valve Relief Recuests k
NOTE'V59 SYSTEM: Main Steam ,
i VALVES: 29AOV-80A, B, C, D CATEGORY: A CLASS: 1 i FUNCTION: These valves.are normally open to provide' steam to :
the main turbine generator and auxiliaries. They T close to isolate steam flow and for containment isolation. t TEST REQUIREMENTS: Per IWV-3415, fail-safe test these valves closed every three months or during cold shutdowns. '
BASIS FOR RELIEF: Fail-safe exercising these valves requires local '
manipulation of valves located inside' the A containment vessel and thus . entry into the
\j containment. During plant operation at power, and on occasion while in cold shutdown, the containment atmosphere is maintained in a nitrogen-inerted ,
condition. During such periods,- ' entry into- the containment is not practical due to personnel safety concerns.
ALTERNATE TESTING: These valves will be fail-safe exercised during '
cold shutdowns-when the containment is de-inerted consistent with the requirements of IWV-3415 and .
the provisions of Note V51.
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
[~ APPENDIX B
!b Va]ve Relief Reauests NOTE V60 i
SYSTEM: Residual Heat Removal VALVES: 10AOV-68A,B CATEGORY: A,C CLASS: 1 FUNCTION: These valves open to provide LPCI injection and close to provide containment and pressure isolation. l TEST REQUIREMENTS: Per IWV-3521, exercise these valves open and closed every three months.
BASIS FOR RELIEF: These valves may be exercised by either operation using the installed air operators or by flow from the RHR pumps into the Recirculation System.
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During plant operation, neither method is practical since the RHR. pumps cannot develop sufficient head to overcome reactor pressure and the air operators are designed to open the valves with zero differential pressure.
At cold shutdown, a zero differential pressure is obtainable and operation with the air operators is possible. However, the theoretical force of the operators does not satisfy the quantitative limit of IWV-3522 (b) . Thus, exercising by using the air actuators can only be considered a part-stroke exercise.
During cold shutdown when the RHR System is in the shutdown cooling mode, these valves are opened by normal shutdown cooling flow. Full accident flow (as required by GL 89-04, Position 1) is currently defined as 13,900 GPM which can only be obtained by operating two pumps in parallel. Unacceptable vibration levels related to system aad component design preclude throttling of the pump flow. Thus, with two RHR pumps in parallel, the resultant flow p) s
would be approximately 17,000 to 18,000 GPM.
has yet to be confirmed that the system can be It operated safely in the shutdown cooling mode at Rev. No. 9 Page 145 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES Valve Relief Recuests NOTE V60 (cont.) this high flowrate due to the size of the common pump suction header.
These valves cannot be fully opened at a single
_ pump flowrate. Thus, full stroke exercising using one pump, in conjunction with confirmation of full stroke valve operation by a non-intrusive testing ;
method, is also not possible.
Therefore, if operation of two RHR pumps .in parallel is not practical, these valves will be disassembled and inspected on a rotating basis, one each refuel outage.
ALTERNATE TESTING: Each valve . will be full flow exercised open (if practical) and closed during each cold shutdown in accordance with the requirements of Note V51.
Should full flow exercising, as outlined above, be found to be impractical, each valve will be
/ partial-stroke exercised with flow at cold shutdown V] and each cycle (normally a refuel outage)- one of these valves will be disassembled and inspected on a rotating basis in accordance with GL 89-04, l Position 2.
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i NEW YORK-POWER AUTHORITY '
. JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX C l'
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SUMMARY
OF CHANGES l
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES O - xc Pump Chancres PAGE PUMP ID(s) CHANGE REASON NONE O
O Rev. No. 9 Page 148 of 150
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
. APPENDIX C Valve Chancres (Rev 8)
PAGE(s) VALVE ID(s) CHANGE REASON
-mmmmmmmmmmmmmmmmmmmu 45,46 02RV-71A Removed setpoints from The setpoints were thru K remarks section changed during 1995 refuel outage. The setpoints were deleted because level of detail is not
. required.
70, 15RBC-21A/B Deleted valves from Determined that 101, 15RBC-22A/B valve table, deleted valves are not 115 l 15RBC-24A/B Cold Shutdown containment isolation 15RBC-26A/B Justifications CS 14 valves and not 15RBC-33 and 15, deleted valves required to be in from Relief Request program.
V19 96,115 46ESW-15A/B Deleted valves from Determined that 46ESW-16A/B valve table and Relief valves are not l Request V19 containment isolation I valves and not i required to be in the Oi program.
72 19VB-1A/B Changed valve type Determined that from CK (check valve) valves were to RL (relief valve) incorrectly identified as check valves.
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i NEW YORK POWER AUTHORITY !
- JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
l INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4
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! O Q APPENDIX C
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Valve Chances (Rev 9) l PAGE(s) VALVE ID(s) CHANGE REASON s' 5 N/A Included IWV-3500 in As written, the i the description of description implied that !
valve testing the band of i25 percent I intervals. of the test interval was j only applied to the test l l schedule for power
! operated valves. It is i i intended to apply to all l
. valve testing.
! 66,140 14 CSP-62AEB Withdrew relief During the 1995 refuel request V55. outage mod M1-94-014 was
! installed to allow reverse flow testing of ,
these valves. J s
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O Rev. No. 9 Page 150 of 150