ML20056D015

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Rev 7 of Ja FitzPatrick IST Program for Pumps & Valves
ML20056D015
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 04/06/1993
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20056D012 List:
References
PROC-930406, NUDOCS 9308020144
Download: ML20056D015 (14)
v • d • e


Text

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i ATTACHMENT I TO JPN-93-048 JAMES A. FIT 2 PATRICK INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES ,

REVISION 7 i

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S INSTRUCTIONS REPI. ACE PAGES IN REVISION 6 OF PROGRAM DOCUMENT WITH REVISION 7 PAGES ATTACHED (13 PAGES)

REMOVE INSERT i i 1 1 36 36 61 61 6P. 62 78 78 141 141 142 142,142a,

-- 142b,142c 166 166 167 167 O

9308020144 930713 77 PDR ADOCK 05000333 Q P PDR b

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT i INSFRVICE TESTING PROGRAM FOR PUMPS AND VALVES

'O Reviewed by: Plant Operations Review Committee I

Me ting No. '}) 045 Date: 3/3i 93 I Approved by: /< ,% < . /N __ Date: '/h / [.3

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RESIDENT MANAGER' Page No. i il 1 2 3 4 5 6 7 8 9 10 11 12 13 Rev. No. 7 6 7 3 3 5 6 1 6 3 6 6 3 5 6 Page No. 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 Rev. No. 1 3 5 3 6 6 3 3 3 6 6 6 6 3 6 Page No. 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 Rev. No. 6 3 3 3 5 1 6 7 6 3 3 3 5 6 5 Page No. 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 Rev. No. 6 6 6 6 5 5 5 5 5 5 5 5 6 6 5 Page No. 59 60 61 62 63 64 65 66 67 68 69 70 71 72 '73 Rev. No. 5 5 7 7 6 6 5 6 5 6 6 5 5 6 6 Page No. 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 Rev. No. 6 6 6 6 7 6 6 5 5 5 5 6 5 5 5

( Page No. 89 -90 91 92 93 94 95 96 97 98 99 100 101 102 '

Rev. No. 5 6 5 5 5 6 5 5 5 5 5 5 6 6' Page No. 103 104 105 106 107 108 109 110 111 112 113 114 Rev. No. 5 5 6 6 5 6 3 6 5 6 6 3 Page No. 115 116 117 118 119 120 121 122 123 124 125 126 Rev. No. 3 3 6 3 5 5 6 3 6 5 1 5 !

Page No. 127 128 129 130 131 132 133 134 135 136 137 138 Rev. No. 6 5 5 3 3 6 6 3 6 3 3 3 Page No. 139 140 141 142 142a 142b 142c 143 144 145 146 147 Rev. No. 1 3 7 7 7 7 7 5 5 3 6 5 Page No. 148 149 150 151 152 153 154 155 156 157 158 159 Rev. No. 5 3 5 5 3 5 5 6 3 6 3 5 Page No. 160 161 162 163 164 165 166 167 Rev. No. 5 5 5 5 5 3 7 7 l

Rev. No. 7 Page i of 11

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8

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1.0 INTRODUCTION

Revision 7oftheJamesAFitzPatrickASMEInserviceTesting(IST)l Program will be in effect through the end of the second 120-month l

1 (10-year) 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 (g) . The third inspection interval begins on July 28, 1995.

This document outlines the IST Program for J.A. Fitzpatrick 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 1

e Title 10, Code of Federal Regulations, Part 50 e Final Safety Analysis Report, J.A. Fitzpatrick Nuclear Power Plant O e 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:

- Standards for Water , Steam , and Radioactive-Waste-Contaminating Components of Nuclear Pcwer 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"

() e NRC Minutes of the Public Meetings on Generic Letter 89-04 Rev. No. 7 Page _.1_ of _1.52_

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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 TESTING PROGRAM Table of Contents Relief Requests (Cont'd)

NOTE V14: Instrument Air................................... 126 NOTE V15: WITHDRAWN........................................ 127 NOTE V16: WITHDRAWN........................................ 127 NOTE V17: HPCI............................................. 128 NOTE V18: WITHDRAWN..... .................................. 130 NOTE V19: Containment Isolation............................ 131 NOTE V20: WITHDRAWN........................................ 133 NOTE V21: WITHDRAWN........................................ 133 NOTE V22: HPCI............................................. 134 NOTE V23: WITHDRAWN........................................ 135 NOTE V24: W ITH D RAWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 5 NOTE V25: W I THD RAWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 5 NOTE V26: WI TH DP AWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 5 ,

NOTE V27: ADS and Main Steam............................... 136 NOTE V28: Excess Flow Checks............................... 138 NOTE V29: Fast Acting Valves............................... 140

% NOTE V30: WITHDRAWN........................................ 142 NOTE V31: WITHDRANN........................................ 142 NOTE V32: Residual Heat Removal............................ 142a NOTE V33: WITHDRAWN........................................ 142c NOTE V34: HPCI............................................. 143 l NOTE V35: HPCI............................................. 145 NOTE V36: WITHDRAWN........................................ 146 NOTE V37: WITHDRAWN........................................ 146 NOTE V38: WITHDRAWN........................................ 146 NOTE V39: WITHD RAWN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 6 NOTE V40: WITHDRAWN........................................ 146 NOTE V41: WITHDRAWN........................................ 146 NOTE V42: WITHDRAWN........................................ 146 NOTE V41: WITHDRAWN........................................ 146 ,

NOTE V44: WITHDRAWN........................................ 146 l NOTE V45: WITHDRAWN........................................ 146 l NOTE V46: Conta(pment Isolation Valves..................... 147  !

NOTE V47: High Pressure Coolant Injection.................. 149 NOTE V48: Containment Atmospheric Dilution................. 150 i NOTE V49: Emergency Service Water.......................... 151 l NOTE V50: Traversing Incore Probe.......................... 152 NOTE V51: Generic - Cold Shutdown Testing.................. 153 NOTE V52: WITHDRAWN........................................ 155 NOTE V53: WITHDRAWN........................................ 155 7 Page 36 of 167

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NEW Y0RK POWER AUTH0R1TY JAMES A. FITZPATRfCK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE SYSTE;1: Residual Heat Renoval -

SYSTEM ID: 10 DRAWING: FM-20A V*LVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IM) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS

.......................-...............................................-..................................-~.--..-........................-...---..--.-----..----------~----

10m0V-668 D-3 2 s 20.00 GL MO TM-1 PI-3 1CHR 262 H-3 2 C 4.00 CK SA - RF-1 10RHR-277 G-8 2 C 4.00 CK SA RF-1 10RNR-42A C8 2 C 16.00 CK SA FF-1 RF-1 10RNR-428 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 10RNR-42D C-3 2 C 16.00 CK SA FF-1 RF-1 10RNR 52A G-6 2 A 2.00 GA MA LJ-3 V19 10RMC-528 G-5 2 A 2.00 GA MA LJ.3 V19 10RHR-64A C-8 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 10RHR 648 C-3 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 REV. NO: 7 PAGE 61 0F 167

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NEW YORE POWER AUTH0RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Resichaal Heat Removal -

SYSTEM ID: 10 DRAWING: FM-20A VALVE 10 DWG CO-OR CLASS VALVE CATEGORY SIZE (lN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 10RMR-64C D-8 2 C 3.00 CK SA PF-1 V32 RF-1 DA-6 10RMR-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-958 35 2 C 0.75 SK SA RF-1 V56 RF-3 10SV 35A E-8 2 C 1.00 RL SA RL-4 10SV-358 E-3 2 C 1.00 RL SA RL-4 10SV-40 D-5 2 C 1.00 RL SA RL-4 REV. NO: 7 PAGE 62 0F 167

(% js NEW YORK POWER AUTH0RITY JAMES A. f lT2 PATRICK NUCLEAR POWER PLANT INSERVICE iESTING PR0 GRAM F0R PUMPS AND VALYES VALVE TA9LE DRAWING: F M- 17A SYSTEM: Redweste - SYSTEM ID: 20 VALVE ID DWG CO-OR CLASS VALVI CATEGORY SIZE (IN) VALVE TTPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 20A0V-C3 F-6 2 A 3.00 BL A0 TM-1 V29 l FC-1 PI-3 LJ-3 20A0V-95 C6 2 A 3.00 BL A0 TM-1 V29 l FC-1 PI-3 LJ-3 20MOV-82 F-7 2 A 3.00 GA MO TS-1 PI-3 LJ-3 20MOV-94 C-7 2 A 3.00 GA Mo TS-1 PI-3 LJ-3 i

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PAGE 78 0F 167 REV. Co* 7-l r

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. NEW YORK POWER AUTHORITY

. JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8

APPENDIX B 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 O 27SOV-120E1, E2, F1, F2 27SOV-122E1, E2, F1, F2 A

A 2

2 Close 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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,' liEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT i l

IN8ERVICE TESTING PROGRAM POR PUMPS AND VALVES (3 APPENDIX B

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Valve Relief Recuests NOTE V30 This relief request has been withdrawn.

NOTE V31 This relief request has been withdrawn.-

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q NEW YORK POWER AUTHORITY J

, JAMES A. FITZPATRICK NUCLEAR POWER PLANT j- f INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

(" APPENDIX B Valve Relief Requests NOTE V32 SYSTEM: Residual Heat Removal (RHR)

VALVES: 10RHR-64A, B, C, D CATEGORY: C 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 Q, 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 j with different size transducers, and faults still ;

occur. l This test method requires the RER pumps to be l operated repeatedly (three to four times) at i minimum flow conditions for the maximum time period 4 (5 minutes) allowed by procedure. Running at this I condition is undesirable, particularly for a test method that frequently does not yield meaningful ,

results. NRC Information Notice 89-08 documented l concerns about pump damage caused by operating at l low flow conditions. When this test is performed l with no flow measurements being taken, the time l spent at minimum pump flow is short.

Page 142a of 167

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT I_NSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B ,

Val _ve Relief Reauests NOTE V32 (cont.)_

In addition, this testing must be performed in a radiation area which has caused increased axposure to personnel while multiple test attempts and transducer repositioning are accomplished. It is '

concluded that continued efforts with this method are not practical.

Attempts were made to distinguish the check valve opening impact.on the valve bonnet using a seismic vibration probe. Meaningful results could not be obtained again due to the high background noise and

  • vibration associated with a pump start at minimum 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

( flow line in comparison with the main line - flow would not be discernable within the 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.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B valve Relief RerJuests NOTE v33 This relief request has been withdrawn.

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Page 142c of 167 7

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. JAMES A. FITZPATRICK NUCLEAR POWER PLANT  !

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES i

O APPENDIX C i i

Pumo Chances

.: PAGE PUMP ID(s) CHANGE REASON NONE i

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Rev. No. 7 Page 166 of 167..

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NEW YORK POWER AUTHORITY

'AMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 O APPENDIX C Valve Chances PAGE(s) VALVE ID(s) CHANGE REASON 61,62, 10RHR- Added PF-1 and DA-6 test Determined that valves are 142,142a, 64A,B,C,0 requirements and Relief not full flow tested per 142b,142c Request Note V32 Code requirements  :

78,141 20A0V-83,95 Added reference to Relief Determined that .alves are Request Note V29 still fast acting O

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