ML20085E460
| ML20085E460 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/12/1991 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20085E457 | List: |
| References | |
| M-710, NUDOCS 9110210002 | |
| Download: ML20085E460 (330) | |
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Enclosure 1 M-20682 RW. 6/B8 r~'s Doctype 601
.I M NUCLEAR SAFETY RELATED PHILADELPHIA ELECTRIC COMPANY PEACH BO'I" TOM ATOMIC POWER STATION UNITS 2 AND 3 Specification For -
1 PUMP AND VALVE '
INSERVICE TESTING PROGRAM SECOND TEN YEAR INTERVAL 2
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SPECIFICATION FOR... NO.
M-710
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( ; INSEP,VICE TESTING PROGRAM, SECOND TEN Rev. No. ,
l N;d./ NUCLEAR YEAR INTERVAL, PEACil BOTTOM ATOMIC ^
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U PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 SPECIFICATTN FOR PUMP AND VALVE INSERVICE TESTING PROGRAM SECOND TEN YEAR INTERVAL J '
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Rev. PEcc PECo IFI/F:t l , 4. C 'e Reisen fer Issue Lead Non . Lead (s) CA A:Orovd hD. SPECIFICATION FOR THE F';:!P M-710 4 .,, q - go, b'M AND VALVE INSERVICE TES TING a,,, g
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' POUER STATION, USITS 2 & 3. tt 26
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PBAPS 2 & 3, IST Program Spec. H-710, Rev. 2 Page 1-11 of 16 Controlled Conv Distributi.clu Nuclear Engineering G. L. Stathes, 63B-3 w Huclear Services, licensing M. C. Kray, 52A-3 PBAPS, ANII: J. J. Fuhrman, A3-4N PBAPS, Installationi R. E, Simpson, PR-2-1 PBAFS, Maintenance I & Ci J. P. Wilson, A4-IS PBAPS, Maintenance I & Ci J. J. Stanley, A3-3H M PBAPS, Maintenance Planning & Scheduling: J. T. Netzer, A2-IN PBAPS, QCi QA Library, B2-S PBAPS, Station Library: A4-4 PBAPS, Station Mod Coordinatori J. B. McLaughlin, A4-4H PBAPS, Station Technical D. R. Meyers, A4-IS X PBAPS, Station Technicali V. C. Ruppert, A3-3N K PBAPS, ST Re-write Grouni J. A. Heyne, AX-1-1 PECo, HQA - HDE Services: T. C. Hinkle. Valley forge Center DAC (2 copies): 61B-5 K Distribution to these individuals is in addition to the HGAP HA031001 distribution requirements for this specification. __ ._. m_._ _m _.._ _ . - NOTE:
" REVISION 1" 0F THIS SPECIFICATION WAS NOT ISSUED BECAUSE THE ORIGINAL ISSUE OF THIS SPECIFICATION (REY. 0) HAD REVISION 1 NOTATIONS IN THE TEXT. THEREFORE, TO CLARIFY THE CORRECT REVISION NUMBER, REVISION 1 WILL NOT BE USED AND THIS REVISION WILL BE NOTED AS Rr/ISION 2.
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PBAPS 2 & 3, IST Ppcgptm ' Sp5c. H-710, Rsv. 2 ; Pag 3 1-111 of 16 > 1 The purpose of this revision is to incorporate Addenda 1, 2, and 3 to Revision 0. Q i Additionally, the purpose of this revision is to revise the IST Program in accordance with the NRC Safety . Evaluation issued in January 1991 and to incorporate the most i current available plant information into the specification. 3 The following EWRs have been addressed in this revision and the changes are noted ! below in the Record Of Changes. l t EWR A0004420 EWR A0006779 ! EWR A0004775 ENR A0035589 i ENR A0006411 EWR A0035774 , EWR A0006493 ' R K Q R D_ 9F _ Glia 3 01 3 :
-1. AEEKGlIP PAQIS Table of Contents, Page 3 Description of change Deleted Cold Shutdown Test Justification 01-VCS-1 and added Relief Request 01-VRR-2 to the Table Of Contents. ,
Reason for changeij Cold shutdown testing is no longer required as described l in Item 4 below. The relief request was added to the- i IST Program as described in item 11 below. j
- 2. AEELCIgp. PAGIjt Text, Page 5 Description of chanoei !
Revised section 2.1 CODE OF FEDERAL REGULATIONS, by updating the second inspection interval commencement ' f dates. The datos were changed from July 6, 1984 and December 13, 1984, to September 19, 1986-and December '
-23, 1985 respectively.
Reason for change: These interval dates were revised per PECo letter to the i NRC dated February 25, 1991. This change was also-addressed in ENR A0035589. ;
- 3. AEFECTED PAQES: Text, Page 6 i Description of-changei Revised section 3.4 NRC LETTERS, by adding reference to Generic le t ter 89--04.
Reason for changei Generic lettor 89-04 is used as a guideline to establish adequate inservice testing procedures and should be refarenced in this specification.
- 4. AFFECTED PAGE_St Text, Page 10 Description of change Revised section 5.2.5 Valve Position Indicator .
Verifica tion, to clarify testing requirements for valves ;
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with multiple remote position indicators. Reason for change Revision 0 of section 5.2.5 required ALL remote pusition indicators for ' valves with indicators- at _ multiple l oca tions to be veri fi ed for accuracy. However, in accordance with ASME Section XI Interpretation XI-1 10, dated November 14, 1988, for valves having remote
- m posi tion indicators at multiple locations (i .e. , remote shutdown panel and control room), only the remote
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position indicator at the loca tion used for exercise testing and stroke timing.the val _ve needs to be verified for accurately indicating valve position. In addition
-. ---- ww v.mX.a 2 isnunm66,in-hG:L a : -- n ~. - ~.~ ~ ~ ~.cwon PBAPS 2 & 3, IST Pp gram Ep;c. H-710, R;v. 2 P g2 1-iv Cf 16 to the ASME interpretation for remote position indicator (S. testing, PEco requires testing of remota position i ! indicators located in the control room regardless of V which remote indicator is used for exercise and stroke time testing. This ir. done to ensure that the control room position in ficator is tested in accordance with ASME Section XI code requirements. This item was addressed in EWR A0006411.
- 5. AFfjpHD PAEM: Appendix A Valve Table, Page 1, 150 Description of changen Deleted Cold Shutdown Test Justification 01-VCS-1. Added quarterly stroke time testing in the closed direction and deleted quarterly partial stroke requirements for main steam isolation valves A0-2(3)-01-080A,B,C,D cnd A0-2(3)-01-086A,B,C.D. Also, deleted reference to 01-VCS-1 in the valve tables.
Reason for change: Technical Specification 4.7.D.I .B(2) requires quarterly exercising of these valves. Therefo a, Inservice testing can be performed quarterly in accordance with ASME Section XI requirements instead of at cold shutdown. This change was addressed in EWR A0035774.
- 6. AEEILQHD_1AQl31 Appendix A, Pago 13 Description of changei Revised Cold Shutdown Test Justification 49-VCS-1 by changing tbo Category from A to B.
Reason for change Category A designation was a typographical error, the O) ( valve tables had the correct designation. discrepancy was identified by the NRC in the IST SER, This Appendix C, Item 3 and was addressed in EWR A0006493.
- 7. AfflCILDJAQ13: Appendix C, Page 2 Valve Table, Pages 3, 4, 5, 6, 80, 81, 82, 96, 99, 10Z, 103, 108, 132, 133, 134, 135, 209, 210, 211, 224, 227, 231, 236 Description of changei Revised Ralief Request GVRR-2 by changing Valve Category from C to A, C. Revised valve tables for all excess flow check valves by changing valvo category rrom C to A, C and added LP-T designa tion to Test Frequency.
Reason for change These excess flow check valves requise leak testing which war identified by the NRC in the IST SER, Appendix Ci Item 1. This was also addressed in EWR A0006493.
- 8. AFFECTED PAGMt Appendix C, Page 4 Valvo Table, Pages 99, 107, 108, 227, 235, 236 Description of change Revised Relief Request GVRR-4 by adding reverse exercising requirements. Revised valve tables for VRV-2( 3)-13-139 A, B C. D and VRV-2( 3)-23-140 A, B.C, D by adding reverse exercise testing requirements.
Reason for change These vacuum breaker valves have a safety function in
,m the closed direction. This was identified by the HRC I T in the IST SER, Appendix C, Item 9 and addressed in EWR
() A0006493.
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- 10. AFFECTED PAGES: Appendix C, Page 5 Valve Table, Pages 2, 131 Description of changei Revised Relief rcquest 01-VRR-1 and the valve tables by adding stroke timo requirements in the open direction for relief valves RV-2(3)-01-071 A,B,C,0,K.
Reason for change: The NRC identified these valves as requiring stroke time testing in the IST SER, Appendix C, Itnm 10. This change was also addressed in EHR A0006493.
- 11. AEEKQTED PAQLSt Appendix C, Page 6 Valve Table, Pages 3, 132 Description of change: Added Relief Request 01-VRR-2. Revised valve table for vaives by deleting 10 year is.iarval test and adding exercise test at cold shutdown and refueling.
C (~ Reason for change: These vacuum breaker / relief valves were tested in accordance with ANSI /ASME OM-1, 10 year interval. However, they are simple chock valves and must be exercised accordingly. Quarterly testing is not possible because these valves are insida primary containment, therefore, testing is at cold shutdown and refueling. This was identified by the NRC in the IST SER, Appendix C, Item 2 and addressed in EHR A0006493.
- 12. AEE1QTED PAGES: Appendix C, Page 19 Description of changei Revised Relief Request 50-VRR-1 to the original Revision 0 wording.
Reason for che naci Relief Request 50-VRR-1, as revised by Addendum 1 to Revision 0, was never used for inservice testing prposes and was inappropriately included in the addendum. The original version of the relief request was reviewed and approved by the NRC and is appropriate for testing purposes.
- 13. AFFECTED PAQXSt Valve Table, Pages 86, 87, 215, 216
{ Description 'of' change Revised the specified normal position from "C" to "0C", and the safety position from "0C" t.o "C" for the following valves:
. A0-2-09-2505 A0-3-09-3505 A0-2-09-2506 A0-3-09-3506 A0-2-09-2507 A0-3-09-3507 A0-2-09-2511 A0-3-09-3511 AD-2-09-2512 A0-3-09-3512
.,,a_ _-- n- w ~.--A...J.--:.a.-- a~~a-.- -.~. .- a - s. l l PBAPS.2 & 3, IST PpCgram Sp;c. H-710, R0v. 2 P g3 1-vi cf 16 i A0-2-09-2520 A0-3-09-3520 p' A0-2-09-2521A,B A0-3-09-3521A,B-(dj A0-2-09-2523 CHK-2-09-40095A,B A0-3+09-3523 CHK-3-09-50095A,B l Reason for change These valves have no safety function in the - open direction. They open and close during normal plant operation. This change was addressed in 04R A0004775, Items 3 and 4.
- 14. AEEECIIILEAGEst Valve Table, Page 93 Description of changei Deleted remote position indication test (PI-T) for valve MO-2-10-033, i I
Reason for changes This valve is passive and is blocked closed with power removed. Remote position indication is not required. This was ' addressed in ENR A0004775, Item 13,
- 15. AEE191EILEAQ13: Valve Table, Pages 90, 92 Description of changei Deleted ASME Section XI leak test requirement (LP-T) for motor operated valve MO-2-10-032 and deleted " PRES ISOLATION VALVE" from the Remarks column of the table.
Added check valve CHK-2-10-029 to the valve table as the pressure isolation valve. Reason for change Due to system configura tion, ASME Section XI leak test can not be performed on valve MO-2-10-032. The required leak test can be performed on check valve CHK-2-10-029, - therefora CHK-2-10-029 will act as the inboard pressuro
,U' e isolation valve. MO-2-10-032 is still the inboard primary containment isolation valve. This chanon was addressed in EWR A0006779.
- 16. AEELCTED PAplSt Valve Table, Pages 97, 105 Description of changee Changed valve category from C to'A.C and added ASME Section XI leak test designation LP-T for the Unit 2 RCIC and HPCI testable check valves, A0-2-13-022 and A0 23-018. Also, added reverse exercise test requirements for these valves.
Reason for change Leak testing and reverso exercising provides added assuranco against over pressurization of the RCIC and HPCI suction piping. This change was addressed in EHR A0004420.
- 17. AEFECTED__.EAQES: Valve Table, Pages 98, 225 Description of change Deleted valves HV-2( 3)-13-010 from the IST Program.
Reason ' for change Check valve CHK-2(3)-13-038 provides the isolation function for the vacuum purnp discharge.
- 18. AFFEQJJD_fAGEQtE Valve Table, Pages 98, 106, 226, 234 Description of change Deleted reverse exercise test for stop check valves HV-2(3)-13-009. HV-2(3)-23-012, and HV-2(31-23-013.
Reason for change Check valves CHK-2( 3)-13-050, CHK-2( 3)-23-065, and CHK-2(3)-23-056 provide the respective isolation function,
l PBAPS 2 & 3, IST Pr'ogtam Spec. H-710, Rev. 2 Page 1-vii of 16 not the stop check valves.
- 19. AFFECTED PAGIS Valve Table, Pages 101, P29 Description of chang-t Valves CHK-2-14-40252 and CHK-3-14-50252 were CHK-2 40244 and CHK-3-14-50244 respectively.
Reason for changei Valves were renumuered by the sta tion. This change was addressed in EHR A0004775, I tem 10.
- 20. AEf_E_QJip PAREft Valve Table, Pages 107. 235 Description of changes Added stroke time requirements in the open direction for valves MO-2-23-4244A and MO-3-23-5244A.
Reason for change These motor operated valves have a safety f unc ti on in the open direction and must be timed in the open direction in accordance with ASME XI Subsection IHV-3412 and 3413. This was addressed in EHR A0004775, Item 5.
- 21. AFFECTED E qiSt Valve Table, Pages 123, 249 Description of change: Changed notation from active ( A) to passive (P) for check valves CHK-2-51-23335 and CHK-3-51-33312. Also, deleted exercise requirements for these check valves.
Reason for changei These check valves are normally closed with a closed safety position, therefore, they are passive. Exsrcise 4 testino is not required for passive. Category A and C check valves.
- 22. AEEEGIED PAGES: Valve Table, Page 125 Description of change Added valve HV-0-52-016B to the IST Program.
Reason for changei Normal alignment change to the CAD system requires that this valve be normally closed with an open safety function. This was addressed in ENR A0004775, i tem 14.
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/NE) EAQE !*^Y ORIGINAL ISSUE (REV. 0) SPEC,'111LE SNEET 1- i-CONTROLLED COPY DISTRIBUTION 1- 11 RECORD OF CNAHOES FOR REVISION 1 1-iii 1,0 INTRODUCTION 5 2.0 REGULATORY REQUIREMENTS 5 2,1 Code of Federal Regulations 5 2.2 Applicable Code 5 2.3 Adoption of Code Case N-415 5 3.0 ADDITIONAL /.EFERENCE DOCUMENTS 6 3,1 UF3AR 6 3.2 Technical Specifications 6 3.3 Operating Procedures 6 3,4 NRC Letters 6 3,5 Draft Regulatory Guide 6 3.6 NRC I.E. Bulletin 6
_ ,,, 8 NIkMEOMDcuments 6
'"< 4,0 INSEPVICE TESTING BOUNDARIES 7 4.1 Scope 7 4,2 Exemptions 7 4,3 Definitions 7 4.4 Valve Categories 8 4.5 System Identification 8 4.6 P&ID's 8 5,0 PUMP AND VALVE SELECTION 9 5.1 Code Requirement Positions for Pumps 9 5.2 Code Requirement Positions for Valves 9 5,3 Al t era ti ons to Section XI Requirements for Pumps 10 5,4 Alterations to Section XI Requirements for Valves 11 5.5 Cold Shutdown Test Justification Discussion 11 5.6 Relief Requests Discussion 11 6.0 IST TABLE DESCRIPTIONS - PUMPS AND VALVES 12 6.1 IST Table - Pumps 12 6.2 IST Table - Valves 13 7.0 RECORDS 16 t')
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"U APPENDJ.CU EAQE
' Appendix A - Valve Inservice Testing Program Cold Shutdown Test Justifications (14 pages) j l
0'a-VCS-2 1 0 7.-VC S-1 2 03-VCS-1 3 06-VCS-1 4 09-VCS-1 5 10-VCS-1 6 10-VCS-2 7 14-VCS-1 8 33-VCS-1 9 . l 1 34-VCS-1 10 35-VCS-1 11 44-VCS-1 12 49-VCS-1 13 51-VCS-1 14 Appendix ) - Pump Inse vice Testing Program Puap Relief Requests (4 pages) GPRR-1 1 GPRR-2 2 GPRR-3 3 l ll-PP,R-1 4
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Appendix C - Valve Inservice Testing Program Valve Relief Requests (22 pages) GVRR-1 1 GVRR-2 2 GVRR-3 3 GVRR-4 4 01-VRR-1 5 01-VRR-2 6 l
- 03-VRR-1 7 l 06-VRR-1 8 l 10-VRR-1 9
! 10-VRR-2 10 l 11-VRR-1 11 13-VRR-1 12 13-VRR-3 13 14-VRR-1 14 14-VRR-2 15 14-VRR-3 16 l 23-VRR-1 17 23-VRR-3 18 50-VRR-1 19 ! 51-VRR 20 l 51-VRR-2 21 SI-VRR-3 22 j u/m
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; j) IST TABLES EAQLS. f sms ,
IST Table - Pumps (5 pages) !
- PBAPS 2 and Common 1-3 :
- PBAPS 3 4, 5 IST Table - Valves (254 pages) 1
- PBAPS 2 and Common 1 - 129 '
- PBAPS 3 130 - 254 i l
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PBAPS 2 & 3, IST Pr:grca ' Sp;c. M-710, R3v. 2 ; Pcs,3 5 cf 16 1.0 IMIRQWRTlRN The Pump and Valve Inservice Testing Prouram for the Peach Bottom Atomic ("l Power Station, Units 2 and 3 (PBAPS-2 & 3). details the technical basis and provides the overall description of the activities planned to fulfill the -Inservice Testing (IST) requirements f or pumps and valves as defined in the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Division 1, " Rules for Inservice Inspection of Huclear Power Plant Comporents". The IST program includes the pumps and valves within the scope of Section 4.1 required to be tested in accordance with Section XI, Subsections IWP and IWV. The IST P ogram consists of two parts; the Program text with appendices, and the IST Tables. The text defines the basin of the IST program. It lists and explains the specific exemptions and m. election criterin applied to safety related pumps and valves, thus defining the scope and extent of the IST testing requirements. The Appendices include the Cold Shutdown Test Justifications, Pump Relief Requests and Valve Relief Requests. The IST Tables contain a system by system listing of specific pumps and valves for each unit, along with the applicable testing requirements for each. They will consist of the following four tableu IST Table - Pumps - PBAPS-2 and Common IST Table - Pumps - PBAPS-3 IST Table - Valves - PBAPS-2 and Common IST Table - Valves - PBAPS-3 The IST Implementing Plans contain additional information pertinent to the "" implementation of the tes ting program. Such information includes. specific Surveillance Test Procedure (ST) used, test frequencies, etc. The IST Implementing Plans are ag.1 a part of this Program document, however, they are sub-tier documents which must reflect the requirements of the IST Program. Q. 2.0 gW1AIAM_MRMigMUlla 2.1 CODE OF FEDERAL REGULATIONS Title 10, Part 50.55a of the Code of Federal Regulations, Paragraph (g)(4) requires that 10-year IST programs comply with the latest edition and addenda of Section XI incorporated by reference in Paragraph (b)(2) on the date 12 months prior to the start of the 120-month inspection interval. The second inspection interval for PBAPS-2 & 3 commenced September 19, 1986 and December 23, 1985 respectively. The use of any later edition and addenda of Section XI is allowed if it has been incorporated in-Paragraph (b)(2) . 2.2 APPLICABtE CODE The second 10 year interval Pump and Valve IST Program complies with Section XI of the ASME Boiler and Pressure Vessel Code. 1980 Edition through Winter of 1981 Addenda (1980W81) as required by 10CFR50.55ath)(2) . All references to subsections IWP and IWV of Section XI in this document correspond to the aforementioned Code Edition, with the exception of the portions addressed in the following paragraph. 2.3 ADOPTION OF CODE CASE N-415 The valve test program adopts Code Case H-415 (approved for use by the HRC per Regulatory Guide 1.147 Rev. 5 and 1986 Edition of Section XI), which permits the use of ANSI /ASME OM-1-1981 as an alternative to the ASME PTC-p) g b' 25.3-1976 referenced in IWV-3510. OM-1-1981 contains requirements for replacement, repair and maintenance, inservice tests and test frequency for safety valves, pressure / thermal relief valves (including vacuum relief valves) and ruptu.e disks (non-reclosing pressure relief devices). 1
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PBAPS 2 & 3, IST Prsgrca i Sp;c. H-710, R:v. 2 i PCO2 6 of 16 j 3.0 ADDIT 10NAL REFERGqlL DQCMtMIS hq 3.1 UFSAR The Updated Final Safety Analysis Report (UFSAR) for PBAPS-2 & 3 is used ; to determine which safety related pumps and valves are within the scope l of this document. 1 3.2 TECHNICAL. SPECIFICATIONS {' 1ho PBAPS-2 & 3 Technical Specification (1.S.) were used in conjunction with the UFSAR in determining the pumps and "alves which are in scope, lhe T.S. surveillance requirements wore compared with the Section XI requirements to determine equivalent testing. Whenever possible, ( equivalent T.S. testing will be used to satisfy Section XI requirements. . The specific Section XI requirements satisfied by T.S. will be specified l either in the test f requency column of the IST Tables or in the associated p N relief request or cold shutdown test justification. i 3.3 OPERATING PROCEDURES ! r The Unit 2 & 5 Operating Procedures were used to determine system operating modes and alignments under normal and emergency conditions, a V 3.4 NRC LETTERS Generic letter 89-04, "Ouidance On Developing Acceptable Inservico Testing Programs",, dated April 3, 1989, is used as a guideline to establish
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adequate inservice testing pr ocedures.
"NRC Staff Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55ato)", .Q January 1978, is used to provide guidance for the establishment of selection philosophy, the program submittal format, and the development
- of relief requests.
"NRC S ta f f Guidance for Complying with certain Provisions of 10CFR50.55a(g) .
Inservice Inspection Requirements", November 1976, is used as a reforence to provide NRC staff guidelines for excluding exercising tests of certain valves during plant operation. 3.5 . DRAFT RE00LATORY GUIDE Division .', Draf t Regulatory Guide and Value/ Impact Statement (Dra f t 2),
" Identification of Valves for Inclusion in Inservice Testing Programs" is used to provide further insight to NRC positions on the contents of the valve program.
3.6 NRC I.E. BULLETIN I.E. Bulletin 83-03: " Check Valve Fultures in Raw Hater Cooling Systems of Diesel Generators" provides recommenda tions on test requirements for check valves. 3.7 NRC I.E. NOTICE-I . E. - Notice 84-74, " Isolation of Reactor Coolant System from Low-Pressure Systems Outside Cont _ainment" was used as a reference for providing.
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' Justification for relief from exercising certain reactor coolant pressure boundary valves.
3.8 ANSI /ASHE OH DOCUMENT 3 (m s . 1 ANSI /ASME OM-1-1981 is used for relief /mafety valve and rupture disk testing per Code Case N-415. ANSI /ASME OM Part 6 and 10, 1987/1987A for pump testing and for valve
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PBAPS 2 & 3, IST Progp&m Sp;c. H-710, R3v. 2 Pag 3 7 of 16 testing,.respectively, are used fo* reference when determining testing requirements. X) 4.C DiRRY1C LILSUtiLg@tiDAgIgi 4,1 SCOPE 4.1.1 Pump IST Program The score of the pump IST program includes all centrifugal and positive displacement type pumps that are provided wi th an emergency power source, that are not exempt by paragraph 4.2.1 and which function tos Mitigate the consequences of an accident or, Shutdown the reactor to .i e,ld shutdown condition. The pumps within this scope are listed in the IST Tables-Pumps, 4.1.2 Valve IST Program The scope of the valve IST procrem includes all valves that are not exempt by paragraph 4.2.2 and which function te, Mitigate the consequences of an accident or, Shutdown the reactor to a cold shutdown condition. The valves within this scope ara listed in the IST Tables-Valves. 4.2 EXEMPTIONS 4.2.1 Pump Exclusions identi fied in INP-1200 i( Note: The term " Exclusions" is used in INP-1200, but is considered synonymous with " Exemptions".
- a. Drivers of pumps except where the driver and pump f orm an integral unit and the pump bearings are in the driver,
- b. Pumps supplied with emergency power solely for operating convenience.
4.2.2 Valve Exemptions Identified in INV-1200
- a. Maintenance Valves - Valves which are used only to isolate components to perform maintenance, including pressure /thernal relief valves which provide overpressure protection for a componer.t that is isolated only for maintenance.
- b. Operating Convenience Valvos - Valves used only for operating convenience, such as manual vent, drain. 4nstrument, and test valves,
- c. System Control Valves - Valves such as pressura regulating, flow control, and manual throttie valves,
- d. Valves in External Control and Protection Systems - Systems responsible for sensing plant conditions and providing signals f or valve operation.
4.3 DEFINITIONS 4.3.1 Active valves valves which are required to change posi tion to accomplish a specific function. 4.5.2 Passive valves - valves which are not required to chance position to
-[b neeer.plish a specific function.
l ! ! 4.3.3 Exercising - the demonstration based on direct or indirec t visual or other ~ i positive indication that the moving parts of a valve function
,a
C ~ <c~. _ - _ - - -mm ., %e +, _
-t PBAPS 2 & 3, IST Peggran; C Sp;c. H-710, RIy. 2 Page 8 cf 16 [
i satisfactorily, i
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4.4 v- / ( VALVE CATEGORIES valves for which heat leakage is limited to a speci fic ; 4.4.1 Category A - maximum amoun'. in the closed position for fulfillment of ( their function. 4.4.2 Category B - valves for which seat leakage in the closed oosition is inconsequential for fulfillment of their function. - 4.4.3 Category C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or fl ow ( direction (check valves). . 4.4.4 Categvry D - valvus which are actuated by an energy source capable of ', only one operation, such as rupture disks or explosive- - actuated valves. 4.5 SYSTEM IDENTIFICATION ) The following is a list of the system numbers and their associated system l name for all systems contained in the IST Program. o . System HMahar 1Xslac 01 Main Steam 02 Reactor-Recirculation ' r 03 Control Rod Hydraulic 04 Nuclear Boiler Vessel snstrusentation - 06 Feedwater. t 07 Traversing Incore Probo (TIP) [}
\, ,,-
09 10 Containment Atmospheric Control Residual Heat Removal (RHR) 11 Standby Liquid Control 12 Reactor Hater Cleanup 13 Reactor Core Isolation Cooling (RCIC) 14 Core Spray 20 Radwasta 25 High Pressure Coolant Injection (HPCI) 32 High Pressure Service Hater 33 Emergency Service Hater 34 Reactor Building Closed Cooling Hater 35 Instrument Air 36 Service Air 44 Chilled Hater (Drywell cooling) 48 Emergency Cooling Hater 49 Standby Gas Treatment 50 Emergency Diesel Generators 51 Instrument Nitrogen System 52 containment Atmesphere Dilution 54 Primary Containment Leak Testing 4.6 P&ID's The following is a list of all the P&ID's identifying pumps and valves within the scope of the IST Program. P&ID iSHEET HUMBERS) SYSTEM M-300 (1) Legend M-315 (1,2,3,4) Emergency Service Ha ter and High Pressure Service Ha ter
,g M-316 (1,3) Cooling Hater-Reactor Bldg.
I 1 M-320 (1) Compressed Air Systen
\wer' =~' M-327 (2,4) Chilled Hater System Drywell Cooling M-330 (1) Emergency Cooling Syatem M-332 (1,2) Primary Containment i.eak Testing
m _ .. _. - _ - - _ m .. , s PBAPS 2 8 3, IST Program > Sp;c. M-?10, Rev. 2 1 Page 9 of 16 , t M-333 (1,2) Instrument Hitrogen - ifi M-351 (1,2,3,4)Huclear Poiler j ( j) M-352 '(1,2,3,4) Nuclear Boiler Vessel Instrumentation 1 M-355 (1,2,3,4) Reactor Recirculation Pump System i M-354 (1,2) Reactor Water Clean-Up System n M-356 (1,2) Control Rod Drive Hydraulic System Part A s M-357-(1,2) Contro) Rod Drive Hydraulic System Part B l H-358 (1,2) Standby Liquid Control System ; M-359 (1,2) Reactor Core Isolation Cooling System i M-360 (1,2) RCIC Pump Turbine Details M-361 (1,2,3,4) Residual Heat Removal System l M-362 (1,2) Core Spray Cooling System t M-365 (1,2). High Pressure Coolant injection System ' h-366 (1,4) HPCI Pump Turbine Details . H-367 (1,2,3) Containment Atmospheric Control System i M-368 (1). Radweste liquid Collection System (Unit 2 and Common) [ M-369 (1) Radwaste Liquid Collection System (Unit 3) i M-372 (1,2) Containment Atmosphere Dilution System ! M-373 (1) Breatbing Air System '! M-376 (1,2) Traversing Incore Probe System ! M-377 (1,4) Diesel Generator Auxiliary Systems M-391 (1) Primary & Secondary Containment Isolation Control ! 5.0 EVME_AHQ.yAkyEhhiECTION j Pumps and valves which are within the scope of ihn Inservice Testing Program, [ as defined in Section 4.1, and are not exempt per Section 4.2, shall be tested i in accordance with the Saction XI Code Edition stated in paragraphs 2.2 and , 2.3. Pumps and valves (as defined in IWV-2000), including all applicable- ; testing requirements and frequencies, are listed in the IST Tables. Pump and 7s valve IST-Table descriptions are found in Section 6.0, When valve testing ! (,} t must be deferred to cold shutdown, Cold Shutdown Test Justifications are provided in Appendix A, Hben the pump or valve testing requirements of the '[ applicable code cannot he met, relief requests are provided in Appendix B or ! C, respectively, , 5.1 CODE REQUIREMENT POSITIONS FOR PUMPS [ This- section indicates the position used to clarify Section XI requirements as they apply for the formulation and the implementation of the pump progrnm. 5.1.1 Pump Inlet Pressure Test circuits on certain pumns are not provided with inlet or dif ferential pressure indicators. These pumps are either submerged in a wet pit or take suction from a storage tenk. Therefore, suction pressures will be calculated , from the fluid level ir. the tank or pit. Sinco IWP-4240 does not specify the method to determine suction pressure, relief will not be requested. However, the particular pumps which require this calculation will be identified in the remarks section of the IST TABLES-PUMPS. 5.2 CODE REQUIREMENT POSITIONS FOR VALVES This section indicates the positions used to clarify Section XI requirements as they apply for the formulation and the implementation of the valve program. 5.2.1 Pr.swive Valves Parawraph 4.3.2 defines passive valves as "valvos which are not required to change position to accomplish a specific function", for this program, passive valves are further defined as those valver where the normal and safety g- g position are the same, and the valvo is not required to chango position during i 4 any normal plant operating condition. Category D passive valves will not be
\~ / '
ine.tuded in IST Tables-Valves unless they have remote position indictetors and are also located in the flow path of a system important to safety that is idle duri no normal plant cueration.
.,_ ; _ g; __ = - s . _ _ m,,.___ _ _
~~.-m< _ . _
b PBAPS 2 & 3, IST Ppagram C Sp;c. H-710, R v. 2 O Pcg3 10 cf 16 0 i e k
- 5.2.2 Cold Shutdown Valve Testing p C For valves -in which testing is Aferred to cold shutdown, testing will O commence within 48 hows- af ter conb shutdown is achieved and will continue until all tests are completo or the plant is ready to return to power. Any
- testing not comple'.ed at one cold shutdown will be performed during subsequent cold shutdowns. _For planned cold shutdowns in which PBAPS-2 & 3 will have q suf ficient time to complain the testing of all valves identified to be tested )
at cold shutdown, exception may be taken to the 48 hour start time. As a t minimum, all cold shutdown valves will be tested during each refueling outage, however, valve testing will not be performed at a frequency greater than L quarterly for Catcoories A, B and C valves. 5.2.3 Cold Shutdown Valve Testing Corrective Action b
?'
Subsections 1HV-3417(b), for categories A and B valves, and INV-3523, for category C valves states "Hhen corrective action is required as a result of testing during cold shutdown, the condition shall be corrected before start- t up." At PBAPS 2 & 3 thb. will only apply to valves that can only be tested at cold shutdown. For valves that can be tested quarterly at power and whereby the Technical Specification allows plant start-up with the valve inoperable (or its associated train or system), then the plant may return to ; power and the valve tested af ter repair. . 5.2.4 Check Valve full / Partial Stroke L In most cases, system design flow through a check valve requires less than
- > full mechanical valve movement. As used in this program, the term full stroke refers to the ability of the valve to pass system design flow or a full mechanical stroke. Any test that v eri fies less than system design -flow capability or full mechanical movement is considered as a partial stroke test.
\
- (d. 5.2.5 Valve Position Indicator Verification Verification of proper remote position indication (IHV-3300) will normally be accomplished by locally observing the position of the valve and comparing ,
it with the remote indication. Some valves are not equipped with a local means to verify position, therefore, position will be verified by the
-observation of system parameters such as flow and pressure during valve cycling. For valves having remote position indicators at multiple locations that include the control room, the control room remote position indicator will be verified for accuracy and tSe *ote position indicator used for .
exercise testing and stroke timing the valve will also be verified for accuracy. If exercise testing and stroke timing are performed using only the , control room remote position indicator, then only the control room remote . position indicator needs to be vorified for accuracy. , f 5.2.6 Fail-Safe Testing of Valves r For fail-safe valves, whereby placing the control switch in the OPEN position i for fail-open valves, and the CLOSED position for f ail-closed valves, results in a loss of actuator power, the fail safe testing requirements of INV-3415 i will be satisfied by the exerciso testing required by INV-3412. l 5.2.7 Measurement of Stroke Times For valves which require stroke time measurement in accordance with IHV-3413, ; stroke timo'will' commence upon movement of the valve control switch and end when the position indication light is illuminated. 5.3 AL.TERATIONS TO SECTION .t1 REQUIREHENTS FOR PUMPS O 5.3.1 Pump Vibration Testing i u' PBAPS 2 & 3 has adopted velocity ( ASME/ AHSI OM, Part 6) instead of l displacement (INP-4510) for measuring pump vibration on all pumps in the IST
_.. Ly%g _ . _ ___ _ _m___ m., _ 6 PBAPS 2 & 3, IST Prcgram i Spic. M-710, R3v. 2 : Page 11 of 16 Program. Justification is provided in . Relief Request GPRR-1, based on the f] conclusion that measuring velocity provides a significant improvement in the predictive capability of vibration testing, which will result in earlier j L (' d a detection of potential problams, y 5.3.2 Pump Bearing Temperature Pump - bearing temperature monitoring (IWP-4310) will not be rerformed. F Justification is prov ded in Relief Request GPRR-2, based on the :enclurion that the' ability of improved vibration testing to detect very small changes e in bearing cendition would preclude any bearing condition severe enough to cause an abnormal rise of the temperature on the bearing housing. $ x" 5.3.3 Pump flow Rate Certain pump test circuits are not provided with installed rate or quantity 1 maters as required by IWP-4600. llowever, in all cases the test circuit is such that a flow rate can-be determined by rate of level change in a tank per unit of time calculations. Since this is an alternate method for measuring ; flow rate, specific relief will be provided in Appendix B fo6 the associated > pumps. ; 5.4 ALTERATIONS TJ SECTION XI REQUIREMENTS FOR VALVES 5.4.1 Increased Testing Frequencies The testing _ frequencies for certain Catigory C and D valves have been __ - increased in compliance with Technical Speci fica tion commitments. -The - specific frequency designations and the associated references are contained in ti.e test f requency section of Table 6.2-1. f 5.5 COLD SHUTDOWN TEST JUSTIFICATION DISCUSSION , t (, .; Section XI permits the dolay of valve testing that is impractical during }
'~
operation, to be performed during cold shutdown. Justification for this delay of testing is provided by the Cold Shutdown Test Justifications included in t Appendix A. Each Cold Shutdown Test Justification is formatted to contain tha
-- f ollowi ng information.
Cold Shutdown Test Justification Number System Valve Identification Number (s) i Category , Function -i Deferred Testing +
- Cold Shutdown Test Justification ~ .
Quarterly Partial Stroke Testing, if applicable ; Cold Shutdown Testing The cold shutdown test justifications are formatted for numerical filing as follows: 1 1 XX-VCS-Y wheres : XX = System designation number i VCS = Valve cold shutdown test justification . Y = Sequential number within any system l
~
l Applicable ' cold shutdown test justification numbers are listed in the VRR/VCS : Number column of the IST Table-Valves. [ 5.6 RELIEF REQUEST DISCUSSION 5.6.1 General ; wn I t i
'~
Hritten relief requests as allowed by 10CFR50.55a(g)(5)(iii) have been . l provided in Appendix B, for pumps, and Appendix C, for valves, tu provide l t
. - - u.-.- - - - --
w- w.-, ;-_. ~ - n---.-n.~. PEAPS 2 & 3, IST Prceram f P Sp;c. H-710, Rsv. 2 P?g3 12 Cf 16 ;I t? e: justif* cation fore .
)
_7-~s - i, l
.( ) Performance of testing requirements on pumps and valves that are impractical L(_,/ L -
during both operation and cold shutdown. p
- The use of alternate tesi no methods - when Code requirements are either j? ~ impractical, or where th. alternate methods provide equal or greater ['
assurance of pump and valve operabili ty. Each relief request is formatted to include the following information: 7 n
- Relief Request Number System (specific relief requests only) .T Pump or Valve Identification Number Category (valves only)
- function =(specific relief requests only) _
- Testing Requirement from which relief is requested 't Basis for1 Relief .
Alternate Tenting 1 5.6.2 Generic Pump and Valve Relief Requests . Generic relief requests are used when a relief request applies to a grouping 4 of pumps or valves (e.g.: all containment isolation volves that are Type C l tested, or'all centrifugal pumps). These relief requests are formatted for numerical filing as follows: , GVRR-Y'or GPRR-Y where a , , . OVRR = Generic valve relief request ; GPRR = ceneric pump relief request Y = Sequential number-
\~ / In the IST Tables-Valves, applicable relief request numbers are listed in the VRR/VCS Number column. .
5.6.5 Specific Pump and Valve Relief Requests , Specific relief requests are used when a relief request applies to specific pumps or valves. They are formatted for numerical filing as follcws: XX-VRR-Y or XX-PRR-Y wherei , XX = System designation r. umber ) VRR = Valve relief request PRR = Pump relief request Y = Sequential relief request number in any system < In the IST Tables-Valves, applicable relief request numbers are listed in the VRR/VCS Number column. 6.0 IST TABIE_yES_QRTHL0 tis - PyMPS AN_D_YALYES 1 6.1 IST TABLE - PUNPS , 6.1.1 Summary These Tables contain an alpha numeric listino of all the pumps include'd in the PBAPS-2=& 3 IST Program. The data contained in these tables identifies the inservice test parameters to be measured or observed, the applicable relief requests and any applicable remarks. A column for testing frequency was not included since all measurements of IST parameters for pumps will be
/
( perfor med quarterly, t ) 6.1.2 Pump Table Format i- - _
- - ~ . _ - 4_
m =ng g.; a ., .;,r = - - - - %% ., ,_ [,, PEAPS 2 & 3e IST Prcgram i Sp;c. H-710e R;y. 2 ( pig] 13 of 16 ,1 f 1
-]- The Pump IST Tables have been organized to provide the following inf ormation - (the numbers in parenthesis correspond to those found on sample Table 6.1-1):
6 (1) . PUMP.NAME OR DESCRIPTIDH The pump description. 4 (2) PUMP ID ND_,,i lhe pump identification number. (3) ffdR: Piping and Instrumentation Drawing on which pump is depicted. (4) CRSED: Location coordinates of the pump on the P&ID. (5) TEST PARAMETER $i This column lists the applicable testing paraneters that will be measured or observed. The parameters listed are those required by the code unless al'ernate testing is provided by relief request . The following is a description of applicable parametersi (a)H - Pump speed (only required for variable speed pumps) ( b) Ei - Pump suction pressure (c)Df_E - Pump differential or discharge pressure (d)R- Pump flowrote (e)Y - Pump vibration veloc;,ty Observe proper pump lubricant level or pressure ( f ) l,/.E - j (6) EILIEF RL9ESJ,i Lists any applicable relief request numbers. (7) R EAPl$i Any additional pertinent information is provided in this space. I (f 6.1.3 Sample Table M.a. .n. i>=n / iE'4."E i m ..n : M89 tea'E M8F 1857 MLitD mmmum Ln.aa. __ rus sat. reen mn uwu L m o> o, m m m m 6.2 IST TABLE - VALVES 6.2.1 Summary - These Tables provide a tabulation of all valves included in the PBAPS-2 & 3 IST Program. The tables are arranged by system and the valves in each system are listed in nlpha-nume-ic sequence. 6.2.2 Valve Table Format Each table has been organized to provide the following informa tion '( the. numbers in parenthesis correspond to those found on sample Table 6.2-11:
+
(1) SYST @i Tnie system name and number that the particular table applies to. (2) VALVE NUMBER: The valve identification number (3) P&ID Piping and instrumentation drawing and sheet y number where the valve is located (4) C_QQRD: Valve location coordinates on the P&ID
a .- -, ~zz;- = _zu.e. _- _. _ 1 PBAPS 2 & 3e IST Progr am Spec. H-710, Rev. 2 PnDo 14 of 16 (5) VALYL _ CAL.i Valve cateoory as identified in paragraph 4.4. (6) ACIt.fA$ e Classification according to IHV-2100, where A s Active and P = Passive (7) $110 Nominal valve sire in inches (b) YALYL_IX.tL i Valve design type s9) At k l1EE lype of actuator i med to change position of the valvo (l0) EQ3J1L01($i operation ( ! HRM - Position during normal plant (including system test modes) (b) SAF - Position to fulfill safety reinted function (c) FAL - Position valve fails to on lors of ac*uator power, if applicable (11) APP. J TYPE _Gi Indicates whether valve requires Appendix J, Type C leak lest, where Y = Yes N
- No (12) 1LSMRLE,_I111 REC.LII21' 1he information contained in this column indicatos the actual t e. .,,, that will be performed. If it.e poi ed testing is different from it.e Section A. requirements, e
-- relief request or -told s,buidown test justification will be provided. The f ollowing information is contained in this columni 1EST - The required testing to be perforned.
FREQ. - The frequency at which the required testing will be performed. (DIRECilDN) - The direction (a) that a valve will be exercised or stroke timed. This information is coded using the codes contained in Table 6.2-2. Tha following are examples of how the inf ormation is formatted in this column Rower R etaltd_xciresi ST-0(0) r 5iroke time quarterly in the open direction. FS-C(C)
- Fail stroke at cold shutdown in the closed direction Check valy m Et-Q(f8R) = Exercise inst naarterly in tho f orwar d and reverses direction.
(13) YRRdCSJ3!MER: All applicable relief request (VRR) and/or cold shutdown test justification (VCS) numbers are listed in thin column. (14) RLtlA.M,$ i Any additionnl pertinent informatior is provided in this space. 6.2.3 Sample Table nnwi..mE N ?fde# . u.ai i,
- m. u, bel n M4 M ll WW FT1, , PMjff_?(1_ 49. J filf f 48 4 Vt.t* S IMMA M EMD 1Ab. tal. 81 3 !?L Ift tea W iA !%s WitumL iattu, tiaal
<a n el> ten ein esa cri .gi tei m .s im 6: Un o ato <m tm uts
w .- a za;aa.m.a2as s aw w .wz.w ;zz..:..-azz.a.u-.s;. x..;,;, m . c -
= r ~ m PBAPS 2 & 3r IST Pergpan Sp:c. H-710, R3V. 2 P:03 15 of 16 6.2.4 Valve Table Codes
( * ( A quick reference table providing definitions f or the codes (abbreviations) used on the Valve Tables is provided. VALVE TABLE CODES VALVE TYPE VALVE TYPE ACTUATOR TYPE CODE DEf!NITION CODE DErlNITION CODE Dr. FIN 1110H AN Angle Globe RD Rupture Disk A0 Air Operated BF Butterfly RL Relief EX Explosive-Operator BL Ball SK Stop Check MA Manuel Operator EK Check TC Testable Check M0 Motor Operator D1 Diophragm 1H Three-Hay NO Nitrogen Operator EX Explosive Vn Vacuum Rollef LA Self-Actuated OL Olobe XC Excess flow Check S0 Solenoid-Or rator GT Gate VALVE POSITIONS TEST DIRECT 10H CODE DESCRIPTION CODE DEf!N1 TION
- 0 Open 0 Open "
C Closed C closed LO locked Open r forward Flow LC Locked Closed R Reverse Flow Determined by systen parameters (e.g. check valve) Al As is DC Open or Clused TEST REQUIREMEN10 TEST FREQUENCY CODE DEFG ITION CODE DErlHITION ET Tull Stroke Exercise per 4 quarterly IWV-3412 or 5522 C Cold Shutdown FS rail Safe per IWV-3415 R Refueling LJ Lenk Test per 10CFR50 R3 Every refueling, and when Appendix ' conditions specified in the LP leak Test per Section XI associated Relief Request exist l PI Remote Position Indication T Every 2 ye9rs Test per IHV-5300 P1 50% each refueling outage Pf Partial Stroke Exercise per TS 4.6.D.1 RD Rupture Disk- P2 Every 5 years per DM-1 1981 RT Relief Valve P5 Every 10 years por DM-1 1981 ST Stroke Time per 1WV-5413 P4 Not Used XT Explosive Valve per IWV-5610 P5 $0% each refueling outogo per 15 4.4. A.2 P6 At leant 20% of = the squib valves every 2 years per IHV-3610-Pt Every refueling outage per TS
.iA (Unit 2) 15 4.4.A.2.a V
x am_.,-- --
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PRAPS 2 1 3, TST PPIOram sp:c. H-710, R:v. 2 Pcos 16 of 16 7.0 RicQRM (~)a The current status of the IST program will be contained in the IST 1mplementing Plans. A record of the actual test results will be contained in the specific surveillance test procedure ustd to perform the test and retained by the Neelear Records Section.
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o f li n 1 9 i' 5 1
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_ ...~..-. _ . - - - - . . . ' - . - - . - . . . ~ - - . , - . - - - - - - - - - ~ - - . - - ~ ~ ~ s'y-vg ; PBAPS 2 & 3, IST Program '
- 7) I spec. H-710, Rev. 2 ;
Ap endix A fr Page 1 of 14 fl ?
., g COLD SHUTDOWN TEST JUSTIFICATION 01-VCS-2, REVISIDH 0 Systems Main Steam Valve (sit MO-2-01-074 M0-2-01-077 M0-3-01-074 M9-3-01-077 Category: A runction: Main steam line header drain inside/outsida primary containment isolation valven.
Deferred Testingt Exercise and stroke time. Cold Shutdown During operation, those valven are normally closed r Test Justificationt which is their required sa f ety position for primary conte'.nment isolation (i.e. all valves receive a containment isolation _ signal). Valven MO-2( 3 )-01-074 are located in the drywell and valves MO-2(3)-01-77 are located in the steam tunnel. The
, drywell and steam tunnel are both high radiation areas during operation and access to these areas is limited to emergencies only. In addition, the drywell is inerted with nitrogen and the steam tunnel is a high temperature area which results in ' limited occupation timen f $r plant personnel, railure in the open position during testing would compromise primary containment isolation.
Quarterly Partial ihn operating circuitry of there valven only permits full Stroke Testingt stroke operation. Cold shutdown Exerciso and stroke time. Testingt __m_u-________-____-._________________________._______m_ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ __
.ws - a,. c-~,, -- - - w . ,. . ,, -. --
g --
~ ~ = _ - _ ,,,~.n-- , w-~
\
PSAPS 2 & 3e IST Pergram
$56c. M-710, R3V. 2 1
,, A50:ndix A Page 2 of 14 j I
; COLD SHUTDOWN TEST JUST1FICATION 02-VCS-le REVISION 0 (Ov) systems Reactor Recirculation j Valvetsli MO-2-02-53A, B MO-5-02-53A, B I Categoryl B 3
Functiont Reactor recirculation pump A and D discharon isolation valves. Deferred Testing Exercine and stroke time. ! Cold' Shutdown Exercising these valvos during normal operation would renairn Test Justifications a reduction in power and interrupting flow in one recirculation loop. Additionally, if these valves failed in the closed position during testino, the plant would bn forced to operate at a reduced power level until the plant could be shutdown for repairn. 1 Quarteply Partial The operating circuite y of those valves only permits full : Stroke Testingt ., stroke operation. Cold shutdown Exorcise and stroke time. Testingt _ .. i 1 D)' v s (% 7 )II e y s- - - - - - - - . m: - o.a r-m-,- -r-s
._a a aaa n n.;. .i. .aa; , : ..w --.. - s -m - .ae, m , t PBAPS 2 & 3, !$T Pr; gram - Sp;c. H-710, R;V. 2 ? Apb:ndiF. A : Page 3 of 14 i f (N COLD SHUTDOWN TEST JUSTIFICATION NO. 03-VCS-1, REVISION 0 i (n)] s ( Systems Control Rod Hydraulic j Valvetsli CHK-2-03-15115AA+HC CHK 3-03-13115AA+HC Categoryt C j Function: Scram accumulator charging and drive water line check valves. j Deferred Tgstingt Exercisa in the reverse direction, ; Cold Shutdown Verification of reverse flow closuie requires securing j Test Justificatient the Control Rod nr ive Pumps, depressurizing the header, and ; monitoring the indivi iual accumulator pressure and alarm to i verify that the valves have closed on reverse flow. Securing the control rod drive pumps and depressurizing the header would i render the control rods inoperable resulting ir, a loss of . control rod reactivity control. This would be in direct conflict with the objective of lechnical Specification 3.5 i which is to assure the ab-111ty of the control rod system to control reactivity, , Quarterly Partial Partial stroke testing requires the same conditions as full i Stroke Testing stroke testing, Cold Shutdown Verification of reverse flow closure will be performed by Testings depressurizing the header and monitoring the individual accumulator pressure and alarms to verify that the valves have [T closed on reverse flow. N] ,
-1 i
I m a _ . ~ . . - . _ _ . _ . -~. .- . , . _ _ . -
. . _ . m---- gc _ ; _,,, , - ____-.~-- w_ .__m______ _ ,,
..k PRAPS 2 & 3, IS1 Pp; gram }.
Sp6c. H-710, R V. 2 t Aph ndix A Page 4 of 14 f.
,em COLD SHUTDOWN TEST JUST1FICATION NO. 06-VCS-1, REVISION 0
( ) N(;,)- f, Systemt Feedwater t. Valvelsit MO-2-06-038A, B g^ M0-3-06-038A, B Category: A , 1-Functions reedwater nystem outside primary containment isolation valves. j Deferred Testing Exercise and stroke time. I Cold Shutdown Valves MO-2(3)-06-038A, B perform a safety function only in ! Test Justifications the closed direction (i.e. containment isointion). These ; valves are open during start-up and shutdown only and connot be orened when reactor pressure in grector than 600 pai. 't Because reactor coolant system pressure during power creration is >600 psig these valvon ennnot be exeretaed. / Quarterly Partial lhe operating c', cuitry of these valves only parmits < Stroke Testingt ,, full stroke operation, j i Cold shutdown Exercise and airoke timo. e Testingt t CT i V} .--
+
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PBAPS 2 & 3, IST PPCDram Sp;c. H-710, R v. 2 Ap>:ndix A , PAUG 5 of 14 Q j COLD SHUTDOWN TEST JUSTIFICATION HO. 09-VCS-1, REVISION 0 Systemt Containment Atmospheric Control
~
Valve (sit A0-2-09-2505 A0-3-09-3505 A0-2-09-2506 A0-3-09-3506 A0-2-09-2507 A0-3-09-3507 AU-2-09-2511 A0-3-09-3511 AL-2-09-2512 A0-3-09-3512 A0-2-09-2519 A0 3-09+3519 A0-2-09-2520 A0-3-09-3520 A0-2-09-2521A, B A0-3-09-3521A, B Category: A runctions reinary containment isolation. Deferred Testingt Exerciso, stroke time, and fail-safe test, cold Shutdown During operation these valves are administratively Test Justificationi blocked closed which is their r equired safety position for ne imary conininment isolation. Iallure of these valves in the, open position during testing would result in a compromise of primery containment inolation capability. Those valven are only operated just prior to start-up and shutdown for inerting/do-inerting purposes at which time they will exorcised and stroke timed, and f a,il-saf e tested. Quarterly Partini The operating circuitry of these valven only permits Stroke Testingt full stroke operation. Cold Ghutdown Exorcise, stroke time and inil-safe test. Testingt { %, .
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l PBAPS 2 & 3, IST PPCDram 1 Sp0c. H-710e R::v. 2 4 Aph:ndix A Pege 6 of 14 [i b o* gJ< COLD SHUTDOWN TEST JUST!FICATION NO. 10-VCS-1, REVIS10H 0 o Systems Residual Heat Removal (RHR) Valve (sit A0-2-10-046A B f A0-3-10-046A, B [ f '9 gory: A, C
>. actions RHR injection check valves-RCS pressure isolation and primary y containment isolation, s Deferred Testing Exorcise in the forward and reverso direction. .
Cold Shutdown Testable check volven AU-2(3)-10-046A, B are closed J Test Justifications during operation and function as both primary conininment isolation valves and Reactor Coolant System pressure icolation 1 valves. During onoration, these valves protect the RfiR System . from Reactor Coolant System pressure. The valves aro located l Inside primary containment which is not accessible during operation, since i t 12 inerted with nitrogen and is a high
. , radiation area. In addition, because these valvos are required -
to be operable for primary containment isolation per technical i specifications (T.S. 3.1), and are inaccer.sible during operation, failure during testing (failure in the open tosition) would require a plant shutdown to repair the valves. + t Quarterly Partial Partial stroke exerciuing results in the same ! situation es full stroke exercising. t Stroke Testingt Exercise in the forward and reverse direction. Cold shutdown y- Testings l 7 h a t I I J, r= -v--*w s.w - , - < - y* .
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/'"T COLD SHUTDOWH TEST JUSTIFICAT10N ".40, 10=VCS-2, REVtSION O (j{
Systemt Residual Heat Remosal (RHR)
?
Valvets)t H0-2-10-017 ) MO-2-10-018 MO-3-10-017 MO-5-10-018 s Categoryl A i Functiont RHR shutdown cooling return inside/outside primary containment isolation, RCS pressure isolation. i Deferred Testingt Exercise and stroke time. ' Cold Shutdown These valves are interlocked to prevent operation Test Justifications whrn Reactor Coolant System pressure is > 75 nwic. Because Reactor Coolant System pressure during power operation is > 75 psio these valves cannot be exercised. Quarterly Partial .a Partial stroke exercising cannot he performed for the Stroko Testingt same reason mentioned above. h Cold Shutdown Exercise and stroke time, Testings (u a) Q.
L.,,, - ' = ZJL .._. .- a_ - - _- _ . ~ . - - - - --_~.---..-~.-----y PBAPS 2 & 3 IST Progetm } spbc. H-710, Rev. 2 Afi$sndix A l P&Oe 8 of 14 . 4 CDiD SHUTDOWN TEST .USTIFICATION NO. 14-VCS-1, REVISION 0
) '
Systemt Core Spray Valva (sit A0-2-14-013A, B Catepony: A, C Functiont Core Spray injection check valves - RCS pressure isolation and primary containment isolation. Testing Rer';aintament(s) Exercise in the forward and reverse direction. Basis for Relieft Testable check valves A0-2-14-013A, B are closed during operation and function as both primary containment inolation valves and Reactor Coolant System pressure isolation valves. During operation these valves protect the Core Spray Systems from Reactor Coolant System pressure. The valves are located inside primary containment which is not accessible during operation since it is inerted with nitrogen and is a high radiation area. Because these valves are required to be y operable for primary containment isolation per technical spweifications (T.S. 3.7), and are inaccessibin during optera ti on , failure durinu testing (failure in the open position) would require a plant shutdown to repair the valves. Alternate Tostingt Full stroke exercisino in the forward and reverse direction will be performed durino cold shutdown by utilizing the air operator. 1
'L/
. - . .n ~. -- .Mua- -- -=~ - a a .- ~ a u L +a.-' PBAPS 2 1 3, 1ST Pp gram , spec. H-710 Ray. 2 ! Appendix A P8ge 9 of 14 : COLD SHUTDOWN TEST JUSTIFICATION 33-VCS-1, Revision 0 Qv Systems Emergency Service Hater (ESH) Valvetsli CHK-2-33-514 CHK-3-33-fl4 Categorrt C L runctiont Prevent ESH flow diversion into Servien Hater System. Deferred Testing Exercise in the reverse direction. Cold shutdown Check valves CHK-2-33-514 and CHK-3-33-514 cannot be Justifications exercised in the reverse direction during nornal plant operation because the present piping configuration does not allow for isolating service water upstream of these check valves. In order to perform a vali:1 reverse closure test during power operation, the servlee water system must be shut-off rendering several plant systemn increrable which include
- Fuel Pool Service Hater Booster Pumps
- RBCCH Heat Exchangers
- Condensate Pump Room Coolers
- Domin Hold Pumps
- Drywell and Control Room Chi!!ers
- Main Generator Hydrogen Coolers '
- Main Turbine tube 011 Coolera
- Vacuum Pump Heat Exchanger
- Reactor Feed Pump Lube Oil Coolers V -
Loss of service water to the above systems can result in equipment damaus. In addition, loss of service water to critical turbine generator nupport equipment will result in a turbine trip and subsequent reactor shutdown. Quarterly Partia! Not applicable. Stroke Testing! Cold Shutdown Reverre flow closure will be verified when service water can Testingt be shut-off. i d(D o k3 i I l l l
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$$bc. H-710 Rov. 2 App:ndix A P&ge 10 of 14 (hj. ') COLD SHUIDOWN TEST JUSTIFICATION 34-VCS-1, REVISION 0 Systemt Reactor Building Closed Cooling Hater Volvo(sit MO-2-5f-2373 t
MO-2-34-2574 MO-3-34-33/4 M0-3-34-3374 CateDorYI A Function Inlet and outlet primary containment isolation valves. Doferred Testingt Exercise and stroke time. Cold Shutdown Testing during operation would cause a lor.s of Test Justifications cooling water flow to the recirculation pump seal and motor oil coolet s. The failure of any one of those valves to coopen after stroking would res. ult in a complete loss of cooling to the associated recirculation pump, which could cause damage to the pump and motor. A damaged pomp or motor, necessitating shutdown, would requira a reduction in reactor power in accordance with Technical Specification 3,6.f.4. Quarterly Partial The operating circuitry of those valves. only permits Stroke Testings full stroke-operation. Cold Shutdown Exercise and stroke tima. Testingt i
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)) COLD SHUTDOWN TEST JUST!FICATION 35-VCS-1, REV1810N 0 vv Systete Instrument Air ;
Valvelsit CHK-2-35-087A. B, C, D CHK-3-35-087A, B , C, D Categoryl C Functiont Main steam isolation valvo accumulator makeup supply check valves. Deferred Testingt Exercise in the reverse direction. Cold Shutdown . Reverse exercisinp verification recluires isolating Test Justificationi and venting the associated instrument air supply header and '. observing the accumulator pressure. Since pressure indication is not rrovided for the accumulators, a test gauge must be installed on a tout connection which is located inside the s'.eam tunnel. The steam tunnel is a high radiation and high temperature area during power operation and necoms is limited a to emergencies only. Quarterly. Partial Not applicable. Stroko Testingt
. Cold Shutdown Reverse exercising will be performed.
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t w ~ - --.- _ . _ - .-- w .- .--
. na. .,x_w-m PBAPS 2 4 3, IST PPC0 ram SD6c. H-710e R:v. 2 App:ndix A Page 12 of 14 - r3 iC); C01.D SHUTDOWN TEST JUST!FICATION 44-VCS-1, REVISION 0 Systems Chilled Hater (P?ywell Cooling)
Valvetsla MO-2-44-2200A, B M0-3-44-3200A, B NO-2-44-2201A, B NO-3-44-3201A, B Category: A Function Chilled water drywnli supply and return header containment isolation valves. Deferred Testingt Exercise and stroke time. Cold Shutdown Exercising these valves during power operation could Test Justificationt result in a trip of the drywell chillers due to a low flow condition. These chillors supply chilled water to the reactor recirculation motor coolers and the drywell fan coolers, and if tripped requirn 3D minutes for restart. Interrupting chilled water flow to the recire. motor coolers, due to n chiller trip, creates the poss.ibility of overhanting and damago
, to the motors which would result in taking the recire, pump out of service. Removing a recire, pump from service would require a reduction in pwer. Interrupting chill water flow to the drywell fan coolers, due to a chiller trip, could result in an increase in drywell temperaturen which would causa an increase in drywell pressure. Normal operating drywell pron urn it. .50 to .75 pslo with a Reactor Protection System trip netpoint of it 2.0 P510 as por Technical Specifications (Table 3.2.A). Therefore, an increase in temperaturn could resul t in a reactor scram.
Quarterly Partial lhe operating circuitry of these valves only permits Stroke Testings full stroke operation. Cold Shutdown Exercise end stroke t i me . Testingt
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$$6c. H-710, R:v. 2 A D:ndix A Page 13 of 14 COLD SHUTDOWN TEST JUSTIFICATION 49-VCS-1, REVISION 1 (v[.} Systems Standby Oas Treatment Valvelsit A0-2-49-20452 AD-2-49-20463 A0-3-49-30459 A0-2-49-20453 A0-2-49-20464 A0-3-49-30460 A0-2-49-20457 A0-2-49-20467 A0-3-49-30461 A0-2-49-20458 A0-2-49-20468 A0-3-49-30462 A0-2-49-20459 A0-3-49-30452 A0-3-49-30463 A0-2-49-20460 A0-3-49-30453 A0-3-49-30464 AD-2-49-20461 A0-3-49-30457 A0-1-49-30467 A0-2-49-20462 A0-3-49-30458 A0-3-49-30468 Categoryl B Function Reactor Building Ventila tion Supply and Exhaust.
Deferred Testingt Quarterly Exercising, rail-safe and Stroke Time Testing. Cold Shutdown In order to test ths valves referenced above. it Test Justifications would be necessary to remove the associated supply fan from
. service. This would cause a high temperature condition in the steam tunnel room which is cooled by the reactor building ventilation system. If temparatures get high enough the reactor would scram. In addition, loss of secondary containment iningrity would be a violation of Technical Specification 3.7.C.I.
- After a supply fan is inken out of servico, approximately 20 to 30 minutes would Le required to reduce the temperature to
("'j en acceptable level in the steam tunnel rooms.
\-'! Quarterly Partial The operating circuitry of those valves only permits i Stroke Testingt full stroke operation.
Cold Shutdown Exercico, stroke tima, and fall-safs tose. Testingt 1 i
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Systemt Instrument Nitrogen Valvols): CHK-2-51-23202A, B CHK-3-51-33202A, B Category: A, C Function Instrument Hitrogen supply to Primary Containment and Containment Isolation. Deferred Testingt Exercise test - reverso direction. Cold Shutdown Exercising these salves during power opera':.on Test Justificationi interrupts instrument nitrogen supply to several important valves inside containment, such as main steam relief valves power operated mode (non-ADS function), the ADS accumulators and the MSIVs. This could compromise the enility of the main steam relief valves (non- ADS functioi) tu operate in the power oper ated relief mode. In addition, luolation of nitrogen to
, the ADS accumulators could also compromise the ability of the ADS valves to function in the ECCS mode. Loss of instrument nitrogen could also cause the MS!Vs to close, increasing the potential for a reactor scram.
Quantoply Pettf 4 Not Applicabin -"" Stroke Tor. ting Cold Shutdown Reverse flow closure will bn verified. Testing p]
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\
v Pumpts): All pumps in the ISI Program Testing Requirement (sla Neasure vibration amplitude displacement quarterly (INP-4500) Basis for Relief ASMr Section XI requiren pump vibration measurement in displacement amplitude, (peak-to-peak composite), to be taken during each inservice test. Although not identified by Section XI, vibration can also be accurately measured using vibration velocity measurements. The criteria for vibration measurement is not sensi tive/ dependent on the pumps spend and provides an absolute value for acceptable limits on vibration. In addition, this technique is an industry accepted method which is sensitive to vibrational changes that are indicative of developino mechanical problems. Velocity measurements provide an acceptable predictive tool to detect changes in the vibration that Irdicate a mechanical problem. Since section XI does not addrens vibration velocity measurement, methods for ter. ting and acceptance cri teria will be in accordance with ANSl/ASME OM, Part 6 - 1987/1987A. Alternate Testingt Pump vibration measurements will be in vibration velocity (in/sec). Acceptance criteria from ANSI /ASME OM, Part 6 - 1987/1987A is summarired in Tabla 1 below. Table 11 Vibration, Velocity lin/sec), Acceptanco Critorian Atten_teMsLRensa Alerl_Ronan RowireLAc11on A Vertical and 0-2.sV, > 2. 5V, -6 v, >6V, Q. Horizontal Centrifugal Pumps or 0 .325 in/see or
>.325 .7 in/ nee or
).7 in/sec (1600 RPM)
@ te: The most limiting of the two r anges olven is applicabin.
8.ctrntable_Runne AletLRanne RenuiteLAction Positive 0-2.5V, > ? . 5V, >6V, Displacement Pumps V, = Vibration Ref erence Value r k ,
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PBAPS 2 & 3, IST Pr: gram Sp;c. H-710, Rev. 2 App;ndix B Page 2 of 4 4 RELIEF REQUEST NO. GPRR-2, REVISION 0
-')' "1
Pumpts): All pumps in the 151 Prouram Testing Requipement(s): Measure bearing temperature annually (IHP-3500) Baris for Relief The measuring of bearisig temperatures along with vibration monitoring are both means of determining the mechanical condition of a pump. However, the condition of a pump bearing would have to seriously degrada to cause a detectable rise of temperature on the bearing housinu, Measuring vibration in velocity provides the ability to detect changes in the mechanical condition of a pump. Therefore, any degradation of a bearing would be detected before an increase of temperature on the bearing housing occurted. Alternate Testing Pump / bearing mechanical condition will be determined using the vibra tion monitoring pr ogram (i .e. measure vibra tion veloci ty). Bearing temper a tur es will not be measured.
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PBAPS 2 & 3, IST PrCgram Sp;c. H-710e R;V. 2 App:ndix 8 Page 3 of 4 O RELIEF REQUEST NO. OfRR-3, REVISION 0 ( NM b PUMP (s ): Diesel fuel 011 Transfer 0AP060 DBP060 DCP060 DDP060 Emergency Service Hater 0AP057 OBP0$7 Emergency Service Water DAP163 (Booster Pumps) OBP163 Imergency Cooling Hater 00P186 TESTING REQUIREMENTIS): Pump instrumentation accuracy shall be within the limits specified in ASME Section XI Subsection IHP Articles INP-4110 and IHP-4120. I! ASIS FOR RELIEF PEco proposes to measure flow using ultrasonic flow instrumentation that is calibrated to an accuracy within 15% of-reading instead of the Code required 12% of full-scale, d Although this equipment does not meet the Code eequirements exactly, it meets the intent of the Code by ensuring that data collected during inservice testing is measured to the degreo of accuracy specified in Articles IHP-4110 and INP-4120. Because the Code does not address digital instruments and of-reading accuracy limits, a conversion from full-scale accuracy to of-reading accuracy is nacensary to compare the ultrasonic instrument accuracy to the accuracy specified in the Coda. Also, because the ultrasonic flow transducers are capable of O (,0~ measuring flow over the entire range of the instrument (0 to 40 feet /second), a percentage of full-scale accuracy would be c meaningless when measuring low flow ratos associated with small diameter pipes. To ensure that the most accurate data is collected during inservice testing, the technicians are provided guidance through the vendor ma.nuals to select the transducer that is best suited for the pipe where flow is being measured. For instruments to be in compliance with ASME Section XI Subsection INP, two requirementa must be natisfied. The first requirement (specified in 1HP-4110, Table IHP-4110-1) states that flow instrumentation must be accurate to within 12X of the full iscale value; the second requirement (specified in INP-4120) states that "the full-scale range of each instrument shall be three times the reference value or less." PEco's interpretation-of these requirements allows for establishing a maximum of-reading error of 16% that would be acceptable per the Code. Magnetic flow meters, which provide greater accuracy, were considered. However, because the magnetic flow meters are not seismically qualified, they are not suitable for use in the required applications. Also, installation of these meters would require significant piping modifications. PEco considers that the ultrasonic flow instruments provide the necessary accuracy for pump performance trending purposes and to detect pump degradation. Also, we consider that we meet the intent of the code since the ultrasonic flow instrument
- is accurate to within 15% of-reading. Although the existing l method of measuring flow is acceptable (i .e., measuring change M
(d in tank level na a function of time), ultrasonic flow measurement providos moro accurate data. ALTERNATE TESTING Use ultrasonic flow instrumentation, which is accurate to within 15% of-reading, for measuring IST flow data.
PRAPS 2 & 3, IST Pr: gram-Sp;c. Ma710, R2v. 2 App:n%ix B Page 4 of 4 ; A> RELIEF REQUEST No. 11-PRR-1, REVISIDH 0 f Mh Systemt Standby liquid Control Pumptsli 2AP040 SAPO 40 2BPO40 3BPO40 Functions to inject a borated solution into the reactor for emergency shutdown in the remote event that the control rod system is : totally inoperable. , Testing Requirementis ts rios rate shall be measured using a rate or quantity meter installed in the pump test circuit (IHP-4600). Basis for Relieft The test circuits for these pumps are not provided with in- ; place flowmators. Testing of each individual pump in accomplished by pumping boron solution from the storage tank to the test tank against a system head of 1225 PS10. During this tent, a rate of level increann in the test tank per unit of time is determined. This rata of level increema is then converted to a flow rate via a calculation. Alternate Testing a flow rate will be determined by a rate of test tank level change per unit of tima calculation. .J :
'e l
l a
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Al>l'ENI)lX C O VAINE INSICitVICIC TESTING l'ItOGilAM ltlCI;1EF llEQUICSTS t
w.- ...__...._,_-._2;w----------=2..w;-- . _.-.w . a _ ww . . u ._ a PEAPS 2 & 3, IST PPC0F03 Sp;c. H-710, Rsv. 2 App:ndix C Page 1 of 21 REl.!EF REQUEST NO. GVRR-1, REVISION 0 ' u
- Valvest Containment Isolation Valves CateDory: A Testing Requirement (sli Leak rate test in accordance with subsection INV-3420.
Basis for Relieft Containment 1*2olation valves are required to be leakage rate tested in accordance with 10CTR50, Appendix J. 1ho leakage rate requirement in based on a total allowable leakage rate for all valves instead of en individual valve leakaan rate. 1HV-2200(a) defines Category A as " valves for which seat leakage is limited to a specified maximum amount in the closed position of fulfillment of their function." Although, leakage rates for containment isolation valves is not limited on an individuni basis, they have been determined to be Category A valves. Since containment isolation valves are Category A, the leakage rate testing requirements of IWV-3420 munt ba satisfied. The leakaan rate testing perf ormed per Appendix J satiaafies the requirements of 1HV-3421 through 3425, hnwover, it does not satisfy the indivfdual valve leakage rate analysis and correctivo actions of IHV-3426 and 3427. In order to prevent i, duplicate leakage testing of thene valves, individual Acakage rates will be assioned for each containment isolation valve and a maximum permissible i riaha ce calculated for each local
)
If thin value is exceeded, than cor rective ' leak rain test. action will be taken to restore valva leakage rates to within 5 acceptable limits. !I.e proposed actions will be taken in lieu
/~ of IWV-34'26 and 1HV-S427.
( Alternate Testinut containment isolation valves will be leak rate tested in accordance with the 10CIR50 Appendix J testing preur am, In addition, individual leak rates will be assigned and a maximum permissible leakage criterion establis.hed for each local leak rate test. ss i - i -
3- . . Pago 3
- VRV-2-01-8096D VRV-2-01-0096K :
VRV-2-01-8096E VRV-2-01-8096L -' VRV-2-01-8096F VRV-3-01-9096A VRV-3-01-9096G VRV-3-01-90968 VRV-3-01-9096R VRV-3-01-9096C VRV-3-01-9096J VRV-3-01-90960 VRV-3-01-9096K VRV-3-01-9096E VRV-3-01-9096L i VRV-3-01-9096F t PECo Response Rollof Hoquest 01-VHR-2 has been added to Revision 2 of the Program. Relief Request 01-VRR-2 includes testing the main , stoam safety /rolief valve ta11 pipe vacuum breakers at refueling and during cold shutdowns when the primary containment is de-inerted.
- 3. The licensee has incorrectly identiflod the reactor building e
ventilation supply and exhaust valves listed in Cold Shutdown rest Justification 49-VCS-1 as Category A valves. Those v ives shuuld be Category B because they are not leak rate te i od. The licensco should correct this error. PECo Respons9 Cold Shutdown Test Justification 49-VCS-1 has boon revised in Revision 2 of the Program to designate the reactor building.vont11ation supply and exhaust valvos as Category B.
- 4. The system modifications to allow flow measurements during testing of the amergency service water, emergency service water booster, and emergency cooling water pumps, OAP057, OBP057, OAP163, OBP613, and OOP186, should be-completed as soon as practicable but no lator than the 1991 refueling outage, l-PECo Response A plant modification-(No. 5110) was completed to allow flow =
testing of the. Emergency Servico Water (ESW) pumps, the ESW booster pumps-and the Emergency Cooling Water pumps. This modification was completed prior to startup from the 1991 Unit 2 refueling outage. L 5. The licensee has identified check valve disassembly as the L alternate testing to verify the full-stroke open capability for the valves addressed in relief requests 13-VRR-2,
PEAPS 2 & 3, IST Pr: gram Sp;c. H-710, ROV. 2 App ndix C l Page 2 of 22 n RELIEF REQUEST HD. CVRR-2, REVIS10H 1 ( V~ 0 Valvest Excess riow Check Valven Ca.'egory A, C Testing Requirement (s): Exercise quarterly tasis for Relief t Excess flow check valves are installed on instrument lines penetrating containment to minimize leakage in the event of an instrument line failure outside the containment in accordance with Regulatory Guido 1.11. The excess flow check valve is basically a spring loaded ball check valve. Since the system in normally in a static condition, the valve ball is held open by the spring. Any sudden increase in flow thru the valve (i.e. line break) will result in a differential pressure across the valve which will overcome the spring and close the valve. Functional testing of valve closure is -- accomplished by s enting the instrument side of the valve while the process side is under pressure and verifying the obsence of leakage thru the vent. The testing described above requires the removal of the associated instrument or instruments from service. Since these instruments are in use during plant operation and cold shutdown, removal of any of these instruments f rom service may cause a spurious signal which could result in a plant trip, an inadvertent initiation of a safety system, loss of decay heat removal and/or the defeating of safety interlocks. / In addition to the plant safety concerns, personnel safety (~ concerns must be considered since the proces.s side of these (*]j valves is normally high pressure (>500 psig) and or high temperature (>200 F) and highly contaminated reactor coolant. In summary, due to the plant and personnel saf ety concerns a'nd plant operating conditions that prohibit the testing of tlase valves quarterly or at cold shutdown, testing will be performed at refueling when decay heat loads are at a minimum and safety systems can be removed from ser vice to prevent inadvertent ~ initiation. Alternate Testingt functional testing will be performed at refuelita. p' s V l 1
. mas awnwwrwwwav - a. w nr.arru.v.e.w.r. w-maa.; mc - m.x x.mww-ww mm PSAPS 2 & 3, IST Pr egnani Sp;c. H-710, R:v. 2 App:ndix C Page 3 of 22
- p. 8tELIEF REQUEST NO. GVRR-3, REVISION 0 i 1 Q, -) Valvest Rapid actuating power-operated valves.
Cate0erY8 A, B Testing Requirement (s) For power operated va ves, the testing frequency shall be increased to once per me ith if the measured stroke time for the valve increases by $i wercent or more from the previous test. +3 Basis for Relieft for rapid actuating power-operated valves, (H application of the above criteria could result in increased testing when th. valves are functionino normally. These valves generally are small air and solenoid operated valves which, because of their s're and actuator types, stroke very quickly. Operating
- h. story on this type of valve indicates that they generally either c.4erate immediately or fail to operate. The intent of the referenced testing requirement is to trend valve n+roke timo as a means of datecting valvo degradation, for rapid actuett% power-operated valves, comparison of stroke times I,
to tha previous miroke timos is not an effective wenns of detecting valve degradation. Because of the reasons eaentioned above, rapid actuating power-operated valve stroke timec will not be compared with the previous stroke times, but will be assigned a maximum limiting str oke time of 2 seconds. Alternate Testing: A maximum limiting stroke time of 2 see will be specified for each rapid actuating power operated valve. If the valva strokes in 2 see or less, it will be considered acceptable and no corrective action will be required. If the valva exceeds 2 seconds, appropriate corrective action will be taken. 4
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. . - - . . . - . . . - - .~.-
4' l PBAPS 2 & 3, IST Pr grara Spic. H-710 R3v. 2 App;ndix C Page 4 of 22 p RELIEF REQUEST NO. GVRR-4, REVISION 1
's -l Valvest VRV-2-13-139A, B C, D VRV-2-234140A, B, C, D VRV-3-13-139A, B, C, D VRV-3-23-140A, B, C, D Category: C Testing Requirement (s): Exercise in the forward and reverse direction.
Basis for Reli ft These check valves, that function as vact.am relief valves, are installed in series parallel and were not provided with air operators to facilitate testing (exercising). The piping configurations in the High Pressure Coolant Injection and Reactor Core Isolation Cooling systems do not allow for individual testing of these valvas. Since a series-parallel arrangement was used, there are multiple combinations of flow paths any one of which would provide vacuum relief. No single valve failure would provont the system from providing vacuum relief. Because single valve failure will not provent the system f rom functioning as designed, and system configuration y does not allow f or individual valve testing, testing as a uni t
~ will verify the system can provide vacuum relief as designed.
Alternate Testingt Vacuum relief valves will be tested quarterly, in the forward j and reverso direction, as a unit. Reverse flow closure will be verified by monitoring 4he HPCI and RCIC turbine exhavst [ vent high temperature alarms located upstream of the valve assemblies. High temperature alarms will indicate steam leakage past these valves. O % U F E s< cD 1 l
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PBAPS 2 & 3, IST Pp:grca Sp;c. H-710, R2v. 2 App;ndix C Page 5 of 22 ('N ret.IEF REQUEST NO. 01-VRR-1, REVISIp*4 1
\ )
) Systems Main Steam Valvelsit RV-2-01-071A,B,C,0 K RV-3-01-071A,B,C,0,K Categoryt B, C Function Depressurizata of the RCS to allow for low pressure coolant injection.
Testing Requipement(s): Quarterly exercise and stroke time. Basis for Relieft If any of these valves fail ta r,-close after testing, the plant would be placed in a LCCA condition. In addition, a recent study (BWR Owner's Group Esaluation of HUREG-07 37. Item II.K.3.16, Reduction of Challeno r and failures of Relief Valves) recommends that the number of ADS openings he reduced as much as possible. Based on this study and the potential for causing a 1.0CA condition, exercise testiau of the ADS valves will be performed during restart af ter refueling. Also, a d;rset method to stroke time the ADS valves is not available since the control room indication only indicates ADS Relief Valve pilot valvo position, and not the actual valve o.se position, An alternate indirect method to stroke time the ADS valVet 'id '.idi'Inble which includes timing the pilot valve and observing plant parnweier changes, Alternate Testing: Exercise during restart after refueling. Stroke time test
;g) during restart af ter refueling b/ timing the interval between
() . pilot valve initiation and observable plant parameter changes. [ l % (/ '
,, _ _ _ . , _ - - - _ _ _ ,_- . _ _ . - , - .m., - , - - - _ - -... _ ,-- PBAPS 2 & 3, IST Pp gram Sp;c. M-710, R3v. 2 App:ndix C Page 6 of 22 RELIEF REQUEST NO. 01-VRR-2, REVISION 0
- (Ush- ' Systems Main Steam Valve ( s )1 -- VRV-2-01-8 096 A, B,C, D, E, F,0, H, J , K, t.
VRV-3-01-9096A,B,C,D,E,r,0,H,J,K,1 Category: C Functiont Main steam safety / relief valve tailpipo vacuum breaker. Testing Requirement (slt Exercise in the forward direction quarterly. Basis for Relieft These vacuum breaker / check valves are located inside the primary containment. During power operation and at cold shutdown, the containment atmosphere is normally inerted with nitrogen gas limiting access to emergencies only. In addition, high radiation levels during power operation prohibit containment entry. Alternate Testingt forward exercising will be verified during all refueling outages and during cold shutdowns when the primary containment u is de-inerted.
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n -- --~n n-- ~- n. -n _ .. u== =-s.- .n--._-- a PBAPS'2 & 3, IST Ppagram Sp;c. M-710, R3v. 2 App;ndix C Page 7 of 22 g~g RELIEF REQUEST No. 03-VRR-1, REVISION 0 System Control Rod Hydraulic Valve (s): CV-2-03-13126AA4HC, CV-3 03-13126AA4HC CV-2-03-13127AA4HC, CV-3-03-13127AA+HC CHK-2-03-13114AA-+HC, CHK-3-03-13114AA4HC Category: B (CV-2(31-03-13126AA+HC, CV-2(3)-03-13127AA4HC) C [CHK-2(3)-03-13114AA4 hcl Function: Control rod drive scram valves Testing Requirement (s)* Exercise, stroke time, and fail-safe test ICV-2(3)-03-13126AA4HC, CV-(3)2-03-13127AA4HC3 Exercise in the forward direction [CHK-2(3)-03-13114AA+ hcl Basis for Relief These valves are located on the hydraulic control units for the control rod drives, whose function is to rapidly insert the control rods on a signal from the reactor protection system. The proper functioning of these valves as a unit is
. most practically verified by performing an actual scram test and measuring control rod insertion times.
Alternate Testing: The control rod scram insertion time testing required - by Technical Specification 4.3.C will be performed in lieu of the Section XI testing.
- a. Af ter each refueling outage, and prior to synchronizing the main turbine generator initially following restart
,G . of the plant, all operable fully withdrawn in sequence T j' rods shall be scram time tested during start-up from the '-? fully withdrawn position with the nuclear system pressure abova 800 psig,
- b. After exceeding 30% power, all previously untested
.operablo' control rods shall be tested, as described above, prior to exceeding 40% power,
- c. Whenever such scram time measurements are made (su.:n as when a scram occurs and the scram insertion time recorders are operable) an evaluation shall be made to provide reasonable assurance that proper control rod drive performance is being maintained.
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aw _ - _ -, - n.. _ . nm : _ - _ _ - - _ l PBAPS 2 & 3, IST Pp: gram ' Sp;c. H-710, R:v. 2 1 App ndix C PaDe 8 of 22 RELIEF REQUEST NO. 06-VRR-1, REVISION 0 ('x,$
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N' i ' System Feedwater l Valve (s): CHK-2-06-028A,B CHK-02-06-096A,B ' i CHK-3-06-028A,B, CHK-03-06-096A,B l Category: A. C Functiont Feedwater system inside/outsido primary containment isolation valves. i Testing Requirement (s) Exercise in the reverse direction. Basis for Relieft The only method to verify reverse ' low closure of these valves is by leak testing. Since these valves are containment isolation valves, they are leak tested during Appendix J, Type C testing at refueling. In order to leak test CHK-02(3)-
.028A,B manual valves located inside the primary containment must-be opened. During power operation and normally at cold shutdown, the primary containment atmosphere is inerted with
.j nitrogen, limiting access to emtgencies only. In addi tion, during cold shutdown, the c o n- nsate system is placed in a-short cycle flow path which b used to maintain proper condensate water qua;ity. Since valves CHK-2( 3)-06-096 A, B must be open to provide a flow path for condensate cleanup, leak testing is not possible. Because leak testing at power is not possible, and is impractical at cold shutdown and could delay plant s tart-up, these valves will be leak tested at refueling.
[h, Alternate Testing Reverse flow closure will be veri fled during Appendix J, Type C
.' testing during refueling, o
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w: . -- _n. - n PBAPS 2 & 3, IST PPCgrCa Sp;c. H-710, R:;v. 2 'l App;ndix C Page 9 of 22 7N RELIEF REQUEST NO. 10-VRR-1, REVISION 1 ( h
%? System Residual Heat Removal (RHR)
Valve (sit- CHK-2-10-019A, B, C, D CHK-3-10-019A, B, C, D Category: C Functions RHR Pump minimum flow recire check outside containment isolation valve. Testing Requirement (slt Exercise in the reverse direction. Easis for Relieft Decause of the system configuration these valves cannot be verified closed using visuni verification, system parameters or by leak testing methods. Valve disassembly will be required to verify reverso direction closure. Disassembly of the valves, if attempted at cold shutdown, could result in a delayed plant start-up. Alternate Testingt Reverse flow closure will be verified at refueling by velve
.; disassembly; partial stroke will be performed af ter valve re-assembly, iq t i-Lf
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-Page 10 of 22 ,
fm RELIEF REQUEST NO. 10-VRR-2, REVISION 1 l
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(N / }r Systemt Residual Heat Removal (RHR) > Valve (s): CHK-2-10-063 CHK-3-10-063 CHK-2-10-064 CHK-3-10-064 CHK-2-10-183A,B CHK-3-10-183A,B CHK-2-10-184A,B CHK-3-10-184A,B ' Category: C Functiont Residual Heat Removal /LPCI Stay-fill supply check valves. Testing Requirement (sli Exercise in the reverse direction. Basis for Relief The above stay-fill check valves are installed in pairs (series arrangements) with no provisions for individual valve testing (ie CHK-10-063 & 064 are in series CHK-10-183 8 CHK-10-184 are in series) . The valves function, in series as a pair, to p
,revent-loss of RHR inventory to the stay-fill system in the event of a stay-fill system failure. Because testing these valves as a pair is preferable to valve disassembly and inspection, relief from testing individual valves is requested.
In addition, Technical Specification 3.5.0 requires that the discharge piping of the LPCI system be filled to prevent water hammer upon system initiation. Testing these valves during-power operation would make the stay-fill system inoperable, - requiring entry into the associated limiting condition for operation. For this reason, testing of the above pairs of valves will be performed at cold shutdowns.
)
('" j Alternate Testing: Valves will be tested as a pair in the reverse direction at cold shutdown. Both valves in the pair will be considered inoperable if testing indicates the valves do not close on . reverse flow. k
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vmu~.waw -- J %- --nku m _ w n....w w - w, , ~~~m n PBAPS 2 & 3 IST Pp: gram Sp;c. M-710, R v. 2 ; App *ndix C : Page 11 of 22 , n., RELIEF REQUEST No. 11-VRR-1, REVISION 0
=t U) 1 Systemt Standby liquid Control Valve (s): CHK-2-11-016 ,
CHK-2-Il-017 , CHK-3-11-016 t CHK-3-11-017 Category A C [CHK-2(3)-ll-016) ! C [CHK-2(31-11-017) ! Function: Standby liquid control injection checks - inside/outside , primary containment, Testing Requirement (s)! Exercise in the forward and reverse direction (CHK-2(3)-ll-016] Exerciso in the forward direction (CHK-2(3)-11-017) Easis for Relieft Verifying forward flow operability requires firing a squib valve and injecting water into the Reactor Coolant System using the standby liquid control pumps. Injection of borated water 4 during operation will result in a ~ reduction in power. Additionally, introduction of relatively colder water into the Reactor Coolant System will cause a thermal cycle (shock) which con result in the promature failure of system components (piping). Since the firing of squib valves requires valve
' disassembly to replace valve internals, firing should be minimized. Therefore, forward flow testing of the check valves will be performed during SLC injection testing as required by Technical Specifications (4,4. A), Reverse flow closure on CHK-2(3)-11-016 can only be accomplished by leak testing which must (Q"/ -. be performed when a squib. valve has been fired (opened) to
. provide a leak test flow path, Because firing squib valves should be minimized as mentioned above, and replacing squib valve internals at cold shutdown could delay plant start-up, reverse flow closure will be verified at refueling.
Alternate Testingt Forward flow operabili ty for CHK-2(3)-Il-016 and CHK-2(3) 017 will be verified at refueling during SLC injection testing. , Reverse flow closu"a for CHK-2(3)-ll-016 will be v erified- a t refueling during Appendix J, Type C testing.
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......=. .- w - -- . _ - - - --- =. a . ~ :-a n -.-~ ~ .-- PBAPS 2 & 3. IST Progenm Spec. H-710, Rev. 2 Appendix C Page 12 of 22 RELIEF REQUEST NO. 13-VRR-1, REVISION 1
=) Systemt Reactor Core Isolation Cooling (RCIC)
Valvets) CHK-2-13-029 CHK-3-13-029 Category C Functiont RCIC pump discharge rocirc chet.k to suppression pool. Testing Requirementisit Exercise in the reverso direction. Basis for Rolieft Decause of the system configuration these valves cannot be verified closed using visual verif 4.ation, system parameters or by leak testing motheds. Valve disassembly will be required to verify r'everse direction closure. Disassen.bly of the valves, if attempted at cold shutdown, could result in a delayed plant start-up. Alternate Testingt Reverse flow closure will be vet ified at refueling by valve disassemblyt partial stroke will be perf ormed af ter valvo re-
.s assembly.
ym _. - -w- - - - m- m.._____--- =- =- PBAPS 2 & 3, IST Pp gram Sp;c. M-710, R;v. 2 App;ndix C Page-13 of 22 ( ~~N RF. LIEF REQUEST NO. 13-VRR-3, REVISION 1 i / VC]' Systems Reactor Core Isolation Cooling (RCIC) Valve (sit A0-3-13-022 Category: C Function RCIC pump discharge check valves to feedwater. Testing Requirement (s): Exercise in the forward direction. Basis for Relieft full stroke exercising using the RCIC pump is not recommended because it would require injection of relatively cold water from the condensate storage tank into the feedwater system. Introduction of relatively et,ld water into the feedwater system will cause o thermal cycle (shock) which could result in the premature failure of system components (piping). Additionally, full stroke exercising is not possible utilizing the air operator currently mounted on the valve because the operator will only move the disc approximately 30% of its full travel. Full stroking therefore, can only be accomplished by valve a disassembly. Valve disassembly if attempted at cold shutdown could result in a delayed plant start-up. Alternate Testing Partial stroking, in the forward direction, will be performed during cold shutdown by utilizing the air operator. Full stroke exercising in the forward direction will be accomplished at refueling by valve disassemblys partial stroke wiil be performed after valve re assembly.
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- -m PEAPS 2 & 3, IST PpIgram Spic. H-710, R;v. 2 App:ndix C Page 14 of 22 p., REl.!EF REQUEST NO. 14-VRR-1, REVISION 1 t M
%M System Core Spray Valva (sit CHK-2-1%-066A. B,C, D CHK-3-14-066A, B, C, D CHK-2-14-21541 CHK-3-14-31541 CHK-2-14-21577A, B CHK-3-14-31577A, B CHK-2-14-29036A, B CHK-3-14-39036A, B CHK-2-14-29051A, B CHK-3-14-39051A, B Category C-Function Core Spray Pump minimum flow check valve primary containment isolation.
Core Spray System stay-fill check valves - primary containment isolation. Testing Requirement (s)* Exercise in the reverse direction. Basis for Relieft- The above referenced valves eli perform a safety function in the reverse direction. Because of system configuration these
.i valves cannot be verified closed using visual verification,
. system parameters or by J enk testing methods. Valve disassembly wili - be required to verify reverse direction closure. Disassembly of those valves, if attempted during cold shutdown, could result in 5 delayed plant start-up.
AlternateTesting Reverse flow closure will be verified at refueling by valve disassembly; partial steoke will be performed af ter valve re-assembly. O ( l-
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m ~ = = =.:== == -;;--;.u;a ;_ -.u.- - -.-._.-. ~.~ - - . - - - - ~ . . PEAPS 2 & 3, IST Progrtm Sp;c. H-710, Rav. 2 Appandix C j Page 15 of 22 RELitF REQUEST NO. 14-VRR-2, REVISION 1
-i O ; Systemt Core Spray Valve (sit A0-3-14-013A, B Category A. C Function Cor Spray injection check valves - RCS pressure isolation and primary containment isolation.
Testing Requirement (s): Exercise in the forward and reverse direction. Basis for Relieft Testable check valves A0-5-14-013A, D are closed during operation and function as both primary containment isolation valves and Reactor Coolant System pressure isolation valves. During operation these valves protect the Core Spray Systems from Reactor Coolant System pressure. The valvas are located inside primary containment which is not accessible during operation since it is inerted with nitrogen and is a high radiation area. Because thes. valves are required to be operable for primary containment isolation per technical
. specificatiors (T.S. 3.7), and are inaccessible during operation, failure during testing (failure in the open position) would require a plant shutdown to repair the valves.
Additionally, full stroke exercising is not possible at cold shutdown utilizing the air operator currently mounted on the valve because the operator will only move the disc approximately 30% of its full travel. Full stroking can only be accomplished by valve disassembly Valve disassembly if attempted at cold shutdown could result in a delayed plant start-up. Alternate Testingt Partial stroking, in the forward and reverse direction, will be performed during cold shutdown by utilizing the air operator. Full stroke exercising in the forward direc tion will be accomplished at refueling by valve disassembly. Reverse flow closure will be verified at refueling by Appendix J and Section XI leak rate testing partial stroke will be performed af ter valve re assembly.
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m_ m . -- m e- =_ -- me ,%,.,,,_.,._ - PBAPS 2 & 3, IST Pp; gram g' Sp;c. H-710, R;V. 2 App ndix C Page 16 of 22 g- RELIEF REQUEST No. 14-VRR-3, REVISION 1 ( j9 Un Systemt Core Spray
- Valve ( s ): CHK-2-14-025A, B, C, D CHK-3-14-023A, B,C,D Category: C Functions . Core Spray stay-fill supply check valves.
Testing Requiremont(sit Exercise in-the roverse direction. Basis for Relief Because of the system configuration these valves cannot ba verified closed using visual verification, system parameters or by lea'K testing methods. Valve disassembly will be required to verify reverse direction closure. Disassembly of the valves, if attempted at cold shutdown, could result in a
~ delayed plant start-up, Alternate Testingt Reverse flow closure will be verified at refueling by valve disassembly; partial stroke will be performed af ter valve re-o assembly.
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Sp!c.-M-710, R3v. 2-AppIndix.C Page 17 of 22
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RELIEF REQUEST No.--23-VRR-1, REVISION 1 j- % I) ; SEstemt- High Pressure Coolant-Injection-(HPCI)
- Valvets): CHK-2-23-062-CHK-3-23-062- .
Category = C Function: HPCI pump disch recirculation to suppression pool' check. Testing Requirement (sli Exercise in the reverse direction.- Basis fon Relieft Because of the~ system configuration these valves canr.ot be verified closed using- visual- verification, system parameters
. or by leak testing methods. -Valve disassembly will be required to verify reverse ' direction closure. - Disassembly ~ of the valves, if attempted at cold shutdown, 'could result-in a *
-delayed glant start-up.,
' Alternate Test ings. Reverse flow closure will be verified at refueling = by valve disassembly; partial stroke will be performed af ter valve. re- ;
.,; assembly. -
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w + - g ., PBAPS 2 & 3, IST Porgram , Sp;c. H-710, R v. 2 i' Appendix C Page 18 of 22 jN RELIEF REQUEST NO. 23-VRR-3, REVISION 1
.( A Nt} - Systems High Pressure Coolant Injection (HPCI)
Valve (s): A0-3-23-018 Categoryt C Functiont HPCI pump discharge check valves to feedwater. Testing Requipements Exercise in the forward direction. Basis Top Relieft Full stroke exercising using the HPCI pump in not recommended because it would require injection of relatively cold water . from the condensate storage tank into the feedwater system. Introduction of relatively cold water into the feedwater system will cause a thermal cycle (shock) which could result in the premature, failure of system components (piping).. Additionally, 4 full stroke exercising is not possible utilizing the air operator currently mounted on the. valve because the operator will only move the disc approximately 30% of its full travel. Full stroking therefore, can only be accomplished by valve
- disassembly. Valve disassembly if a ttempted at cold shutdown could result in a delayed plant start-up, Alternate Testingt Partial stroking, in the forward direction, will be performed during . cold shutdown by utilizing the air operator. Full stroke exercising in the forward direction will be accomplished at refueling . by valve disassembly; partial stroke will be pSrformed af ter valve re-assembly.
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fn PBAPS 2 & 3, IST Pr: gram Sp;c. H-710, R v. 2 g Appendix C Page 19 of 22 RELIEF REQUEST NO. 50-VRR-1, REVISION 2 (f NV'j ' System! Emergency Diesel Generators Valve (sit' A0-0-50-7231A, B,C, D A0-0-50-7232A, B, C, D SV-0-50-7235A, B,C, D , Category B Fi"1ction Emergency diesel generator starting air valves I Testing Requirement (s!! Stroke time measurement. Basis for Relieft These valves are non ASME and were supplied as part of the l diesel generator skid. The valves were not provided with any position indication, therefore stroke timing by local or remote position indication is not possible. Significant degradation or failure of these valves to operate would, however, be indicated by an inct eased starting time on the emergency diesel generator or its failure to start. Because it is not possible to measure individual valve stroke times, emergency diesel generator starting times will be measured in its stead. Alternate Testingt In lieu of the individual valve stroke time testing required by IHV-5413, failure of the emergency diesel generator to start within 10 seconds will be evaluated to determine if the cause can be attributed to the associated starting air valves. (NOTE: start is dnf aned as the diesel accolerating to 200 rpm i in response to a start signal), Alternate isolation of air headers will verify individual performance for valves 7251 and 7232, m J 1 [ \ l
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PBAPS 2 & 3, IST Pr:grca Sp;c. H-710, RIV, 2 App;ndix C Page 20 of 22 r x- RELIEF REQUEST No. 51-VRR-1, REVISION 0
;( Di
%& Systems Instrument Nitrogen Valvels): CHK-2-51-23205A, B, C, 0, K CHK-2-51-082Ai B, C, D CHK-3-51-33205A, B, C, G, K CHK-3-51-082A, B, C, D Catege: f t C Fur.tiont Main steam safety relief, ADS valve accumulator nitrogen supply check valves.
Testing Requirement (sit Exerciso in the reverse direction. ; Basis for Relieft Verification of reverse exercising reqcires isolating tho associated instrument nitrogen header and v4nting the upstream side of the check valvo while pressure in applied to the downstream side of the valve. These valvos are located inssde the primary containment and testing requires, s,otering the containment. During power operation and cold shut down, . the y containment atmosphere is normally inerted with nitrogtn limiting access to emergencies saly. In addi e.i on . high radiation levels during power operations prohibis containment entry.
> ' Alternate Testing Reverse exercising will be vorified curing at!' refueling outages and during cold shutdowns whrn the primary containment is de-inerted.
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PBA58 2 & 3, IST-Pesgr00 Sp;c. M-710, R3v.=2 App;ndix C Page 21 of 22 RELIEF REQUEST NO._51-VRR-2, REVISION 0 g 1 System -
/d = Instrument Nitrogen f
Valveis ): CHK-2-51-257A, B C, 0, K CHK-3-51-257A, B, C, G, K _ Category C Punctiont- Main steam safety relief, ADS valve accumulator nitrogen supply-check valves.
-Testing Requirement (s): Exercise in the forward and reverse direction.
-Basis for Relieft Verifica tion of - reverse exercising requires isolating the associated instrument nitrogen header and venting the upstrea s side through a test connection located ' inside the; primary containment. -To verify forward exercising requires lowering the pressure in - the associated ADS accumulator with the-nitrogen supply isolated, then opening the nitrogen supply and observing that ADS accumulator pressure . increases. Since installed pressure - indication is not provided for the ADS - ,
d accumulators a test gaupo-must be - installed- on a' t e.st ; connection' located inside the . primary - containment. - During > power operation and cold shutdown, the containment atmosphere is- normally inerted with nitrogen . limiting access to < emergencies only. In addition. high radiation levels during =
- + - - -
- l power operations prohibit containment' entry; -v
' Alternate Testingt Forward and reverso exercising will be _verifiod -- during ' all':
- refueling outages and during cold shutdowns when the primary c, i; ' containment is de-inerted.
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. ,m - - RELIEF REQUEST NO. 51-VRR-3, REVISION 0 ;
s h t e/-i - Systems- Instrumed Nitrogen valvets): CHK-2-51-23261 CHK-3-51-33261 j Category: A, C l i Funct$ mt Primary Containmert Isolation. ; i' Testiny Requirement (s): Exercise in the reverse direction, Basis for Relieft The only method to veri fy reverse flow closure of these valves , is by leak testing. Since the:,,e sal v es have a primary function of conteinment iselation, they are leak tested during Appendix J, Type C testing at refueling. In order to leak test ; the valvss, a manual valve located inside the torus must be closed. During power operation and cold shutdown, thu . containment atmosphere is normally inerted with nitrogen, limiting access to emergencies only. Becauss testing cannot l>e accomplished at po m , and leak testing at cold shutdown u could delay plant start =up, these valves will be leak testod + during refueling. . Alternete Testingt Reverse flow closure will be verifled during Appendix J. Type C f testing during refueling,
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b-14
._ R ,
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-SPEC. M-710:
REVI$10N 2
, ' IST 1 ABLE -- PUMPS 'PAGE NO: 1 PEACH BUTTCM ATOMIC POWER STATION UNIT 2 & COMMGN DATE: 06/03/91
.1 PUMP , TEST . RELIEF j
. PUMP NAME OR DESCRIPT70N ID. NO. P&ID COORD. . PARAMETERS ' RCouEST REPARKS 4
. . k CORE SPRA) (CS) 2AP037 M-362(SHT.1) D-6 Pi, D/P, G, V, CPRR-1, C#RR-2 +
L/P~ CORE SPRAY (CS) 2BP037. M-362(SMT 1) D-3 Pi, D/P, Q, V, . CPRR-1, GPRR-2 L/P CORE SPRAY (CS) 2CP037 N-362(SHT 13 D-4 Pi, D/P, 0, V, CPRR-1, CPRR-2 -;
' L/P - i ie
- I CORE SPRAY (CS) -2DP037 M-362(SMT 1) D-2 'Pi D/P, o, V,. GPRR-1,'GPRR-2 L/P f .
DIESEL FUEL O!L TRANSFER CAP 060 M-377($HT 41 G-6 Pi, D/P, Q, V,- 'GPER-1, CFRR-2, L/P CPRR-3 .. DIESELFUELCILTRANSfEN '0BP060 ' 'M-377(SMT 4) E-6 Pi, DIP, 0, V, 'GPRR-1, GPRR-2, t L/# CPRR-3 DIESEL FUEL CIL TRANSFER OCP060 ~ M-377(SHT 4) D-6 Pi, D/P, C, V, cr1R-1, GPRR-2, y L/P GPRR-3 Dif SEL FUEL O!L TRANSFER CDPO60 M-377(SHT 4) 8-6 Pi, D/P, Q, V, .GPRR-1, GPRR-2, L/P CPRR-3 g EMER0EbCY COOLING WATER (ECW) 00P186 M-330(SHT 1) .G-4 Pi*, D/P, V, GPRR-1, CPER-2, ' *CALCJLATED 14LET PRESS. (TEXT F j 0, L/P ' GPRR !
'5.1.1).
EWERGENCY SERVICE WATER-(ESW) CAP 057 H-315(SMT 1) 7-7 Pi*, D/P, V, GPRR-1, CPER-7,
- CALCULATED INLET PRESS. (TEXT l C, L/P CPRR-3 5.1.1). f t
i EMERCEECY SERVICE EATER (ESW) CBP057 M-315(SHT 4) A-5 Pi*, D/P, V, GPRR-1, GPRR-2, *CALQaLATED INLET PRESS. (TEXT o, L/P GPRR-3 3.1.1). i I . l 1
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^Q tp _f SPEC,$,,710 REVIS!DN 2' IST TABLE - PUMPS PAGE No: 2 FEACH BOTTOM ATOMIC POWER STATION - 11 NIT 2 F. COMMON DATE: 06/03/91 PUMP - TEST' PELIEF, PLMP KAME OR DESCRIPTION ID. NO. - P&ID ' - COORD. FARAMETERS REQUEST- REMARKS EMERGENCY SERVICE WATER BOOSTER CAP 163 . M-330(SMT 1) E-6 Pi,'D/P, V, CFRR-1, GPRR-2, C, L/P . GPRR-3 EMERGENCY SERVICE WATER BOOSTER OBP163 M-330(SHT 1) 0-6 Pi O/F, V, GPRR-1, GPRR-2, C, GPRR-3 ,
-4 HIGH PRESSURE COOLANT INJECTION (hPCI) 20P033/038 M-366(SMT 1) f-6, 7 d, P.
'P, 0, DPRR-1, GPRR-2
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. 4 HIGH PRESSURE SERVICE VATER (HPSW) - 2APO42 M-315(SHT 1)' A-7 Pl*, D/P, Q,- GDRR-1, GPRR-2
- CALCULATED INLET PRESS. (TEXT. i Y, L/P 5.1.1).
HIGH PRESSURE SERVICE WATER (HPSW) 2EPO42 M-315(SMT 1) A-5 Pi*, D/P, 0, GPRR-1, GPPR-2 *CALCutATED INLET PRESS. (IEXT V. L/P '5.1.1). HIGM PRESSURE SE9VICE WATER (HPSW) 2CPO42 M-31S{SHT 1) A-6 Pi*, D/P, 0, GPRR-1, GPRR-2
- CALCULATED INLET PRESS. (TEXT
- V, L/P 5.1.1). {
H!GH PRESSURE SERVICE WATER (HPSW) 2DPG42 M-315(SNT 1) A-4 #i*, D/F, C, GPRR-1, GPRR-2
- CALCULATED INLET PRESS. (TEXT J V. * /P 5.1.1). Io R
REACTOR CORE ISOLATIOti COOLING (RCIC) 20P036 M-360(SMT 1) E-7 N, Pi, D/P, Q, GPRR-1, GPRR-2 l; V, L/P { RESIDUAL HEAT REMOVAL (RMR) 2APC35 M-361(SMT *) A-5 Pi, D/P, Q, V, GPRR-1, GPRR-2 L/P 4 e 2BP035 C-5 Pi, D/P,' Q, V, CPRR-1, GPRR-2 fg RESIDUAL HEAT REMOVAL (RPR) M-361(SHT.2) L/P k-RESIDUAL HEAT REMOVAL (RFR) 2CP035 . M-361(SHT 1) 8-5 Pi, D/P, C, V, GPRR-1, GPRR-2 I k-L/P t r; y, k N I s E 6
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IST 1ABLE - PtNPS "PAGE h0: ' .3 PEACH BOTTOM' ATOMIC POWER STAflON - Uni!T 2 & COMMON DATEt 06/03/91 h PtMP TEST- .? LIEF PUMP HAME OR DESCRIPTION 'ID. NO. P&ID COORD ~ PARAMETERS REQUc;T ' REMARES RESIDUAL NEAT REMOVAL (RNR) 2DF035 M-361(Si!T 1) "A-5 Pi, D/P, 0, Y, GPRR-1, GPRR-2 L/P W STAW ST LIQUID CONTROL (SLC) 2APO40 M *,58(SMT 1) E-5 Pi*, D/P, Q, 11-PRR-1, CPRRat, ' CALCULATED INLET PRESS. (TEXT V, L/P CPRR-2 5.1.1) , STANDSY LIOUID CONTROL (SLC) 2sPC40 H-358(SNT 1) D-S Pl*, D/P, 0, '1-11-PRR 1, GPRR-1,
- CALCULATED INLET PRESS. (TEXT Y, L/P GFRR-2 5.1.1) e t
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COORD. PAR.O'E T E RS REQUEST REMARr5 { ID. NO. P1lD PUMP NAME OR CESCRIPTION l 3AP037 M-352(SMT 2) D-6 Pi, D/P, Q, V, GPRR 1, GPRR-2 { CORE SFRAY (CS) L/P 1 D-3 Pi, D/P, Q, V, GDRR-1, GPER-2 ,
,3BP037 P-362(SMT 2)
( CORE SPRAT (CS) L/P f I 0-4 Pi, D/P, Q, Y, iGrRR-1, CPRR-2 CORE SPRAf (CS) 3CP037 M-362(SNT 2) L/P fl CP9R-1, GPRR-2 ;l 3DP037 M-362(Spi 2) D-2 Pi, D/P, c, V, l CORE SPRAY (CS) L/P il I M-366(SitT 4) F-7 W, Pi, D/P, Q, GPRa-1, GPRR-2 [ HIGH PRESSURE COOLANT INJECTION (HPC!) 30P033/03S V, L/P { I 5-7 Pi', D/P, Q, CPRR-1, GPRR-2 *CALCULATEC IWLET PRESS. (TENT M GM PRESSURE SERVICE WATER (NPSW) 3APO42 M-315{$MT 3) V, i/P 5.1.1). h[ t a-5 Pia, D/P, c, GPsa-1, CPER-2
- CALCULATED IWLET PRESS. (TEXT [
M-315tSWT 3) HIGH PRESSURE SERVICE WATER <hPSW) 3EPO42 V, L/P 5.1.1). [ [ M-315(SMT 3) B-6 Pi*, D/P, C, GPER-1, GPRR-2
- CALCULATED IKLET PRESS. (TEXT j HIG4 PRESSURE SERVICE WATER (NPSV) 3CP042 V, L/P 5.1.11. 3 3DPO42 M-315(SPT 3) 8-4 Pi*, D/P, G, GFER-1, GPRR-2
- CALCULATED INLET PEESS. (TEXT f H10H PRESSURE SERVICE WATER (HPSW) 5.1.1).
V, L/P t E-7 N, Pi, D/P, Q, GPRR-T, GPRR-2 3cPC36 M-360(SMT 2) REACTOR COPE ISOLATION COOLIAG (RCIC)
/, L/P i
e A-5 Pi, D/P. c, V, GPRR-1, C;sR-2 RESIDUAL HEAT RE*80 VAL (RPR) 3AP035 M-36"(SuT 3) L/P A s b i i
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. REVISION 2 4
"1ST TASLE - PUMPS- PAGE NO: L S'- A FEACH BOTTOM ATOMIC. POWER STATION UNIT 3 DATE: 06/03/91 ,
PUMP . TES) RELIEF PUP *.P NAME OR DESCRIPTION ID. NO. P&lD COORD.' PARAMcTERS REQUEST REMARKS' )
.1 RESIDUAL HEAT REMOVAL (RNa) 35PC35 H-361(SMT 4) C-5 . Pi,' D/P, r,, y, . cpRR.1, GPRR-2 ,
L/P ' ]
' RESIDUAL REAT REMOVAL ('RHR) 3 CPG 35 M-361(SMT 3) B-5 .Pi, D/P, 0, V, GPRR-1, GPRR-2 t/P I RESIDUAL 'fiEAT REMOVAL (RHR) '30P035 ' M-361(sHT 4) A-5 PI, D/P, 0, V, 'GPRR-1, CPRR-2 L/P I'
STANDBY LIQUID CONTROL (SLC) 3APO40 M-355(SMT 2) E-5 Pi*, D/P, C, 11-PRR-1, GPRW-1,
- CALCULATED INLET PRESS. (TEXT'
'] e V, L/P GPRR-2 5.1.1).
STAND 8Y L10VID CONTROL (SLC) 3BPO40 M-35S($NT 2) D-5 Pl*,'D/P, 0, 11-FRR-1, GFRR-1,
- CALCULATED INLET PRESS. (TEXT. f V, L/P GPRR-2 5.1.1) i i
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o 1 SPEC. M-710 , EEvisloeg 2 - PAQE NO: 1 IST TABLE - VAivES CATE: 06/03/91 PEACH BOf f 0M ATOMIC PCf TR STAT:GN - UNIT 2 & COMMON SYSTEM: 01 MAIN STEA9 POSITION VALVE ACT. APP. J TEST FREQUENCY WR/VCS VALVE VALVE ACT/ RCMARILS y WRM SAF FAL TYPE C (DIRECTION) NUMSER NUMBER P&l0 COORD CAT. PAS SIZE TYPE TYPE g 5 C ET-0, FS-Q(C), CVRR-1 PENT. M-7A G-4 A A 26 GL NO O C Y AO-2-01-080A M-351 (SMT 1) ST-G(C), LJ-1, P2-1 I ET-c, FS-C(C), CVRR-1 PENT. N-73 C-3 A A 26 Gt NO O C C Y AO-2-01-OSCS M-351 (SMT 1) ST-G(C), LJ-T, P!-T ,, 3l ET-C, FS-Q(s., GYRR-1 PENT. N-TC M-351 (SNT 2) G-4 A A 26 CL ko O C C Y I AC-2-01-CSCC ST-C(C), LJ-T, P -T ?! I 26 MO O C C Y ET-c, FS-Q(C), GVRR-1 PENT. N-73 {; AO-2 01-C80D H-351 (SMT 2) C-3 A A ct ST-C(C), L)-7, PI-T j, L PENT, N-7A 0, 26 GL A0 0 C C Y ET-Q, FS-C(C), GVRR-1 M-351 (SNT 1) C-2 A A A0-2-01-086A ST-G(C), LJ-T, PI-T l] PENT. N-73 ), A 26 GL A0 0 C C Y ET-0, FS-0(C), GVKR-1 A0-2-01-C86B M-351 (SHT 1) C-2 A ST-C(C), LJ-T, P2-7 {' i; A0 0 C C Y ET-C, FS-C(C), CVRR-1 PEMT. k-7C f, A0-2-01-OS6C M-351 (SHT 2) G-2 A A 26 CL ST-Q(C), LJ-T, PI-T ; x 0 C C Y ET-C, FS-C(C), CVER-1 PENT. 3-7D . [: M-351 (SHT 2) C-2 A A 26 CL A0 i AO-2-01-0360 ST-C(C), LJ-T, P2-1 f. 5 ET-0, FS-C(C), GVRR-1 PENT. W-57 C-7 .75 GL A0 OC C C Y A0-2-01-316 M-351 (54T 2) A A ST-Q(C), LJ-T, PI-T f' t A . 75 CL A0 OC C C Y ET-0, TS-c(C), CVRR-1 PENT. E-57 l AC-2-01 217 M-351 (SHT 2) C-8 A ST-G(C), LJ-1, PI-T I
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FAGE 30: 3 IST TABLE - VALVES - PEACH BOTTCM ATCPIC POCR STAT 104 - L; WIT 2 & COMr*C4 CATE: C6/03[71 i STsTEM: C1 MA14 STEAM { FOS! TION AF'. J TEST FREQUENCY VRR/YCs k VALVE ACT/ VALW ACT. VALVE WUMBER F&ID COORD CAT. FAs S!IE TYFE TTFE MEM SAF FAi TTFE C (DIRECTION) wuMBER #E=AEK5 l, 0 s ET-Re(F) 01-WR-2 ) M-351 (SMT 1) E-5 C A 6 VR 54 C - VPV-2-01-SO96A 1 C 0 - u ET-R3(F) CT-VER-2 VRV-2-01-80966 P-351 (sHT 1) E-5 C A 6 VR SA C1-W R-2 I 6 SA C 0 - 4 ET-R&(F) VRV-2-01-8096C M-351 (sMT 1) B-6 C A VR i E-5 C A 6 W sA C 0 - m E;-aJCF) C1-Yet-2 f VRV-2-01-50?60 M-351 (sMT 1) d C 0 - 4 ET-R&(F) 01-VER-2 VRV-2-01-E076E M-351 (SMT 1) B-5 C A 6 VR SA p l 9 4 0 - # ET-R9(F) 01-VRR-2 VRV-2-Ci-5076r M-351 (sgT 1) 34 C A 6 VR SA C k 0 - 5 ET-R;(F) 01-VRR-2
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- xfC-2-02-064D M-353 (SMT'2). E-7 4
0 C - t ET-E(F), PI-T, LP-T svat-2 M-353 (SMT 1) A-3 A, C 'A 1 NC - SA , k XFC 2-02-3C5A - cv .-2 f 0: C . ET-,(r), ri-1, tP-T
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IST TABLE - VALVES FACE WO: 1P 3l PEACM BOTTOM ATOMIC POWER STA!!CE - UNIT 2 & CCPMON CATE: 06/C3/91 Il
. V SYSTEM: 03 COWTROL' ROD HYDRAULIC POSITION {j
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- j. CMK 2-03-13114BJ M-357 (SMT 1) F-8 C A .75 CK SA C o -
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,c:UMBE2 P&lD CDORD CAT. PAS SIZE TYPE TYPE WRM SAF FAL TYPE C (DIRECTION) WUMBER REMARKS j _ _ _
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SPEC. M-710 REVISION 2 IST TABLE - VALVES FACE NO: 14 PEACM BOTT(M AT0=1C POWER STAT 104 - L1tti 2 & CDPMOR CATE: 06/03/M I ' -SYSTEn: 03 CONTROL RCO NYDRAbLIC l POSITION VALVE , VALVE ACT/ . VALE ACT. AFP. J TEST FREQUENCY *tR/VCS -f [ j' - 8: UMBER P&ID COORD CAT. PAS SIZE TYPE TYPE #RM SAF TAL TYPE C (DIRECTIC4F) NUMBER REPARKS E L F-8 .75 0 ET-R(F) 03-VRR-1 6t' CW-2-03-131?4EI M-357 (SMT 1) C A CK SA C - N
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PACE No: 16 IST TABLE - VALVES - PEACM SOTTOM ATOMIC POJER STATION - UNIT 2 & CCrepi :CATE: 06/03/91 l { SYSTEM: 03 CONTROL RCO NYDRALF.!C .~; POSIT 104 VALVE.ACT. APP. J TEST FREcuENCT V8RTES { VALVE VALVE ACTI NUM6ER REMARES S&to COCRD CAT. PAS $1ZE TYPE TTPE- htM SAF FAL TTFE C (DIRECTION) NUMBER C 0 - # ET-R(F)- 03-WR-1
'CNE-2-03-13114F0 M-357 (SMT 1) F-8 C A- .75 CK -SA C- 0 -N ET-R(F) 03-VER-1 CH1-2-03-13114FP N357 (5MT 1) F-8 C A .75 CE SA
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.75 CC 5A C 0 - N ET-R(F) 03-Vat-1 CHC-2-03-13114FV M-357 (SMT 1) F-S C A 6
3 C 0 - N ET-R(F) 03-VRR-:- thK-2-03-13114FW M 337 (SHT 1) F-8 C A .75 CK SA A- .75 CC $A C O - N ET-a(F) 03-vt4-1 CHC-2-03-13114Fx M-357 (SMT 1) F-6 C
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C 0 - N ET-R(F) C3-VRt-1 CNr-2-03-131140A M-357 (sNT 1) F-8 C A .75 CK SA sa C 0 - N ET-R(F) 03-VRR-7 CNK-2-03-13114GB M-35'/ (sMT 1) .F-8 -C. A .75 CC 0 - N ET-R(F) C3-VRR-1
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-DATE:
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- ll CM 2 03-13114G1 ' M-357 ($HT 1) F-8 C A .75 CK CA C 0 -- N ET-R(F) 03-vRR-1 CM-2-03-13114GJ M-357 (SMT 1) F-$ 'C A .75 CK ' SA C 0 - N ET-R(F) 03-VRR-1 CHK-2-03-13114GK M-357 (sHT 1) F-8 C A .75 CK SA C 0 - N ET-R(F) 03-VRR-1
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M 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 D 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 C D E 3 3 3 3 3 3 3 3 3 3 3 3 3- 3 3 3 F - - - F M M M M M M M M M M M M M M M + L O R T v 5 W F X F Y F Z F A G 8 0 C G 0 0 E G F G 3 0 4 0 I C J G C G N 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 O 1 1 1 1 1 1 1 1 1 1 1 - 1 1 1 1 C 1 1 1 1 1 1 1 1 1 1 : 1 1 1 1 1 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 - - - - - - - - - - - - - - - - 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 C 0 0 0 C 0 0 0 0 C 0 0 0 C 0 C M: R - - - - - - - - - - - - - - - - E T E E V B 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 S L M K K K T A U M M M M M M H M v M M M M h M M S V h C C C C C C C C c C C C C C " C I livll ' llf ,;l[!(l,llfiil ll l fl -
4 f i SPEC.'M-7TO REv15104 2 l 1 IST TABLE - VALVES PAGE NO: 29 ;q I PEACM BOTTOM ATCMIC POWER STAi!CM - UNIT 2 & COMMON CATE:. 06/C3/91 SYSTDt: 03 CONTROL RCD MTDRAULIC ,; POStT104 !i k V*.LVE YALVE ACT/' VALVE ACT. APP. J TEST FREQUENCY VER/vCS NtMBER F&tD , COORD CAT.' PAS SIZE TYPE TYPE NRM SAF FAL TYFE C (DIRECTION) WUMBER RENARK3 ., CHK-2-03-13115GL . M-357 (SNT 1) F-4 C A .5 CK SA CC C - N ET-C(R) 03-vCS-1. 4 CHK-2-03-131150M M-357 (SMT 1) 'F-4 C A .5 CK SA CC C - N ET-C(R) 03-vrs.1
.[:
C M-2-03-13115GN M-357 (SMT 1) F-4 C A- .5 CK SA UC C - N ET-C(R) 03-vCS-1 ;. 4 l
; CHK-2-03-13115GO M-357 (SMT.1) F-4' C A .5 CK SA CC C -- N ET-C(R) 03-VCs-1 i. . s 1
2 CMK-2-03-13115GP M-357 ( *T 1) F-4 C A .5 CK SA OC C - N ET-C(R) 03-VCS-1 gj m. 2: CHK-2-03-13115Go M-357 (SnT 1) F-4 C A .5 CK SA OC C - N ET-C(R) 03-vCS-1 j;
. p
. CHK-2-03-13115CR M-357 (SNT 1) F-4 C A .5 CK SA OC C - N f * -U R ) C3-VCS-1 CMC-2-03-15115GS M-357 GMT 1) F-4 C. A .5 CK SA ' OC C - N El-C(R) 03-VCS-1 h r
i' ,'atK-2-03-13115GT M-357 (Sni 1) F-4 C A .5 CK SA OC C - M ET-C(R) 03-VCS-1 $; ! 1l CW-2-03-13115GU M-357 (SMT 1) F-4 C A .$ CK SA OC - C - N ET-C(R) 03-VCS-1 I! 1 L CHK-2-03-13115GV M-357 (SMT 1) F-4 C A .5 CK SA CC C - N ET-C(R) 03-vCS-1 L!
$)
CMK-2-03-13115Gnt M-357 (5571) F-4 C A .5 CK SA OC C - N ET-C(R) 03-vCS-1 g; I 5 ! CHK-2-03-13115CX M-357 (SMT 1) F-4 C A .5 OK SA OC C - N ET-CCR) 03-vCS-1 F k k CHK-2-03-13115GY M-357 (S.HT 1) F-4 C A .5 CK SA OC C - N ET-C(R) C3-VCS-1 CM-2-03-13115GZ M-357 (SHT 1) F-4 A .5 CK OC C - N ET-CCR) C3-vCS-1 o C SA 9i CI CK-2-03-13115HA M-357 (SMT 1) F-4 C A .5 CK SA DC C - N ET-C(R) C3-VCS-1 h
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h g L i y 1, SPEC. M-710 j REVISION 2 ( i PAGE NO: 30 g IST TABLE - VALVES CATE: 06/03/**. ) PEACM BOTTOM ATCMIC POWER STf. TION - UNIT 2 , C&a*0N i s l STSTEM: 03 CONTROL RCI) HYDRAULIC ; PCSIT:ON 4
- AP#. J TEST FREQUENCY VER/VCS VALVE ACT/ ACT.
VALVE NUMBER REMARES l CAT. PAS SIZE VYt' TTPE hRM SAF FAL TIPE C (D!RECTION) hc 3ER F&lD COORD _. ~. - OC C N ET-C(R) 03-VCS-1 l F-4 C A .i SA CHK-2-03-13115Ha M-357 (SHT 1) $ ET-C(R) 03-VCS-1 { F-4 C A .5 CK SA OC C - N
, 1 CHK-2-03-13115HC M-327 (SHT 1)
( A .5 CK S a. C - N ET-Q(R) II CH0 2-03-13138u M-357 (SHT 1) G-6 C
'i 3:
A .5 CK SA 0 C - N ET-C(R) !i CHK-2-03-13133A5 M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-C(R) CHK-2-03-13138AC M-357 (SHT 1) G-6 C l A .5 CK SA 0 C - N ET-0(R) CHK-2-03-13138A0 M-357 (SHT 1) G-6 C I A .5 CK TA 0 C - N ET-C(R) CHK-2-03-13138AE M-357 (SHT 1) G-6 C f-j f A .5 CK SA 0 C - N ET-G(R) l ChK-2-03-13138AF M-357 (SHT 1) G-6
- g..
A .5 CK SA O C - N ET-Q(R) ! CHK-2-03-1313 SAG M-357 (SHT 1) G-6 C 0 ET-Q(R) C - N CHO 2-03-13138AH M-357 (SHT 1) G-6 C A .5 CK SA t A .5 CK SA O C - N ET-QCR) CHK-2-03-13138AI M-357 (SHT 1) G6 C A .5 CK SA O C - N ET-Q(R) CHK-2-03-13135AJ M-357 (SHT 1) G-6 C i A .5 CK SA O C - N ET-C(R) e CNK-2-03-13138AK M-357 (SHT 1) G-6 C l i i IT-0(R) g G-6 C A .5 CK SA o C - N CHK-2-03-13138AL M-357 (SHT 1) i N ET-C(R) [ G-6 C A .5 CK SA o C - CHK-2-03-1313 SAM M-357 (SMT 1) $" g A .5 CK <A o C - N El-C(R) i G-6 Chez-03-13138AN M-357 (SHT 1) C t i i I s I {
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l e O 9 t h 8 I SPEC. M-710 FEVISION 2 i PAGE NO: 31 f
,4T TABLE - VALVES DATE: 06/03/91 FE ACH BOT 10M ATOMIC POWER STATION - tNIT 2 & CCN 3, SYSTEM: 03 CON 7kOL ROD NYDRAULIC POSITI(* 1:
VALVE ACT. APP. J TEST FREQUENCY "RR/VCS VALVE VALVE ACT/ REMARKS NLMBER P&ID COORD CAT. PAS SIZE TYPE TYPE NRM SAF FAL TYPE C (DIRECTION) NUMBER t(. A .5 CK SA 0 C -N ET-CIR) CHK-2-03-13138A0 M-357 (SHT 1) G-6 C F A .5 CK SA 0 C - N ET-0(R) b CHK-2-03-13138AP M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-0(R) CHK-2-03-13138Ac M 357 (SHT 1) G-6 : CHK-2-03-13138AR M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-c(R) j e A .5 CK SA O C - N ET-0(R) CNK-2-03-13138AS M-357 (SHT 1) G-6 C E A .5 CK SA 0 C - If ET-C(R? CHK-2-03-1313 SAT M-357 (SMT 1) G-6 C I I 0 N ET-Q(R) ; CHK-2-03-13138AU M-357 (SMT 1) G-6 C A .5 CK SA C - A .5 CK SA 0 C - N ET-Q(R) h CHK-2-03-1313aAV M-357 (SHT 1) G-6 C ET-CCR) h' G-6 C A .5 CK SA 0 C - N ChX-2-03-1313EAW M-357 (SHT 1) 3 0 C N ET-Q(R) { CHK-2-03-1313 sax M-357 (SHT 1) G-6 C A .5 CK SA t. 0 f. N ET-Q(R) ; CHK-2-03-1313SAY M-357 (SMT 1) G-6 C A .5 CK SA k y G-6 C A .5 .CK SA 0 r - N ET-Q(R) CHK-2-03-13138AZ M-357 (SHT 1) & i A CK SA 0 C - N ET-Q(R) ? CHK-2-03-13138BA M-357 (SHT 1) G-6 C .! A .5 CK SA 0 C - N ET-C(R) CHK-2-03-13138BB M-357 (SHT 1) G-6 C , ( f
.5 CK SA 0 C - N ET-C(R)
CHK-2-03-13138aC M-357 (SHT 1) G-6 C A A .5 CK $A 0 C - N ET-c(R) CHK-2-03-1313RBD M-357 (SHT 1) G-6 C I i e 5 t i e i f?
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3
' SPEC. M-710 ,
REVISION 2 3 IST TABLE - VALVES PAGE #0: 32 PEACH BOTTOM ATOMIC POWET. STATION - UNIT 2 & COMMON DATE: 06/C3/91 SYSTEII: 03 CONTROL RCD HTDRAULIC' POSITION , j VALVE VALVE ACT/ VALVE ACT. APP. J TEST FREQUENCY VRR/VCS NUMBER P&lD COORD CAT. PAS . SIZE TTPE TYPE NRM SAF FAL TYPE C (DIRECTION) NUMBER REMARKS CHK-2-03-13138SE M-357 (SHT 1) - G-6 C A .5 CK SA 0 C. - N ET-C(R)
~
.CHK-2-03-131388F M-357 (SMT 1) G-6 'C A .5 . CK SA 0 C -
'N ET-Q(R)' .
-CHK-2-03-131388G M-357 (SHT 1') G-6 C' A .5 CK SA 0 C -
N ET-Q(R) CHK-2-03-131388H M-357.(SHT 1). G-6 'C A. .5 CK SA 0 C - N ET-C(R)' l CHK-2-03-1313 FBI M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-C(R) CHK-2-03-13138sJ M-357 (SMT 1) G-6 C A .5 CK SA 0 C - N ET-Ott)
' CHI-2-03-131383K M-357 (SHT 1) G-6 -C A .5 ' CK SA 0 C -
N ET-C(R) a CHK-2-03-131388L M-357 (SMT 1) G-6 C A .5 ' CK . SA 0 C - N ET-Q(R) CHK-2-03-13138BM M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-0(R) i i CHK-2-03-13138BN M-357 (SHT 1) G-6 'C A .5 CK SA 0 C - N ET-C(R) CHK-2-03-1313880 M-357 (SHT 1) G-6 C A .5 CK SA C C - N ET-Q(R) l CHK-2-03-13138SP M-357 (SHT 1) G-6 C. A .5 CK SA 0 C - N ET-Q(R) i 0 l CHK-2-03-131388Q M-357 (SHT 1) G-6 C A .5 CK SA C. - 4 ET-Q(R) l . CHK-2-03-13138ER M-357 (SHT 1) G-6 C A .5 CK - SA 0 C - N ET-C(R) ( CHK-2-03-13138SS M-357 (SMT 1) G-6 C A .5 CK - SA 0 C - N ET-C(R) CHK-2-03-131388T M-357 (SHT 1) G-6 C A .5 CK SA 0 C -- N ET-Q(R) i e
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g 6 e > ' d, wl o . > SPEC. M-710
' REVISION 2 IST TABLE e VALVES PACE No:- 33 . ,1
.FEACH BOTTOM ATOMIC POWER STATION - UNIT 2 & COMMON DATE: 06/03/911-i
' SYSTEM: 03 CONTROL RCD HYDRAULIC POSITION
'1 VALVE -VALVC ACT/ VALVE ACT. APP. J. TEST FREQUENCY VRRA*CS EUMSER P&!D COORD . CAT. PAS SIZE TYPE TYPE NRM SAF FAL TYPE C (DIRECTION) WUP'BER REMARKS CHK-2-03-131388u M-357 (SHT.1; G-6 C A .5 CK SA O C -
N ET-Q(R) .. CHK-2-03-131388v M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-Q(R) 1 1 CHK-2-03-131383W M-357 (SHT 1) G-6 C A .5 CK. SA O C - N ET-Q(R) ..j W CHK-2-03-13138BX M-357 (SHT 1) G-6 :C. A .5 CK 'SA 0 C N ET-Q(R) 'h i < i 'CHK-2-03-131388Y M-357 (3HT 1) G-6 C A .5 CK' SA ' O C - N ET-QCR)
.I CHK-2-03-1313832 M-357 (SNT 1) G-6 C A' .5 CK- SA O C -
N ET-QO ) CHK-2-03-13138CA M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-Q(R) CHK-2-03-13138Cs M-357 (SHT.11 G-6 C A .5 CK SA O C - N ET-Q(R) ChK-2-03-13138CC M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) 1 W (i 0
- CHK-2-03-13138CD M-357 (SHT 1) G-6 C A .5 CK ' SA C -
N ET-Q(R) CHK-2-03-13138CE M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-QtR) CHK-2-03-1313BCF M-357 (SHT 1) G-6 C 'A .5 C". SA - 0 C - N ET-Q(R) g k s CHK-2-03-1313BCG M-357 (SMT 1) G-6 C A '.5 CK ~SA 0 C - N ET-Q(R) .. $ h
,A .5 O ET-Q(R) N CHK-2-03-13133CH M-357 (SHT 1) - G-6 C CK ' SA ' C -
N
.N CHK-2-03-1313 SCI M-357 (SHT 1) G-6 C A .5 CK SA 0 C -
N ET-Q(R) CNK-2-03-13138CJ H-357 (SHT 1) G-6 C 'A .5 'CK' SA 0 C - N ET-Q(R) k - d b 4
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SPEC. M-710-lfg
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- REVISION 2 '
. l, PAGE NO:. - 34 L I,'
IST T MLE - VALVES CATE: 06/03/7* PEACH BOTTOM ATOMIC POWER STATION - UNIT 2 & CCMMON
~
S* STEM: 03 CONTROL RCD HYDRAULIC
- PCSITION VALVE ACT. APP. J TEST TREQUENCY VER/VCS V3.LVE VALVE ~ACT/ '
WUMBER REMARKS CAT. PAS SIZE TYPE TYPE WRM SAF' FAL -TYPE C (DIRECTION) WUMSER .PE!D COCRD A .5 'CK SA o C. -
.N ET-o(R) {
'CHK-2-03-13138CK M-357 (SMT 1) G-6 C' ki A .5 CK ' SA 0 C -
# ET-C(R)
CHK-2-03-13138CL M-357 (SWT 1)- G-6 C H G-6 C A .5 . CC , SA 'O C - N ET-C(R) CHK-2-03-13138CM M-357 (SHT- 1) G-6 C A .5 ' CK SA 0 C - N ET-C(R)
'CHK-2-03-13138CN~M-357 (SMT 1) (I G-6 C A .5 CK SA 0 C .- N ET-C(R)
CHK-2-03-13138CO M-357 (SHT 1) ' h G-6 C A .5 CK SA 0' C - N ET-Q(R) CHK-2-03-13138CP M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) CHK-2-03-1313800 M-357 (SHT 1) G-6 C A- .5 CK SA o C - M ET-c(R) CHK-2-03-13138CR M-357.(SHT 1) G-6. C A .5 CK SA 0 C - N ET-C(R) ; CHK-2-03-1313SCS M-357 (SHT 1)* 0 N ET-C(R) ( C A CK SA C -- CHK-2-03-13138CT M-357 (SHT 1)- G-6 G-6 C A .5 .CK SA O C - N ET-Q(R) CHK-2-03-13138CU M-357 (SMT 1) g.; A .5 CK SA 0 C - N ET-C(R) f CHK-2-03-13138CV M-357 (SHT 1) G-6 C k CHK-2-03-13138CW M-357 (SMT 1) G-6 C 'A .5 CT SA 0 C - N ET-GCR) f G: G-6 C' A .5 CK SA 0 C - N ET-c(R) CHK-2-03-13138CX M-357 (SMT 1) A .5 CK SA 0 C - # ET-C(R) CNK-2-03-13138CY M-357 (SMT 1) G-6 C I G-6' C. A .5 CK SA 0 C - N ET-C(R) CHK-2-03-13138C2 M-357 (SHT 1) I I J l.._- ,-
)
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( w).(s / ' 7' t SPEC. M-710' REV1510N 2
'f IST TABLE - VALVES PAGE NO: 35 PEACH BOTTOM ATOMIC Poi.'ER STATION - UNIT 2 & COMMON DATE: 06/03/91 i
STSTEn: 03 CONTROL RG) HYDRAULtC . POS1T10N VALVE VALVE ACT/ VALVE ACT. APP. J TEST FREQUENCY VER/VCS - NUMBER P&lD C00RD CAT. PAS SIZE TYPE' TYPE NRM SAF FAL TYPE C (CIRECTION) NUMBER' REMARKS . ChK-2-03-1313SDA M-357 (SHT 1) 'G-6 C A .5 CK SA O C - N ET-G(R$ CHK-2-03-13138D8 M-357 (SHT 1) C-6 C A .5 CK SA 0 C - N ET-Q(R) CHK-2-03-13138DC M-357 (SMT 1) G-6 .C A .5 CX - SA 0 C - N ET-Q(R) ! a CHK-2-03-13138DD M-357 (SHT 1) G-6 'C A .5 CK SA O C - N ET-Q(R) l L CHK-2-03-13138DE M-357 (SHT 1) G-6 C A .5 CK SA 0' C - N ET-Q(R) i CHK-2-03-13138DF M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) k i
.5 O ET-Q(R) $
CHK-2-03-13138nG M-357 (SHT 1) G-6 C. A CK SA C - N CHK-2-03-13138DF M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) ' g.
-8
~
. CHK-2-03-13138DI H-357 (SHT 1) G-6 C A .5 CX' SA 0 C - N ET-Q(R)
I
.5 0 ET-C(R)
' CHK-2-03-13138DJ M-357 (SHT 1) G-6 C 'A CK . SA C -
N l CHK-2-03-131380K M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N- ET-Q(R) CHK-2-03-131380L M-357 (SHT 1) G-6 C -A .5 - CK SA O. C - N ET-Q(R) 4 CHK-2-03-13138DM M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-Q(R) CHK-2-03-131380u M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-Q(P) CHK-2-03-1313SD0 M-357 (SMT 1)- G-6 C A .5 CK SA 0 C - N ET-Q(R) I CHK-2-03-13138DP M-357 (SHT 1) G-6 C A .5 CK SA 0 C N ET-Q(R) 1 i l
-. .~. . . . . . . . . _ . . . .. . . - - ., . . . . . . ..._ -.._ _ . _ . . . - . . _ _ - . . . _ . . ~ . . . . . _ . _ . - . . _ ~ . _ _ . ~ _ _..,,.m -
O Q O O) .-
^l SPEC. M-710 '
{ REVIS10N 2 il IST TABLE - VALVES PAGE NO: 36 - PEACH BOTTOM ATOMIC POWER STATIO4 - UNIT 2 & COPa40N DATE: 06/03/91; STSTEM: 03 CONTRot.' ROD HYDRAULIC-PCSITION
' 'iALVE VALVE ACT/ - VALVE ACT.: APP.. J TEST FREQUEkCY VRR/vC3 EURBER PSaD COORD CAT. .FAS SIZE TYPE TYPE NRM SAF FAL TYPE C (DIRECTION) NUMSER REMARKS
.CMK-2-03-13118DO M-357 (SHT it) G-6' C A .5 CK SA o C -
N ET-Q(R) il CHK-2-03-1313802 **-357 (SHT 1)
. G-6 C A .5 .. CK SA 0 .C -
N ET-C(R)' ;
.CHK-2-03-13138DS M-357 (SHT 1) G C A .5 CX : SA O C -
M ET-Q(R)
- CHC-2-03-131380T M-357 (SHT 1) G-6 C A- .5 ' CK. SA 0 C -
N ET-0(R)
. l CHK-2 03-1313800 H-357. (SMY 131 G -6 C A .$ CK SA G C -
N ET-C(R)
=i CNK-2-03-13?$3DV M-357 (CHT i) G-6 C A .5 CK SA O C -
N ET-Q(R) (.itI-2-03-1313Ecv et-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) ! h CHK-2-03-13'350X M-357 (SHi 1) C6 .C A .5 CK SA O C - N YT-C(R) i i CHK-2 03-131360Y M-357 (SHT 1) .G C' 'A .5 CK SA ' 0' C - N ET-c(R) l h CHK-2-03-131380Z M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) i CHK-2-03-13138EA M-357 (SMT 1) G-6 C A .5 CK SA O C - N ET-C(R) k CHK-2-03-13'3SE8 H-357 (SHT 1) G-C C' A .5 CK SA 0 C - N ET-C(R) i, l 1 "CHK-2-03-13136EC M-357 (SHT 1) C-6 ' .C' A .5 CK SA 0 C - tl ET-Q(R) I i CHK-2-03-1313 SED M-357 (SHT 1) C-6 C A .5 Cr SA O C + N ET-Q(R) OK-2-03-13138EE M-357 (Sat.1) G-6 C A .5 CK SA 0 C - N ET-Q(R) i CHK-2-G3-1313S:EF M-357 (sHT 1) G-6 C A .5 CK SA 0 C - w ST-c(R) 'l l
- t.
lSFEC M-710' 'I REVISION 2. t
?
IST TABLE - VALVES PAGE NO: 37
'PEECH BOTTOM ATOMIC POWER STATION + UNIT 2 & COMMON DATE: .. 06/G3/91-
' SYSTEN: .03 CONTROL RCD HYDRAtr.IC
. POSITION JVALVE : VALVEI ACT/ VALVE ACT. APP. .t- TES1 FREQUENCY VER/VCS WESER .PEID COORD . CAT. PAS SIZE' TYPE- ' TYPE- WRM SAF FAL TYPE C (DIFECTION) - NUMBER REMARKS-
=l CHK-2-03 1313 BEG 'M-357 (SHT;1) G-6 C : A- .5 :CK SA 'O C - N ET-o(R) . (
CHK-2-03-13138EH M-357 (SHT 1') G-6 CL .A .5 ' CK ' SA ' O- C - N' ET-Q(R)' 1 C M-2-03-1313SE1 M-357 (SHT 13 ' G-6 C A .5 ' CK SA ' O C - N ET-o(a) C K-2-03-1313SEJ M-357 (SHT 1) - C-6 ' C A' .5 CK ' SA . O C - N ET-Q(R)' 1
- C W-2-03-1313SEK M-357 (SMT 1) ' . G C 'A .5 CK SA 0 C -
N ET-C(R)
'ChK-2-03-1313 BEL M-357 (SMT 1) G-6 C A .5 CK SA 0 'C -. N ET-c(R) i i
C M-2-03-13138EM M-337 (SHT 1) ..G-6 C A .5 CK SA 0 C . N' ET-Q(R) e t , I i 'CNK-2-03-13138EN M-357 (SHT 1) G-6 C A .5 CK SA 0 C - N ET-c(R) .}
'C M-2-03-1313SEO M-357 (SHT 1) C-6 C- A .5 CK SA 0 C -
N- ET-c(R) , CHK-7-03-13138EP M-357 (SHT '1)' G-6 C A .5 CK SA 0 C - N ET-Q(R) CNK-2-03-13133E0 M-357 (SHT 1) G-6 C A' .5 CK SA 0 C - N ET-c(R) CHK-2-03-1313SER M-357 (SHT 1) ' G-6 C A .5 CK SA 0 C - N ET-Q(R) CHK-2-03-13138Es M-357 (SHT 1) G-6 C A .5' CK u: O C - N ET-C(R)
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-l; POSI110N VALVE /CT/ ' VALVE ACT. APP. J TEST FREQUENCY VRR/VCS YAlbE TYPE TYPE WRM SAF FAL TYFE C .(DIRECTION) NUMBER REMARKS NUMBER P&!D COORD CAT. PAS S!ZE CHK-2-03-13138EW M-357 (SNT 1) G-6 C A .5 CK- ' SA ' O C - N ET-Q(R)
CHK-2-03-13'38Ex M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) CHK-2-03-13138EY M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) CHK-2-03-13138EZ M-357 (SNT'1) G-6 C A .5 CK. SA O C - N ET-QtR) t G-6 C A .5 CK SA O C - k ET-C(R) g CHK-2-03-1313SFA M-357 (SHT 1) - . CHK-2-03-13138F8 M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-0(R) 4 CHK-2-03-1313SFC M-357 ;SHT 1) G-6 C A .5 CK SA O C - N ET-C(R) I; CHK-2-03-13138FD M-357 (SNT 1) C-6 C A .5 CK SA O C - N ET-C(R) CHK-2-03-13138FE M 357 (SHT 1) G-6 C A .5 CK SA O C - N 'ET-C(R) l1 8 CHK-2-03-13138FF M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) { [: M ET-Q(R) 5-G-6 C A .5 CK SA O C - CHK-2 03-13138FG M-357 (SMT 1) ! CHK-2-03-13133FH M-357 (SHT 1) G-6 C A .5 CK' SA O C - N ET-c(R) fI'
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i SYSTEM: 03 CONTROL ROD HYDRAULIC POLITION VALVE VALVE ACT/ VALVE ACT. APP. J TEST (REQUENCY VRRfVCS NRM SAF. FAL TYPE C (DIEECTION) NUMBER' PEMARKS' NUMBER P&lD COORD CAT. PAS Si2E TYPE- TYPE y CHK-2-03-13138FM M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-C(R)
.4 CHK-2-03-1313SFW M-357 (SHT 1) G-6 C A .5 CK SA O C -- N 17-0(RT.
- e ! CHK-2 03-1313SFO M-357 (SHT 1) G-6 C A .5 Cr; SA O. C - N ET-C(R) 'f I CHK 2-03-1313SFP M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-C(R) CHK-2-03-13138FQ M-357 (SMT.1) G-6 C A' .5 CK SA ' O C - M ET"Q(R) CHK-2-03-1313SFR M-357 (SHT 1) G-6 C A .5 CK SA L C - N ET-Q(R) CHK-2-03-13133FS M-357 (SHT 1) G-6 C A .5 -CK SA O C - N ET-c(R) CHK-2-n3-1313SFT M-357 (SHT 1) G-6 C A. .5 CK SA O C - N ET-c(R) CHK-2-03-13138FU M 357 (SMT 1) G-6 C A .5 CK SA O C - N ET-Q(R)
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'IST TABLE - VALVES PAG" NO: ? 40 - [.
PEACH BOTTOM ATOMIC POWER S1ATION - UNIT 2 & COMMON DATE: 06/03/91 SYSTEM: 03 CONTROL ROD HTDRAULIC' POSITION VALVE VALVE ACT/ ' ' VALVE ACT. APP. J TEST FREQUENCY VRR/VCS ' NUMBER 'P&lD COORD CAT. PAS SIZE '. TYPE TTPE NRM SAF FAL TYPE C '(DIRECTION). NUMBER REMARKS' CHK-2-03-13138GC M-357 (SHT 1) G-6 C ;A .5' CK SA . O C -- N ET-C(R) Y _ j;- CHK-2-03-13138CD M-357 (SHT 1) 'G-6 C A .5' CK . ' SA O .C - N ET-Q(R) . E L.I CHK-2-03-1313SCE M-357 (SHT 1) G 'C A' .5 . CK SA O C - N ET-Q(R) q)
- t; CHK-2-03-13138CF M-357 (SHT 1) G-6 C A' '.5 CK SA O .C - N ET-G(R) f; CHK-2-03-13138GG M-357 (SMT 1) G-6 C A. .5- CK. SA O C -
N- ET-c(R) ; CHK 2-03-13138GH M-357 (SMT 1) G-6 C' A .5 CK SA O C -
'N ET-Q(R) {
I CHK-2-03-13138GI M-357 (SHT 1) G-6 C A .5 : CK SA O C - N ET-C(P) G-6' .5 O C N ET-Q(R).
-[I CHK-2-03-13138GJ M-357 (SHT 1) C A CK SA CHK-2-03-13138GK M-357 (SHT 1) G-6 C A .5 CK- SA O C -
N ET-C(R) CHK-2-03-13138GL M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-Q(R) CHK-2-03-13138CM M-357 (SHT 1) G-6 C' A .5 CK SA' O C - N -Ei-Q(R) ir CHK-2-03-13135GN M-357 (SHT 1) G-6 C A .5 CK SA O C - N ET-otR) CHK-2-03-1313SGO N-357 (SHT 1) C-6 C A .5 CK SA O C - N ET-C(R) h G-6 A .5 CK SA O C - N ET-o(R) Ip CHK-2-03-13138CP M-357 (SHT 1) C
. CHK-2-03-13133Go M-357 (SHT 1) G-6 c A .5 CK SA O C - N ET-Q(R)
CHK-2-03-13138GR M-357 (SHT 1) G-6 C .A .5 CK SA . O C - N ET-Q(R) i u
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SPEC. N-710 REVISION 2 { PAGE ar0: 41 IST TABLE - VALVES DATE: 06/03/91 FEACH SOTTOM ATCMIC PC'TR
. STATION - UNIT 2 & COMMON y
SYSTEM: 03 CONTROL RCD HYDRAULIC k FOSITION VALVE ACT. APP. J TEST FREQUENCY VRR/VCS VALVE VALVE ACT/ NUMBER REMARKS 9110 COORD CAT. PAS $1ZE TYPE TYPE NR9 SAF FAL TYPE C (DIRECTION) NUMBER V G-6 C A .5 CK SA O C - N ET-Q(R) 3 CHK-2-03-13133GS M-357 (SMT 1) i 0 - N ET-0(R) f CK-2-03-13138GT M-357 (SMT 1) G-6 C A .5 CK SA C y C-6 C A .5 CK SA o 0 - N Er-o(R) CHK-2-03-13138GU M-357 (SHT 1) ;
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ET-0, FS-C(C), CVER-1 FENT, N-38 M-356 (SMT 1) H-4 A A 1 GL AO 0 C C Y CV-2-03-032s ST-C(C), LJ-T, F1-T O C C Y ET-Q, FS-G(C), CVER-1 FEET. e-38 M-356 (SHT 1) F-6 A A 2 GL AO CV-2-03-033 ST-C(C), LJ-T, PI-T I t Y i I .
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SPEC. n-710 REVISION 2 i k. IST TABLE VALVES PAGE No: 42 t
'PEACs BOTTOM ATOMIC POWER STATICJ - UNIT 2 & COMMos DATE: .06/0!/91~ !
SYSTEM: 03 CONTROL R00 HYDRAULIC j POSITION I VALVE VALVE ACT/ - VALVE .ACT. APP. J TEST FREQUEECY- VER/VCS I NUMBER P&lD COORD CAT. FAS SIZE TYPE TYPE WRM SAF FAL: TYPE C (DIPECTION) NUMSER REPARKS- i
.CV-2-03-035A 'M-356 (SMT 1) N-8 2 'A A 1 GL- A0 0 C C Y ET-0,.FS-Q(C), GYRR-1 DINT, M36 _
ST-G(C), LJ-T, PI-T CV-2-03-0358 M-356 ($HT 1) H-4 A A 1 GL AO ~ O C C 'Y' ET-0, FS-Q(C), CVER-1 PENT. 0 33 ST-Q(C), LJ-T, PI-T l h
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CV-2-03-036 M-356 (SHT 1) F-6 A A 2 CL Ao . O C- -C Y ET-0, FS-Q(C), CVER-1 PIM , N-35 ST-Q(C), LJ-T, PI-T k i CV-2-03-13126AA M-357 (SHT 1) F-6 8 A 1 GL A0 C G 0 W ET-R, FS-R(0), 03-V2R-1 'I ST-R(0), PI-T CV-2-03-13126AB M-357 (SNT 1) F-6 B A 1 CL AO C 0 0 N ET-R, FS-R(0), 03-VER-1 [ ST-R(D), PI-T
.CV-2-03-13126AC M-357 (SMT 1) F-6 S A 1 GLL AO C 0 0 N ET-8, FS-RCO), 03-VRR-1 h ST-R(0), PI-T' CV-2-03-13126AD M-357 (SMT 1) F-6 B A 1 CL A0 C 0 0 N ET-R, FS-R(0), 03-vta-1 ;
ST-R(0), PI-T A CV-2-03-13126AE M-357 ($HT 1) F-6 B A 1 CL AD C 0 0 N ET-R, FS-R(0), 03-VRR-1 5 ST-R(0), PI-T CV-2-03-13126AF M-357 (SMT 1) F-6 B A 1 GL A0 C 0 0 N ET-R, FS-RCO), 03-vtR-1 ST-R(D), PI-T cv-2-03-13126AG M-357 (SMT 1) F-6 B A 1 GL A0 C 0 0 W- ET-R, FS-P(0), 03-VER-1 ST-R(0), PI-T : t 1 5 d'
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,-- f SPEC. M-710. 'T
. REVISION 2.' !I' a8
' PAGEi NO: 44
'IS' TABLE - VALVES OATE: 06/03/91 g-FEACH BCTTOM ATONIC POWER STATION - LNIT 2 4 Ch ' u i ;
SYSTEM: 03 CCNTROL ROD HYDRAULIC POSIT 10N [ APP. J TEST FREOL;EWCT VRR/VCS 7 VALVE ACT/ VALVE ACT. % VALVE NUMEER REMARKS i P&!D ,COORD CAT. PAS SIZE TYPE TYPE: ' NRM SAF FAL TYPE C (DIRECTION) NUMSER 0 0 m. ET-R, FS-R(0), 03-YRR-1 ~ CV-2-03-13126AR M-357 (SNT 1) F-6 B ;A 1' GL AO C
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r A0 C o o N ET-R,' F S'-R(0), 03-v2R-1 T+5 8 .A 1 GL CV-2-03 13126AS M-357 (SHT'1: ST-R(0), 91-T AO C 'O O N . ET-R, FS-R(0), - 03-VPR-1 .I F-6 8 A 1 GL- ) CV-2-03-13126AT ' M-357 (SHT 1) ST-R(0), PI-( h. AO C 0 0 'N ET-R, FS-R(0), C3-vRR-1 F-6 8 A 1 GL CV-2-03-13126AU M-357 (SHT 1) ST-R(0), PI ' .! t C i 0 0. N ET-R, FS-a(0), 03-vRR-1 F+6 8 A 1 CL A0 C CV-2-03-13126AV M-357 (SHT 1) ST-R(0), PI-T AO C 0 0 W ET-a, FS-R(0), 03-v2R-1 .7 F-6 8 A 1 GL CY-2-02-13126AW M-357 (SMT 1) t-ST-R(0), PI-T a-1 A0 C 0 0 N ET-R, FS-R(0), 03-vtR-T F-6 8 A 1 GL CV-2-03-13126Ax M-357 (SHT 1) ST-R(0), PI-T , i - C 0 0 W ET-R, FS-R(0), 03-vRR-1 F-6 B A 1 CL AO l CV-2-03-13126AY M-357 (SNT 1) ST-R(0), PI-T. , 0 0 W ET-R, F3-R(0), 03-vRR-1 F-6 8 A 1 GL AO C CV-2-03 13126AZ M-357 (SHT 1) ST-R(0), P!-T 0 0 N ET-R, FS-R(0), 03-vRA-1 A0 C CV-2-03-13126BA M-357 (SHT 1) F-6 8 A 1 GL ST-R(0), Pi-T { e r i N
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'REVIS10W 2 IST TABLE - VMVES PAGE NO:. 45 - %
PEACH BOTTOM ATOMIC POWER STATION I (JNIT 2 & COMMON DATE: ^06/03/91l 'l - L SYSTEM: 03 CCNTROL F00 HYDRAULIC u POSITION . YALVE VALVE ACT/ VA'.VE ACT, APP. J TEST FREQUENCY VRR/VCS NUMBER P&lD COORD CAT. PAS SIZE TYPE TYPE kRM S/ F FAL TYPE C (DIRECTION) EUMBER REMAPKS . CV-2-03-13126BB' M-357 (SHT 1) F-6 8 A' 1. GL A0 C' O O. N ET-R, FS-R(0), 03-VRO 1 j; ST-R(0), PI-T l
'CV-2-03-13126BC M-357 (SHT 1) F-6 B A 1 GL A0 C 0 0 N ET-R, FS-RCO), 03-VRP-1 [
.ST-R(0), PI-T p CV-2-03-1312680 M-357 (SHT 1) F-6 B A 1 CL A0 C 0 0 N ET-R, FS-R(0), 03-VER-1 ST-R(0), PI-T CV-2-03-13126BE M-357 (SNT 1) F-6 B A 1 GL p.0 C O O N ET-R, FS-R(0), 03-V2R-1 ST-R(0), PI-T L
CV-2-03-131268F M-357 (SNT i) F-6 B A 1 GL A0 C 0 0 N ET-R, FS-R(0), 03-VRR-1 I; Si-R(C), PI-T ! T o CV-2 03-131268G M-357 (SHT 1) F-6 B A 1 CL A0 C 0 0 N ET-R, TS-R(0), 03-VRR-1 ST-R(0), PI-T CV-2-03-13126BH M-357 (SHT 1) F-6' B A 1 ' GL AD C O O E ET-R, FS-R(0), 03-VRR-1 ST-R(0), PI-T CV-2-03-1312681 M-357 (SHT 1) F-6 B A 1 GL A0 C 0 0 N ET-R, FS-R(0), 03-VRR-1 ST-R(0), PI-T cv-2-03-131268J M-357 (SHT 1) F-6 B A' 1 GL A0 C 0 0 N ET-R, FS-R(0), 03-vRR-1 ST-R(0), PI-T CV-2-03-13126sK M-357 (SHT 1) F-6 B A 1 GL AO C O O N ET-R, FS-R(0), 03-VRR-1 ST-R(0), P!-T , . I 1 L i L t L lL I ij
. I
,l' SPEC. M-710 [
REVISION 2 V PAGE kO: 46 IST TABLE - VALVES CATE: 06/03/'J1 PEACH BOTTOM ATOM 1r POWER STATION - UNIT 2 & COMMON SYSTEM: 03 CONTRCL ROD HTORAULIC [ POSITICN 5 APP. J TEST FREQtJENCY VRR/VCS VALW i,CT . VALVE VALVE ACT/ NUMSER REMARKS CAT. PAS SIZE TYPE TYPE NRM SAF FAL TYPE C (DIRECTION) NUMBER P&!D COORD ET-R, FS-R(0), 03-WR-1 CV-2-03-13126BL M-157 (SHT 1) F-6 B- A 1 ct Ao C 0 0 N ST-R(0), Pf-T
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F-6 B A 1 CL CV-2-03-131266M M-357 (SHT 1) ST-R(0), Pi-T h I 03-YRR-1 R' Ao C 0 0 N El-R, FS-R(0), M-357 (SHT 1) F-6 8 A 1 GL ST-R(0), PI-T h CV-2-03-131268N i; 5 0 ET-R, FS-R(0), 03-VER-1 A CL AO C 0 N k CV-2-03-1312680 M-357 ($HT 1) F-6 B 1 ST-R(0), P!-T j'
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0 N ET-R, FS-Rt0), 03-VFR-1 0 CV-2-03-131268P M-357 (SHT 1) F-6 B A 1 CL A0 C ST-R(0), PI T {M O N ET-R, FS-R'M 03-VRR-1 GL AO C O p. CV-2-03-1312650 M-357 (SHT 1) F-6 B A 1 ST-RCO), P!-T E 0 ET-R, FS-R(0), 03-vRR-1 A GL AO C 0 N p CV-2-03-13126BR M-357 (SHT 1) F-6 B 1 ST-R(0), PI-T 6 p 0 ET-R, FS-R(0), 03-VRE-1 GL Ao C 0 N - CV-2-03-13126SS M-357 ($HT 1) F-6 C A 1 ST-R(0), P!-T 0 0 N ET-R, FS-R(D), 03-vat-1 F-6 B A 1 CL A0 C # CV-2-03-13126BT M-357 (SHT 1) ST-R(0), PI-T D a 0 ET-R, FS-R(0), 03-vRR-1 s GL Ao C 0 N j CV-I-03-131268J M-357 (SMT 1) F-6 A 1 ST-R(0), P!-T ; L
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f} + (:0(% SPEC. D-710~ REVISION 2 [i l PAGE NO: .
.45 j' IST TABLE . VALVES 06/03/91 DATE:
' PEACH BOTTOM ATOMIC POWER STATION - UNIT 2 & COMMON ~
r I
^
SYSTEM: 03 CONTROL R00 HYDRAULIC APP. J TEST FREQUENCY VRR/VCS 1rALVE ACT/ YALVE ACT. - VALVE WJMBER REPARKS COORS CAT, PAS SIZE TYPE TYPE' NRM SAF TAL TYPE C (D!RECTION) . ! NUMBER P&lD .. C 0 0 N ET-R, FS-R(0), 03-vRR-1 F-6 8 A 1 'CL A0 CV-2-03-13126CF M-357 (SHT 1) ST-R(0), Pl=T C 0 0 N ET-R, FS'-R(C), 03-VRR-1 F-6 S A 1 CL AO
.CV-2-03-13126CG M-357 (SHT 1) ST-R(0), PI-T CL A0 C 0 0 N' ET-R, FS-R(0),. 03-VRR-1 ,'
H-357 (SMT 1) ' F-6 B A 1 'O CV-2-03-13126CH ST-R(0), PI-T h r-ET-R, FS-R(0), 03-VRR-1 F-6 8 A 1 CL A0 C' O. O N f CV-2-03-13126CI M-357 (SHT 1) ST-k(0), P!-T
) <'
C 0 0 N ET-R, FS-R(0), 03-VRR-1 F-6 8 A 1 GL AO CV-2-03-13126CJ M-357 (SHT 1) ST-R(0), P3-7 j .- lI ET-R, FS-R(0), U3-VRR-1 g 8 CL A0 C 0 0 N CV-2-03-13126CK M-357 (SHT 1) F-6 A 1 ST-R(0), PI-T
~ .;
03-VRR-1 l CL A0 C 0 0 N ET-R, FS-R(D), M-357 (SHT 1)_ F-6 B A 1
'I CV-2-03-13126CL ST-R(0), PI-T 6l ET-R, FS-R(0), 03-VRR-1 hl
'B . GL A0 C 0 0 W
CV-2-03-1312.6CM M-357 (SMT 1) F-6 A 1 ST-R(0), PI-T C 0 0 N ET-R, FS-R(0), 03-VRR-1 g! F-6 8 A 1 CL AO <g ' CV-2-03-13126CN M 357 (SHT 1) ST-R(0), PI-T . E!
$1 ET-R, FS-R(0), 03-VRR-1 g; A- CL AD . C 0 0 W CV-2-03-13126CO M-357 (SNT 1) F-6 B T hj ST-R(0), PI-T V
E f
-r F:
't.
Y rt ! h
' p
- , , w 1.
' ' % .. { _:
SPEC & 710 .- - REVISION 2 - f.l PAGE NO: 49 L 1[ IST TABLE - VALVES PEACH BOTTCM ATOMIC POWER STAT 10N - UNIT 21 COMMON DATE: 06/03/91 4: SYSTEM: 03 CONTROL ROD HTDRAULIC POS!!a0W
. VALVE ACT. APP. J TEST FREQUENCY VER/VCS {
j VALVE VALVE ACT/ hRM SAF FAL TTPE C (DIRECTIO4) NUMBER REPARKS NUMBER P&ID COORD CAT. PAS SIZE T1PE TTPE _ __ ___ g 0 0 ET-R, FS-R(0), C3-vPR-1 'i CV-2-03-13126CP M-357 (SHT 1) F-6 B A 1 Cf. A0 C M ST-R(0), PI-T [ A0 C 0 0 N. ET-R, FS'-R(0), 03-vRR-1 e CV-2-03-13126CO M-357 (SHT 1) F-6 B A 1 GL - ST-R(0), P!-! . k M-357 (SMT 1) F-6 8 .A 1 . GL A0 C 0 0 N ET-R, FS-R(0), C3-vRR-1 CV-2-03-13126CR ST-R(0), PI-T , y! M-357 (SHT 1) F-6 B A 1 GL AO C 0 0 N ET-R, FS-R(0), 03-VRR-1 CV-2-03-13126CS ST - R (*)), PI-T M-357 (SHT 1) F-6 B A 1 ! GL A3 C O O N ET-R, FS-R(0), 03-YRR-1 CV-2-03-13126CT ST-R(0), PI-T M-357 (SHT 1) F-6 S. A 1 GL A0 C 0 0 W ET-R, FS-R(0), 03-VRR-1 cv-2-03-13126Cu ST-R(0), PI-T
.R F-6 8 A GL A3 C 0 0 W' ET-R, FS-R(0), 03-VRR-1 CV-2-03-13126CV M-357 (SHT 1) 1 ST-R(0), PI-T F-6 8 A CL A0 C 0 0 .N ET-R, FS-R(0), 03-vRR-1 CV-2-03-13126CW M-357 (SMT 1) 1 ST-R(0), PI-T F-6 A GL A0 C 0 0 N ET-R, FS-R(0), 03-VRR-1 CV-2-03-13126CX M 357 (SHT 1) B 1 ST-Rt0), PI-T .y F-6 8 A 1 GL AO- C 0 0 N ET-R, FS-R(0), 03-VRR-1 'CV-2-03-13126CT M-357 (SHT 1) '
ST-R(0), Pt-T i-
.1' .
A1 x I
. . _- - , - . . _ , , . , . _ . , , . , . . . , , m,y m_ . f,., m __ m , , .__ ,,,. _ _ g .%
a - N k t SPEC. **-710 g l SEVISION 2 [ I f IST TARL5 - VA:.YES PAGE WO: 50 [ CATE: 06/03/91 PEACH BGTTOM A!OMIC POWER STATION - UNIT 2 & COMM'.A SYSTEM: 03 CCHIROL ROD HYORAULIC r W IT 04 VALVE VALVE ACT/ VALVE ACT. app.J 'EST FREQUEktY , VRR/VCS WUMSER REMARKS {g TYPE TYPE UM SAF FAL TYPE C (DIRiCT;ON) NUMSER P&fD C00RD CAT. PAS SIZE +
]
AC C 0 0 N IT-R, FS-R(0), 03-VRR-1 F-6 A 1 GL CV-2-03-13126CZ M-357 (SNT 1) B ST-R(0), P!-T J k V e A GL A0 C O O N ET-R, FS-f(0), 03-VER-1 CV-2-03-131260A M-337 (SHT 1) F-6 8 1 h ST-R(0), PI-T t CV-2-03-1312608 M-357 ($HT 1) F-6 B A 1 CL AD C O O ?! ET-R, rS-2(0), C3-VRR-1 'fa ST-P(0), PJ-T e. W F-6 B A 1 GL A0 C 0 0 W ET-R, FS-R(0), 03-VRR-1 f CV-2-03-13176DC M-357 (SHT 1) ST-R(0), PI-T g Ci GL AO C 0 0 W El-R, FS-R(0), C3-VER-1 CV-2-03-13126DO M-357 (SHT 1) F-6 B A 1 5l ST-R(0), P!-T M, e h i GL AC C C 0 W ET-R, FS-R(0), 03-VRE-1 CV-2-03-1312cCE M-357 (SMT 1) F-6 B A 1 ST-R(0), P!-T n[I i;. ET-R, FS-R(0). G3-VER-1 g 0 l l CV-2 1312N)F M-357 (SHT 1) F-6 B A 1 GL AO C 0 M ST-R(0), P!-T ), A0 C 0 0 W ET-R, FS-R(0), 03-vRR-1 [l! g CV-2-03-13126DG M-357 (SHT 1) F-6 B A 1 GL
$i ST-R(0), PI-1 5!
Il 0 0 W ET-R, FS R(0), C3-VER-1 a! A0 CV-2-03-13126DH M-357 (SdT 1) F-6 B A 1 GL C ST-Rio), 93-1 ('
>l A0 C C 0 W ET-R, FS-R(0), 03-YRR-1 F-6 8 A 1 GI.
CV-2-03-131260! M-357 (SHT 1) ST-R(0), PI-T kl h l' k
?:
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{
.k :
.,.7
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2, w mr .
- SPEC. M-710 REVISION 2 IST TA3LE - VALVES PACE wo: 51 PEACM BOTTCH ATOMIC POWER STATION - tJNIT 2 & CmMoh GATE: 06/03/91 i
SYSTEM: 03 CONTROL ROD NYDRNJLIC POSITION VALVE VALVE ACT/ VALVE FACT. APP. J TEST FREGUENCY VRR/VCS NUMBER- F&l0 .COORD CAT. PAS -SIZE T1PE ' TYPE NRM SAF FAL TYPE C. (DIRECTION) NUMBER REMARKS s CV-2-03-131260J M-357 (sHT 1) 7-6 s A 1 ct. 'A0 C' o o N ET-R, FS-R(0), 03-VRR-1 ST-R(0), PI-T l if CV-2-03-13126DK M-357 (SHT 1) F-6 B A 1 - GL A0 C O O N ET-R, FS-R(0), 03-WR-1 ST-R(0), P!-T k CV-2-03-131260L M-357 (SHT 1) F 8 A 1 CL AO C 0 0 N ET-R, FS-R(0), 03-YRR-1 ST-R(0), Pi-T CV-2-03-13126DM N-357 (SHT 1) .F-6 B A 1 GL A0 C O O N. ET-R,'FS-R(0), 03-VRR-1 , ST-R(0), Pt-T
-1 CV-2-03-13126DN M-357 (SMT '1) F-6 8 A. CL ' Ao C o 0 N ET-R, FS-R(0), 03-YRR-1 1
{ ST-R(0), PI-T CV-2-03-1312U)c M-357 (SHT 1) F-6 8 A 1 CL AO C 0 0 N ET-R, FS-R(0), '03-VER-1 ST-R(0), PI-T CV-2-03-131260P M-357 (SHT 1) F 6 A 1 GL A0 C 0 0 N ET-R, FS-R(0) 03-VER-1 ST-R(0), PI ' s
^
CV-2-03-1312600 M-357 (SHT 1) F-6 B A 1 GL ' A0 C 0 0 N ET-R, FS-R(0), 03-VRR-1 ST-R(0), PI-T CV-2-03-13126DR M-357 (SHT 1) F-6 B A 1 CL AO C 0 a N ET-R, FS-R(0), 03-VuR-1 ST-R(C), PI-T
}
CV-2-03-131260s M-357 (SHT 1). F-6 B A 1- CL. AO C 0 0, N ET-R, FS-t(0), 03 VRR-1 ST-R(C), PI-T 1
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SPEC. M-710 REVISION 2 : IST TABLE - VALVES PAGE NO: 66 f PEACM BOTTOM Afow!C Pol 4R STATIO4 - 1J41T 2 & C&aion CATE: 06/03/91 STSTEM: 03 CONTROL RCD RTDRAULIC i POSITION , VALVE VALVE ACT/ VALVE ACT. APP. J TEST FREQUEWCY VRR/VCS f NUMSER P&lD COORD CAT. PAS SIZE TYPE TYPE NRM SAF FAL TYPE C (D!RECTION) NUPSER REMARits { CV-2-03-13127CA M-357 (SMT 1) F-7 8 A .75 CL A0 C 0 C h ET-R, FS-R(0), 03-VER-? j ST-R(0). P!-T { CV-2-03-13127tB M-357 (SMT 1) F-7' 8 A .75 GL A0 C 0 0 N ET-R, FS-R(0), 03-VER-1 ST-R(0), PI-T j i CV-2-03-13127CC M-357 (SMT 1) F-7 a .A .75 GL Ao C o o N ET-F, FS-R(0), G3-VPR-1 ) ST-R(0), PT-T , CV-2-03-13127CD- M-357 (SHT 1) F-7 8 A .75 CL AO C 0 0 N ET-R, FS-R(w), 03-VRR-1 ST-R(0), PI-T f I CV-2-03-13127CE M-357 ($MT 1) F-7 8 A .75 GL A0 0 0 0 N ET-R, FS-R(0), 03-VRR-1 g ST-R(0), PI-T i CV-2-03-13127CF M-357 (SMT 1) F-7 8 A .75 GL AO 'C O O E ET-R, FS-R(0), 03-WRR-1 f
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!$T TASLE - VALVES ' PAGE so: 80 PEACH SOTTCM ATOMIC POWER STATIOW - UNIT 2 & CCMMCM OATE: 06/C3/91 !
STSTEM: 04 WUCLEAR BCILER VESSEL IkSTRUMENTATION PCSITION ; V!. LYE VALVE: ACT/ VALVE ACT. APP. J TEST FREQUENCY VRR/VCS j WIMBER P&ID C00RD CAT. PAS SIZE TYPE TYPE mRM SAF FAL TYPE C (DIRECTION) wJ46ER REMARES .i j XFC-2-04-011 M-352 (SMT 1) G-6 A, C A 1 XC SA 0 C - u ET-R(F), PI-T, LP-! QTR-2 f' XFC 2-04-015A M-352 (SNT 1) F-6 A, C A 1 XC SA 0 C - N' ET-R(F), PI-T, LP T OTR-2 XFC-2-04-015B M-352 ($8!T 2) 7-6 A, C A 1 XC SA O C - N ET-R(F), PI-T, LP-T GVRR-2 f XFC-2-04-017A M-352 13NT 1)- E-6 A, C 'A 1 XC SA 0 C - N ET-R(F), PI-T, LP-T GVRR-2 6 XTC-2-04-017B M-352 (SMT 2) E-6 A, C A 1 XC' SA 0 C - # ET-R(F), PI-T, LP-T GVRR-2
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