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| FLORIDA POWER and LIGHT COMPANY NUCLEAR ENERGY SERVICES 700 Universe Boulevard I l Juno Beach, Florida 33408 SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL INSERVICE TESTING PROGRAM -
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| FOR PUMPS AND*/ALVES l
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| ST. LUCIE NUCLEAR POWER PLANT ;
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| UNIT NO. 2 I l
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| l DATE OF COMMERCIAL OPE.% TION: AUGUST B, 1983 FLOPIDA POWER & LIGHT i P.O. BOX lib FT. PIERCE, FL. 34954
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| ! I t
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| l NAC DOCKET NUMBER: 50-389~ !
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| \
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| l DOCUMENT GUMBER: JN S-. ;S L-2 0 4 - 2 REVISION 0
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| ..-.......-.~........n.,e---.
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| I . I; i' ' / .%Iahl'aOiE/
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| '' ~ 'O ti6i C ,.Cu t.'.!'O. BEFC C. .
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| 1; v.!TH A CW:'Ou.ED DOCU .*T T l !
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| 1
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| .. O hE? AtiD i.lGHT 00.
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| , le
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| ! C T. LUCtE PLANT 1 i
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| } r,, ,7:- - " - 7 :D INiilAL 3 J
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| t, , '.- u ..n 4..qu,L '
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| ST. LUCIE PLANT F.EVIEWS AND APPROVAL 5: M. i
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| -. t PREPARED BY:
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| Al SZ PLAT T g
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| .i! ENGIk$iR '
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| DATE: ((1((#/[ )
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| 1 APPRO''ED BY : .
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| A IATE: 7 2I P L TEST & CODE SUPERVISOR /
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| f
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| , I
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| / I
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| /.. \
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| 9704070041 970325 PDR FOIA BINDER 96-485 PDR J
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| s O- O I p {]^~ ~ ~ ~
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| 07/16/93 Table of Contents Pag,e
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| __ Table of Contents "
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| Record of Revisions i 11 1.0 Introduction 1
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| 2.0 Applicable Documents 2
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| 3.0 3.1 Inservice Testing Program For Pumps Code Compliance 3 -
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| 3.2 Allowable Ranges of Test Quantities 3 3.3 Testing Intervals 3 3 .- 4 Pump Program Table 3 3.5 Relief Requests for Pump Testing 4 4
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| 4.0 Inservice Testing Program For Valves ,
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| 4.1 Code Compliance 5 4.2 Testing intervals 5 4.3 Stroke Time Acceptance Criteria 5 -
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| 4.4 Check Valve Testing 5 4.5 Valve Program Table 5 4.6 6 4.7 Relief Requests For Valve Testing Cold Shutdown Testing 6 6
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| Appen' dices A Pump Program Tables B
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| Pump Program Requests For Relief C Valve Program Tables D Valve Program Requests For Relief E
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| Cold Shutdown Justifications i
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| y e
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| -4
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| O o.
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| peytsi~on D ~ -~~
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| 07/16/93 RECORD OF REVISIONS REVISION DESCRIPTION OF REVISIO1 DATE NUMBER REASON FOR THE CHANGE REVISED-APPROVALS._
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| 0 Second 10-year submittal 07/16/93 a
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| 1 1
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| l-_.___.-__.- - - - - - - - - - - - - - - - - - - -
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| Revision 0 1
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| 07/16/93 1 a
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| INSERVICE TESTING (IST) PROGRAM PLAN ST. LUCIE UNIT 2 ;
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| ==1.0 INTRODUCTION==
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| i 4
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| i Revision 0 of the St. I ASME Inservice. Inspection (IST)Lucie Unit 2 Second 10-Year Interval }
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| through the end of the second<120-monthProgram will be interval in effect
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| : 10-year) j unless revised and reissued for reasons o(ther than the i routine per 10 CFR update 50.55a(g). _ required at the start of the third intervai j
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| defined as follows: The second inspection interval is Begins Ends August 8, 1993 August 8,
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| $ 2003 This document outlines the IST Program for St. Lucie Plant, Unit 2, based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, References in this document to "'WP" 1986 Edition (the Code). i i or "IWV" correspond to '
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| Subsections IWP and IWV, respectively, of the ASME Section I
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| XI, 1986 Edition, unless otherwise noted.
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| 1 4
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| The inservice testing identified in this Plan are to be l j
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| j performed specifically to verify the operational readiness of pumps and valves which have a specific function in '
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| i mitigating the consequences of an accident or in bringing i
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| a the reactor to a safe shutdown. i
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| .i e s
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| +
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| 6 1
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| O c l
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| -~'ReVisfon~ 0~ ~~
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| . _ 07/16/93 3.0 INSERVICE TESTING PROGRAM FOR PUMPS 1
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| 3.1 Code Compliance )
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| This IST Program for pumps meets the requirements of :
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| Subsection'IWP of the Code and any interpretations or l additional
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| : 04. Where requirements imposed by Generic Letter 89- i be impractical, these requirements have been determined to !
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| conformance would cause unreasonable hardship without any compansating increase in safety, or an alternative test provides an acceptable level of, quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR
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| : 50. 55a (g) (5) (iii) and Generic Letter 89-04.
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| 3.2 Allowable Ranges of Test Quantities -
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| .- l The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all measurements of pressure, flow, and vibration except as provided for i in specific relief requests. In some cases the i
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| performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating parameter that falls outside the allowable ranges as set forth in Table IWP-3100-2. Should such a situation arise, an expanded allowable may be determined, on a case-by-case basis, in accordance with l IWP-3210 and ASME Code Interpretation XI-1-79-19. l 3.3 Testing Intervals The test frequency for pumps included in the Program will be as set forth in IWP-3400 and related relief requests. A band of +25 percent of the test interval may be applied to a test schedule as allowed by the St.
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| Lucie Unit 2 Technical Specifications to provide for operational flexibility.
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| 3 m .
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| O O 4
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| 4
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| - - Re vi s ion-O-- - --
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| 07/16/93 4
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| ' l 3.4 Pump Program Table Appendix A lists those pumps included in the IST Program with references to parameters to be measured and applicable requests for relief. I j 3.5 Relief Requests for Pump Testing
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| : 3. Appendix testing. B includes all [elief requests related to pmmp For convenience, the sequential numbers of ;
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| i the relief requests are carried-over from the previous I submittal for the first inspection interval.
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| ! I k
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| .___. _ _ . - m._ ._ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ __ ...
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| Revislon 0
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| _ 07/16/93 :
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| 4.0 INSERVICE TESTING PROGRAM FOR VALVES 4.1 Code Compliance l
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| This IST Program for valves meets the requirements of !
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| Subsection IWV of the Code and any interpretations or additional requirements imposed by Generic Letter 89-04.
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| Where these requirements have been determined to {
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| i be impractical, conformance would cause unreasonable !
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| hardship without any compensating increase in safety, or an alternative test provides an acceptable level of I quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR
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| : 50. 55a (g) (5) (iii) and Generic Letter 89-04.
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| 4.2 Testing Intervals i The test frequency for valves included in the Program will requests.
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| be as set forth in IWP-3400 and related relief A band of +25 percent of the test interval may be applied to a test schedule as allowed by the St. '
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| Lucie Unit 2 Technical Specifications to provide for operational flexibility. Where quarterly testing of valves is impractical or otherwise undesirable, testing may be performed during cold shutdown periods as permitted by IWV-3412(a). Justifications for this deferred testing are provided in Appendix E.
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| 4.3 Stroke Time Acceptance Criteria When required, the acceptance criteria for the stroke times of power-operated valves will be as set forth in Generic Letter 89-04.
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| 4.4 Check Valve Testing ;
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| Full-stroke exercising of check valves to the open position using system flow requires that a test be j performed whereby the predicted full accident condition !
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| flow rate through the valve be verified and measured.
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| Alternatively, non-intrusive inspection techniques may be used to verify full stroke with less than full
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| " accident" flow rate.
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| 5
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| Revision 0 )
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| _ 07/16/93 )
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| l 4.5 Valve Program Table i
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| Appendix C lists those valves included in the IST !
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| Program with references to required testing, respective test intervals, and applicable requests for relief.
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| '~
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| 4.6 Relief Requests for Valve Testing
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| ) Appendix D includes all relief requests related to valve testing. For convenience, the sequential numbers of the relief requests are carried-over from the a
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| previous submittal for the first inspection interval.'
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| 4.7 Cold-Shutdown Testing i
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| Where it is determined to be impractical to exercise '
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| valves during normal plant operation and exercising can be performed under cold shutdown conditions, the valve program table is so noted and justification for test deferment is provided in Appendix E.
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| 1 l
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| I 6
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| r o Revision 0
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| _ 07/16/93 1
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| Appendix A Pump Program Tables i
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| e 3
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| +
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| 4
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| )
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| i
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| 1 r o e
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| usuu FL0tIDA POLAR AW LIGNT COWANYs o nuse ss e s s e s m u en ma n n e e n u ne nu s e u s essen e n PUMP TABLES REylslim j Saint Lucie Nuclear Ploet . Unit 2 eso.
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| DATE : 07/16/93 PAeg 1 Pue NtMSER o n ee smose s sen e eses ses sesse INLET sDIFF.
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| s es FLOW se s s e ss e ma ne s es eas DEscalPfl0N CL Coo $ PEED PRES.
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| BEAtlNG PRES. RATE VittA.
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| ~.................................................tD......................................TEw.
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| AfW 2A AUXILIAtf FEEDWATER Puer 3 N*Y3 NA 7 REMARKS Y T PR 4 T N:Pt.1 AFW 29 AURILIAtf FEEDWRTER M8EP 3 N 13 NA Y Y T PR 4 Y N:PR 1 I AFW 2C i AUKILIAlf FEEDW4TER PWIP 3 8: 13 Y Y Y T:PR 4 Y N:PR 1 BAM 2A totlC ACID MAKEUP PLMP 2 S5 NA Y PR 8 Y T PR 5 Y N:Pt.1
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| ; 4AM 28 60 tlc ACID MAKEW PLMP 2 C5 NA Y:Pt 8 Y Y:Pt 5 Y N:Pt.1 CCW 2A
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| ; CCMPONENT C00 LING WATER PUMP 3 F 16 NA Y Y Y Y N PR.1 CCW 28 CCMPONENT COOLING WATER PUMP 3 F 17 NA Y Y Y Y N:Pt 1 CCW 2C CCMPOWENT COOLING WATER PUMP 3 F 16 NA Y Y
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| ' Y Y N:PR 1 CNC 2A CHARGING PdMP 2 C3 NA Y Y T Y:PR 12 N:PR 1 CMG 28 CHARGING PG4P 2, E 3 NA Y Y Y T:Pt=12 k:Pt.1 CMG 2C CHARGING PU w 2 G3 NA Y Y Y 7:P3 12 N:Pt 1
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| ; Cs 2A CONTAINMENT SPEAT Pur 2 G4 NA Y:PR 15 Y Y PR 6 Y
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| ' N:PR 1 CS 28 i CONTAINMENT SPRAY PUMP 2 H-4 NA Y:PR 15 Y Y PR 6 Y N:PR 1 NPSI 2A 1 NI PRES $ SAFETY INJECTION PUtP 2 0-6 NA Y PR 15 Y Y PE 9 Y N:PR 1 MPSI 28 M1 PRESS SAFETY INJECTION PLMP 2 B6 NA Y:PR 15 Y Y PR 9 I Y N:PR 1 NYD 2A NYDRAZINE PUMPS 2 C 11 Y i
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| W:PR 1TW:PR 17 T PA 17 Y PR 14 N:Pt.1 NYD 28 NYDitAZINE PW@t 2 0 11 Y N PR 17N:PR 17 Y:PR-17 Y PR 14 N:PR 1 ICW 2A INTAKE C00 LING WATER PtMP 3 H4 K4 Y PR 11 Y Y Y:PR 13 N:Pt 1 I ICV 25 INT.*KE COOLING WATER PUw l
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| l 3 H7 NA Y:PR-11 Y Y Y:PR 13 N:PR*1 4
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| ICW 2C 1NThKE COOLING WATER PLMP e 3 H5 kA Y:PR 11 Y Y Y:PR 13 N:PR*1 LPsl 2A LD PRE 3$ 5AFETY INJECTION PUMP 2 E6 kA Y:PR 15 Y 7:PR 10 T PR 10 N PR 1 LPSI 25 LD PRESS SAFETY INJECTION PUMP 2 06 NA Y:PR 15 Y Y:Pt 10 Y PR 10 N:PR 1 l
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| i Revision 0 07/16/93 1
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| .- a Appendix B Pump Program Relief Requests l
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| , . - . - - . - - . . - - - - - - . . . . - _ ~ -- -- -- - --- - --
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| Revision 0 i 07/16/93 +
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| l t
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| RELIEF REQUEST NO. PR-1 COMPONENTS:
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| l All pumps in the Program !
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| l SECTION.XI REQUIREMENT.
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| The temperature of all centrifugal pump bearings outside the main flow path and of the main shaft bearings of I reciprocating pumps shall be measured at points selected to !
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| be responsive to changes in the temperature of the bearings, (IWP-3300, 4310) l BASIS FOR RELIEF: -
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| The data associated with bearing temperatures taken at one-year intervals provides little statistical basis for determining the incremental degradation of a bearing or any meaningful trending information or correlation.
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| In many cases the pump bearings are water-cooled and thus, bearing temperature is a function of the temperature of the cooling medium, which can vary considerably.
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| Vibration measurements are a significantly more-reliable indication of pump bearing degradation than are temperature measurements. All pumps in the program are subjected to vibration measurements in accordance with IWP-4500.
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| Although excessive bearing temperature is an indication of.
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| an imminent or existing bearing failure, it is highly
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| ~
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| unlikely that such a condition would go unnoticed during routine surveillance testing since it would manifest itself in other obvious indications such as audible noise, unusual vibration, increased motor current, etc.
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| Any potential gain from taking bearing measurements, which in most cases would be done locally using portable instrumentation, cannot offset the cost in terms of dilution of operator effort, distraction of operators from other primary duties, excessive operating periods for standby pumps especially under minimum flow conditions, and unnecessary personnel radiation exposure, i 4
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| B-1
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| 1 e e !
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| - - -'~~ ~ ~ ' ~ ~
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| }
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| Revision 0 i 07/16/93 j RELIEF REQUEST NO. PR-1 (cont.) I BASIS FOR RELIEF (cont.):
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| Based on the reasons similar to those set forth above, the ASME deleted the requirement for bearing temperature
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| '' measurements in ASME OM Code, gubsection ISTB, the revised version of the Code for pump testing.
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| ALTERNATE TESTING:
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| None.
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| I B-2
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| _ . . . . . . . . . ~ ~ ~ . . . _ - - - . - . - - ~ ~ - ~ ~
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| -- - - - - - - - + - - -
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| Revision 0 07/16/93 1
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| 1 RELIEF REQUEST NO. PR-3 '
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| i WITHDRhWN !
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| (Rev 0, 07/16/93) {
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| . I l
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| l 1
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| i t
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| i 1, _ _ . _ , _ _ . . . . _ . - - - - - - - - - - - - ' ~~ ~ ~~
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| Revision 0 07/16/93 RELIEF REQUEST NO. PR-4 COMPONENTS:
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| i Auxiliary Feedwater (AFW) Pumps 2A thru 2C (2998-G-080, Sh 2) '
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| SECTION XI REQUIREMENT:
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| Each inservice observation of test shall include all quantities in Tablethe measurement IWP-3100-1.and (IWP-3300)
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| Pump flow rate shall be measured during the test. (Table IWP-3100-1) '
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| '~
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| BASIS FOR RELIEF:
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| There are only two practical flow paths available for performing inservice testing of the AFW Pumps. These include the primary flow path into the main feed supply lines and thence to the steam generator, and the minimum-flow recirculation (mini-recire and bypass test loop) which returns to the condensate storage tank. The former is provided with flow rate measuring instrumentation however the mini-recire flow instrumentation. line is a fixed resistance circuit with no Pumping from the auxiliary feedwater system into the steam generators during plant hot operation is impractical and undesirable for the following reasons:
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| During auxiliary feedwater injection via the main afeedwater lines whiledifferential large temperature the plant is operating at power, (approximately 375 deg-F) could exist that would result in significant thermal shock and fatigue cycling of the feedwater piping and steam generator nozzles.
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| Based on the expected duration of the testing and the flow rate of the pumps (150 to 200 gpm), it is expected that the cooldown of the steam generator would induce cooldown.and contraction of the reactor coolant system resulting in undesirable reactivity variations and power fluctuations.
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| B-5 i
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| i
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| I p
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| _. 07/16/93 RELIEF REQUEST NO. PR-4 (cont.)
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| r ALTERNATE TESTING:
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| During quarterly testing of the AFW pumps while the pumps are operating through the. fixed-resistance mini-recirc line, pump differential pressure and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
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| During testing performed at cold shutdown, pump differential pressure, flow rate, and vibration will be measured and evaluated per IWP-3100 and IWP-3200. Testing during cold shutdowns will be on a frequency determined by intervals between shutdowns as follows: ;
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| ~
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| *~
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| For intervals of 3 months or longer.- each shutdown.
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| For intervals of less than 3 months - testing is not required unless 3 months have passed since the last shutdown test.
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| This alternate testing agrees with the requirements of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
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| 4 l
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| B-6
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| Revision 0 07/16/93 RELIEF REQUEST NO. PR-S COMPONENTS:
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| Boric Acid Makeup (BAM) Pumps 2A and 2B (2998-G-078, Sh 121)
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| ~~ "
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| SECTION XI REQUIREMENT:
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| Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.
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| (IWP-3300)
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| Pump flow rate shall be measured during the test. (Table IWP-3100-1) -
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| BASIS FOR RELIEF:
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| 1 There are three practical ' flow paths available for performing inservice testing of the BAM Pumps. These include the primary flow path into the charging pump suction header, a recirculation line leading back to the refueling water tank, and the minimum-flow recirculation (mini-recirc and bypass test loop) which returns to the BAM Tanks. None of these flow paths is totally satisfactory for the following reasons:
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| Operating the BAM Pumps discharging into the charging pump suction header requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps.
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| This, in turn, would result in the addition of excess boron to the RCS. This rapid insertion of negative reactivity would result in a rapid RCS cooldown and depressurization. A large enough boron addition would result in an unscheduled plant trip and a possible initiation of Safety Injection Systems.
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| During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS.
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| The waste management system would be-overburdened by the large amounts of RCS coolant that would require processing to decrease its boron concentration.
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| B-7 I
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| I
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| i I
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| , Revision 0 07/16/93 1 1
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| RELIEF REQUEST NO. PR-5 (cont.)
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| The second circuit recirculates water to the Refueling Water Tank (RWT) or the Volume Control Tank (VCT).
| |
| During normal plant operation at power it is j undesirable to pump to the RWT and deplete the BAM Tank inventory.-
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| '' One of the two BAM Tanks is maintained at Tech. Spec. level while the other is used as required
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| +
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| for plant operation. The Tech. Spec. B7W Tank cannot be pumped from because it must be :ncintained at a . level near the top of the tank.
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| The other BAM Tank's level will vary from test to test by as much as 15 to 20 l feet. This variance in pump suction pressure will have l
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| ' a direct affect on pump head and flow such that test l repeatability would be questionable. -
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| The minimum-flow recirculation flow path is a fixed i resistance circuit.- No flow rate measuring !
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| instrumentation is installed in this line. Pumping boric acid from tank to tank would be possible but the i
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| ' flow rates would be small, limiting pump operation to l the high head section of the pump curve. In addition, one of the two BAM Tanks is maintained at Tech. Spec.
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| ' level while the other is used as required for normal plant operation. The Tech. Spec. BAM Tank cannot be puxaped from because it must be maintained at a level near the top of the tank. This narrow band limits the amount that can be pumped to it or from it to only a few hundred gallons. The other BAM Tank's level will as 15will'have to 20 feet.
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| vary from test to test by as mu This variance in pump suction pch ressure a direct affect on pump head and flow such that test i l
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| repeatability would be questionable.
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| l e
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| 9 J
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| B-8 d
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| W ,
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| l Revision 0 !
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| _ 07/16/93 I RELIEF REQUEST NO. PR-S (cont.)
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| ALTERNATE TESTING:
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| During quarterly testing of the BAM pumps, while the pumps are operating through the fixed-resistance mini-recirc line, pump differential pressure and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
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| During pump testing performed differential at each pressure, reactor flow rate, refueling and outage,be vibration will '
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| measured and evaluated per IWP-3100 and IWP-3200.
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| This alternate testing agrees with the requirements of NRC'-- .
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| Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
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| 9
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| ?
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| O i l
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| I I
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| B-9 1 1
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| I 1
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| 9 o T
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| l_...._.,..-. . - _ - . - - - - - -- - - - - - - - - - - - ~
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| 07/16/93 :
| |
| RELIEF REQUEST NO. PR-6 1 COMPONENTS:
| |
| Containment Spray (CS) Pumps 2A and 2B (2998-G-088)
| |
| 'SECTION XI REQUIREMENT:
| |
| Each inservice observation of test shall include all quantities in Table the measurement IWP-3100-1.and (IWP-3300)
| |
| Pump flow rate shall be measured during the test. (Table IWP-3100-1)
| |
| BASIS FOR RELIEF: -
| |
| There inservice aretesting two practical of the CS flow paths available for performing Pumps.
| |
| pumps borated water from the RWT to the RCS via the low- These include one that pressure injection header and the other, minimum-flow recirculation (mini-recire and bypass test loop) which returns to the RWT.
| |
| The first would require modifying the shutdown cooling lineup while in cold shutdown; however, the shutdown cooling system cannot provide sufficient letdown flow to the RWT to accommodate the necessaryfull core design cooling flowfunction.
| |
| from the RWT while maintaining Thus, the only practical time for testing these pumps via this flow path is during refueling outages when water from the RWT is used to fill the refueling cavity.
| |
| The rainimum-flow recirculation flow path is a fixed resistance circuit containing a flow limiting orifice however no flow rate measuring instrumentation is installed.
| |
| l ALTERNATE TESTING:
| |
| \
| |
| The CS pumps are operated through the fixed-resistance mini-recire line during the quarterly pump testing. Pump differential pressure and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
| |
| B-10
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| I 1
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| . . - - . . . - . - - - . - - - - .- ---- - - - - - -- - - - ~ ^ ~ ~
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| Revision 0 07/16/93 i
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| RELIEF REQUEST NO. PR-6 (cont.)
| |
| ALTERNATE TESTING:(cont.)
| |
| Duringdifferential pump the pump pressure, testing performed each reactor refueling, flow rate, and vibration will be measured and evaluated per IWP-3100 <
| |
| and IWP-3200.
| |
| This alternate testing agrees with the requirements of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
| |
| 9 I
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| j l
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| B-11 1
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| I
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| , ,, I
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| ~
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| i l
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| 1 l
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| Revision 0 l 07/16/93 RELIEF REQUEST NO. PR-7 l I
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| l 1
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| 1 WITHDRhWN (Rev 0, 07/16/93) :
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| - l 1
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| I 1
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| 1 i
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| 1 l
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| 1 l
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| 1 l
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| l l
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| l 1
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| l l
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| i B-12 l
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| _ _ _ _ _ . _ _ .. . .. . -.----- - - - - - - - - - - - - - - - - - - - - - ' ~ ~ ~ ~
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| Revision 0 l 07/16/93 l
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| . I RELIEF REQUEST NO. PR-8 i COMPONENTS: I Boric Acid Makeup Pumps 2A and 2B (2998-G-078, Sh 121)
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| SECTION XI REQUIREMENTS: ,
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| 1 Each inservice test shall' include the measurement and observation bearing of all quantities in Table IWP-3100-1 except temperatures, which shall be measured during at least one inservice test each year. (IWP-3300) {
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| t i
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| ; BASIS FOR RELIEF: I The system installation does not measuring pump suction pressures, provide and thus, anythe mechanism for requirement for measuring suction pressure and pump differential ;
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| pressures cannot be satisfied. A measure of pump suction pressure can, however, be determined by a calculation using the height of liquid in the boric acid makeup tanks. Since there is essentially fixed resistances between the tanks and the pumps this will provide a consistent value for suction pressures.
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| I Since the tank levels are not expected to vary significantly during the tests, tank levels and associated calculations will only be taken once during each test instead of prior to pump operation and during operation as required by Table IWP-3100-1.
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| j ALTERNATE TESTING:
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| The boric acid makeup pump suction pressures will be calculated based on the height of liquid in the associated tank once during each inservice test. Subsequently, these calculated values will be used to determine pump differential pressures for evaluation of pump parameters.
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| D B-13 l I
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| o o
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| , - . . _ _ . . . - - . . - . . - - - - - - - - - - - - - - - - - - - ~-- - - - - ~
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| Revision 0 07/16/93 RELIEF REQUEST NO. PR-9 COMPONENTS:
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| High Pressure Safety Injection (HPSI) Pumps 2A and 2B (2998-G-078, Sh 130)
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| SECTION XI REQUIREMENT:
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| Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1.
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| (IWP-3300)
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| BASIS FOR RELIEF:
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| During quarterly testing of the HPSI Pumps, the pumps cannot develop sufficient discharge pressure to overcome reactor coolant system (RCS) pressure. Flow is routed through a minimum flow test line leading to the refueling water tank (RWT). This line has no installed flow rate measuring instrumentation and measuring flow rate during quarterly testing is not practical.
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| During cold shutdown conditions, full flow operation of the HPSI pumps to the RCS is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.3.
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| NRC Generic Letter 89-04, Position 9, allows elimination of minimum flow test line flow rate measurements providing inservice tests are performed during cold shutdowns or refueling under full or substantial flow conditions where pump flow rate is recorded and evaluated.
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| ALTERNATE TESTING:
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| During quarterly testing of the HPSI Pumps, pump differential pressure and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
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| During testing performed at each reactor refueling, pump differential pressure, flow rate, and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
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| This alternate testing agrees with the guidelines of NRC Generic Letter 89-04, Position 9 and, as such, is considered to be approved upon submittal.
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| B-14
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| = 6 l
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| Revision 0 07/16/93 RELIEF REQUEST NO. PR-10 COMPONENTS:
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| Low Pressure Safety Injection (LPSI) Pumps 2A and 2B (2998-G-078, Sh 131) ,
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| j
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| '~ '
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| SECTION XI REQUIREMENT: l l
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| Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1. l l
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| (IWP-3300) i i
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| BASIS FOR RELIEF:
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| )
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| .- l During quarterly testing of the LPSI pumps, the pumps cannot l develop sufficient discharge pressure to overcome reactor j coolant system (RCS) pressure. Flow is routed through a minimum flow test line leading to the refueling water tank !
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| (RWT). This line has no installed flow rate measuring instrumentation and measuring flow rate during quarterly i
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| {
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| testing is not practical. 1 i
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| During cold shutdown, the LPSI pumps are used for residual heat removal. The substantial flow tests can be performed at this time. Pump differential pressure and flow rate will be recorded. However, induced vibrations in the system piping while the reactor coolant pumps (RCPs) are running mask any meaningful LPSI pump vibration data.
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| ALTERNATE TESTING:
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| During quarterly testing of the LPSI Pumps, pump differential pressure and vibration will be measured and evaluated per IWP-3100 and IWP-3200.
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| Substantial flow testing will be performed during cold j shutdowns. Pump differential pressure, flow rate, and 1 vibration (if RCPs secured) will be measured and evaluated per IWP-3100 and IWP-3200. Testing will be on a frequency determined by intervals between shutdowns as follows:
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| For intervals of 3 months or longer - each shutdown. ,
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| For intervals of less than 3 months - testing is not required unless 3 months have passed since the last shutdown test.
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| B-15
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| e A Revision 0
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| -. 07/16/93 RELIEF REQUEST NO. PR-12 COMPONENTS:
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| Reactor Coolant Charging Pumps 2A, 2B, and 2C SECTION XI REQUIREMENT:
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| .c The frequency response range of the readout system (for instrument used to measure vibration amplitude) shall be from one-half minimum speed to at least maximum pump shaft -
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| rotational speed. (IWP-4 520 (b) )
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| BASIS FOR RELIEF:
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| The reactor coolant charging pumps operate at approximately ~
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| 210-215 rpm which equates to a rotational frequency of 3.5 Hz. In accordance with the ASME Code, the frequency response for the vibration instruments would have to be one half of this or 1.75 Hz. Following an investigation of available and potentially suitable instrumentation, it has been determined that instruments satisfying this requirement for the charging pumps are not commercially available. 3 ALTERNATE TESTING:
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| l For an interim period of seven months (March 1994), during 1 testing of these pumps, vibration will be measured as required by IWP-4510, except that the lower frequency response for the instruments will be 10 Hz. During this time efforts will be made to procure Code-acceptable instrumentation or justify the continued'use of non-conforming instruments.
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| l l
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| B-17
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| - _ . _ _ _ _ . . _ _ . . . . . _ . _ .. . _ _ _ _ ~ . ._ __
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| e &
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| i Revision 0
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| _ 07/16/93 RELIEF REQUEST NO. PR-13 COMPONENTS:
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| Intake Cooling Water Pumps 2A, 28, and 2C
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| "~
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| SECTION XI REQUIREMENT:
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| a The frequency respanse range of the readout system (for instrument used to measure vibration amplitude) shall be from one-half minimum speed to at least maximum pump shaft rotational speed. (IWP-4520(b))
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| BASIS FOR RELIEF:
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| The St. Lucie Plant completed a major . upgrade to its ASME '~
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| pump vibration program in August 1991 to better comply with the Code. As part of the upgrade, new vibration instruments were purchased. The instruments were chosen for their ease of use and reliability; however, the instrument's lower frequency response does not comply with the Code when used on the Intake Cooling Water pumps. The intake cooling water pumps operate at a shaft speed of approximately 885 rpm.
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| Based on this speed and the Code requirement, the instrumentation used to measure vibration (displacement) would require a response range down to 7.38 hz. The existing instruments are capable of a lower frequency response to 10 hz, 2.62 Hz higher than the Code.
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| ALTERNATE TESTING:
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| For an interim period of seven months (March 1994), during testing of these pumps, vibration will be measured as required by IWP-4510, except that the lower frequency response for the instruments will be 10 Hz. During this time efforts will be made to procure Code-acceptable instrumentation or justify the continued use of non-conforming instruments.
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| B-18
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| o 4 l
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| Revision 0 i 07/16/93 I
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| RELIEF REQUEST NO. PR-14 l COMPONENTS:
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| Hydrazine Pumps 2A and 2B L
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| .- -SECTION XI REQUIREMENT: ,
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| The frequency response range of the readout system (for
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| ' instrument used to measure vibration amplitude) shall be i from one-half minimum speed to at least maximum pump shaft rotational speed. (IWP-4 520 (b) )
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| BASIS FOR RELIEF: 1 The hydrazine pumps are characterfzed as metering pumps and - l operate at extremely slow speed (as low as 37 rpm). This equates to a rotational frequency of 0.62,Hz. In accordance with the ASME Code, the frequency response for the vibration instruments would have to be one half of this or 0.31 Hz.
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| Instruments satisfying this requirement for the hydrazine pumps are commercially unavailable.
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| Low frequency vibration of these pumps is considered to be relatively insignificant. Any binding or excessive bearing wear within these pumps would be discovered by audible noise 4
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| gearing.
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| or excessive vibration at the driver and reduction ALTERNATE TESTING:
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| ' For an interim period of seven months (March 1994), during testing of these pumps, vibration will be measured as required by IWP-4510, except that the lower frequency i response for the instruments will be 10 Hz. During this time efforts will be made to procure Code-acceptable )
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| instrumentation or justify the continued use of non-conforming instruments.
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| 1 B-19 1
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| o 4
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| Revision 0 07/16/93 RELIEF REQUEST NO. PR-16
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| '' a WITHDRAWN \
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| (Rev o, oy,3g,93) l I
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| B-21
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| e d Revision 0 07/16/93 RELIEF REQUEST NO. PR-17 COMPONENTS:
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| Hydrazine Pumps 2A and 2B (2998-G-088)
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| __ SECTION XI REQUIREMENTS: ,
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| Each inservice test shall include the measurement and observation of all quantities in Table IWP-3100-1 except bearing temperatures, which shall be measured during at least one inservice test each year. (IWP-3300)
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| Symmetrical damping devices or averaging techniques may be used to reduce instrument fluctuations to within 2% of the - -
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| observed reading. (IWP-4150)
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| BASIS FOR RELIEF: ,
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| The Hydrazine Pumps are positive displacement pumps with a variable speed drive. They operate at a very low rpm and ,
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| flow rate (0.71 to 0.82 gpm). The flow instrument orifice :
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| is located in the pump's suction line. Its output signal pulsates sharply with each stroke and cannot readily be averaged. The flow recorder for the hydrazine pumps, FR !
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| 2-2, displays a wide trace for flow rate. The only way to :
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| know the true flow rate of the pumps is to collect the pumps output in a container and measure it.
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| )
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| During the 1992 Unit 2 refueling outage, several flow tests per hydrazine pump were performed. The discharge of one l pump was directed to a container of a known volume. The amount of time to fill the container was measured and then l used to calculate an average flow rate for the pump. Each l of the flow tests for each pump were performed at a different pump rpm. A correlation between pump rpm and average flow rate was developed and compared to the expected value. The measured and the expected correlations between rpm and flow rate were in close agreement. The expected correlation was based upon piston diameter, piston stroke, and pump rpm. Based upon these results, hydrazine pamp flow rate can be accurately set by selecting the proper pump rpm.
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| B-22
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| e 4 Revision 0
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| _- 07/16/93 RELIEF REQUEST NO. PR-17 (cont.)
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| BASIS FOR RELIEF (cont.):
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| Frequent performance of the above mentioned flow testing can not be performed. Hydrazine is a highly flammable liquid with cumulative _ toxic affects'when absorbed through the skin, inhaled, or ingested. It has also been identified as a known carcinogen.
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| ALTERNATE TESTING:
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| During the quarterly pump tests, each pump's rpm will be -
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| measured to verify the required flow rate of 0.71 to 0.82 gpm. Pump flow will be recorded but not alert trended and vibration will be measured during the quarterly tests.
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| During each refueling outage at least one flow test will be performed for each pump to verify proper performance. Pump vibration will be measured during this flow test.
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| B-23
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| e 4 l
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| .- . .. . _ . . - - - . . - - . . . . - . . . - - . - . - - - . . ~ . - - . . - -. - - - ..
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| .- a Appendix C i Valve Program Tables l 1
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| * 4 j l
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| Revision 0 07/16/93 Florida Power & Light Company INSERVICE TESTING - VALVE TABLES St. Lucie Nuclear Plant - Unit 2
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| .............................................. AGE P
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| : 1
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| ,, LEGEND i
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| VALVE NUMBER The plant alpha-numerical designator for the I subject valve COORD The coordinate location of the valve on the designated drawing CL The ISI Classification of,the valve as per the -
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| respective ISI boundary drawings CAT The valve category per-Paragraph IWV-2200 SIZE I The valve's nominal size in inches '
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| TYPE The valve type A/P The active (A) or passive (P) determination for the valve.
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| ACT. TYPE The valve actuator type as follows:
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| AO Air-operated DO Diaphragm-operated MO Electric motor-operated MAN Manual valve PO Piston-operated S/A Self-actuated SO Solenoid-operated NORM POS. Designates the normal position of the valve during plant operation at power REM IND Notes if a valve has remote position indication FAIL MODE Identifies the failure mode (open or closed) for a
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| . valve. FAI indicates the valve fails "as is".
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| 9
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| . . .- . = . . - - . .- -. . . - . - . _ - - . - - - ... - - . . - - - _ - - . .
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| . 4 i
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| l 1
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| _ . . _ . . - - - - - - - - - - - - - -- 1 Revision 0 07/16/93 Florida Power & Light Company INSERVICE TESTING.- VALVE TABLES _._ _ ..
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| St. Lucie Nuclear Plant - Unit 2 PAGE : 2 j
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| ..............--=.-=.---. == .....--. =====.-==.--...............
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| ............---========-.....-------========.....................
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| .- LEGEND (Cont.)
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| EXAM Identifies the test requirements for a valve as follows:
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| CV/. Check valve exercise to closed position.
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| ' C'J/ C Check valve full-stroke exercise to open position.
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| CV/PO Check valve partial-stroke exercise to - .-
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| open position.
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| . EC Exercise to closed position. For all category A or B power-operated valves ;
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| stroke times will be measured unless i excluded by an associated relief request.
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| EE Exercise valve to verify proper operation and stroking with no stroke time measurements. Requires observation of system parameters or local observation of valve operation. !
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| EO Exercise to open position. For all category A or B power-operated valves stroke times will be measured unless excluded by an associated relief request.
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| FS Fail safe test INSP Disassembly and inspection of check valves PEC Partial closure exercise for power-operated valves PI Position indication verification '
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| SLT-1 Seat leakrate test per 10 CFR 50, App J SLT-2 Seat leakrate test for pressure isolation valves.
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| SRV Set point check for safety / relief valves
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| .-. . . . . _ . . . - - . - .. . ~ . - . .. . _ _ . . - . _ . . ..-
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| 1 e &
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| i
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| - - -gevTsion 0 4 _ 07/16/93 4
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| 1 i Florida Power & Light Company '
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| INSERVICE TESTING - VALVE TABLES ~~ ~
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| l St. Luci~e' Nu~cl~e~ar ~ Plant''- Unit 2 PAGE : 3 1
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| LEGEND (Cont.)
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| TEST FREQ The required test interval as follows:
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| QR Quarterly (during plant operation)
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| CS Cold shutdown as defined by Technical Specification 2Y 'Every 2 years RF Each reactor refueling outage (cycle). In the case where this is designated for safety / relief valves ANSI /ASME OM-1-1981 ,
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| i SP Other (See applicable Request for Relief) i l
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| RELIEF REQ Refers to the specific relief ~ request associated l' q
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| 4 with the adjacent test requirement. (See Appendix D) i 1
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| mr
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| o 4 l
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| l
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| ' ..................... .......n ........ . .. w......... ..
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| FLORIDA POWR AW LIG!IT COWANY VALVE TABLES REVISION: 0 Saint Lucie musteer Plant - thit 2 DATE : 07/16/73
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| . .. . r PAGE : 4
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| . .. . ..= u.. ... n P & ID: 2996 6 07B SN 107 SYSTEM: REACTOR C00
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| .... u........ .. .... n . n....... n.. = ..u .LANT SYSTEN
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| ..w..n..u...=.......w...
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| VALVE NUMBER ACT. NORM RDL FAIL TEST RELIEF C00W. CL CAT. SIZE TYPE A/P TYPE P EXAN
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| ............... ...... .. .... ...... ...... ... ...... 08. IIS NODE V 1460 PRE 0 REG. P8staEE 6-4 2 8 1.000 SLOSE A 30 LC YES PC EO CS IT
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| . . . . . . . . .G6. . . 2. .B . . . . . . . . . . . . . . . . . . . . . PI.................
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| V.1461 1.000 GLost A Sif LC YES FC E0 CS
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| . . . . . . . . .E6. . . 2. .8 . . . . . . . . . . . . . . . . . . . . . Pt.................
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| V 1462 2Y 1.000 CLOSE A $0 LC YES FC EO CS
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| . . . . . . . . .E6. . . 2. .5 . . . . . . . . . . . . . . . . . . . . . Pt.................
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| V-1463 2Y 1.000 GlosE A So LC YES FC E0 CS i 27
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| . . . . . . . . .04. . . 2. s. . . . . . . . . . . . . . . . . . . . . . P!.................
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| V-1464 I
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| 1.000 GlosE A 30 LC YES FC EO CS - .
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| . . . . . . . . .E4. . . 2. .5 . . . . . . . . . . . . . . . . . . . . . PI.................
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| V 1465 2Y 1.000 closE A SC LC YES FC E0 CS 2f
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| ...................................Pt V 1466 G5 .................
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| 2 5 1.000 Glost . A SO LC YES FC E0 CS
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| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Pt ................
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| 2T 1
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| I i
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| a
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| -. _ - . . . . . . . .. _ _ . . ~ . . . . . _ . . . . _ . - . _ . . ..__. _ - _ . . - . . . - . _ _ _ . . . . . . . - .-. . .-
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| I e-J i
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| i 1
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| ' ae..- .e ..e ....e. e. e......e.ea..... ee .....
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| FLORIDA POWR AS LIGilf Cof*ANY. e VALVE TABLES REVISION: 0 Saint Lucie mueteer Plant - Imit 2 DATE : 07/16/93 PAst : 5 P & 10: 2998 8 078 su 100 ...-.--.e..... .
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| ...m.. . .._
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| SYSTEN: REACTOR C00LANT STSTW
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| _ . _ . . .- ... e. . ..e. ...
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| VALVE 1M eER ACT. IIORN REN FAIL TEST RELIEF C002. CL CAT. SIIE TYPE A/P TYPE POB. Im I V 14M
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| .........................................ESE F6 1 8 EXAN FRES REG.
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| RM 3.000 eLost A 30 C YES FC EO CB IT
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| . . . . . . . . .D-6. . . 1. B. . . . . . . . . . . . . . . . . . . . . . Pt.................
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| V 1475 3.000 GLOSE A SF C YES FC EO CS 27
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| . . . . . . . . .Fa5. . . 1. B. . . . . . . . . . . . . . . . . . . . . . P!.................
| |
| V 1476 3.000 CATE A 14 0 0 YES FAI EC QR 21
| |
| . . . . . . . . .D5. . . 1. .5 . . . . . . . . . . . . . . . . . . . . . P1 V 1477 .................
| |
| 3.000 GATE A 18 0 0 TES FAI EC QR
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Pt 27 O
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| d 9
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| 6
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| \
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| \
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| \
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| f 9
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| e l
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| ._ ._ - - -- - . . - - . - . _ _ - _ _ . - . . _ . . . _ _ _ _ ._. - . .- . _ ~ . . .
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| 9 4 4
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| i i
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| i 1 - - - - - - - - -- -- _ _ _ - _ _ . . _ _ . _ _ _ _ _ _ _ , _ ____
| |
| , e ssessenesseeeeeeeeeeeeeeeeeeeeeeeee eeeeeeee s ee' sseee FLORIDA PohER AW LIGNT COMPANY eeeeeeee eee ss e eeeeeeeeeeeeeees i
| |
| VALVE TABLis REVISION: 0 Saint Lucie musteer Plant . LMit 2 DATE : 07/16/93
| |
| _a _see- PAGE 6 P & 10 2998 8 0 M SN 109 _seme n u me n e= = = esseessesso useu en enes seesmessmene . e e- SYSTEN: REAC104 C00LANT SYSTEN
| |
| :eessessesseeweesenesesammes seeeeeneessemennessemeen 'oeusase'esees WALVE taseEt ACT. MORM REN FAIL TEST REllEF COORD. CL CAT. SIZE TYP
| |
| ............... ...... .. .... ...... ....E.. A/P TYPE PCB. l e MODE EXAN
| |
| ... ...... .... FRES RES. RE MRE V 1209 46 1C ... .... ......... .... ...... ........S...
| |
| ................ .3.000
| |
| . . . .SArtT
| |
| .T A S/A C to SRV RF V 1201 E6 1C 3.000 SAF ..............................
| |
| A S/A C
| |
| # .V 1202
| |
| . . . . . . . . . . . . . . . . . . . .ETY ......r.
| |
| NO SRV RF G6 1C 3.000 SAFETY ........................
| |
| .......................A $/A C NO StV RF 4
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| h i
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| 4 6
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| e l
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| i i
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| 1 i
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| 4 s
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| Y i
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| J l
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| v it 4
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| 4 i
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| . _ . . - _ _ ._ . . _ . . . _ . . _ - _ . _ _ . . . _ _ _ . . _.-. _._._m . _ _ . . . _ . . . _ _ _ _ . _ .
| |
| 9 4 a
| |
| 2
| |
| .......... .m u s.
| |
| ... u n w .. = = ..n u ... us w .... ... . n = . u .... ..... n...
| |
| FLORIDA POWER As LIGNT COMPANY ~ ..
| |
| VALVE TABLES REYlSION: 0 l Saint Lucie mueleer Plant . Unit 2 DATE : 07/14/93
| |
| .. PAIE : ?
| |
| r.......u.---- . = . ...--
| |
| P E ID: 2998 G 078 SN 120 $7sfEM: CNEMICAL AW VOLLM CON 1ROL
| |
| ............= u.... ..........n....n. .___
| |
| __.-__n..=..........n...
| |
| ACT. NonM REN FAIL TEST RELIEF WALVE IUseER C00 5 . CL CAT. SIZE TYPE A/P TYPE POS. le MB EXAM V 23A5 F8
| |
| .. .... ...... ...... ... ...... .... ... ...E. ......... .... FRE4 RES.
| |
| estatus 3 C
| |
| . . . . . . . . . . . . . . . . .2.000 V 2522 ET
| |
| . . . RELIEF . . . . . A. S/A . . .C. . .to. /A N 3RV RF 2 A 2.000 Stoet A DO O YES FC EC CS
| |
| < FS CS Pt 27 2f
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SLT v 2531 1
| |
| G5 3 C
| |
| . . . . . . . . . . . . . . . . .2.000 . . . aELIEF . . . . . A. 5/A . . .C. . .N0. N/A SRY RF e
| |
| l l
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| l
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| ~
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| FLtml0A POWR Am LIGNT COWANY - REVISION: 0 VALVE TABLES DATE : 07/16/93 ,
| |
| Saint Lucie Mustew Plant . Unit 2 Pact : 3 l P & 10 2908 6 075 SN 121 SYSTEM: CNENICAL Am WOLLSE CONTROL
| |
| ..... j ACT. NORM REN FAIL TEST RELIEF VALVE IRMBER 000se. CL CAT. SIZE TYPE A/P TYM POS. I m McDE EMAN FRES RE4. REMARKS FCV-2210f C2 25 1.000 GLOBE A 00 C YES PC RC - M F8 M PI 27
| |
| " .................................................... I V 2115 F5 3 C 4.000 RELIEF A SM C NO BRV RF V 2118 F-4 2C 4.000 CHECK A S/A 0 NO CV/0 GR V 2177 C3 2 C 3.000 CNECK A S/A C NO CV/0 RF VR 5 ,
| |
| CV/PO CS VR 5 V 2190 06 2 C 3.000 CNECK A S/A C NO CV/C QR VR 5 j CV/0 RF VR 5 CV/PC CS VR 5
| |
| ...................................................;'~ -
| |
| v 2191 E3 2 C 3.000 CNECK A S/A C NO CV/o RF VR 5
| |
| , CV/PC CS VR 5 V 2311 F3 2C 0.500 RELIEF A $/A C NO SRV RF v 2443 C4 2 C 3.000 CNECK A S/A 0 NO CV/C GR CV/O RF VR 6 CV/PO GR VR 6 v 2444 B4 2C 3.000 CNECK A $/A C NO CV/C GR CV/0 RF VR 6 l CV/P0 QR VR-6 V 2446 75 3 C 0.750 RELIEF A S/A C NO N/A SRV RF ;
| |
| .................................................... l V 2447 F5 3 C 0.750 RELIEF A S/A C N0 N/A SRY RF V 2501 F-4 2 3 4.000 CATE A No 0 YES FAI EC CS E0 CS Pt 27 V 2504 F3 2 8 3.000 GATE A No C YES FAI EC QR EO QR Pt 2Y V 2505 G7 2 A 0.750 CLost A 00 0 YES FC EC CS FS CS Pt 2Y SLT 1 2Y
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| : n. .... .. . . .
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| FLORIDA POWS AW LIGNY 039ANY ... ..........
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| ~ ....
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| VALVE TABLES REVISION: 0 Saint Lucie Euclear Plant
| |
| * Lhlt 2 DATE : 07/16/93 PAGE 9-
| |
| __w . u... ..
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| P & ID: 2998 0 078 me -CN - 121 (cont) SYSTBet CNEMICAL AW VOLL8E CONTROL
| |
| --u...--...............n.....
| |
| ACT. NORM KEN Fall WALVE tapett TEST RELIEF
| |
| ..............~ ...... '400AD...CL.... CAT. SIN ....E..
| |
| ...... YYP A/P TYPE POB. l a MODE ERAN PR Age. WetMR V 2507 n7 25 ... ...... .... ... .... ......... ..ES 0.750 E 0BE A 00 .. ...... ........ .
| |
| LO YES 70 EC GR
| |
| . . . . . . . . .C6. . . 2. .e . . . . . . . . . . . . . . . . . . . . . P1 V 2508 2Y 3.000 GATE A NB C YES FAI EO QR
| |
| . . . . . . . . .C7. . . 2. .8 . . . . . . . . . . . . . . . . . . . . . P3 v 2509 2Y 3.000 GATE A No C YES FAI E0 et
| |
| . 2514 V . . . . . . . .C3. . . 2. .8 . . . . . . . . . . . . . . . . . . . . . Pt 2Y 3.000 GATE A NO C YES FAI EO et
| |
| . 2524 V . . . . . . . .F7. . . 2. .A . . . . . . . . . . . . . . . . . . . . . Pt 2Y 0.750 CLosE A 00 0 YES FC EC CS F8 CS "
| |
| PI 2Y
| |
| . . . . . . . . .E.4 v 2525 . . . .3 .8. . . . . . . . . . . . . . . . . . . . . SLT 1 2Y 4.000 GATE *A NO C YES FAI EC 04
| |
| , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Pt.................
| |
| Y 2526 2Y E3 2C 4.000 CNECK A S/A C NO CV/O RF VR 5
| |
| . . . . . . . . . B4 V 2650
| |
| . . . .2. 0. . . . . . . . . . . . . . . . . . . . . CV/PO CS VR 5 1.000 CLosE A 00 0 YES FC EC QR FS QR
| |
| . . . . . . . . .04. . . 2. .8 . . . . . . . . . . . . . . . . . . . . . PI 2f V 2651 1.000 CLOSE A DO O YES FC EC 04 FS OR
| |
| . 2674 V . . . . . . . .F4. . . 3. C. . . . . . . . . . . . . . . . . . . . . . Pt 2Y 4.000 CHECK $/A 0 WO
| |
| .......................A............................. CV/0 Qt O
| |
| * s J
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| i FLORIDA POWER AW LIGNT COMPANY ~
| |
| ! YALVE TABLES REVISl0N 0 Saint Lucie Nuclear Plant . Unit 2 DATE : 07/16/93 PAN : 10 P & ID: 2998 G 078 SN 122 SYSTEN CNENICAL AW VOLL5E CONTROL ACT. NORM REN Fall TEST RELIEF VALVE BRMBER C00AD. CL CAT. SIZE TYPE A/P TYPE P08. I m NODE EXAM FR RES.
| |
| ............... ...... .. .... ...... ...... ... ...... .... ... .... ......... ..ES.. ...... RENRRES SE*02 01 C.7 13 2.000 GLOBE A SO O YES PO EC GE 80 GR FS OR P1
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2Y...........
| |
| SE 02 02 57 1B 2.000 GLOSE A SO O YES 70 EC QR EO QR FS QR PI 27 SE 02 03 D7 18 2.000 CLORE A 30 LC YES FC EC CS EO CS FS CS PI 2
| |
| .........................................Y...........
| |
| SE 02 04 07 1 8 2.000 Clost A So LC TES FC EC CS
| |
| . E0 CS FS CS Pl 2
| |
| ........................................ 1...........
| |
| V 2167 G2 2C 2.000 CNE W A S/A C NO CV/C et CV et
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . /0 ................
| |
| V 2168 E2 2C 2.000 CNECK A $/A C NO CV/C QR CV/0 QR Y 2169 C2 2C 2.000 CNECK A $/A C NO CV/C QR CY/0 QR Y 2318 E3 2 C 0.500 RELIEF A S/A C NO SRV RF Y-2321 D3 2C 0.500 RELIEF A $/A C WO SRV RF Y 2324 C2 2 C 1.500 RELIEF A $/A C NO SRV RF E2 Y 2325 2C 1.500 RELIEF A S/A C N0 SRV RF Y 2326 G2 2C 1.500 RELIEF A $/A C WO SRV RF Y 2340 G1 2 8 2.000 GATE A MAN C WO FAI EE QR V 2431 08 1C 2.000 CNECE A $/A C NO CV/0 CS Y 2432 C8 1 C 2.000 CNECK A S/A 0 No CY/0 QR
| |
| * a i
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| 1 FLORIDA POWR AIS LIGNT COWAlff _- REvistou 0 I VALVE TASLES '
| |
| DATE : 07/16/93 saint Lucie Nuclear Plant imit 2 PAGE : 12
| |
| : n. - --.:
| |
| P & ID 2998 8 078 SN 130 SYSTEM: SAFETY INJECTION SYSTEM
| |
| .... ... . ..... . u. .=.. .. - . .. ......... u -.
| |
| ACT. WORM REN Fall TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TVPE Pos. las MtDE EXAM FRES REO. REMARKS FCV 3301 E2 25 10.000 IUTFLT A MO LO YES FAI EC GR PI 27 FCV 3306 F-4 2 8 10.000 SUTFLY A MO LO YES FAI EC GR e
| |
| NCV 3512 E2 2 0 10.000 BUTFLY A MO LC YES FAI EO P1 27 GR PI 27 MCV 3657 F4 2 3 10.000 SUTFLY A No LC YES FAI EO QR Pt 27 SE 03 2A G2 2 A 2.000 GLost A 50 C YES FC EC QR EO OR FS QR -
| |
| PI 2f SLT 1 2f VR 4 SE 03 28 G2 2 A 2.000 CLosE A 30 C YES FC EC QR EO QR FS OR PI 2T SLT 1 27 VR-4 SR 03 1 A6 3 C 0.750 RELIEF A S/A C NO SRV RF SR 03 2 A5 3 C 0.750 RELIEF A S/A C N0 SRV RF SR 07 1A E-7 2C 0.750 RELIEF A $/A C NO SRV RF SR 0715 D8 2 C 0.750 RELIEF A S/A C NO SRV RF V 07000 F7 2 C 14.000 CHECK A S/A C NO CV/0 RF VR 7 CV/PO QR VR 7 v 07001 E7 2C 14.000 CHECK A $/A C NO CV/0 RF VR 7 CY/P0 QR VR 7 V 3101 M3 3 C 2.000 CNECK A S/A C WO CV/0 RF VR 32 CV/P0 CS VR 32 V 3102 06 2 C 2.000 CHECK A S/A C NO CY/PO GR VR 30 INSP RF VR 30 6
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| , FLORIDA P0lER AGE LIGNT COWANY - REYisl0N: 0 4 VALVE TABLES DATE : 07/16/93 4 Saint Lucie Nuclear Plant Unit 2 PAM 13 1
| |
| s P 8 ID: 2998-4 078 BR 130 (cont) SYSTm: SAFETY INJECTION SYSim
| |
| 'KCT.~ Te0AN DEN FAIL TEsf RELIEF VALVE IEseER COORD. CL CAT. SIZE TYPE A/P TYPE POS. Its NODE EMAM FRES REO. RENRRES
| |
| ............... ...... .. .... ,. a . ...... ... ...... .... ... .... ......... .... ...... ....... ..
| |
| V 3103 0-5 2 C 2.000 Cuat A S/A C NO CW/PO et VR.30 INSP GF VR 30 V 3104 E6 2 C 2.000 CNECK A S/A C NO CV/C W CV/0 AF VR-28 CV/PO GR VR 28 l V 3105 D6 2 C 2.000 CHECK A S/A C NO CV/C GR
| |
| : CV/0 RF VR 28 CV/P0 GR VR 28 1 V 3106 F5 2 C 10.000 CNECK A S/A C NO CY/0 CS
| |
| $ CV/PC QR 4
| |
| .................................................... 1 V 3107 E5 2 C 10.000 CNECK A S/A C , M0 CV/0 CS
| |
| ' ~
| |
| CV/PO QR
| |
| ?. H3 4
| |
| V 3201 3 8 2.000 GLOSE A MAN C #0 FAI EE OR 4
| |
| V 3401 07 2 C 6.000 CHECK A S/A C NO CV/0 RF VR 8 CV/PO GR VR-8 V 3407 N3 3 C 0.500 RELIEF A S/A C NO SRV RF 2 V 3410 s7 2 C 8.000 CNECK A S/A C NO CV/0 RF VR 8 CV/PO GR VR 8
| |
| : V 3412 C4 2 C 1.000 RELIEF A S/A C 10 0 SRV RF J ....................................................
| |
| V 3414 B5 2 C 3.000 S/CNEE A $/A C NO CV/C QR VR 9 CV/0 RF VR-9 i
| |
| CV/PO CS VR-9 I V 3417 04 2 C 1.000 RELIEF A S/A C WO SRV RF V 3427 05 2 C 3.000 S/CNEK A S/A C No CV/C CS VR 9 CV/0 RF VR 9 CV/P0 CS VR 9 V-3430 G-6 2 C 1.000 RELIEF A S/A C NO SRV RF i V 3431 N-6 2 C 1.000 RELIEF A S/A C NO SRV RF V 3432 E7 2 3 14.000 GATE A MO LO YES FAI EC QA PI 2Y 1
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| FLORIDA PO W R A m LIGNT Co wANY -
| |
| REVISION'O VALVE TA8LES DATE : 07/16/93
| |
| ; Saint Lucie Nucteer Plant Unit 2 PAGE : 15 P 8 103 2998 4 078 SN 130 (cont) SYSTMs SAFETT INJECTION SYSTEN i l
| |
| ACT. Noan REN FAIL TEST RELIEF VALVE IRaeEt C00AD. CL CAT. SIZE TYPE A/P TYPE P06. l e MODE EXAM FREE REe. RENARES
| |
| ; V 3544 C2 28 3.000 ELSEE A ND LC YES FAI EC E 80 GR
| |
| : PI 27 V 3547 C5 2C 3.000 CNECK A S/A C NO CV/C CS VR 10 CV/0 RF VR 10 CV/P0 CS VR-10 l
| |
| , V 3550 C2 2 8 3.000 GLOBE A NO LC YES FAI EC QR i EO QR PI 2T V 3551 A2 2 5 3.000 GLORE A MO LC YES FAI EC QR EO OR -
| |
| ~
| |
| PI 2Y V 3570 C3 2C 1.000 RELIEF
| |
| * A S/A C ho SRV RF V 3654 5-5 2 8 6.000 GATE A NO LO YES FAI EC QR P1 27 V 3656 D5 2 a 6.000 GATE A M0 LO YES FAI EC QR Pt 27 V 3658 G7 2 8 12.000 GATE A NO LC YES FAI EO QR
| |
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| |
| V-3659 G6 2 8 3.000 CATE A M0 LO TES FAI EC QR 1
| |
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| |
| .................................................... l V 3660 G5 2 B 3.000 GATE A M0 LO TES FAI EC QR !
| |
| P! 27 )
| |
| v 3688 H5 2C 2.000 RELIEF A $/A C NO SRV RF
| |
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| |
| VALVE TASLES REVISION: 0 Saint Lucie munteer Plant - Unit 2 DATE : 07/16/93 4 .
| |
| Pb't : le
| |
| { P & ID: 2996 6-978 se 131 __
| |
| ; ..... .. . SYSYEN: SAFETY INJECTlou SYSTEM ACT. h0AM REN FAIL TEST RELIEF WALVE tRMBER C00AD. CL CAT. SIZE TYPE A/P TYPE POB. l e MOD EXAN FREE REG. BEM4AES
| |
| ............... ...... .. .... ...... ...... ... ...... .... ... ...E NCV 3415 #-7 25 6.000 SLeEE A W C YES FAI E0 et P 2Y
| |
| ....................................t ................
| |
| "*~ NCV 3616 E7 2 8 2.000 GLOSE A BD C YES FAI EO GR i . . . . . . . . .G7. . . . . . . . . . . . . . . . . . . . . . . . . . Pt HCV 3617 2Y 2 8 2.000 CLDEE A MD C YES FAI EO OR 2Y a
| |
| . . . . . . . . .F7. . . . . . . . . . . . . . . . . . . . . . . . . . Pt.................
| |
| McV 3625
| |
| < 2 5 6.000 CLOSE A MO C YES FAI E0 et P
| |
| . . . . . . . . E7 MCV 3626
| |
| . . . . 2...B . . . . . . . . . . . . . . . . . . . . . .I................ 2V 2.000 ClosE A MO J.
| |
| C YES FAI EO QR j P 2Y
| |
| ....................................t ................ .
| |
| McV 3627 E.7 2 3 2.000 CLost A M0 C YES FAI EO i
| |
| " QR j
| |
| . . . . . . . . .D7. . . . . . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| NCV*3635 2Y 2 8 6.000 CLOSE A MO C YES FAI E0 et
| |
| , 2Y
| |
| ......................'.............PI* .................
| |
| i i McV 3636 C7 2 B 2.000 CLOBE A NO C YES FAI E0 GR l
| |
| . . . . . . . . .C*7. . . . . . . . . . . . . . . . . . . . . . . . . . PI NCV* 3637 2Y 2 8 2.000 GlosE A M0 C YES FAI EO QR 2Y
| |
| ...................................Pt ...............a.
| |
| l MCV 3645 B7 2 8 6.000 CLO8E A No C YES FAI EO OR 2Y
| |
| ...................................Pt.................
| |
| McV 3646 A7 2 B 2.000 GlosE A Mo C YES FAI EO QR
| |
| . . . . . . . . .A7. . . . . . . . . . . . . . . . . . . . . . . . . . PI MCV 3647 2Y 4
| |
| 2 8 2.000 CLOSE A MO C YES FAI EO QR i
| |
| 2Y
| |
| ...................................PI................. !
| |
| 1 V 3113 G7 2C 2.000 CNECK A S/A C WO l 1 CV/O RF VR 11 '
| |
| CS VR 11
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CV/PO ............ ....
| |
| j V 3114 N7 2C 6.000 CMECK A $/A C MO CV/C CS t !
| |
| CS 3
| |
| j
| |
| . . . . . . . . .F7 V 3124
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . CV/0 .................
| |
| 2 C 6.000 CNECK A $/A C k0 CV/C CS
| |
| } . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Cv/0 CS e
| |
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| .. 4..... . . ...................... w....n == . . w ..... . ... ...
| |
| FLORIDA PonER AS LIGNT COWANY -
| |
| REVISION: 0 VALVE TABLES DATE : 07/16/93 Saint Lucie Nuclear Plant - tmit 2 PAM 17 m . -- . .
| |
| P S ID: 2990 6 078 SN 131 (cent) SYSTEN: SAFETT INJECTION SYSTEN i
| |
| .u.u....n..........n....u... -
| |
| m,-. .. ..... . ......
| |
| ACT. NORh REN FAIL TEST RELIEF WALVE NIAeER C00RD. CL CAT. $1ZE TYPf A/P TYPE P08.le umE EJEAN FRES RES. REN4AKS
| |
| ............... ...... .. .... ...... ...... ... ...... .... ... .... ......... .... ...... ........... i V 3133 C.T 2 C 2.000 CNEtt A S/A C NO CVM RF VR 11 CV/Po CS VR.11 <
| |
| v 3134 D*T 2 C 6.000 CNECK A S/4 C NO CV/C CS Cv/o CS V 3143 A7 2 C 2.000 CHECK A $/A C NO CV/0 RF VR 11 CV/PO CS VR 11 V 3144 sT 2 C 6.000 CNECK A S/A C NO CV/C CS CV/0 CS v 3468 06 2 C 2.000 RELIEF A $/A C Wo say RF
| |
| ................................................... ~~
| |
| V 3469 03 1 C 0.750 RELIEF A S/A C NO SRV RF
| |
| ~
| |
| ..................... 3 .............................
| |
| V 3480 E3 1 A 10.000 CATE A NO LC TES FAI EO CS PI 27 SLT 2 SP VR 29 V 3441 E4 1 A 10.000 GATE A ND LC YES FAI EO CS PI 2f SLT ?, SP VR 29 V 3482 E4 1 C 0.750 RELIEF A S/A C NO SRV RF V 3483 08 2 C 2.000 RELIEF A S/A C NO SaY RF V 3524 F5 1 AC 3.000 CHECK A $/A C WO CV/C SP VR 12 CV/0 RF VR 12 CV/PO CS VR 12 SLT 2 SP Vit 2 V 3525 F4 1 AC 3.000 CHECK A S/A C WO CV/C SP VR 12 CV/0 RF VR 12 CY/PO CS VR 12 SLT 2 SP VR 2 S VR 12 V 3526 C5 1 AC 3.000 CHECK A S/A C WO CV/C SP VR 12 CV/0 PF VR 12 CV/P0 CS VR 12 SLT 2 SP VR 2 I
| |
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| l FLORIDA POWR AIS LIGilt C00 PANT REvill0N: 0 i
| |
| ~'
| |
| . VALVE TABLES DATE : 07/16/93 ;
| |
| Salht Lucle Nuclear Plant Unit 2 PAM : 30 '
| |
| j P & Its 2WS 4-975 Os 132 (eent) SYSTest SAFETY IsJgCTIOu sYsfal i 1
| |
| At? -10eme Ret FAlt -- -- TEST RELIEF-- - '
| |
| VALVE NL8eER COORD. CL CAT. SIZE TYPE A/P TYPE PCs. la IIBE EXAM FRE4 RE3. REMAGES V 3219 F4 2 AC 12.000 CRECK A S/A C up CV/C W VR 13 luSP W W 13 ET 2 W. VR 2 V 3217 E5 1 AC 12.000 CNECK A SPA C 10 0 CV/C SP VR 14 CV/PG Cs VR-14 INSP SP VR 14 SLT 2 SP vt 2 V 3221 N3 2 C 1.500 RELIEF A S/A C 10 0 Stif RF V 3225 F3 2 AC 12.000 CNECK A S/A C 80 0 CV/C SP VR 13
| |
| !!!SP SP VR 13 SLT 2 SP VR 2 V 3227 E2 1 AC 12.000 CNECK
| |
| * A S/A C 10 0 CV/C SP VR 14 i
| |
| CV/P0 CS VR 14 ;
| |
| !NSP SP VR 14 SLT 2 SP VR-2 V 3231 06 2 C 1.500 RELIEF A 8/A C WO SRV RF V 3235 C6 2 AC 12.000 CNECK A s/A C WO CV/C SP VR 13 INSP SP VR-13 SLT 2 SP VR 2 V-3237 B5 1 AC 12.000 CNECK A S/A C NO CV/C SP VR 14 CV/PO CS VR 14 INSP SP VR 14 SLT 2 SP VR 2 V 3241 03 2 C 1.500 RELIEF A S/A C 00 0 SRV RF V 3245 C3 2 AC 12.000 CHECK A S/A C WO CV/C SP VR 13 INSP SP VR 13 SLT 2 SP VR*2 V 3247 82 1 AC 12.000 CHECK A S/A C 10 0 CV/C SP VR 14 CV/PO CS VR 14 INSP SP VR 14 SLT 2 SP VR 2 e
| |
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| FLORIDA PohEt AS Litaff COIFAfff .
| |
| REV1810N 0 '
| |
| VALVE TABLBB DATE : 07/16/95 Selat Lucie nuclear Plant a mit 2 PAet : 21 l P & ID: 2998 8 075 SII 132 (cent) BYSTEles SAPETY IEJECTION 8757W1 ACT. IIORII REI6 FAIL TEST RELIEF VALVE etseta C00AD. CL CAT. 3128 YYPE A/P TYPE P08. lie IInDE EX4ll FREG RES. RE814AES V 32S8 E3 1 AC 4.000 Clem A S/A C e CV/C y Wa 15 l CV/O CS WR 15 SLT*2 F WR 2 V 3259 E6 1 At 6.000 CNE M A SfA C 11 0 CV/C SP VR 15 CY/0 CS VR 15 SLT 2 SP VR 2 V 3260 B6 1 AC 6.000 CufCK A S/A C NO CV/C SP VR 15 CV/0 CS VR 15 SLT 2 SP VR 2 V 3261 B3 1 AC 6.000 CNECK A S/A C WO CV/C SP VR*15 CV/O CS VR 15 SLT 2 SP VR 2 -
| |
| V 3611 F6 2 B 1.000 CLOSE A DO C YES FC EC QR FS OR PI 2T
| |
| .................................................... l V 3614 F6 1B 12.000 GATE' A 11 0 LO YES FAI EC CS Pt 27 V 3621 F3 2 B 1.000 OLOSE A DO C YES FC EC QR FS QR 1 PI 27 I
| |
| .................................................... l V 3624 F3 i B 12.000 GATE A sID LO YES FAI EC CS PI 2Y l
| |
| ....................................'................ )
| |
| V 3631 56 2 5 1.000 CLOSE A 00 C YES FC EC QR FS OR '
| |
| P1 27
| |
| .................................................... 1 V 3634 B6 1 8 12.000 GATE A 81 0 LO YES FAI EC CS I P1 27 V 3641 B3 2 0 1.000 CLOSE A D0 C YES FC EC QR FS QR Pt 27 V 3644 B3 1 8 12.000 GATE A 10 0 LO YES FAI EC CS Pt 27 9
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| |
| YALVE TA8LES DATE : 07/16/93 Saint Lucie Nutteer Plant a Unit 2 PAGE : 22
| |
| .----....u.u...
| |
| P & 10 2M S 4-SFB 85 132 (cent) SYSTEN: SAPETY INJECTION SYSTEN
| |
| .......u...............s...u...u....u..u...uun..
| |
| ACT. WORN ROI FAIL- ~ YEif RELIEF---
| |
| VALVE tRMBER CDOAD. CL CAT. SIZE TYPE A/P TYPE P08. I W MODE EXAM FREO RES. BEMARES V 3FIS sF 2 B 1.000 GLOSE A 30 C YES FC EC CS E0 CS FS CS.
| |
| - PI iT
| |
| . .........................r. .........................
| |
| V 3734 s7 2 8 1.000 GL0sE A 30 C YES FC EC CS EO CS FB CS PI 2Y V 3735 G4 2 8 1.000 CLOSE A 30 C YES PC EC CS E0 CS FS CS 4
| |
| P1 2Y V 3736 G4 2 B 1.000 GlosE A S0 C YES FC EC CS EO CS FS CS P1 2Y i
| |
| V 3737 D*T 2 8 1.000 GLOSE A 30 C YES FC EC CS E0 CS FS CS PI 2Y
| |
| \ . . . . . .
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| 1 4
| |
| V 3738 D7 2 5 1.000 CLOBE A 50 C YES FC EC CS E0 CS l
| |
| FS CS PI 2Y V 3739 D4 2 B 1.000 GL0eE A S0 C YES FC EC CS EO CS l FS CS Pt 2Y V 3740 04 2 8 1.000 ClosE A S0 C YES FC EC CS E0 CS FS CS P1 2Y e
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| .... .... ... u n. ...... .... ... 1 FLORIDA POWR Am Lit.RT COePANY -
| |
| REVISION: 0 l VALVE TA8LES DATE : 07/16/93 Saint Lucie aucteer Plant . Unit 2 pag 23 P & ids 2HG E 0?B SN 153 SYSTEN: SAprLins SYSTSN
| |
| ...... u .. ............u...... .. ... ..u... ..... ..... ....
| |
| ACT. WORM REN Fall TEST RELIEF VALVE WUWER CDORD. CL CAT. SIZE TYPE A/P YtPE Pol, l e se0DE EXAN FRES REG. REMARKS SE 05 1A 47 2 A 0.375 8 LOSE A 30 C TES FC EC GR FS M PI 27 .
| |
| . , SLT 1 2T I SE 05 18 FT 2 A 0.375 CLOBE A 30 C YES FC EC GR FS OR PI 27 SLT 1 27 SE 05 1C E7 2 A 0.375 CLOSE A $0 C YES FC EC OR FS QR PI 2Y SLT 1 2Y
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - .- l SE 05 iD C7 2 A 0.375 CLOSE A $0 C YES FC EC QR FS QR PI 27 i SLT 1 2T SE 05 1E C5 2 A 0.375 CLOSE A S0 C TES FC EC GR l FS OR :
| |
| PI 27 l
| |
| SLT 1 2Y i
| |
| .................................................... )
| |
| v 5200 F6 2 A 0.375 CLOSE A $0 C YES FC EC QR FS 08 PI 2f SLT 1 2Y V 5201 E6 2 A 0.375 CLOSE A So C YES FC EC QA FS OR PI 27 i SLT 1 27
| |
| 'V 5202 D6 2 A 0.375 CLOSE A $0 C YES FC EC QR FS OR PI 2Y SLT 1 2Y l
| |
| V 5203 F5 2 A 0.375 CL0eE A S0 C YES FC EC QR FS OR Pt 2Y ;
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| SLT 1 27 l s
| |
| | |
| i 1
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| 1 s ee s e s ses soa s soss e s s e s s emo sesm a sse s se ss es s e.see sse ssee. c ss as.same.e ssess e s- - me - __ e I FLORIDA POWER AW LirsNT COMPANY REVill0N: 9 VALVE TABLES DATE : 0T/16/93 Saint Lucie nuclear Plant . Unit 2 PAaE 25 e s o n -- - -
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| P & 10: 2998 8 078 SN 160 SYSTEMS W4sTE nANAGEMENT ST87EN .
| |
| . o e e e . e o e..o. ..o.s e. e.e..e o.e oe.e o eo....es _.e._ _.--... o.s e.e - . _ se. 1 ACT. NORM REN FAIL TEST RELIEF l VALVE Insett C00W . CL CAT. SIZE TYPE A/P TYPE POB.le NWE EMAN FRES RES. RBenaus j
| |
| ............... ...... .. .... ...... ...... ... ...... .... ... .... ......... .... ...... ........... 4 V 6341 ET 2A 3.000 DIAPW ' A 30 0 TES PC EC GR I FS E l PI 27 l
| |
| < SLT 1 27
| |
| ................................................... l V 6342 E6 2 A 3.000 DIAPN A DO O YES FC EC QR )
| |
| FS GR -
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| |
| SLT*1 27 ;
| |
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| |
| FLORIDA POWER Am LIGNT COWANY VALVE TA8LES REYlSlost 0 l Saint Lucie nuclear Plant
| |
| * Unit 2 DATE : 07/16/93
| |
| .- PASE : 36 P & ID: 2998 S*978 SS 163 SYSTEM: llLSTE MANAf9ENT SYSTEN
| |
| ...... . .... ...... . .- . l
| |
| ~~ ^ -
| |
| . .. ... ..... .. I
| |
| "~~"4CT'. NORM REN FAIL TEST RELIEF VALVE ILMBER i C00AD. CL CAT. 31ZE TYPE A/P TTPE POS. lie Mt
| |
| .........................................................IE V 6718 E*7 2A EXAM FREG RES. RENARES 1.000 DIAMI A De O VES PC EC et I FS OR PI 21 w 2Y
| |
| . . . . . . . . .C7 v 6761
| |
| . . . . . . . . . . . . . . . . . '. . . . . . . . . SLT 1 2A 1.000 CLOSE A A0 0 YES FC EC et FS 04 PI 2f 27
| |
| . . . . . . . . .ET V 6750
| |
| . . . .2 .A. . . . . . . . . . . . . . . . . . . . . SLTal .................
| |
| 1.000 DIAPN A 00 0 YES PC EC QR 1
| |
| FS OR P1 2Y 27
| |
| . . . . . . . . .C7 V-6792
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . SLT.1 . . . . . . . . . . . . . . . . . " -
| |
| 2 AC 1.000 CHECK A S/A C No CV/C CS 27
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SLT*1 .................
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| FLORIDA POWER A S LIGMT COMPANY ~
| |
| REVIS105: 0 VALVE TASLES-DATE 07/16/95 Saint Lucie musteer Plant
| |
| * Unit 2 PAm 27
| |
| .- .- an P & 10: 2998 8 079 Su i system: MAlu STEAM SYSTEM u....-..m ... u.n.. .-- . m m .
| |
| ACT. MORM REN Fall TEST RELIEF VALVE IRMBER C005. CL CAT. SIZE TYPE A/P TYPE P08.le MBE EXAM FREE RE4. REmaES MCV 08 1A E-12 28 34.000 SLOSE A PO O YES EC C8 PEC GR PI 27
| |
| # .........................gr..........................
| |
| MCV 08 18 C.13 2 8 34.000 GLost A PO O YES EC C8 PEC QR Pt 27 MV 08 12 N8 2 8 4.000 GATE A MO C YES FAI EC QR -
| |
| 80 QR PI 27 MV 08 13 N 10 2 3 4.000 GATE A MO C YES FAI EC QR EO GR -
| |
| PI 2f MV 08 14 E-8 2 8 8.000 GATE P M0 LO YES FAI EC QR PI 27 MV 08 15 E 10 2 8 8.000 CATE P M0 LO YES FAI EC QR Pt 27 MV 0816 0 10 2 8 8.000 GATE P M0 LO YES FAI EC QR P3 2Y MV-08 17 D8 2 8 8.000 GATE P Mo LO YES FAI EC QR Pt 27 MV 08 18A J8 2 8 10.000 ANGLE' A Mo C YES FAI EC QR EO QR PI 2Y MV 08 188 D 10 2 3 10.000 ANGLE A M0 C YES FAI EC QR EO QR PI 2Y MV 08 19A J 10 2 8 10.000 ANGLE A No C YES FAI EC QR EO QR 2T
| |
| ...................................'PI .................
| |
| MV-08 198 D8 2 8 10.000 ANGLE A MD C YES FAI EC QR EO QR PI 27 9
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| l
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| FLORIDA POWER AND LIGNT COMPANY _. REVISION: 0 VALVE TASLES DATE : 07/16/73 Saint Lucie Nucteer Plant . Unit 2 PAGE : 38 P & 10: 2MG 4 079 SN 1 (cont)' SYSTEM: N5ldSTEAMSYSTEM
| |
| .u.........u. . .. u.u ..... .. . . ........... .su .u....-
| |
| ACT. ' NORM REN FAIL ~ TEST RELIEF ~ ~ {
| |
| VALVE tue8ER C00AD. CL CAT. 812E TYPE A/P TTPE Pos le seQDE ExAN FREE REO. RENAAU MV 08 1A K 13 2 0 3.000 SLGAE A B C YES FAI EC et PI 27 4
| |
| MV 08 18 C 13 2 e 3.000 SL0eE A NO C YES FAI EC GR PI 2Y MV 08 3 N 14 3 5 4.000 CLORE A No LO YES FAI EO GR PI 27
| |
| ................................................... l SE 08-1 N8 2 B 0.750 CL0sE A SO O TES FO EC GR I P1 2Y i
| |
| .................................................... l SE 08 2 N 10 2 5 0.750 CLORE A S0 0 YES FD EC QR l PI 27 l
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- - 1 V-08130 L 10 3 C A.000 CHECK A S/A 0 NO CV/0 CS CV/PO OR VR 31 INSP RF VR 31 i
| |
| V 08163 L 10 3 C 4.000 CHECK A S/A 0 NO CY/0 CS CV/PO GR VR 31 INSP RF VR*31 l
| |
| V-8201 J 12 2 C 6.000 SAFETY A $/A C NO SRV RF V 8202 J 12 2 C 6.000 SAFETY A S/A C NO SRY RF I v 8203 J 12 2 C 6.000 SAFETY A S/A C NO SRV RF t .
| |
| V 8204 J 12 2 C 6.000 SAFETY A S/A C NO SRV RF V 8205 C 11 2 C 6.000 SAFETT A S/A C NO SRV RF V 8206 Call 2 C 6.000 SAFETY A S/A C WO SRV RF v 8207 C 11 2 C 6.000 SAFETY A $/A C NO SRV RF V 8208 C 11 2 C 6.000 SAFETT A S/A C NO SRY RF V 8209 J 12 2 C 6.000 SAFETT A S/A C NO SRV RF V 8210 J 12 2 C 6.000 SAFETT A $/A C NO SRV RF 4 V 8211 J 12 2 C 6.000 SAFETY A S/A C NO SRV RF 3
| |
| 4 4
| |
| * e FLORIDA POWS Am LIGNT Co*ANY VALW TABLES REvitics: 0 l
| |
| Saint Lucie Nucteer Plant . Unit 2 DATE : 07/14/93 l _- -
| |
| PAGE : 29 P & ID: 2990*E 079 58 1 (cont) SYSTENs NAIN SitAN SYSTEN ACT. monM REN FAIL TEST RELIEF VALVE IU SER COORD. CL CAT. SIZE
| |
| ............... ...... .. .... ...... ......T7M V 8212
| |
| ...A/P TVM POB. IIS MIBE
| |
| ...... .... ... .... ..EXAN FREG RE4. RENAeKS J 12 2 C
| |
| . . . . . . . . . . . . . . . . . 4.000
| |
| . . . .SA . . NTY
| |
| . . . A. S/A
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| . . .C. . .NO. . EEV i RF V 8213 C 11 2 C
| |
| ', . . . . . . . . . . . . . . . . 4.000
| |
| .V 5214 . . . .SAFETT
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| . . . . pA .S/A . .C. . .NO. . . . .SEV. . . .RF...........
| |
| C 11 2C 6.000 SAFETY A $/A C NO BR RF
| |
| ....................................V V 8215 . . . . . ...........
| |
| C 11 2C 6.000 SAFEff A $/A C NO SAY
| |
| .V 8216
| |
| . . . . . . . .C . 11
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| . . 2. .C . . . . . . . . . . . . . . . . . . . . . . . . . . .RF...........
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| 6.000 SAFEff A $/A C N0 SRV
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| VALV. TA8LES REVISION: 0 Saint Lucie aucteer Plant . Unit 2 DATE : 07/16/93 PAGE :
| |
| P & ID: 2995 G 000 Sa 2 ... n . u .. .n m e.30 SY
| |
| . u.. u...w . ...num.... STEM: n.n.
| |
| FEEDWATER SYSTEN w . u.w.u..n w...... = nn .
| |
| VALVE tamBER ACT. MORM REN FAIL TEST RFLIEF C00AD.
| |
| ............... ...... ..CL CAT.
| |
| .... SI2I....E..
| |
| ...... TYP A/P TYPE P08.Im NmE EXAM FRES R MCV 09 1A S.14 28 20.000 GATE A 70
| |
| ...... .... ... .... ......... .... ..E4. RSchaus 0 YES 70 EC Cs PS CS
| |
| "** PEC QR
| |
| .. PI
| |
| ..............'.........e...............'27 MCV-($=18 B*13 2 8 ...........
| |
| 20.000 GATE A P0 O YES F0 EC CS 75 CS MC M .
| |
| 2Y
| |
| ...................................PI NCV 09-2A E 13 2 B .................
| |
| 20.000 CATE A PO O YES 70 EC CS 78 CS PEC QA
| |
| . . .09.28. . . . .E . 13 . . 2. .8 . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| 27 "
| |
| McV 20.000 GATE A PO O TES 70 EC CS FS CS PEC QA
| |
| . . . . . . . . .Gate MV 09 09 . . . 2. .5 . . . . . . . . . . . . . . . . . . . . . Pt 27 4.000 GLost A NO C YES FAI EC QR EO QR 27
| |
| . . . . . . . . .I. 15 MV 09 10 . . 2. .B . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| 4.000 GL.0et A Mo C YES FAI EC QR EO QR
| |
| . . . . . . . . .G-12 MV 09 11 . . . 2. .3. . . . . . . . . . . . . . . . . . . . . P1................. 2Y 4.000 GLOSE A M0 C- YES FAI EC QR EO QR 2Y
| |
| ...................................PI MV 09 12 1 12 2 3 .................
| |
| 4.000 CLOSE A MD C YES FAI EC 04 EO OR
| |
| . . . . . . . . .N .17. .3. 8. . . . . . . . . . . . . . . . . . . . . 98 MV-09 13 21 2.500 GATE A MO C YES FAI EO QA 2f
| |
| ...................................PI NY 09 14 N 17 3 8 .................
| |
| 2.500 CATE A Mo C YES FAI EO QR 2Y
| |
| ...................................PI .................
| |
| | |
| o .
| |
| _ . . . . - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - -
| |
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| FLORIDA POWS Am LIGNT COMPAarf
| |
| .... .. u u......u .... u .u . ... u n .........u . . u... -
| |
| VALVE TABLES REvlsitus 0 l Saint. Lucie Nuclear Piet Unit 2 DATE : 07/16/93
| |
| .. PAGE : 31
| |
| ', _- _. ..u : ., un ....u . . ..u . .u - -
| |
| P & ID: 2998 8 000
| |
| .. u ..
| |
| SN 2 (cont) SYSTENs FEED mTER SYSTEN
| |
| . .u ... ... . ......... .. ... . .u ....u u n.. u n . u n... .
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| ACT. WORN REM Fall TEST RELIEF VALVE lASSER C00AD. CL CAT. SIZE TYPE A/P TYPE Pos. I m NCD EXAN FRES RES.
| |
| SE 09 2
| |
| ...E. ......... .... ...... ...........
| |
| REMAKS K.15 3 5 4.000 EAff A to TES PC EC C CS W 33 EE OR W 33 i E0 CS W 33 w , FS
| |
| . OR P 27 l
| |
| SE-09 3 J 15 3 5 4.000 GATE A So C YES FC EC CS VR 33 EE OR VR 33 E0 CS W-33 FS OR P 27
| |
| . . . . . . . . .Matt SE-09-4
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . .I ................
| |
| 3 3 4.000 CATE A S0 C YES FC EC CS VR 33 EE OR VR 33 .
| |
| E0 CS VR 33 FS QR P 2Y
| |
| ....................................I ................
| |
| SE 09 5 l 11 3 5 4.000 GATE A $0 C YES FC EC CS VR 33 EE OR W 33 E0 CS W 33 FB OR P 2Y
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .I ................
| |
| V 09107 N 14 3 C 4.000 CNECK A S/A C NO CS
| |
| . . . . . . . . .G-15 V 09119
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . CV/0 .................
| |
| i l
| |
| 2 C 4.000 CHECK A S/A C NO
| |
| . . . . . . . .01. . . . . . . . . . . . . . . . . . . . . . . . . . .CV/0................
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| .V 09120 CS i 2 8 4.000 CATE A MAN Lo WO FAI QR
| |
| ...................................EE v 09123 L 14 3 C 4.000 CHEC A $/A C NO
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| .v 09135
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| . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . CV/0 .................
| |
| CS 1 15 2 C 4.000 CNECK A S/A C NO
| |
| .V*09136
| |
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| |
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| |
| . . NO
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| . . .FAI. . EE 4.000 GATE V 09139
| |
| . . . . . . . . . . . . . . . . . .OR...........
| |
| J 14 3 C 6.000 CHECK A S/A C M0
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CV/0................
| |
| .V 09151 CS G 12 2 C
| |
| . . . . . . . . .D4. . . . . . . .4.000 . . . .CHECK
| |
| . . . . A. .$/A. .C. . . . . . . CV/O NO CS v 09152 2B 4.000 CATE A MAN LD WO FAI EE
| |
| .v-09157
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .OR...........
| |
| l 12 2 C 4.000 CHECK A $/A C MO
| |
| .v-09158. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .CV/0 . CS 0 13 2 3 4.000 CATE
| |
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| |
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| ...................u.a...u........u....u......u......u n..
| |
| FLORIDA POWER AS LIGNT COMPANY
| |
| . ....n
| |
| ~
| |
| VALVE TABLES REVIS10u 0 Saint ..;u Lucie Nucteer Plant Unit 2 DATE : 07/16/93 n . PAE : 32
| |
| _..an..........==.u..u==....n.-
| |
| P & ID: 2990 G-000 $N 2 (cont) STsTENs FEEDWATER SYSTEN
| |
| ......n u u ..... . ....u m-- ------------------- - -- --- -- . . ... .n ...
| |
| ACT. uCRM REN FAIL TEST RELIEF I VALVE nue8ER C00RD. CL CAT. $12E TYPE A/P TTPE POS.18 IED EXAN FRES Rie.
| |
| Y-09252
| |
| ...E. ......... .... REMARES 5 16 2C 18.000 CNE M A 8/A 0 ;
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .NO. . CV/0
| |
| .V 092% GR
| |
| ................. i E 16 2 C
| |
| '_ . . . . . . . . . . . . . . . . .18.000
| |
| . . . . CNE
| |
| . . . .M.,.A S/A . . .0. . .NO. . CV/0 GR j
| |
| V 09303 L 13 3 C 2.000 CNECK A S/A C N0 CV/PO GR VR 27 RF VR 27
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .INSP V 09304 N 12 3 C 1.500 CHECK A $/A C WO CV/PO QR VR 27 RF VR 27
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .INSP V 09305 ................
| |
| N 13 3 C 1.500 CHECK A $/A C ho CV/PO OR VR 27 i' RF VR*27
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .INSP ................
| |
| ~
| |
| . - l I
| |
| l i
| |
| 1 4
| |
| 9
| |
| | |
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| |
| *.w -, en w
| |
| .w,. =m.-- ---i.,e r
| |
| .....u ..... ... u.m.... .u. .. ....u. . . ...
| |
| FLORIDA PMR Am LIGNT COWAarY ~
| |
| VALVE TABLES REVISION: 0 Saint Lucle Nucteer Plent . Unit 2 DATE : 07/16/73 pag 35 4 P & 10 2998 8-082 SYSTEN INTAEE COOLING WATER SYSTEN
| |
| .............. .......... ...=.u ..... --
| |
| VALVE NUMBER ACT. NonM REN Fall TEST RELIEF C005. CL CAT. 312E TTPE A/P TYP P05. 1 5 NGDE ENAN F000 NEG.
| |
| ............... ...... .. .... ...... ...... ... ....E NV 21 2 E5 38 24.000 IUTFLY A e
| |
| .. .... ... .... ......... .... ...... ...MetWB 0
| |
| TE8 FAI EC M IV -
| |
| . . . . . . . . .E4. . . . . . . . . . . . . . . . . . . . . . . . . . P1 MV 21*3 .................
| |
| . 35 24.000 BUTFLT A MD 0 TES FAI EC GR
| |
| . . . . . . . . .C4. . . 3C St 21196
| |
| . . . . ... . . . . . . . . . . . . . . . . . FI................. 2Y 3.000 RELIEF A S/A C N Say RF
| |
| ........................'...... 0.....................
| |
| sa 21243 C5 3C 3.000 RELIEF A $/A C
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .NO.....................
| |
| TCV 14 4A SRV RF s3 38 30.000 BUTFLT A PO O NO F0 E0
| |
| * en VR 34 QR
| |
| ...................................f5 .................
| |
| * TCV 14 45 B4 3 8 30.000 tuTFLT A PO 0 NO F0 E0 et VR 34 -
| |
| et 4
| |
| . . . . . . . . .N4. . . 3. .C . . . . . . . . . . . . . . . . . . . . . FS V 21162 .................
| |
| 30.000 CNECK A t/A 0 WO CV/C QR
| |
| . . . . . . . . .n6 V 21205
| |
| . . . .3C. . . . . . . . . . . . . . . . . . . . . . CV/0 QR 30.000 CNECK . A S/A 0 NO CV/C QR l . . . . . . . . .M.7 V 21208
| |
| . . . .3C. . . . . . . . . . . . . . . . . . . . . . CV/0 GR 30.000 CNECK A S/A 0 NO CV/C OR s
| |
| ...................................am a i 1
| |
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| 4 4
| |
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| |
| FLORIDA POW R A m LIGNT COWANY VALVE TABLES
| |
| .. REVIS10s: 9 DATE : 07/16/95 i Saint Lucle musleer Plant
| |
| * Lhlt 2 Pact : 34 1
| |
| ..u : _ _
| |
| su P & ID: IMO s SEB SYSTEM: CO WouENT C00Libt SYSTEN n u ... . -
| |
| .. u
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| VALVE TABLE 8 REVISION: 0 Saint Lucie Nucteer Plant Unit 2 DATE : 07/16/93 s PAGE : 36
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| |
| REVISION: 0 l
| |
| Saint Lucie Nutteer Plant Unit 2 DATE : 07/14/93
| |
| .... : . =. u n u PAGE : 37 P & ID: 2998 8 004 SYSTEM: MAGUP WATER SYSTEN
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| |
| AEVISIOut 0 Saint Lucie Nuclear Plant Unit 2 DATE : 07/16/93 .
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| |
| VALVE TABLES ~ afvlSION: 0 I Solnt Lucie Nuclear Plent
| |
| * Unit 2 DATE : 07/14/93 !
| |
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| V-07256 E8 2C 0.500 CHECK A $/A C is0 AF VR 24
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CV/0 .................
| |
| e
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| * e a
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| 4 FLORIDA POWS Ale LIGilf CEDDAlff VALW TABLES _............-......n Saint
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| . ~- Lucie sueleer Plant
| |
| * Unit 2 REVill0W: 0 Daft 07/16/98 P & ID: 2998 8-006 .
| |
| PAGE : 43 1 ...... . . m(cont) STlftM CONT . ... .
| |
| ..... ......AINENT . . -SPAAF SY$ FEN VALVE IfuMBER CO . . ...
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| SIM TYP A/P ACT.
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| ffPt Ifonst aER Fall _. .
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| P08, V 0TISS ..ORD.
| |
| F.
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| CL CAT..... .. ....
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| ....E.. ...... EXAll TEsf RELIEF PRES 2C ... ......'.. . .le IEst.. .... ......... .....
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| . . ..SES.
| |
| REBIAME
| |
| ........ 8. . . . . . . . . . . 0.500 Cu A s/A e li ......-
| |
| 4 V 07412 8 10
| |
| ...........2. .C . . .0.500
| |
| .ta...........e . . . . . . . . . . .M .........
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| CNECK A et/s er 34
| |
| . . . . . . . . 8/A C
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| .(...
| |
| MO CV/0 QR i
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| n 4 "'
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| 4 k
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| 4 4
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| 1 6
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| i t
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| 4 e
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| 4 1
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| 4
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| ?
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| I 4
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| d J
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| i i
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| 1
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| * e emessene
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| :somasseemmenesessenessessenesessessessesseseeenemonessessesseeeesessesse.
| |
| FL0s104 POWR Am LIGNT COWANY -
| |
| REVISION: 0 VALVE TABLES DATE : 07/16/93 Saint Lucie nuclear Plant . Unit 2 PAE : 44 o__ _e. os.- -- - se P 8 10 2998 6 0P1 $YST151: NIBCELLANEQUB BYSTEMS ese e.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeesesses== eeeeeeeeeemesse-eassesseme===ese=essee ne==esseesesome ACT. NonM REN Fall TEST RELIEF WALvt tu ett C00aB. CL CAT. SIZE TYPE A/P TYPE POS. l e NQDE EXAN
| |
| ............... ...... .. .... ...... ...... ... ...... .... ... .... ......... ....PRE..ES. 8R BINAES V 06 191 B4 2A 8.000 GATE P NAN C NB SLT 1 27 VR- & W.tE
| |
| ........................................... 4......
| |
| V 00 139 L.10 2A 0.375 GLost P NAN LC 41 0 RT 1 2Y V 00 1A0 N 10 2 A 1.000 GlosE P IIAN LC NO SLT*1 27 V 00 143 N 11 2 A 1.000 GLOSE P NAN LC N0 SLT 1 2Y V 00 144 L 11 2 A 0.375 Glost P NAN LC N0 SLT 1 2Y -
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| 8 1
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| 4 O
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| | |
| e e
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| .. :. m . .. .. ... a....
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| FLMIDA Pon4R AfD LIGNT COePANY :- ...
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| VALVE 1ASLll REvtsl0N: 0 Saint Lucie haclear Plant
| |
| * lihlt 2 DATE : 07/14/93 PAC el P & ID 2990*S 9F2 SN 1
| |
| . SYSTEN:
| |
| .. - MISC. SAMPLlas SYSTEMS
| |
| ... . - . .. 1 VALVE IApeER ACT. MORN REN FAIL j COORD. CL CA TEff RELIEF
| |
| ............... ...... .. ...T.. SIM TYPE A/P TYPE P PRES BRG
| |
| ~
| |
| FCV 36-1 . . . . . . . . . . . . . .. ... .... .os.
| |
| ...I ...
| |
| le NWE EXAN
| |
| .... ......... .... .... ARMMS s*2 2A 1.000 SLOSE A 30 0 . ...........
| |
| YES PC EC GR 78 et e PI 27
| |
| ..........................e. RT 1 FCV 26 2 G6 2A 1.000 GLOSE A 00
| |
| . . . . . . . . . . . . . 2Y ...........
| |
| 0 YES FC EC QR FS GR P1 2f 2Y
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| ...................................RT1 FCV 26 3 N2 2A .................
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| 1.000 GLOSE A 00 0 YES FC EC GR FS OR P1 2Y
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| . . . . . . . . . N6
| |
| . . . .2. A. . . . . . . . . . . . . . . . . . . . . .SLT ................ 1 27 .
| |
| FCV 26 4 1.000 CLOSE A DO O YES FC EC QR FS 04 PI 2Y 27
| |
| . . . . . . . . . I2 FCV 26 5 . . . .2.A. . . . . . . . . . . . . . . . . . . . . .SLT*1 ................
| |
| 1.000 E 00E A 00 0 YES FC EC QR FS OR PI 27
| |
| . . . . . . . . . l6 FCV 26 6 . . . .2.A. . . . . . . . . . . . . . . . . . . . . SLT*1 21 1.000 EOSE A 00 0 YES FC EC QR FS OR P1 27
| |
| . . . . . . . . . 3. .13. .2 . A. . . . . . . . . . . . . . . . . . . . . SLT.................
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| FSE 27 10 1 27 0.375 CLost A $0 C YES FC EC 04 EO OR FS OR PI 2Y
| |
| . . . . . . . . .C. 13 FSE 27-11 . . .2 .A. . . . . . . . . . . . . . . . . . . . . SLT 1 27 0.375 CLOSE A SC C YES FC EC QR EO OR FS OR PI 2f
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| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SLT 1 27 9
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| 4
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| * O l 1
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| l 4
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| ..... u....u .u . . . u.... u u .. .... .. .
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| FLORIDA POWB AaC LIGNT COWANY VALVE TABLES u .. . . . . ..uu u... .u ..uu REVISION: 0
| |
| .Saint
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| .u -
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| Lucie_ma leer Plant a Unit 2
| |
| _ r_
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| DATE : 07/16/93 l PAGE 46 P E ID: 2996 6 092 Su i u....=.uu mu .un l
| |
| ........ ... . .. (. cont). SYSTEN:
| |
| . ......_.L MISC. SAM IINi -SYSTEMS 4
| |
| VALVE NL*IBER ACT. NORM REN Fall
| |
| ... ... .. ............. {
| |
| C00RD. CL CA
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| ..........................T.. ......
| |
| F9E 2712 SIZE TYPE A/P TYPE P
| |
| ...... ... ...... .os. Its ... NODE EEAN TEST RELIEF Fate REG. BEN S.15 2A 0.375 ELORE A 30 C YES FC EC
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| ......... .... ...... ...... ARKS .....
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| t et {
| |
| EO QR i
| |
| \
| |
| C FS QA PI 2Y i
| |
| 2Y FSE 27 13. . 5. .15 . . 2. .A. . . . . . . . . . . . . . . . . . . . . . . . . . . SLT 1 0.3 M GLOGE A $0 C YES FC EC QR EO QR FB QR PI 2Y 4
| |
| . . . . . . . . .s. 15 FSE 2714 . . .2 .A. . . . . . . . . . . . . . . . . . . . . SLT 1 2Y !
| |
| 0.375 GlosE A $0 C YES FC EC QR 1
| |
| t EO QR FS QR
| |
| * Pt 2T 2Y FSE 2715. . .0. 13 . . . 2. .A. . . . . . . . . . . . . . . . . . . . . . . . . . .SLT................ 1 0.375 closE A SO C YES FC EC QR EO QR FS QA P! 2Y 2Y t FSE 2716. . .D. .13 . . .2A . . . . . . . . . . . . . . . . . . . . . . . . . . . SLT 1 0.375 CL0sE A 30 C YES FC EC QR EO QR FS QR PI 2Y i . . . . . . . . .D. 14 FSE 27-17 . . .2. A. . . . . . . . . . . . . . . . . . . . . .SLT ................ 1 2Y j 9.375 CLost A $0 C YES FC EC QR
| |
| ; EO QR FS QR P! 2Y I 2Y FSE 2718. . .D. .14. . 2. .A. . . . . . . . . . . . . . . . . . . . . . . . . . .SLT................ 1 0.35 C tAE A So C YES FC EC QR EO QR FS QR PI 2Y I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .SLT.1 ................
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| 2Y 4
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| 5 1
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| i l
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| j l
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| i I
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| v
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| 'f
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| * a
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| - --- r - e. - ~.. ... , _ , _ _ _ _ . _ . . . _ ~ . - - - -
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| FLORIDA Polet AW LIGNT COWANY . .... _
| |
| VALVE TA8LES I REvilleur 9 Saint
| |
| . Lucie Wucteer Plant
| |
| * Unit 2 DATE : 07/16/93
| |
| ..- = FAM AT P ..,
| |
| & ids 2998 8 092 351 .. _
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| . . SYSTEM MISC. SAMP u(cent)n m ...... =.m. LING SYSTEMS \
| |
| VALVE MJtBER COORD. CL
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| ......uu......-
| |
| ACT. NORM REN FAIL l
| |
| SIZE TYPE A/P TVPE P TEST RELIEF
| |
| )
| |
| FSE 27' 4 A 13 2ACAT.. . . . . . . . . C. . . . . . . .EXAN. . . .... ......
| |
| 0.375 GLOSE ' A 30 FR
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| . REM OS 4kg
| |
| . 15 NEDE YES FC EC GR
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| . SD et i FS GR ,
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| , Pl 21 l
| |
| . . . . . . . . . 8. .13 FSE 27 9 . . 2A
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| . . . . .0.375
| |
| . . . CLOSE
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| . . . . .A.".50
| |
| . . . . . . . .LLT-1 ................
| |
| 2Y C YES FC EC j GR EO GR FS GR PI 2Y
| |
| . . . . . . . . . 3. 14
| |
| . . 2. AC*
| |
| . . . . . . . . . . . . . . . . . . . . . . SLT 1 2
| |
| 2Y V 27101
| |
| +
| |
| ' 0.375 CHECK A $/A C NO CV/C CS CV/0 QR I 2Y .
| |
| V 27102. . . .s. 14 . . .2. At
| |
| . . . . . . . . . . . . . . . . . . . . . . . . . . SLT 1 0.375 CHECK A $/A C WO CV/c CS 1
| |
| CV/0 QA ,
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| . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . SLT 1 27 )
| |
| 6
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| ................. 1 9
| |
| 4 e
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| h
| |
| | |
| e ,
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| .. .. . . . =.. ... .. ..-
| |
| FLORIDA MRES AfD LIGNY CENFANY _. REVISION: 0 J
| |
| VALVE TABLES DATE : 07/16/93 ,
| |
| Saint Lucle sucLeer Plant tmit 2 ___
| |
| PAGE : 48 P & ID: 2998-8-878 SYSYBis NVAC ACY. NORM REN FAIL TEST RELIEF VALVE NLaeER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IIS MODE EXAN FRE8 RES. REMARES j
| |
| ............... ...... .. .... ...... ...... . ... ...... .... ... .... ......... .... ...... ........... I FCV 25-1 C-2 2 3 48.000 IUTFLY A PO C VES PC EC CS l
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| 78 CB 1 PI 2Y ;
| |
| .................................................... \
| |
| **~ C3 FCV 25 2 2 A 48.000 M FLY A Per C YES FC EC CS FS CS PI 2Y SLT 1 2Y VR 4 & VR 16 FCV-25 3 C4 2 A 48.000 M FLY A P0 C YES FC EC CS FS CS PI 2Y SLT 1 2Y VR 4 & W 16 FCV 25 4 C6 2 A 48.000 BUTFLY A PC C YES FC EC CS FS CS P! 2Y SLT 1 2Y VR 4 & VR 16 FCV 25 5 C7 2 A 48.000 BUTFLY A PC C YES FC EC CS FS CS PI 2Y SLY 1 2Y W 14 FCV-25 6 C8 2 B 48.000 SUTFLY A P0 C YES FC EC CS FS CS PI 2Y FCV 25 7 C 15 2 A 24.000 BUTFLY A P0 C YES FC EC QR EO QR FS GR PI 2Y SLT 1 2Y VR 16 FCV 25 8 C 15 2 A 24.0M BUTFLY A PC C YES FC EC QR EO QR FS GR PI 2T SLT 1 2Y VR-16 V 25 20 C 13 2 AC 24.000 CHECE A S/A C 10 0 CV/C CS CY/0 CS SLT.1 2Y VR 16
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| | |
| . .. . . . _ . . . . _ . . . _ . - _ ~ ._.__ ,_.. - .. . - _ . - - . . . - _ - . . . - . . - - . - -
| |
| * O l i
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| 1 l
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| l 1 -- - - - - - - - . - _ _ _ _ _ _ _ . . _ __ . _ . , _ _ _ _ _ _
| |
| FLORIDA POWER W LIGNT CCW ANT l REVISION: 9 i
| |
| VALVE TABLES DATE : 07/14/93 I
| |
| ' Saint.Lucie Nucteer Plan * . Unit 2 PAGE : 49 l
| |
| i P & ID: 29 M 4 878 (cent) $YSTEM: NVAC I i . . .. .
| |
| ACT. NCAN REN PAIL TEST RELIEF '
| |
| j VALVE IRAett C005. CL CAT. SIZE TYPE A/P TYPE POS. le 8mt Em FRES RES. REMARE V 5 21
| |
| ........S ...
| |
| i
| |
| " C 13 2 AC 34.000 CEECK A S/A C NO CV/C CS j CV/O CS I SLT-1 2T VR 16 '
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| w .................................................... a 1
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| s i
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| Y a
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| 4
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| +
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| 1 4
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| 1 f
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| I 4
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| i 1
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| 1 1
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| \
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| j l
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| 1
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| 9 o I
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| l 1
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| . . . ~ . . - . . - - - - ---
| |
| FLORIDA POWER A S LIGNT COWANY ..
| |
| 4 . VALVE TABLES , REVISION: 0 Saint Lucie nuclear Plant . Unit 2 DATE : 07/1uf3
| |
| ....- PAaE : 50 2
| |
| ; P & ID: 2998 8 879 SN 2 SYSTEM: NVAC VALVE IRMBER ACT. Mom REN Fall TEST RELIEF C00R3. CL CAT. SIZE TYPE A/P TYPE POS EXAM FRES RES.
| |
| ............... ...... .. .... ...... ...... ... ...... ... IS MODE ... .... ......... .... ...... ...........
| |
| REMARS
| |
| ; FCV 25 14 E4 38 12.000 auTFLY A le 0 TES FAI EC et s0 en
| |
| '; 2T e ...................................Pt FCV 25 15 ET .................
| |
| i, 3 5 12.000 SUTFLY A N0f 0 YES FAI EC GR i EO QR
| |
| .FCV-25
| |
| . . .16. . . . .E5. . . 3. .8 . . . . . . . . . . . . . . . . . . . . . Pt................. 2Y 12.000 BUTFLY A MO O TES FAI EC QR E0 GR 2T
| |
| . . . . . . . . .ES. . . 3. .1 . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| FCV-25 17 12'.000 BUTFLY" A NO O ' YES FAI EC QR EO QR 27 " - -
| |
| ...................................PI FCV 25 18 .................
| |
| C 17 3 B 6.000 SUTFLY A MO O YES FAI EC QR i
| |
| ....... , . . . . . . . . . . . . . . . . . . . . . . . . . . .I ................
| |
| P 27 ,
| |
| FCV 25 19 # 17 3 5 l 6.000 SUTTLY A 10 0 0 YES FAI EC QR Pt 2T FCV 25 26 A 17 3 B a
| |
| 10.000 EUTFLY A MD 0 YES bl EC QR 2T
| |
| * ...................................Pt FCV-25 25 .................
| |
| i A 17 3 8 10.000 SUTFLY A 80 0 YES FAI EC QR i
| |
| l 2Y d1
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| ...................................Pt .................
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| l 1
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| 4 l
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| 1 5
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| 4 i
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| 1 -
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| i 1
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| i
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| }1 9
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| h J
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| 4 4
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| l l l 2
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| f i
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| | |
| e .
| |
| e ese PobER FLORIDA oneseeneseemseeseseeeesessenessessemeses Als LIGuf COMPANY seassessessessee esesensessesenseeseeem seeee VALVE TABLES REVISION: 0 Saint esse - Lucle Nuclear Plant . thlt 2 DATE 07/16/93 PAGE : 51 P & ID: 2996 s sF9 su 3 SYSTEN WVAC
| |
| .__esemesseeeeeeeeeeeeeeeeeeees.
| |
| menesessessesmeesseessemenessenseemans:weessames-- -
| |
| _seeeeeeeeeeeeeeeem enemmese- _see ACT. NORM REN FAIL TEST RELIEF VALVE NL8et.R C00RB. CL CAT. SIZE T
| |
| ............... ...... .. .... ...... A/P ffM POB. ItB NIBE EMAN
| |
| ..YPE....
| |
| ... ...... .... ... .... ......... PREG AEG. WIAME FCV 25 11 a.4 20 .... ...... ...... ...
| |
| 14.000 AUTFLT A NB C YES P&I EC GR 80 GR'
| |
| " . . . . . . . . J4 FCV 25 12
| |
| ................. .c. . . . . . . . . PI 2Y 2 3 16.000 IUTFLY A M0 C YES FAI EC QR EO QA
| |
| . . . . . . . . .1 . 14. . 2. B. . . . . . . . . . . . . . . . . . . . . . Pt.................2r FCV 25 13 12.000 BUTFLY A M0 C YES FAI EO QR
| |
| . . .25.20. . . . .M1. . . 2. A. . . . . . . . . . . . . . . . . . . . . . PI.................2f FCV 8.000 EUTFLY. A P0 C YES FC EC QR FS 08 PI 2Y
| |
| . . . . . . . . .M2 . . . .2 .A. . . . . . . . . . . . . . . . . . . . . SLT 1 27 VR 4 & VR 16 FCV 25 21 8.000 SUTFLY A P0 .................
| |
| C YES FC EC QR FS QR P1 27
| |
| . . . . . . . . .N2 FCV 25 24 . . . .2A. . . . . . . . . . . . . . . . . . . . . . SLT 1 2Y VR 4 8 VR 14 8.000 SUTFLY A P0 C YES FC EC QR FS GR PI 2Y
| |
| . . . . . . . . .K3 . . . .2 .8. . . . . . . . . . . . . . . . . . . . . SLT 1 2Y VR 4 & VR 16 FCV 25 29 4.000 SUTFLY A M0 C YES FAI EC QA
| |
| . . . . . . . . .H4. . . 2. 8. . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| FCV-25-30 27 20.000 BUTFLY A M0 C YES FAI EC QR EO QA 2f
| |
| . . . . . . . . .J4. . . 2. 8. . . . . . . . . . . . . . . . . . . . . . PI.................
| |
| FCV 25 31 20.000 suTFLT A N0 C YES FAI EC QR
| |
| , E0 08 2Y
| |
| ...................................PI FCV 25 32 H-4 2B .................
| |
| 30.000 SUTFLY A M0 O TES FAI EC QR EO QR
| |
| . . . . . . . . .J4. . . 2. B. . . . . . . . . . . . . . . . . . . . . . P1.................
| |
| FCV 25 33 27 30.000 SUTFLY A MD 0 YES FAI EC QR EO QR
| |
| ................. Pt
| |
| . . . . . . . . . . . . . . . . . . . . . . . 2Y...........
| |
| 4 I
| |
| l
| |
| | |
| _. . . __ _ . . . _-- __ . _- -~ --- .. - - - - - . _ _ _ - . - .
| |
| i e a 4
| |
| l ..u .. =. ='.===u.d. === ..u....=..
| |
| FLORIDA POWER Am LIGNT COWANY = ....... .=== ..
| |
| VALVE TA8LES REVISION: 0 DATE : 07/14/95 Saint Lucle Nucteer Plant - talt 2 PAM
| |
| ..........=....=u...=.2
| |
| . . = -
| |
| 5 P & ID: 2998 G 879 su 3 (cent) sist NVAC
| |
| .... .= ......... . .EN:
| |
| l i
| |
| ......u.........u.-
| |
| ACT. WORN REN FAIL i
| |
| VALVE MLaett C00m. CL CAT. SIZE TYPE A TEST RELIEF
| |
| ............... ...... .. .... ...... ...... TYPE POB. le tube EXM FREG RES. !
| |
| } FCV 25 34 Nt 28 4.000 EW PL1 A le
| |
| ./P........................................REMAES ... . )
| |
| t n
| |
| C ftS FAI EC W 27
| |
| ...................................PI FCV 25 36 u1 2A # ................. i 8.000 aUTFLf A PO ;
| |
| C YES FC EC OR
| |
| \. !
| |
| Fs OR ,
| |
| PS 21 2r VR 4
| |
| . . . . . . . . .J6. . . .2 . C. . . . . . . . . . . . . . . . . . . . . SLT-1 V 25 23 .................
| |
| & VR 16 24.000 CHECK A S 1
| |
| . . . . . . . . .N.4. . . . . . . . . . . . . . . . ./A..........................
| |
| V 25 24 C NO CV/0 QR ,
| |
| 2C '
| |
| . . . . . . . . . . . . . . . . 24.000 . . . . CHECK
| |
| . . . . .A./A 5 1
| |
| 1 C Wo CV/0 QR
| |
| , .......................... l l
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| I i
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| i l
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| l 1
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| l l
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| 4 5
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| 4 1
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| i 1
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| | |
| o 2 d
| |
| i Appendix D Valve Program Requests for Relief I
| |
| 1 l
| |
| l
| |
| | |
| .- 5 L
| |
| ~ Revision 0 07/16/93 RELIEF REQUEST NO. VR-1 SYSTEM:
| |
| i Various COMPONENTS: ,
| |
| Any valves tested during cold shutdown conditions.
| |
| CATEGORY:
| |
| Various FUNCTION: ~~
| |
| i Various SECTION XI REQUIREMENT:
| |
| \
| |
| Valves shall be exercised ... unless such operation is not t practical during plant operation. If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full stroke exercised during cold shutdowns. Full stroke exercising during cold shutdowns for all valves not full-stroke 1 exercised during plant operation shall be on a frequency determined by the intervals between shutdowns as follows:
| |
| For intervals of 3 months or longer - exercise during each shutdown. (IWV-3412, IWV-3415 and IWV-3522)
| |
| BASIS FOR RELIEF:
| |
| In many instances testing of all valves designated for testing during cold shutdown cannot be completed due to the l brevity of an outage. It has been the policy of the NRC l
| |
| that if testing commences in a reasonable time and l i
| |
| - reasonable efforts are made to test all valves, then outage extension is not required when the only reason is to provide the opportunity for completion of valve testing. !
| |
| ASME/ ANSI OMa-1987, Operation and Maintenance Of Nuclear
| |
| . Power Plants, Part 10 (Paragraphs 4.2.1.2 and 4.3.2.2) recognizes this issue and allows deferred testing as set
| |
| , forth below.
| |
| 4 D-1 i
| |
| 1 1
| |
| | |
| .- - .. . - - . . ~ . .- - - . . - . - . ~ . .. . . . - . -
| |
| O b i i
| |
| b i
| |
| Revision 0 07/16/93
| |
| : i
| |
| , RELIEF REQUEST NO. VR-1 (cont.)
| |
| e ALTERNATE TESTING:
| |
| j For those valves designated to be exercised or tested during cold shutdown, exercising shall commence as soon as
| |
| '' practical after the plant reaphes a stable cold shutdown l j
| |
| condition, as defined by the applicable Technical Specification, cold shutdown. but no later than 48 hours after reaching
| |
| ~
| |
| If the outage is sufficiently long enough 4
| |
| for the testing of all the cold shutdown valves, then the
| |
| * 48-hour requirement need not' apply. If the 48-hour requirement is waved, then all cold shutdown valves must be ;
| |
| i tested during the outage.
| |
| Valve testing need not be performed more often than once every cold shutdown except as provided for in IWV-3417 (a) .
| |
| Completion of all valve testing during a cold shutdown outage is not required if the length of the shutdown period is insufficient to complete all testing. Testing not completed prior to startup may be rescheduled for the next shutdown in a sequence such that the test schedule does not omit nor favor certain valves or groups of valves. '
| |
| The program tables identify those valves to which cold shutdown testing applies. Refer to Appendix E for discussion of the justification for allowing cold' shutdown vs. quarterly testing for the various affected valves.
| |
| i l
| |
| l D-2
| |
| | |
| .. - . __ _ . . - ~ . _ _ _ _ . ~.- - -._ _ ___._. _ ._. _. _ . _ ._
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| <. t i
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| i Revision 0 07/16/93 '
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| ~
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| I i
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| RELIEF REQUEST NO. VR-2
| |
| * i SYSTEM:
| |
| * i i
| |
| 4 Safety Injection (2998-G-078, Sh.131 & 132) 5
| |
| ,_ COMPONENTS: ,
| |
| j V-3217 V-3227 V-3237 V-3247 j V-3258 V-3259 V-3260 V-3261 1
| |
| V-3215 V-3225 V-3235 V-3245 V-3524 V-3525 V-3526 V-3527 k
| |
| CATEGORY:
| |
| i
| |
| ~
| |
| A/C (Check Valves)
| |
| ; FUNCTION:
| |
| ! These check valves open to provide for high-pressure and-t low-pressure safety injection to the RCS. Each of these-l valves is designated as a pressure isolation valve (PIV) and J
| |
| provides isolation of safeguard systems from the RCS. ;
| |
| 3 SECTION XI REQUIREMENT: '
| |
| i The leakage rate for valves 6-inches or greater shall be evaluated per Subsection IWV-3427(b).
| |
| b
| |
| , BASIS FOR RELIEF:
| |
| a i Leak testing of these valves is primarily for the purpose of L confirming their capability of preventing over-pressurization and catastrophic failure of the safety
| |
| ; injection piping and components. In this regard, special j leakage acceptance criteria is established and included in
| |
| ' the St. Lucie 2 Technical Specifications (Table 3.4-1) that addresses the question of valve integrity in a more appropriate manner for these valves. Satisfying both the Technical Specification and the Code acceptance criteria is l not warranted and implementation would be difficult and
| |
| ; confusing. Specifically applying the trending requirements
| |
| [ of IWV-3427 (b) would result in frequent and excessive maintenance of these valves. The continuation of a strict leakrate acceptance criteria and more frequent testing than i specified by the Code gives a high degree of assurance that j these valves will satisfactory perform their* safety function. '
| |
| 4
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| : D-3 f
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| w -e y q r
| |
| | |
| _ .- ~ - _ . . _. .
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| a s Revision 0 07/16/93
| |
| , RELIEF REQUEST NO. VR-2 (cont.)
| |
| ALTERJATE TESTING:
| |
| Th:
| |
| leakage rate acceptance be established per the St.
| |
| criteria for these valves will Lucie Unit 2 Technical :
| |
| 4
| |
| '' Specifications, Table gpm are unacceptable.
| |
| 3.4-1. , Leakage rates greater than 1.0 l Each of the Reactor Coolant System Pressure Isolation Valve check valve shall be demonstrated operable by verifying leakage to be within its limits:
| |
| : 1. At least once per 18 months.
| |
| : 2. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours or more and if leakage testin'g has not been performed in the previous 9 i months.
| |
| : 3. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.
| |
| : 4. Following valve actuation due to flow through the valve (s) while in MODES 1,2,3, or 4:
| |
| A. Within 24 hours by verifying valve closure, and B. Within 31 days by verifying leakage rate.
| |
| l D-4
| |
| | |
| l 4 ; ,
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| I Revision 0 ,
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| 07/16/93 {
| |
| l SYSTEM:
| |
| RELIEF REQUEST NO. VR-3 l
| |
| Various COMPONENTS:
| |
| '~
| |
| Various '
| |
| CATEGORY:
| |
| 1 Various FUNCTION:
| |
| This is a generic request for relief SECTION XI REQUIREMENT:
| |
| If, for power-operated valves, an. increase in stroke time of 50% or more for valves with full-stroke times less than or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed (IWV-3417 (a) ) ,
| |
| )
| |
| BASIS FOR RELIEF: l The stroke time measurements taken during testing of fast-acting valves (those less than 2 seconds) are subject to considerable variation due to conditions unrelated to the material condition of the valve (eg. test conditions, operator reaction time).
| |
| In accordance with Generic Letter 89-04, Position 6, an alternate method of evaluating stroke times is considered acceptable.
| |
| ALTERNATE TESTING:
| |
| The stroke time evaluation for those valves designated in the Plant Test Procedures as " fast-acting" will not account for successive increases of measured stroke time per IWV-3417(a) with the change in test frequency as required. In lieu of this, the assigned maximum limiting value of stroke time will be established at 2 seconds. Upon exceeding the 2-second limit, the valve will be declared inoperable and corrective action taken in accordance with IWV-3417(b).
| |
| D-5
| |
| | |
| a L 4
| |
| i Revision 0 07/16/93 RELIEF REQUEST NO. VR-4 1
| |
| i SYSTEM:
| |
| Primary Containment
| |
| : - COMPONENTS: , ,
| |
| 1
| |
| : PENETRATION NO. DRAWING NO. VALVES e
| |
| i 10 2998-G-8'18
| |
| ; FCV-25-4 and Blank Flange
| |
| ' 11 2998-G-878 FCV-25-2 and FCV-25-3 23 2998-G-083 24 HCV-14-1 and HCV-14-7 2998-G-083 HCV-14-2 and HCV-14-6 '~
| |
| ~ i
| |
| ! 41 1
| |
| 2998-G-078 Sh 130 SE-03-2A and SE-03-2B l 54 2998-G-091 V-00-101 and Blank Flange 4
| |
| 56 2998-G-879 FCV-25-36 and FCV-25-26 57 2998-G-879 FCV-25-20 and FCV-25-21 l
| |
| . CATEGORY:
| |
| i I A or A/C i l
| |
| 4 FUNCTION:
| |
| i l j These valves are closed to provide containment isolation.
| |
| SECTION XI REQUIREMENT:
| |
| Category A valves snall be seat leak tested and a maximum
| |
| ! permissible leakage rate shall be specified. Individual valve leakage rates ahall be evaluated per IWV-3426 and IWV-1 4
| |
| 3427. (IWV-3426, IWV-3427, NRC Generic Letter 89-04) j BASIS FOR RELIEF:
| |
| For several containment systems, individu.a1 leakage rate tests are impractical due to the configuration of the i system's piping and components. In these cases it is 5
| |
| ' customary to perform leakage tests with the test volume between valves in series or behind valves in parallel paths.
| |
| t i
| |
| i D-6
| |
| -m--
| |
| r- - . yy , e-- ,..,,-,,,y w- --- , - - , -
| |
| * 6 Revision 0 07/16/93 RELIEF REQUEST NO. VR-4 (cont.)
| |
| BASIS FOR RELIEF (cont.): !
| |
| '' In these cases where individypl valve testing is impractical, the valves in multiple valve will be leak tested simultaneously arrangements.
| |
| A maximum permissible leakage rate will be applied to each combination of valves or valve and blank flange. In each of the valve pairs, the two valves are equal in size and type, and the leakage limit is in proportion to their size. The blank flanges used in testing penetrations 10 and 54 have diameters similar in size to their associated valves FCV-25-4 and V-00101. The ' -
| |
| leakage limit assigned to each pair is such that excessive i leakage through any valve, or flange, would be detected and the appropriate corrective action taken..
| |
| . ALTERNATE TESTING:
| |
| The above stated valves and blank flanges will be leak rate tested in pairs. Leakage measurements from tests of multiple valves or blank flanges will be evaluated in accordance with IWV-3426 and IWV-3427.
| |
| D-7
| |
| | |
| l i
| |
| Revision 0
| |
| _- 07/16/93 l'
| |
| RELIEF REQUEST NO. VR-5 SYSTEM: !
| |
| Chemical and Volume Control (2998-G-078 Sh 121)
| |
| COMPONENTS:
| |
| V-2177 '
| |
| V-2190 '
| |
| V-2191 V-2526 l CATEGORY:
| |
| ~ .
| |
| C FUNCTION:
| |
| V-2177 and V-2526 open to provide a flow path for emergency boration from the boric acid makeup pumps to the suction of the charging pumps. Likewise, V-2190 opens to provide a flow path for emergency boration via gravity drain from the boric acid makeup tanks to the suction of the charging pumps. V-2190 closes to prevent recirculation to the boric acid makeup tanks when the boric acid makeup pumps are in operation. Valve V-2191 opens to provide a flow path from the refueling water tank (RWT) to the suction of the charging pumps.as an alternate supply of borated water for boration.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF Testing these valves in the open direction requires the introduction of highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps. This, in turn, would result in the addition of excess boron to the RCS. A rapid insertion of negative reactivity could result in a rapid RCS cooldown and depressurization and possibly a plant trip.
| |
| D-8
| |
| | |
| i b
| |
| a j
| |
| Revision 0 ,
| |
| 07/16/93 t
| |
| RELIEF REQUEST No. VR-5 (cont.)
| |
| BASIS FOR RELIEF (cont. ) :
| |
| l During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of
| |
| '' maintaining proper plant chemistry and the inherent i difficulties that may be encountered during the subsequent i startup due to over-boration of the RCS. The waste i
| |
| management system would also be overburdened by the large amounts of RCS coolant that would require processing to >
| |
| decrease the boron concentration. I l
| |
| i Typically, the boron concentration is increased for shutdown !
| |
| margin during cooldown and prior t,o reaching cold shutdown ~~ -
| |
| conditions. This is the only practical time to perform the partial stroke exercise test since boration during shutdown and startup is undesirable.
| |
| In the event that circumstances 4
| |
| prohibit testing during cooldown, testing for that cold !
| |
| shutdown may be deferred to the next cooldown evolution.
| |
| ALTERNATE TESTING:
| |
| l 1
| |
| Check valve V-2190 will be verified closed quarterly. l l
| |
| Each of these valves will be part stroke exercised once l during each cold shutdown per VR-1 and full stroke exercised !
| |
| during each reactor refueling eui. age. If exercising during i the cooldown evolution is impractical, testing for that cold shutdown period may be deferred.
| |
| l l
| |
| l D-9
| |
| | |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-6 SYSTEM:
| |
| Chemical and Volume Control System (2998-G-078, Sh 121)
| |
| COMPONENT:
| |
| V-2443 V-2444 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide a flow path from the boric acid makeup pumps to the emergency boration header. The to prevent recirculation flow through an idle pump.y close SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-2322. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full-stroke testing these valves requires operating the boric acid makeup full accident pumps at flow through or near each valve.rated flow and verifying Such testing would cause the introduction of. highly concentrated boric acid solution from the boric acid makeup tanks to the suction of the charging pumps. This, in turn, would result in the addition of excess boron to the RCS. This rapid insertion of negative reactivity would result in a rapid RCS cooldown and depressurization. A large enough boron addition would result in an unscheduled plant trip and a possible initiation of Safety Injection Systems.
| |
| During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS. The waste management system would be overburdened by the large amounts of RCS coolant that would require processing to decrease its boron concentration.
| |
| D-10
| |
| | |
| # 0 l
| |
| i Revision 0 07/16/93 RELIEF REQUEST NO. VR-6 (cont.)
| |
| BASIS FOR RELIEF (cont. ) :
| |
| '~
| |
| A second rate circuitinstrumentation measuring that circulates water to the installed howeverVCT has it isflow limited to approximately 30 gpm. During an accident, either pump's discharge check valve must be able to pass a minimum i
| |
| flow capable charging pumps of matching the demand of the two running (greater than 80 gpm.).
| |
| ALTERNATE TESTINGi Each of these valves will be partial stroke exercised (open ' -"
| |
| and closed) quarterly.
| |
| During testing of the boric acid makeup pumps performed during each reactor refue, ling (See Relief Request PR-5),
| |
| system flow rate will be measured to verify full stroke (open) of these valves.
| |
| l l
| |
| l l
| |
| l l
| |
| 4-4 1
| |
| h D-ll i
| |
| | |
| . - _ _ _ . ... . - . _ ~. - . . . - -
| |
| w .
| |
| 1 Revision 0 07/16/93 b
| |
| RELIEF REQUEST NO. VR-7 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 130) a COMPONENTS:
| |
| a V-07000 V-07001 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the RWT to the suction of the associated low-pressure safety injection pump.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising these valves to the open position requires injection into the RCS via.the LPSI pumps . During plant operation this is precluded because the LPSI pumps cannot develop sufficient discharge pressure to overcome primary system pressure. At cold shutdown, the shutdown cooling system cannot provide sufficient letdown flow to the RWT to accommodate full design flow from the RWT while maintaining the necessary core cooling function. Thus, the only practical opportunity for testing these valves is during refueling outages when water from ,the RWT is used to fill the refueling cavity.
| |
| ALTERNATE TESTING:
| |
| T,hese valves will be partial-flow exercised during quarterly testing of the LPSI pumps via the minimum flow circuit and full-flow exercised during each reactor refueling outage.
| |
| D-12
| |
| | |
| ,_ __ _. ._- _ - _ ..__.._ _._ _ .~. . . _ _ _ _ _ _ _ . . . _ _ , _ - . _ _ , _ . _ . . _ .
| |
| I 1
| |
| l Revision 0 i 07/16/93 !
| |
| I i
| |
| i RELIEF REQUEST NO. VR-8 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 130)
| |
| COMPONENTS:
| |
| 3 V-3401 V-3410
| |
| ; CATEGORY:
| |
| J C 4
| |
| FUNCTION:
| |
| These valves open to provide flow paths from the RWT and the containment sump to the suction of the associated high- l pressure safety injection pumps (HPSI). !
| |
| ; SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521) i BASIS FOR RELIEF:
| |
| 1 Full stroke exercising these valves to the open position requires injection via the HPSI pumps into the RCS. During plant operation this is precluded because the HPSI pumps cannot develop sufficient discharge pressure to overcome primary system pressure. During cold shutdown conditions, operation of the HPSI pumps is restricted to preclude RCS
| |
| * system pressure transients that could result in exceeding
| |
| ' the pressure-temperature limits specified.in the Technical Specifications, Section 3.4.9.
| |
| ALTERNATE TESTING '
| |
| These valves will be partial-flow exercised during quarterly testing of the HPSI pumps via the minimum flow circuit and fpil-flow exercised during each reactor refueling outage.
| |
| This alternate testing satisfies the requirement of Generic Letter 89-04, Position 1.
| |
| D-13 .
| |
| 6
| |
| | |
| l l
| |
| 1 l
| |
| - I- . -. - - - .
| |
| > Revision 0 07/16/93 RELIEF REQUEST NO. VR-9 SYSTEM:
| |
| j Safety Injection (2998-G-078 Sh 130)
| |
| ,_ COMPONENTS: ,
| |
| V-3414 V-3427 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the respective HPSI pumps to the high pressure safety injection headers.
| |
| They close to prevent recirculation through an idle pump.
| |
| SECTION XI REQUIREMENT:
| |
| 4 Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising these valves to the open position requires injection into the RCS via the HPSI pumps. During plant operation this is precluded because the HPSI pumps cannot develop sufficient discharge pressure to overcome
| |
| ; primary system pressure. During cold shutdown conditions, i
| |
| full flow operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.
| |
| Partial flow exercising of these valves can be performed by one of the following two methods: when the HPSI pump is used to refill a SIT or when a HPSI pump is recirculated back through the SIT to RWT drain line. Partial-stroke exercising the check valves by filling a SIT can not readily be used because the acceptable SIT level band, specified by the Technical Specifications, is very narrow. The SIT are only refilled on an as needed basis; therefore, the partial flow test cannot readily be incorporated into a quarterly test.
| |
| D-14
| |
| | |
| a
| |
| ~-
| |
| Revision 0 i
| |
| _. 07/16/93 RELIEF REQUEST NO. VR-9 (cont.)
| |
| l BASIS FOR RELIEF: (cont.)
| |
| Partial-stroke exercising of these check valves quarterly can not be performed by using the SIT to RWT drain line.
| |
| This method requires that the' containment isolation valves, 4
| |
| one of them a manual valve, be opened to complete the flow path. This would constitute a breach of containment integrity, as defined in Technical Specifications 3.6.1.1, and therefore use of this flow path is precluded in Modes 1, 2, 3, and 4.
| |
| ALTERNATE TESTING: -
| |
| These valves will be verified closed quarterly and full-flow exercised to the open position during each reactor refueling outage.
| |
| These valves will be part-stroked open during cold shutdown per VR-1.
| |
| e D-15
| |
| | |
| e <
| |
| l I
| |
| Revision 0 07/16/93 I RELIEF REQUEST NO. VR-10 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 130) l COMPONENTS:
| |
| V-3522 V-3547 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the high-pressure safety injection pumps to the RCS for hot-leg injection. Should the normal charging header become disabled, these valves are required to close to direct charging flow to the RCS via the HPSI headers.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising of these valves would require operating a high pressure safety injection (HPSI) pump and injecting into the reactor coolant system through the hot leg injection system. At power operation this is not possible because the HPSI pumps do not avelop sufficient discharge pressure to overcome reactor coolant system pressure. During cold shutdown conditions, full flow operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.
| |
| D-16
| |
| | |
| a e
| |
| ' ~~~
| |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-10 (cont.)
| |
| BASIS FOR RELIEF: (cont.)
| |
| Partial-stro).e exercising of these check valves quarterly can not be parformed by using the SIT to RWT drain line.
| |
| 1
| |
| '' This method requires that the, containment isolation valves, one of them a manual valve, be opened to complete the flow path.
| |
| This would constitute a breach of containment integrity, as defined in Technical Specifications 3.6.1.1, i and therefore use of this flow path is precluded in Modes 1, 2, 3, and 4.
| |
| j ALTERNATE TESTING:
| |
| At least once during each reactor refueling outage these valves will be full-stroke exercised to the open position.
| |
| 2 These check valves will be partial-stroke exercised to the open position and subsequently stroked closed during cold shutdowns per VR-1.
| |
| 2 1
| |
| This alternate te;-ring satisfies the requirement of Generic Letter 89-04, Position 1.
| |
| D-17
| |
| | |
| 1
| |
| * 4 j Revision 0 07/16/93 RELIEF REQUEST NO. VR-11 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh' 131)
| |
| __ COMPONENTS: ,
| |
| V-3113 V-3133 V-3143 V-3766 CATEGORY:
| |
| C FUNCTION: .
| |
| These valves open to provide flow paths from the high-pressure safety injection headers to the RCS.
| |
| SECTION XI REQUIREMENT 1 Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising of these valves would require i operating a high pressure safety injection (HPSI) pump at nominal accident flow rate and injecting into the reactor coolant system. At power operation this is not possible because the HPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure.
| |
| During cold shutdown conditions, full flow operation of the HPSI pumps is restricted to preclude RCS system pressure i transients that could result in exceeding,the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.
| |
| D-18
| |
| | |
| - 4
| |
| ..u . . -
| |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-11 (cont.)
| |
| BASIS FOR RELIEF (cont.):
| |
| Partial flow exercising of these valves is performed whenever its associated SIT is refilled. The acceptable STT _
| |
| i
| |
| '_ level band specified by the Tpchnical Specification is very narrow. The SITS are only refilled on an as needed basis; therefore, the partici flow test cannot readily be incorporated into a quarterly test.
| |
| Partial-stroke exercising of these check valves quarterly can not be performed by using the SIT to RWT drain line. i This method requires that the containment isolation valves, j one of them a manual valve, be opened to complete the flow path.
| |
| This would constitute a breach of containment i integrity, as defined in Technical Specifications 3.6.1.1, and 2, 3,therefore and 4.
| |
| use of this flow path is precluded in Modes 1, l ALTERNATE TESTING: t These valves will be partial flow exercised during cold shutdown per;ods per VR-1.
| |
| At least once during each reactor refueling outage these valves will be full-stroke exercised to the open position.
| |
| 9 D-19
| |
| | |
| O 4 i
| |
| Revision 0 07/16/93 I
| |
| j RELIEF REQUEST NO. VR-12 i SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 131)
| |
| ,_ COMPONENTS: ,
| |
| l V-3524
| |
| ' V-3525 V-3526 i V-3527 CATEGORY-A/C FUNCTION:
| |
| These valves open to provide flow paths from the high- '
| |
| pressure safety injection pumps to the RCS for hot leg injection and close to isolate the safety injection headers from the high pressure of the reactor coolant system.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521) l BASIS FOR RELIEF:
| |
| Full stroke exercising of these valves would require ,
| |
| operating a high pressure safety injection (HPSI) pump at nominal accident flow rate and injecting into the reactor l coolant system. At power. operation this is not possible l i
| |
| because the HPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure. i l
| |
| During cold shutdown conditions, full flow operation of the HPSI pumps is restricted to preclude RCS system pressure transients that could result in exceeding the pressure-temperature limits specified in the Technical Specifications, Section 3.4.9.
| |
| D-20
| |
| | |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-12 (cont.)
| |
| BASIS FOR RELIEF (cont.):
| |
| Partial-stroke exercising of check valves V-3524 and V-3526
| |
| '' quarterly line.
| |
| can not be performed by using the SIT to RWT drain valves, This method requires that the containment isolation one the flow path. of them a manual valve, be opened to complete This would constitute a breach of containment integrity, as defined in Technical Specifications 3.6.1.1, is precluded in Modes 1, and therefore use of this flow path 2, 3, and 4.
| |
| These are simple check valves with,no external means of '
| |
| position indication, thus the only practical means of verifying closure is by performing a leak test or back flow test.
| |
| Performing leak tests of V-3524 and V-3526 involves a considerable effort. The test connection for these valves are room,located in a high radiation area in the pipe penetration aboveandthe one floor.of the two connections is located over 12 feet Testing during operation would constitute an unreasonable burden on the plant staff.
| |
| The other check valves, V-3525 and V-3527, have upstream pressure alarms.
| |
| Should either valve leak by, the pressure instruments would detect the increase and alarm in the control room when the alarm setpoint is exceeded.
| |
| ALTERNATE TESTING:
| |
| These check valves will be partial-stroke exercised to the open position and subsequently stroked closed during cold shutdowns per VR-1.
| |
| These valves will be full-stroke exercised to the open position at least once during each reactor refueling outage.
| |
| This satisfies the requirements of Generic Letter 89-04, Position 1.
| |
| At least once every 18 months these valves will be verified to close in conjunction with PIV leak testing (see VR-2).
| |
| I,n addition, V-3525 and V-352'7 will be leak tested if the upstream pressure monitors indicate alarm during normal operation.
| |
| D-21
| |
| | |
| -. --- - . _ - .- _ .~ .. _ _ -
| |
| t b 4
| |
| ~
| |
| Revision 0 07/16/93 1
| |
| RELIEF REQUEST NO. VR-13 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 132)
| |
| .. COMPONENTS: ,
| |
| V-3215 .
| |
| V-3225 V-3235 V-3245 CATEGORY:
| |
| ) -A/C i
| |
| FUNCTION:
| |
| These valves open to provide flow paths.from the safety 2
| |
| injection tanks to the RCS and close to isolate the tanks from the high pressure of the reactor coolant system and the
| |
| ; safety injtetion headers.
| |
| SECTION XI REQUIREMENT:
| |
| 4 Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| 2 3
| |
| Full stroke exercising of these valves would require injecting from a tank under nominal pressure into a de-pressurized reactor coolant system. At power operation this j
| |
| is not possible because the SIT pressure is insufficient to overcome reactor coolant system pressure.
| |
| Under a large break LOCA accident conditions, the maximum (peak) flow rate through these valves would be approximately 20.,000 gpm. During cold shutdown or refueling outages, the required test conditions for developing this full accident 4
| |
| flow cannot be established.
| |
| 2 D-22 I
| |
| 9
| |
| | |
| ? 6 f
| |
| ~
| |
| Revision 0 07/16/93 l l
| |
| RELIEF REQUEST NO. VR-13 (cont.)
| |
| l l
| |
| BASIS FOR RELIEF (cont. ) : '
| |
| The SIT discharge isolation valves are motor operated valves
| |
| __ with a nominal stroke time oL 52 seconds. Therefore, the isolation valves cannot.be used to simulate the LOCA flow conditions by opening them with a full or partially pressurized SIT. The resulting discharge flow rate would only increase gradually due to the long stroke time of the discharge isolation valve. The flow rate would not be anywhere near the expected peak blowdown rate of 20,000 gpm.
| |
| expected during a large break LOCA.
| |
| ._ L FP&L has reviewed the operating and maintenance history of {
| |
| these valves and similar valves used throughout the industry under comparable conditions. Based on these reviews, there l
| |
| 1s no evidence of valve degradation with respect to their '
| |
| ability to open and satisfactorily pass the required flow.
| |
| It is apparent from the failure data that the primary mode of failure is related to valve leakage - both past the seat and external through the body-bonnet and hinge pin gasket joints. It should also be noted that these valves are not subjected to any significant flow during plant operation as well as maintenance periods; thus it is unlikely that these valves would experience any service-related damage or wear.
| |
| Although check valve disassembly is a valuable maintenance tool that can provide a great deal of information about a valve's internal condition, due to the difficulties associated with these maintenance activities, it should only be performed under the maintenance program at a frequency commensurate with the valve type and service. In this light, FP&L considers the frequency of inspection for these valves of once each 10-year inspection interval to be adequate to ensure the continued operability of these valves.
| |
| These are simple check valves with no external means of position indication, thus the only practical means of verifying closure is by performing a leak test or back flow test. The back flow tests are performed as part of the l
| |
| pressure isolation testing per VR-2.
| |
| i t
| |
| D-23
| |
| | |
| I l
| |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-13 (cont.)
| |
| ALTERNATE TESTING: i At least once during each ISI (10 year) inspection interval i
| |
| , , _ each of these valves will be disassembled, inspected, and manually stroked to_ verify operability. Should a valve !
| |
| under inspection be found to be inoperable, then the remaining three valves will be inspected during the same ;
| |
| outage. Assurance of proper reassembly will be provided by performing a leak test or partial-flow test prior to l returning a valve to service following disassembly.
| |
| These valves will be verified closed in conjunction with PIV~~ ~
| |
| See VR-2 for PIV testing frequency.
| |
| 1 leak testing.
| |
| l l
| |
| l i
| |
| 4 l
| |
| I D-24
| |
| | |
| v s l
| |
| l Revision 0 07/16/93 RELIEF REQUEST NO. VR-14 SYSTEM:
| |
| Safety Injection (2998-G-078 Sh 132)
| |
| __ COMPONENTS: ,
| |
| V-3217 V-3227 V-3237 V-3247 CATEGORY:
| |
| A/C FUNCTION:
| |
| These valves open to provide flow paths from the safety injection headers to the RCS and close to isolate the headers from the high pressure of the reactor coolant system.
| |
| SECTION XI REQUIBEMENT:
| |
| Check valves shall be exercised at least once every 3 months, e:teept as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising of these valves would require injecting from a tank under nominal pressure into a de-pressurized reactor coolant system. At power operation this is not possible because the SIT pressure is insufficient to overcome reactor coolant system pressure.
| |
| Under a large break LOCA accident conditions, the maximum (peak) flow rate through these valves would be approximately 20,000 gpm. During cold shutdown or refueling outage the required test conditions for developing this full accident flow cannot be established.
| |
| D-25
| |
| | |
| 3' s >
| |
| 1 .
| |
| 1
| |
| :i s
| |
| j -
| |
| Revision 0 07/16/93
| |
| ;- RELIEF REQUEST NO. VR-14 (cont.)
| |
| 4 BASIS FOR RELIEF (cont. ) : '
| |
| The SIT discharge isolation valves are motor operated valves with a nominal stroke time of,52 seconds.,,Therefore, the isolation valve cannot be used to simulate-the LOCA flow conditions by opening it with a full or partially pressurized SIT. The discharge flow rate would only i increase gradually due to the long stroke time of the discharge isolation valve. . The flow rate would not be anywhere near the expected peak blowdown rate of 20,000 gpm.
| |
| J expected during a large break LOCA.
| |
| j FP&L has reviewed the operating and maintenance history of
| |
| * these valves and similar valves used throughout the industry under comparable conditions.
| |
| These four valves have been in
| |
| )
| |
| operation.in Unit 2 since the plant startup in 1983. A total of 3 plant work' orders have been initiated for work on
| |
| : these valves. Of the,three work orders, one was to repair
| |
| , seat leakage identified by a seat leakage test and the other two were for disassembly and inspection per Generic Letter 89-04. A search of the Nuclear Plant Reliability Data System for problems with valves similar to these revealed 12 reports - 7 due to seat leakage and the remaining 5 were related to gasket leaks. Based on these reviews there is no l evidence of valve degradation with respect to their ability i
| |
| 1.
| |
| to open and satisfactorily pass the required flow. It is apparent from the failure data that the primary mode of 4
| |
| failure is related to valve leakage - either past the seat or externally through the body-bonnet and hinge pin gasket joints.
| |
| 4 In order to disassemble and inspect these valves , the reactor coolant system must.be placed in mid-loop or i
| |
| " reduced inventory" condition for several days. In response to issues raised in NRC Generic Letter 88-17, FP&L is concerned about continued operations with the plant in a 4
| |
| condition of " reduced inventory." During these periods, the risk of over-heating the core is increased due to the higher
| |
| ; probability of an incident where shutdown cooling is lost.
| |
| , This risk is' compounded by the reduced volume of water available to act as a heat sink should cooling be lost.
| |
| 4 Since 1982 there have been at least six (6) reported events 2
| |
| in the industry where cooling flow was lost while a plant was in a " reduced inventory" condition.
| |
| . D-26 4
| |
| 4
| |
| | |
| - . _ . . ~ . ._ .-- .
| |
| e >
| |
| l l
| |
| l Revision 0 !
| |
| t 07/16/93 l
| |
| RELIEF REQUEST NO. VR-14 (cont.)
| |
| :I BASIS FOR RELIEF (cont. ) :
| |
| Although check valve disasssably is a valuable maintenance tool that can provide a great deal of information about a
| |
| - valve's internal condition, dye to the difficulties
| |
| ! associated with these maintenance activities, it should only i be performed under the maintenance program at a frequency commensurate with the valve type and service. Given the '
| |
| i lack of evidence that these valves are experiencing significant failures with respect to their capability of passing the design flow rates and the apparent sensitivity ;
| |
| of the valves to leak testing, a frequency of inspection for i
| |
| these valves of once each 10-year inspection interval is ~~ -
| |
| i adequate valves.
| |
| to ensure the continued operability of these These are simple check val'es v with no external means of
| |
| ' position indication, thus the only practical means of i
| |
| verifying closure is by performing a leak test or back flow test.
| |
| 4 The back flow testing is performed as stated in VR-2.
| |
| In addition to periodic leak testing, the upstream pressure of each valve is monitored by a pressure indicator and alarm. Should any of these valves experience even minor t
| |
| leakage, the upstream pressure alarm would alert plant personnel.
| |
| ALTERNATE TESTING:
| |
| During cold shutdown and refueling periods, each of these valves will be partial-stroke exercised with approximately 1,750 gpm (8 percent of maximum accident flow) using the LPSI pumps per Relief Request VR-1.
| |
| At least once during each ISI (10 year) inspection interval d each of these valves will be disassembled, inspected, and manually stroked to verify operability. Should a valve under inspection be found to be inoperable, then the 4
| |
| remaining three valves will be inspected during the same outage. Assurance of proper reassembly will be provided by performing a leak test or partial-flow test prior to i
| |
| r,eturning a valve to service following disassembly.
| |
| These valves will be verified closed in conjunction with PIV leak testing. See VR-2 for PIV testing frequency.
| |
| D-27
| |
| | |
| e e t
| |
| t
| |
| _ _ _ _ _ _ _ _ . - - _ _ ~ _
| |
| t
| |
| , ' Revision 0 07/16/93 RELIEF REQUEST NO. VR-15 '
| |
| SYSTEM:
| |
| i Safety Injection (2998-G-078 Sh 132) i . COMPONENTS:
| |
| V-3258 V-3260 V-3259 V-3261 ;
| |
| CATEGORY: I A/C I
| |
| FUNCTION:
| |
| These valves open to provide flow paths from the high/ low pressure safety injection headers to the RCS and close to isolate system.
| |
| coolant the headers from the high pressure of the reactor SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by'IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Since no full flow recirculation path exists, full stroke exercising of these valves would require operating a low pressure safety injection (LPSI) pump at nominal accident flow rate and injecting into the reactor coolant system. At power operation this is not possible because the LPSI pumps do not develop sufficient discharge pressure to overcome reactor coolant system pressure.
| |
| Partial flow exercising of these valves is performed when ever its associated SIT is refilled. These valves are Pressure Isolation Valves which requires that they are verified flow through closed them. and leak tested within 24 hours following The acceptable SIT level band specified by the Technical Specification is very narrow. The SITS are only refilled partial flow test cannot on an as needed basis; therefore, the readily be incorporated into a quarterly test.
| |
| D-28
| |
| | |
| e o
| |
| ~~
| |
| Revision 0 07/16/93 4
| |
| RELIEF REQUEST NO. VR-15 (cont.)
| |
| * BASIS FOR RELIEF (cont. ) :
| |
| These are simple check valves with no external means of position indication, thus the only practical means of verifying test.
| |
| closure is by performing a leak test or back flow ALTERNATE TESTING:
| |
| These valves will be partial flow tested and then verified closed whenever its associated SIT is refilled.
| |
| These valves will be full-stroke exercised to the open ~~
| |
| position VR-1.
| |
| during cold shutdown periods per Relief Request These valves will be verified closed in conjunction with PIV leak testing. See VR-2 for PIV testing frequency.
| |
| 1 I
| |
| 1 l
| |
| l 1
| |
| O D-29
| |
| | |
| 1 r l
| |
| 1 Revision 0 07/16/93 l
| |
| RELIEF REQUEST NO. VR-16 SYSTEM:
| |
| 1 Primary Containment
| |
| ._ COMPONENTS: ,
| |
| )
| |
| Valves 6-inches NPS and larger subject to leakage rate testing per 10CFR50, Appendix J.
| |
| CATEGORY:
| |
| A/C (Check Valves)
| |
| A (Motor-operated valves) ~
| |
| FUNCTION: 1 Each of these valves is designated as a containment isolation valve maintaining the leakrate integrity of the primary containment in-the case of an accident.
| |
| SECTION XI REQUIREMENT:
| |
| The leakage rate for. valves 6-inches nominal pipe size and i
| |
| larger shall be evaluated per subsection IWV-3427 (h) . (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| l The usefulness the burden of applying this requirement does not justify of compliance. !
| |
| Generic Letter 89-04, Position This 10.position is supported by the i
| |
| )
| |
| ALTERNATE TESTING: i Leakrate test results for containment isolation valves six (6) inches nominal pipe size and greater will be evaluated l per IWV-3426 and IWV-3427 (a) however, the requirements of IWV-3427(b) will not be applied. This satisfies the requirements of Generic Letter 89-04, Position 10.
| |
| D-30 i
| |
| | |
| b
| |
| ~
| |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-17
| |
| .*~.:
| |
| WITHDRAWN (Rev 0, 07/16/93) a D-31
| |
| | |
| f a
| |
| ~~ Revision 0
| |
| : 07/16/93 RELIEF REQUEST NO. VR-18 SYSTEM:
| |
| j Makeup Water (2998-G-084)
| |
| COMPONENT 2 ,
| |
| V-15328 CATEGORY:
| |
| A/C FUNCTION: ~~
| |
| This valve. closes to provide primary containment for the penetration containment related building.to the makeup water supply line to the SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IUV-3521)
| |
| BASIS FOR RELIEF:
| |
| This is a simple check valve with no external means of position indication, thus the only practical means of verifying test.
| |
| closure is by performing a leak test or back flow Performing such a test demands that the makeup water supply line be isolated. This effectively isolates the sole supply of fire water to the containment which is unacceptable under any plant conditions. Thus, prior to leaktesting in this manner an alternate firewater source must be established by rigging several temporary fire hoses through the maintenance hatch to the various fire fighting stations in the containment building. This is not possible during normal operation when primary containment is required and would constitute an undue burden on plant personnel ;
| |
| i during cold shutdowns.
| |
| ALTERNATE TESTING:
| |
| At least once every refueling outage, this valve will be verified to close in conjunction with the Appendix J leak testing program.
| |
| D-32 I
| |
| i l
| |
| | |
| P =
| |
| I
| |
| _. Revision 0 !
| |
| 07/16/93 )
| |
| RELIEF REQUEST NO. VR-19 1
| |
| ; SYSTEM: 1 Instrument Air (2998-G-085, Sh 2) I i -
| |
| COMPONENT: <
| |
| 4
| |
| , V-18195 i CATEGORY: '
| |
| 4
| |
| , A/C FUNCTION: ~
| |
| This valve closes to provide primary containment for the penetration containment building.
| |
| related to the instrument air supply line to the ;
| |
| i SECTION XI REQUIREMENT:
| |
| check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| { BASIS FOR RELIEF:
| |
| This is a simple check valve with no external means of position indication, thus the only practical means of verifying closure is by performing a leak test or back flow test.
| |
| air to the Such a test necessates isolation of all instrument containment. There are over 50 valves, instruments, and controllers supplied by this one line.
| |
| During a normal refueling outage when leak testing is normally performed, an alternate instrument air compressor must be connected to the isolated section of the instrument air components.
| |
| line in order to supply air to critical air-operated The supply hose from the air compressor to the instrument air line is typically routed through the containment maintenance hatch.
| |
| During normal plant operation this is not practical due to the many critical operational components supplied by the instrument air system, the requirement to maintain primary containment plant transients.
| |
| integrity, and the potential for unacceptable D-33
| |
| | |
| P e l
| |
| Revision 0 l 07/16/93 i
| |
| RELIEF REQUEST NO. VR-19 (cont.)
| |
| BASIS FOR RELIEF (cont.)
| |
| During cold shutdown, the activities associated with entry 1 into the containment building, securing all instrument air
| |
| __ inside.the containment, and opening the maintenance hatch to provide the alternate air supply are extensive and would likely result in an extension of any interim outage (cold shutdown period). Thus testing this valve during cold shutdown periods is considered to be an unreasonable burden on the plant staff and not commensurate with the potential gain in plant safety afforded by performance of this test.
| |
| ALTERNATE TESTING: '~
| |
| At least once every refueling outage, this valve will be verified to close in conjunction with the Appendix J leak testing program.
| |
| 9 D-34
| |
| | |
| ~ Revision 0 07/16/93 RELIEF REQUEST NO. VR-20 SYSTEM:
| |
| Containment Spray (2998-G-088)
| |
| __ COMPONENTS: ,
| |
| V-07119 V-07120 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the refueling water tank (RWT) to the containment spray and safety injection suction headers.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke . exercising of these valves would require :
| |
| simultaneous operation of one HPSI pump and one LPSI pump injecting into the RCS, and one containment spray pump injecting into its spray header to verify the maximum design accident flow. Such a test is not practical during any plant operational odes.
| |
| ALTERNATE TESTING:
| |
| During quarterly pump testing each of these valves will be partial-stroke exercised via recirculation through the minimum flow test circuits of the various systems. The valves will also be partial-stroke exercised during the series of pump substantial flow tests and check valve exercises performed each refu'eling outage.
| |
| D-35
| |
| | |
| S' s Revision 0 07/16/93 RELIEF REQUEST NO. VR-20 (cont.)
| |
| ALTERNATE TESTING (cont.):
| |
| 1 d During each reactor refueling outage at least one of these
| |
| ''_ valves will be disassembled, inspected, and manually stroked to verify operability. Should a valve under inspection be i
| |
| found to be inoperable, then the other valve will be inspected during the same outage, after which the rotational !
| |
| inspection schedule will be re-initiated. This satisfies 2
| |
| l the requirements of Generic Letter 89-04, Position 2 and, as such, is considered to be approved upon submittal. !
| |
| l l
| |
| 4 l l
| |
| l 4
| |
| I f
| |
| D-36
| |
| | |
| i ,
| |
| i i
| |
| i
| |
| ~^
| |
| Revision 0 07/16/93
| |
| , RELIEF REQUEST NO. VR-21 SYSTEM:
| |
| Containment Spray (2998-G-088)
| |
| COMPONENTS: ,
| |
| V-07129
| |
| . V-07143 CATEGORY: I l
| |
| C l FUNCTION:
| |
| 1 These valves open to provide flow paths from the respective containment spray pump to the containment spray headers.
| |
| SECTION XI REQUIREMENT: i Check valves shall be exercised at least once every 3 4
| |
| months, except as provided by IWV-3522. (IWV-3521)
| |
| { BASIS FOR RELIEF:
| |
| ' Full stroke exercising of these valves would require operating each containment spray pump at nominal accident flow rate. Exercising these valves via the normal containment spray flow path would result in spraying down the containment - an unacceptable option. The only other practical flow path available for such a test requires i
| |
| pumping water from the refueling water tank (RWT) to the reactor coolant system (RCS) via the shutdown cooling loops.
| |
| During plant operation, the containment spray pumps cannot develop sufficient discharge pressure to overcome RCS pressure.
| |
| i i
| |
| ' At cold shutdown, the shutdown cooling system cannot provide sufficient letdown flow to the RWT to accommodate full i '
| |
| design flow from the RWT while maintaining the necessary core cooling function.
| |
| D-37 P
| |
| * o I
| |
| ~~
| |
| Revision 0 07/16/93
| |
| )
| |
| RELIEF REQUEST NO. VR-21 (cont.)
| |
| ALTERNATE TESTING:
| |
| Each of these valves.will be partial-stroke exercised
| |
| -.- quarterly in conjunction with testing of the containment spray pumps via the minimum flow test line.
| |
| During each refueling outage, least once to demonstrate each valve will be exercised at full stroke capability.
| |
| ?
| |
| D-38
| |
| | |
| ry e 1
| |
| ~ Revision 0 s
| |
| 4 07/16/93
| |
| , RELIEF REQUEST NO. VR-22 i
| |
| 1 SYSTEM:
| |
| Containment Spray (2998-G-088)
| |
| __ COMPONENTS: < !
| |
| V-07172 V-07174 i l i
| |
| CATEGORY:
| |
| i 1 C l
| |
| - .. j l
| |
| FUNCTION:
| |
| i These valves open to provide flow paths from tr.e containment l
| |
| sump to the headers containment during spray and safety injection suction recirculation.
| |
| 2 SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521) j BASIS FOR RELIEF:
| |
| There are no provisions for full or partial flow exercising those valves. In order to pass full flow through these valves, the containment sump must be flooded and followed by simultaneous operation of one HPSI pump injecting into the RCS and one containment spray pump injecting into its spray header. Such a test is not practical during any plant operational mode.
| |
| i ALTERNATE TESTING:
| |
| During each reactor refueling outage at least one of these
| |
| ,~
| |
| valves will be disassembled, inspected, and manually stroked to verify operability. Should a valve under inspection be f.ound to be inoperable, then the other valve will be inspected during the same outage, after which the rotational inspection schedule will be repeated. This satisfies the requirements of Generic Letter 89-04, Positio,n 2 and is considered to be approved upon submittal.
| |
| D-39 f
| |
| | |
| 44 s I
| |
| I i
| |
| ~~ Revision 0 07/16/93 RELIEF REQUEST NO. VR-23 SYSTEM:
| |
| Containment Spray (2998-G-088)
| |
| COMPONENTS: <
| |
| V-07192 V-07193 1
| |
| CATEGORY: '
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the respective containment spray headers to the containment spray rings.
| |
| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF:
| |
| Full stroke exercising of these valves would require '
| |
| operating each containment spray pump at nominal accident flow rate. Since exercising these valves through the normal containment spray flow path would result in spraying down the containment, this is considered impractical.
| |
| Since flow through these valves is not possible; non-intrusive test methods, should they become approved, would not work on these check valves.
| |
| l l
| |
| I D-40 i i
| |
| l l
| |
| )
| |
| | |
| V '' +
| |
| ' Revision 0 07/16/93 RELIEF REQUEST NO. VR-23 (cont.)
| |
| ALTERNATE TESTING:
| |
| During each reactor refueling outage at least one of these valves will be disassembled,. inspected, and manually stroked to verify operability. Should a valve under inspection be found to be inoperable, then the other valve will be inspected during the same outage, after which the rotational inspection schedule will be re-initiated. This satisfies j the requirements of Generic Letter 89-04, Position 2 and, as such, is considered to be approved upon submittal.
| |
| D-41
| |
| | |
| i F ,
| |
| 1 1
| |
| +
| |
| 1 Revision 0 l 07/16/93 {
| |
| RELIEF REQUEST NO. VR-24 SYSTEMT '~~
| |
| Containment Spray (2998-G-088)
| |
| COMPONENTS:
| |
| V-07256' V-07258 CATEGORY:
| |
| C FUNCTION:
| |
| These valves open to provide flow paths from the hydrazine pumps to the respective containment spray pump suction i header. i SECTION XI REQUIREMENT:
| |
| Check valves months, shall be exercised at least once every 3 except as provided by IWV-3522. (IWV-3521)
| |
| BASIS FOR RELIEF: ;
| |
| Testing these valves using the only flow path available (via the hydrazine pumps) would contaminate the containment spray system and refueling water tank with hydrazine. - Each of the hydrazine pumps discharge through its check valve into the suction piping of its containment spray pump. The hydrazine would then be pumped to the RWT during the quarterly containment spray pump Code test using the mini-flow recirculation line. Continued testing would build up the concentration in its storage tank.
| |
| of hydrazine in the RWT and deplete the level ALTERNATE TESTING:
| |
| During each reactor refueling outage these valves will be full-stroke exercised.
| |
| D-42
| |
| | |
| t' ,
| |
| ~~ Revision 0 07/16/93 RELIEF REQUEST NO. VR-25 WITHDRAWN (Rev 0, 07/16/93) l 4
| |
| D-43
| |
| | |
| t- o n.
| |
| ^
| |
| Revision 0 07/16/93 RELIEF REQUEST NO. VR-26 WITHDbWN (Rev 0, 07/16/93) l l
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| I l
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| i l
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| D-44
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| l JP e i
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| i '
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| Revision 0 i l 07/16/93 j RELIEF REQUEST NO. VR-27 l SYSTEM:
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| ~
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| Feedwater System (2998-G-080, Sh 2)
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| ,_ COMPONENTS: , ,
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| V-09303 l V-09304 l V-09305 CATEGORY:
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| C ,
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| ' "~
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| l FUNCTION:
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| These valves open to provide flow paths from the auxiliary l
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| ' feedwater pump discharge to the condensate storage tank to ensure adequate pump cooling during low flow conditions.
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| SECTION XI REQUIREMENT: l l Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
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| BASIS FOR RELIEF:
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| There is no flow rate instrumentation available to verify i valve full-stroke exercising of these valves as required by i Generic Letter 89-04, Position 1.
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| ALTERNATE TESTING:
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| ! During quarterly pump testing each of these valves will be partial-stroke exercised via recirculation through the minimum flow test circuits with no flow measurements.
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| t D-45 l
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| i
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| 9 l ~
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| hevision 0 07/16/93
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| )
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| * RELIEF REQUEST NO. VR-27 (cont.)
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| ALTERNATE TESTING (cont.):
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| During each reactor refueling' outage at least one of these i valves will be disassembled, inspected, and manually stroked to verify operability. Should a valve under inspection be 4
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| ' found to be inoperable, then'the other two valves will be inspected during the same outage, after which the rotational inspection schedule will be re-initiated. This. satisfies l
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| the requirements of Generic Letter 89-04, Position 2.
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| 4 i
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| 8 D-46 i
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| " Revision 0 07/16/93 RELIEF REQUEST NO. VR-28 SYSTEM:
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| i Safety Injection System (2998-G-078, Sh 130)
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| __ COMPONENTS: ,
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| V-3104 V-3105 CATEGORY:
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| C FUNCTION:
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| These valves open to provide for mini-flow recirculation flow paths from the low pressure safety injection pumps to the refueling water tank. This minimum flow through the respective pumps removes pump heat in the event they are operating under low or no flow conditions. The valves close to prevent recirculation through the idle pump, and to prevent overpressurization of the LPSI piping from the discharge pressure of the.HPSI pump.
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| SECTION XI REQUIREMENT:
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| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521)
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| BASIS FOR RELIEF:
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| There is no flow rate instrumentation available to verify valve full-stroke exercising as required by Generic Letter 89-04, Position 1.
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| ALTERNATE TESTING:
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| During quarterly pump testing each of these valves will be partial-stroke exercised (open) via recirculation through the minimum flow test circuits with no flow measurements.
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| D-47
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| - - - . - . .. - . . . ~~ - -- -...-..---- - . - . .. . . - - . . - . . . - .
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| (l*
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| * j I
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| .-- l Revision 0 07/16/93 RELIEF REQUEST NO. VR-28 (cont.)
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| l ALTERNATE TESTING (cont.):
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| During each reactor refueling outage these two valves will !
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| . ,_ be flow tested. The test wiLa calculate the flow through the mini-flow line by draining the reactor coolant system through the line while observing the pressurizer level drop or refueling water tank level increase. The level change divided by the time can be used to verify the full flow exercise of the two check valves.
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| I I
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| D-48 l
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| i-i
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| l 4
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| .( e t
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| P i
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| I i _. Revision 0 h 07/16/93 RELIEF REQUEST NO. VR-29 SYSTEM:
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| 1 4
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| Safety Injection (2998-G-078, Sh.131)
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| .,_ COMPONENTS: <
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| i
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| ; V-3480 V-3651 i
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| V-3481 V-3652
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| ! CATEGORY:
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| 1' .
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| 1 FUNCTION:
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| a The motor-operated valves open for residusi heat removal recirculation during shutdown.
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| designated as a pressure isolation Each valve of these valves is i
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| isolation of safeguard systems from the RCS. (PIV) and provides SECTION XI REQUIREMENT:
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| 1 The leakage rate for valves 6-inches or greater shall be l
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| )
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| evaluated per Subsection IWV-3427 (b) . (IWV-3521)
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| BASIS FOR RELIEF:
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| l Leak testing of these valves is primarily for the purpose of confirming their capability of preventing over-pressurization and catastrophic failure of the low pressure safety injection piping and components. In this regard, special leakage acceptance criteria is established and included in the St. Lucie 2 Technical Specifications (Table 3.4-1) in a more appropriate manner for these valves.that addresses the quest Satisfying both the Technical Specification and the Code accepta.nce criteria is not warranted and implementation would be difficult and confusing.
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| l l
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| D-49 l
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| r a l
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| Revision 0
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| _. 07/16/93 l
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| RELIEF REQUEST NO. VR-29 (cont.)
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| 1 l
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| ALTERNATE TESTING:
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| The leakage rate acceptance criteria for these valves will be established per the St. Lucie Unit 2 Technical Specifications, Table 3.4-1.
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| : l. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the, previous test by an amount that reduces the i margin between measured leakage rate and the '
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| maximum permissible rate of 5.0 gpm by 50% or -
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| greater.
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| : 2. Leakage rates greater than 1.0 gpm, but less than or equal-to 5.0 gpm, are unacceptable if the latest measured r~te a exceeded the rate determined by the pre'viouis test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
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| : 3. Leakage rates greater than 5.0 gpm are unacceptable.
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| Each Reactor Coolant System Pressure Isolation Valve motor-operated valves shall be demonstrated operable by verifying leakage to be within its limits:
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| : 1. At least once per 18 months, and
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| : 2. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve.
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| D-50
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| (
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| * l Revision 0 07/16/93 RELIEF REQUEST NO. VR-30 (cont.)
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| ALTERNATE TESTING (cont.):
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| During each reactor refueling outage at least one of these valves will be disassembled, inspected, and manually stroked to verify operability. Inspections shall be scheduled such that valves will be checked in a rotating sequence such that each valve is subject to inspection at least once every three (3) years. Should a valve be found to be inoperable, then the other valve will be inspected during the same outage, after which the rotational inspection schedule will be resumed. This satisfies the requirements of Generic -
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| Letter 89-04, Position 2. ,
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| I St. Lucie Unit 2 was granted a one time relief by the NRC for the disassembly of V-3103 during the 1992 refueling outage. Both check valves must be disassembled during the next refueling outage. See NRC SER letter from Herbert N.
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| Berkow to J. H. Goldberg dated 2 June 1992.
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| t 4
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| D-52
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| < a 4
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| 1
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| ~' Revision 0 07/16/93 RELIEF REQUEST NO. VR-31 (cont.)
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| ALTERNATE TESTING (cont.):
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| During each reactor refueling outage at least one of these valves will be disassembled, Jnspected, and manually stroked to verify operability. I i
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| found to be inoperable, Should a valve under inspection be be inspected during the same outage,then the which after remaining the other valve will )
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| rotational inspection schedule will be re-initiated.
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| Following flow or leak valve re-assembly no testing is possible (partial-testing) i prior to placing the valves in service, thus none will be performed. This satisfies the requirements of Generic Letter 89-04, Posit' ion 2 and, as . . -
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| such, is considered to be approved upon submittal.
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| e J
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| l d
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| 4
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| )
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| 4 e
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| D-54
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| L
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| __ l
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| _. Revision 0 I 4
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| ! 07/16/93 RELIEF REQUEST NO. VR-32
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| ; SYSTEM:
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| Safety Injection (2998-G-078, Sh 130)
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| , , _ COMPONENTS: e V-3101
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| ). CATEGORY:
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| C . ,
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| I
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| ~
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| FUNCTION: -
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| j This valve opens to provide a flow path for borated wat7r i from the safety injection tanks (SIT's) to the volume control tank (VCT) to provide sufficient water inventory for I plant unavailable.
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| cooldown should the refueling water tank (RWT) become 1
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| SECTION XI REQUIREMENT:
| |
| Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-3521) i
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| ; BASIS FOR RELIEF:
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| 4 Transferring the large quantity of water from a SIT to the VCR needed to verify full stroke would result in a {
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| significant increase of the boron concentration within the !
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| VCT and in the charging system makeup to the reactor coolant system (RCS) as well, i
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| During normal plant operation, any increase of the VCT boron concentration could result in the excessive boron concentration in the RCS along with the insertion of negative reactivity. Ultimately, the RCS would experience i t
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| cooldown and depressurization with *.he potential for a plant trip.
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| 4
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| ) e 1
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| d D-55
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| / ,
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| I
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| ; ' Revision 0 07/16/93 RELIEF REQUEST NO. VR-32 (cont.)
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| BASIS FOR RELIEF (cont.)
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| During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of
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| __ maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent 4
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| startup due to over-boration of the RCS. The waste 1 management system could also be overburdened by the large amounts of RCS coolant that would require processing following dilution activities. During cold shutdown, transferring a limited quantity of water (less than that needed to confirm full stroke) from a SIT is practical. -
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| ALTERNATE TESTING:
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| i This valve will be partial flow tested during cold shutdowns per VR-1 and full-flow exercised once every refueling nutage.
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| i i
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| i 1
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| 3 d
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| 1 D-56
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| /' ., l
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| ~ Revision 0 07/16/93 RELIEF REQUEST NO. VR-33 SYSTEM:
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| Feedwater (2998-G-080, Sh 2)
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| _. COMPONENTS: <
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| j i
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| SE-09-2 SE-09-3 SE-09-4 SE-09-5 CATEGORY:
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| B 1
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| .- \
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| FUNCTION: I I
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| These solenoid valves cycle open and closed during an AFAS actuation to control auxiliary feedwater flow to the steam generators.
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| SECTION XI REQUIREMENT:
| |
| If, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 sec. or 50% or more for valves with full-stroke times less than or equal to 10 see is ,
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| i observed, test frequency shall be increased to once each month until corrective action is taken ... (IWV-3 414 (a) )
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| BASI'S FOR RELIEF:
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| These valves are pilot-operated, normally closed, solenoid globe valves. When their solenoid coil is energized, the magnetic force lifts the pilot disk, opening the pilot orifice in the main disk. Any pressure in the chamber above
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| -the main disk then vents through the pilot orifice to the downstream side of the valve. With the pressure vented above the main disk, the up' stream pressure acting on the lower side of the main disk lifts it off the' main seat opening the valve. In the absence of a pressure differential, no pressure force exists tending to seat the disc, therefore the magnetic force of the solenoid coil is sufficient, acting through the stem, pilot disc, and pin, to directly lift the main disc off the seat, opening the valve.
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| D-57
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| - ..= - - .. . _ - - -- .-.-.- . - . -
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| Revision 0 07/16/93 l RELIEF REQUEST NO. VR-33 (cont.)
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| BASIS FOR RELIEF: (cont.)
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| Due to_this arrangement, the stroke times measured without
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| '' differential pressure are slower and vary significantly from test to test causing the valves to be subjected to increased testing per IWV-3417 (a) frequently and unnecessarily.
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| i In order to establish the appropriate pressure conditions needed for proper testing.the associated AEW pump must be in operation discharging into the steam generators. Pumping from the auxiliary feedwater system into the steam ;__
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| i generators during normal operation is impractical and *_
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| 4 undesirable. Injecting the relatively cold auxiliary feedwater into the main feedwater lines while the plant is i
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| operating at power would cause a large temperature i
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| differential (approximately 375 deg-F) . Significant thermal j
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| shock and fatigue cycling of the feedwater piping and steam generator nozzles ceuld result.
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| ALTERNATE TESTING: I During quarterly testing, these valves will be exercised and !
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| fail-safe tested. During this exercising stroke times will be not recorded be applied.but the corrective action of IWV-3417(a) will If a valve stroke time should the maximum allowed stroke time it will be placed out of service. i During cold shutdown periods the valves will be exercised per VR-1. During this testing valve stroke times will be 4
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| recorded and evaluated (including corrective action) in accordance with IWV-3417 (a) .
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| 4 8
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| D-58 1
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| ,' s l
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| Revision 0 07/16/93 RELIEF REQUEST NO. VR-34 SYSTEM: i i
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| Component Cooling Water (2998-G-082)
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| ,, COMPONENTS: ,
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| TCV-14-4A TCV-14-4B CATEGORY:
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| B
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| ~; -
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| FUNCTION:
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| These control valves regulate the flow of intake cooling water through the component cooling system heat exchangers.
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| In the event of loss of air pressure or electric power these valves fail open.
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| SECTION XI REQUIREMENT:
| |
| If, for power operated valves, and increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater than 10 sec. or 50% or more for valves with full-stroke times less than or equal to 10 see is observed, test frequency shall be increased to once each month until corrective action is taken ... (IWV-3414 (a) )
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| BASIS FOR RELIEF:
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| These two valves are operated via air signals from their temperature controllers.
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| In the manual mode of operation the positioning manipulating air signal from the controllers is varied by a rheostat. Due to the slow response time of the controllers, in the manual mode there is the potential for a large variation in valve stroke time from test to test. This inherent variability is sufficient to cause a valve to fall into the increased test frequency corrective action range without any significant physical change in the mechanical condition of the valve.
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| D-59
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| j 3 s l
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| . l 4
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| ' Revision 0 07/16/93 i
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| RELIEF REQUEST NO. VR-34 (cont.)
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| 1 BASIS FOR RELIEF: (cont.)
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| These valves can also ba operated (opened) by closing the I valve using the manual controller and then isolating and
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| __ venting the control air signal to the valves. The elapsed time required to isolate and then vent the control air is added to the time required to vent the air pressure from the valve operator to arrive at the measured valve stroke time. i Thus the measured stroke time is as much a function of the capability of the individual operator to manipulate the i valves as it
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| ', is the mechanical condition of the valve.
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| Typically successive stroke times vary sufficiently to cause, !
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| )
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| the valves to be subjected to increased testing per IWV- ,
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| 3417 (a) frequently and unnecessarily.
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| 2
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| ; ALTERNATE TESTING:
| |
| During quarterly testing, these valves will be exercised and fail-safe tested. During this exercising stroke times will 1 be recorded not be applied. but the corrective action of IWV-3417(a) will If a valve stroke time should the maximum
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| , j allowed stroke time it will be placed out of service.
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| t i
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| l D-60
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| > a i
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| ~ ~ - ~ - - ~+- .. . . _ . . _ _ . _ ,__ _ , , _ _
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| l l
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| l l
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| l l
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| 4 Appendix E l I
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| *~ l Valve Program Cold Shutdown Justifications a
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| I 1
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| I l
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| (
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| l 1
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| 4 4
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| 4
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| i' s
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| _. Revision 0 07/16/93 Appendix E: COLD SHUTDOWN JUSTIFICATIONS This appendix is intended to provide the justification for performing valve exercising only at cold shutdown conditions as permitted by IWV-3412 (a), 3415 and 3522. Specifically included in this category are the following:
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| A valve whose failure in a position other than its \
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| normal position could jeopardize the immedit.e safety of the plant or system components; A valve whose failure in a position other than its normal position could cause all trains of a safeguard system to be inoperable; A valve whose failure in a position other than its normal- position that might cause a transient that could lead to a plant trip; or '
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| When test requirements or conditions are precluded by system operation or access.
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| Cold shutdown testing is performed under conditions outlined in Relief Request VR-1.
| |
| Reactor Coolant (2998-G-078, Sh 107)
| |
| V-1460 thru V-1466 Reactor Coolant System Gas Vents These valves are administratively controlled in the key-locked closed position with the power supply disconnected to prevent inadvertent operation. Since these are Class 1 isolation valves for the reactor coolant system, failure of a valve to close or significant leakage following closure could result in a loss of coolant in excess of the limits imposed by Technical Specification 3.1.3 leading to a plant shutdown. Furthermore, if a valve were to fail open or valve )
| |
| j indication fail to show the valve returned to the fully l closed position following exercising, prudent plant 1 operation would probably likely result in a plant shutdown.
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| i i
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| E-1
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| ( v l
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| l 4
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| . ~
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| Revision 0 07/16/93 l
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| Reactor Coolant (2998-G-078, Sh 108)
| |
| V-1474 and V-1475 Power-Operated Relief Valves
| |
| '_ Due to the potential impact of the resulting transient i should one of these valves open prematurely or stick in the 4 open position, it is considered imprudent to cycle them during plant operation with the reactor coolant system pressurized. ~
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| 1
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| : i l
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| ' Chemical & Volume Control (2998-G-078 Sh. 120) -
| |
| V-2522 Letdown Line Containment Isolation Valve 4
| |
| Closing this valve during operation isolates the letdown
| |
| ' line from the RCS .ind would result in undesirable pressurizer trip.
| |
| level transients with the potential for a plant If a valve failed to reopen, then an unexpected plant shutdown would be required.
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| j j
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| Chemical & Volume Control' (2998-G-078 Sh. 121) 1 i V-2501 Volume Control Tank Outlet Valve
| |
| ' Cycling this valve during operation of a charging pump would 4
| |
| isolate the VCT from the charging pump suction header
| |
| - damaging any operating charging pumps and interrupting the flow of charging water flow to the RCS with the potential of RCS transients and plant trip.
| |
| V-2505 and V-2524 RCP Control Bleedoff Isolation Valves 4
| |
| Exercising either of these valves to the closed position when any of the reactor coolant pumps (RCP's) are in i operation would interrupt flow from the RCP seals and result in damage to the pump (s).
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| E-2
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| o ;
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| . _ _ _ _ _ _ _ _ _ - - - - - - -- - ~ ~
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| .. Revision 0 !
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| 07/16/93 '
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| l I
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| Chemical & Volume Control (2998-G-078 Sh. 122) i SE-02-03 and SE-02-04 Auxiliary Pressurizer Spray Valves
| |
| . Opening either of these valves (or failure in the open position) transientduring plant operation would cause an RCS pressure safety andthat leadcould potentially adversely affect plant to a plant trip. In addition, the pressurizer thermal shock.spray piping would be subjected to undesirable l
| |
| V-2431 Auxiliary Pressurizer Spray Check Valve -
| |
| In order to test this valve, either SE-02-03 or SE-02-04 must be opened. Opening either of these valves (or failure '
| |
| in the open position) during plant operation would cause an RCS pressure transient that could potentially adversely affect plant safety and lead to a plant trip. In addition, the pressurizer spray piping would be subjected to undesirable thermal shock. ,
| |
| V-2440 !
| |
| Charging Pump Discharge Check Valve To Safety Injection Opening this valve requires operating a charging pump and discharging into the RCS via the safety injection nozzles.
| |
| Thermal cycling of the safety injection nozzles is undesirable and should be avoided.
| |
| 9 E-3
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| u~ a
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| ,. Revision 0 e
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| 07/16/93 ,
| |
| V-2515 and V-2516 Letdown Line Isolation Valves 4
| |
| closing these valves during operation isolates the letdown j '_ line from the RCS and would result in undesirable l pressurizer trip. level transients <with the potential for a plant shutdown would befailed If a valve to reopen, then an unexpected plant !
| |
| required. !
| |
| i V-2523 and V-2598 l 4
| |
| Charging Line Isolation Valves i
| |
| Closing these valves during operation isolates the charging pumps from the RCS and would result in undesirable -
| |
| pressurizer level transients with the potential for a plant trip and potential damage to the charging pumps.
| |
| failed to reopen, If a valve required. then an unexpected plant shutdown would be l
| |
| Safety Injection / Residual Heat Removal (2998-G-078 Sh 130) 3 V-3106 and V-3107 LPSI Pump Discharge Check Valves During normal plant operation sufficient discharge pressure,to pump through these valvesthe LPSI Pump l to the RCS and exercise them in the open direction. These j valves will be partial flow exercised quarterly and full ,
| |
| flow exercised each cold shutdown. 1 V-3463 Isolation Valve for SIT Test /RWT Return Header 4
| |
| Cycling this manual valve would constitute a breach of containment integrity, as defined in Technical Specifications precluded 3.6.1.1, in Modes 1, and therefore opening this valve is 2, 3, and 4.
| |
| f 1
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| l l
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| 3 E-4
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| : j. *k ' ;
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| J-i, 1
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| }
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| ' Revision 0 07/16/93
| |
| }-
| |
| Safety Injection / Residual Heat Removal (2998-G-078 sh 131)
| |
| V-3114, V-3124, V-3134, and V-3144 t
| |
| LPSI Cold Leg Injection Check Valves During normal plant operationy the LPSI Pumps cannot. develop i
| |
| ; sufficient discharge pressure to pump through these valves to the RCS and exercise them in the open direction.
| |
| V-3480, 3481, 3651, and 3652-t Shutdown Cooling RCS Isolation Valves
| |
| * These. valves are provided with electrical interlocks that , .
| |
| 3 prevent opeaing whenever Reactor Coolant System pressure '
| |
| ! exceeds 275 psia. This precludes exercising these valves in '
| |
| i
| |
| .i any plant condition other than cold shutdown.
| |
| \ V-3545, V-3664, and V-3665 Shutdown Cooling Isolation and cross Connect Valves
| |
| ! The motor-operated valves V-3664 and V-3665 are isolation j
| |
| valves.for shutdown cooling and V-3545 is the cross connect valve between the two trains of shutdown cooling. These i valves are normally locked closed. A failure of these j
| |
| valves in any other position could jeopardize the integrity
| |
| ' of the Low Pressure Safety Injection System.
| |
| ! Safety Injection / Residual Heat Removal (2998-G-078 Sh 132) 4 V-03002 thru V-03005 Safety Injection Tank (SIT) Drain Line Check Valves a
| |
| Exercising these valves requires draining of each of the SITS. This is not censidered to be an appropriate nor l
| |
| {
| |
| prudent activity.to perform during plant operation due to !
| |
| 4 the obvious safety issues related to-SIT inventory and l chemistry control.
| |
| i J
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| 4 1
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| )
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| 1 E-5 i
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| 2
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| sq .
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| l l
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| ~
| |
| Revision 0 07/16/93 V-3614, V-3624, V-3634, and V-3644 SIT Discharge Isolation Valves Stroke testing normal operationthese valves is not in the closed direction during; possible.
| |
| ', locked open with their breakgy opened.The Also valves theyare are normally i
| |
| interlocked with pressurizer pressure to prevent these i valves from closing with RCS pressure >276 psia. Therefore, the valves cannot be cycled except during cold shutdowns.
| |
| V-3733 thru V-3740 SIT Vent Valves Cycling any of these valves during normal plant operation ' '
| |
| with the SITS pressurized is undesirable since if a valve i were to fail to re-close depressurization the result of the affected SIT.would be Waste Management (2998-G-078, SH 163)
| |
| V-6792
| |
| : Nitrogen Gas Supply Containment Isolation Check Valve This is a simple check valve with no external means of 1
| |
| position indication, thus the only practical means of verifying closure is to perform a backleakage test.
| |
| Performing such a test requires entry into the containment ;
| |
| building operations.
| |
| and thus is impractical to do during plant i Main Steam (2998-G-079 Sh 1)
| |
| HCV-08-1 A&B Main Steam Isolation Valves During plant operation at power, full closure of either of these valves is not practical as it would require isolating j a steam generator which would result in a severe transient on the steam and reactor systems and a possible plant trip.
| |
| 4 4
| |
| E-6
| |
| | |
| . . - - - .. . - . - ~_ .- - . . - - . __ . -
| |
| sq a 1 i
| |
| l Revision 0 07/16/93 4
| |
| l
| |
| , V-08130 and V-08163 3 Steam-Driven AFW Pump Steam Supply Check Valves r
| |
| Full stroke operation of these valves requires operating 2C AFW Pump and full accident flow rate which is not practical 3
| |
| __ during plant operation at power. (Ege Relief Request PR-4) '
| |
| 4
| |
| 'eedwater (2998-G-080 Sh 2)
| |
| HCV-09-1 A&B and HCV-09-2 A&B Main Feedwater Isolation Valves l During plant operation at power, closure of any of these ~
| |
| valves is not practical as it would require isolating a steam generator which would result in a severe transient on the steam and reactor systems and a plant trip.
| |
| i V-09107, 09123, and 09139 .
| |
| Auxiliary Feedwater Pump Discharge Check Valves Full-stroke exercising of these valves would require operation of the related auxiliary feedwater pump and injection of cold water (85 deg-F) into the hot (450 deg-F) !
| |
| feedwater supply piping. This, in turn, would result in i unacceptable thermal stress on the feedwater system piping components.
| |
| V-09119, 09135, 09151, and 09157 Auxiliary Feedwater Supply Check Valves Full-stroke exercising of these valves would require operation of a related auxiliary feedwater pump and injection of cold water (85 deg-F) into the hot (450 deg-F) feedwater supply piping. This, in turn, would result in unacceptable thermal stress on the feedwater system piping comoonents.
| |
| p 6
| |
| E-7
| |
| | |
| gg- ,,
| |
| Revision 0 07/16/93 Instrument Air (2998-G-085, Sh 2)
| |
| HCV-18-1 Primary Containment Instrument Air Supply Closing this valve isolates dkerating air to critical components in the containment building including the pressurizer spray valves and CVCS letdown isolation valves and could cause severe plant transients and a plant trip.
| |
| Failure in the closed position would cause a plant shutdown.
| |
| Miscellaneous Sampling (2998-G-092, Sh 1) -
| |
| V-27101 and V-27102 Hydrogen Sampling Return Line Containment Isolation Check Valves This is a simple check valve with no ex'ternal means of position indication, thus the only practical means of verifying closure is to perform a backleakage test.
| |
| Performing such a test requires entry into the containment .
| |
| building to do duringand plant breaching of the system, thus it is impractical operations.
| |
| i Heating, (2998-G-878)
| |
| Air Conditi'oning, And Ventilation, & Air Conditioning FCV-25-1 thru FCV-25-6 Primary Containment Purge and Vent Valves I These valves are required to remain closed at all times when the plant is operating in Modes 1 through 4, thus they are not required to operate (close) during operational periods.
| |
| Due to the large size of these valves and the potential for damage as a result of frequent cycling, it is not prudent to ,
| |
| j operate them more than is absolutely necessary. !
| |
| V-25-20 and V-25-21 !
| |
| Containment Vacuum Breakers j
| |
| These valves can only be exercised manually requiring direct !
| |
| access to each valve. Since these valves are located within.
| |
| the containment building, access is limited and not routinely practical.
| |
| i E-9 i
| |
| | |
| 1 e
| |
| :s. p 1
| |
| j v
| |
| _ _ _j.lCcmponent.: . _ _ _ _ _ _ _ . _ _ Sys t_0 'L_ _'"raj.n_:
| |
| Fac: PSL_ Unit:_0 2 _ j l Associate: Assign Priority: C3 MASTER Name: PCM-109-294 SETPOINT CHANGE TO Work Type: 3 WORK ORDER TASK HYDRAZINE LOW LEVEL ALARM Location: RAB/RTGB-206 LMD /2 - - 94025805 01
| |
| / \
| |
| Defect / Request: SETPOINT CHANGE A0" \
| |
| /
| |
| ER/PWO: 64 / 3600 i N ^ , Chg Loc: 910 g g pg -
| |
| / PAGE 1 of 5 If ~'
| |
| - m Detailed Explanation: Jl MD T\i
| |
| - .N IMPLEMENT PCM-109-294 SETPOINT CHANGE 1 lI " @W ' $3 EKM Work Request: 94015181 Def Tag: PCM-109-294 Loc:
| |
| h kM Trbl/Brkdown: N LCO: N Unit Cond Rec: 8 NPRDS: N Fail Date: Time: Det: Stat: Symp:
| |
| Originator: WAP000F PAULSEN WA Date: 10/12/94 Dept: IC Approve By: WAP00QF PAULSEN WA Date: 10/12/94 Task Determinacion Data:
| |
| IST Required : N NCR/CR -
| |
| NA Safety Class:
| |
| PMT Required . Y PCM : 109-294 Q Group : B RWP Required : Y RWP No . Assign To : 74/
| |
| 10 CFR 50.49 . N EQ Doc Pkg .N Est M/H : 16.00 Reg Guide 1.97 : N Seismic Cat . I Crew Qty : 2 ASME XI(ISI) Reqd : N Scaffold Req : N Insul Rem : N Security Clearance: N Fire Prot Reg: N
| |
| :learance Required: Clearance No :
| |
| ~
| |
| QC Requirements: QC Required - Y
| |
| .ZD 2:TY I'I'"'ECTICT 7EQUIR:-Eha
| |
| ) iL i . ! / f- f
| |
| /r ;i l
| |
| //.=,j iF G More:
| |
| =========================================== -. ===========================
| |
| j= Work Order Task
| |
| | |
| == Description:==
| |
| | |
| ! Standarc: 1.
| |
| l l
| |
| SEE PAGE : FOR TASK OESCRIPTION. l l
| |
| l 1
| |
| l More: Y
| |
| ============================================================================= l Planned 3y WAP000F PAULSEN WA Date: 10/12/94 l Pkg Appr Ey WAP000F PAULSEN WA Cate: 10/12/94 Time: 09:44 1
| |
| ;C Approval CSM00FK MELODY DS Date: 10/12/94 l
| |
| . **** .............** cpgp27 ;3g AppgoyAL 73 37Ag7 .....******************
| |
| NPS $ tar: Permission: L ,
| |
| z LCO(Y/N). V
| |
| * Star: Date/ Time m ~~ , c ' 19
| |
| * l
| |
| .:FS ::mtletion Nctif;
| |
| ::=c1. Cate/ Time:
| |
| I/ /3/ "
| |
| i- &)W \
| |
| ,J4
| |
| /
| |
| Crr Major Failure:
| |
| Magor Action
| |
| :sf.: e?.cy Tag RemCved Y/Ni ;c d
| |
| | |
| )
| |
| '. -r e m n o n e n t a.. _ _ __.._ cysLP7 Traizu !
| |
| Associate: Assign Priority: C3 _. .Fac L_ESL._ MASTER Unit.I Q2__ < l l
| |
| Name: PCM-109-294 SETPOINT CHANGE TO Work Type: 3 WORK ORDER TASK )
| |
| HYDRAZINE LOW LEVEL ALARM Location: RAB/RTGB-206 LMD: 2 94025805 01 l Defect / Request: SETPOINT CHANGE ER/PWO: 64 / 3600 l Chg loc: 910 l PAGE 2 of 5 l Continuation of Task
| |
| | |
| == Description:==
| |
| | |
| /\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\- '
| |
| /\/\/ \
| |
| : 1. VERIFY THAT YOU ARE WORKING ON hHE CORRECT UNIT J - --------- (~-y-- (JNY AND COMPONENT (S): SIGNATURE /DATE
| |
| /\/\/\/\/\/\/\/\/\/$/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\/\
| |
| NPWO WORK DESCRIPTION FOR PCM-109-294 IS AS FOLLOWS:
| |
| b.. NOTIFY OPERATIONS THAT A LOOP CALIBRATION OF THE HYDRAZINE STORAGE TANK LEVEL INDICATION WILLL PROCEED.
| |
| 2.OBTAIN A TEMPORARY CHANGE AND / OR PROCEDURE CHANGE REQUEST FOR THE NEW LOW LEVEL ALARM SETPOINT OF 36.7 INCHES VERIFIED BY : DATE: ///f,3g
| |
| : 3. ADJUST THE ALARM BISTABLE FOR NEW S OF JQ.6 NCHES.
| |
| VERIIFIED BY : *M ht .
| |
| /-A sJH '
| |
| DATE: Jk
| |
| : 4. PERFORM LOOP CALIBRATION PER I&C P OCEDURE 2-1400064L," INSTALLED PLANT INSTRUMENTATION CALIBRATION (LEVEL) PEP,THE QI-3-1 TESTING DOCUM VERIFIED B DATE: /
| |
| SYSTEM SUPVISOR T. NEWHOUSE l 1 l
| |
| {
| |
| 0
| |
| }
| |
| i
| |
| | |
| 'h 1
| |
| 7, T 'N i.. [ Component: _ _ _ . _ _sys_ ;._Q 7_.___J'ra ' - - I c ac_; . PS L_ Unit L .02__.
| |
| l Associate: Assign Priority: C3 MASTER Name: PCM-109-294 SETPOINT CHANGE TO Work Type: 3 WORK ORDER TASK
| |
| , HYDRAZINE LOW LEVEL ALARM I Location: RAB/RTGB-206 LMD: 2 94025805 01 5
| |
| Defect / Request: SETPOINT CHANGE ER/PWO: 64 / 3600
| |
| ; Chg loc: 910 i PAGE 3 of 5 4
| |
| 6 JOURNEYMANS WORK REPORT
| |
| , Actual Start Date: Time: Actual Completion Date: Time:
| |
| !A C &G / l.3ff$l / f .3 0 l Note: Journeyman shall sign and date text after their entries.
| |
| ! Trouble Found:
| |
| This Section is NOT Applicable for FMs or other planned jobs i[3T EQUIP.
| |
| . $ f
| |
| ?SL J_=G ( _ .
| |
| (5L (72 8 88 -
| |
| FOL l Del Work Performed: ' "
| |
| * SM 4M S* b I 'T l JW a/n/;r
| |
| </ / ,
| |
| l j
| |
| I i 1 i
| |
| l i Continued on Additional Sheets: Y N Suggestions For Future Planning /Vartance Reason: ,
| |
| 1 l
| |
| 1 t
| |
| I E E.y.;~=-= eChi=>'- ate sureret=:r : ate ;C :nspector Oate D D= jun l~l'I Y'W.{ g j ) l f 9[
| |
| s ,
| |
| m -
| |
| | |
| C ATTACHMENT FAC. W/O# UNIT ER PWO# LOC.
| |
| PSL 94025805 02 64 3600 910 EQUIPMENT #: LIS-07-9 JOURNEYMAN'S"WORK REPORT ACTUAL START DATE/ TIME: COMPLETION DATE/ TIME:
| |
| 12/01/94 0400 12/k[94 1530 TROUBLE FOUND: NONE, PCM WORK / REPAIRS PERFORMED: CBTAINED PERMISSION FROM OPS. SUBMI'ITED TC # 2-94-337 FOR APPROVAL BUT COULD NOT OBTAIN PERMISSION DUE TO FRG BEINO REQUIRED.
| |
| INFORMED SUPERVISOR OF RESULTS. ~ e G.SHACKETT y
| |
| /k .
| |
| 12/01/94 OBTAINED APPROVED TC AND NOTIFIED OPS OF START. PERFORMED SETPOINT CHANGE PER PCM-109-294 SAT IAW NPWO TASK DESCRIPTION. PMT SAT PEl% QI-3-PR/PS 1. RELEASED TO OPS. INFORMED SUPERVISOR OF RESULTS. V ,
| |
| / _
| |
| G.SHACKETT _
| |
| _ /F e+ .
| |
| 12/13/94
| |
| - p
| |
| /
| |
| SUGGESTIONS FOR FUTURE PLANNING / VARIANCE REASON:
| |
| TEST EQUIPMENT TYPE PSL# PSL # PSL #
| |
| KEITHLEY S81 l HEISE 861 l !
| |
| TORQUE WRENCH ~ 793 l PART # / NAME M&S# SERIAL REMOVED INSTALLED SUPERVISOR DATE
| |
| ?) . .10a 5 t 2 14- 4 4
| |
| | |
| l 1
| |
| QI 3-PR/PSL-1 )
| |
| Revision 30 l February, 1994 ATTACHMENT 4 PC/M TESTING DOCUMENT PC/M Number 109-294 Supplement Number 0 ,
| |
| i Plant / Unit PSL/2 NPWO Number __3 Goo !
| |
| l 1.
| |
| | |
| ==Title:==
| |
| SETPOINT CHANGE TO THE HYDRAZINE LOW LEVEL ALARM (LIS-07-9) 2.
| |
| | |
| ==Purpose:==
| |
| THE PURPOSE OF THIS PCM IS CHANGE THE SETPOINT FOR THE HYDRAZINE LOW LEVEL ALARM. THE PURPOSE OF THIS QI-3 IS TO PROVIDE INSTRUCTIONS FOR TESTING MODIFICATIONS PERFORMED BY l THIS PCM. '
| |
| : 3.
| |
| | |
| ==References:==
| |
| | |
| 1 3.1 PCM 109-294 l 3.2 I&C PROCEDURE 2-1400064L, INSTALLED PLANT INSTRUMENTATION CALIBRATION (LEVEL), i
| |
| : 4. .Orerequisites:
| |
| NONE
| |
| : 5. Instrumentation:
| |
| 5.~. MILLIAMMETER - TRANSMATION 1040 CR ECCIVALENT.
| |
| 5.2 VOLTMETER - KEITHLEY '_97, FLUKE 9600 CR EQUIVALENT.
| |
| : 6. Related System Status:
| |
| NONE 1
| |
| | |
| .m._ . . .. . = _ _ _ .- .m m. . . . . _ . . _ __ - _ . ._ ._ ._.__..___.-_,_.-_._.._-.____.__.m
| |
| ;O i
| |
| QI 3-PR/PSL-1 Revision 30 February, 1994
| |
| . ATTACHMENT 4 PC/M TESTING DOCUMENT PC/M Number 109-294 Supplement Number 0 Plant / Unit PSL/2 #
| |
| NPWO Number MOD l
| |
| i i
| |
| ! 7. Special Materials or Equipment:
| |
| l NONE j 8. Temporary Connections:
| |
| l NONE
| |
| : 9. Precautions and Limitations:
| |
| l USE EXTREME CAUTION WHEN CONNECTING AND DISCONNECTING
| |
| ! ENERGIZED CIRCUITS.
| |
| ' 10. Records Required to be included in the PC/M Package:
| |
| THE COMPLETED PLANT WORK ORDER AND THIS TEST DOCUMENT SHCULD BE INCLUDED WITH THE PCM.
| |
| l 11. Acceptance Criteria:
| |
| i i
| |
| r l
| |
| . Attach additional sheets if necessary.
| |
| THE HYORAZINE STORAGE TANK LEVEL ALARM (S-10) SHALL ALARM AT '
| |
| [ 36.7" -i- 0.4".
| |
| i i
| |
| l:
| |
| , l l
| |
| }
| |
| i l
| |
| 4 2
| |
| - _ ._.. . - . ._ ., . . - _ . _ _ - - , _ _ - - - . ~ . . _ , . . , _
| |
| | |
| . - - . - - - - . - _ . .-..--a--.--..- . - . . - _ . . -
| |
| QI 3-PR/PSL-1 Revision 30 February, 1994 ATTACHMENT 4 PC/M TESTING DOCLHENT PC/M Number 109-294 Supplement Number 0 Plant / Unit PSL/2 ' NPWO Number -3 ' 00
| |
| : 11. Acceptance Criteria: (continued)
| |
| : 12. Detailed' Procedure:
| |
| Steps meeting the acceptance criteria must be identified as such and contain verification signatures and dates. Attach additional sheets if necessary.
| |
| PERFORM A L 9 LOOP CALIBRATION PER RFJERENCE) 2. 2,
| |
| < e , .4 e. 4 o.aw.~f
| |
| ,/ih[
| |
| v s
| |
| | |
| I id l
| |
| GI 3-PR/PSL-1 i Revision 30 February, 1994 l 1
| |
| ATTACHMENT 4 PC/M TESTING DOCUMENT PC/M Number 109-294 Supplement Number 0 Plant / Unit PSL/2 '
| |
| NPWO Number _3 OO
| |
| : 12. Detailed Procedure: (continued) l l
| |
| l Test Form Prepared Ey:
| |
| Mike Altermatt Cate _ 0 -/12-/94~
| |
| Engineer / Supervisor l
| |
| I I
| |
| l l
| |
| l
| |
| | |
| - - . - . - . . . . - . - . ~ . _ - - . _ . - - - . ~ . _ . . . _ . ~ - - . _ . . - . . ~ . - - . . - . . - . . - _ . - - - . . .-
| |
| -d
| |
| , QI 3-PR/PSL-1 Revision 30 February, 1994 i
| |
| . ATTACHMENT 4 I
| |
| PC/M TESTING DOCUMENT I
| |
| PC/M Number 109-294 Supplement Number 0
| |
| ! Plant / Unit PSL/2 NPWO Number 3 $ OU _.
| |
| 1 1
| |
| : 13. Testing Documentation: l (Record all pertinent testing i'nformation either here or on the Journeyman's Work Report). i l
| |
| 1 i
| |
| I i
| |
| i i 1 i l i !
| |
| 1 1
| |
| .i 1
| |
| 1 Test Conducted by:" . Date /d /3 //f/
| |
| pourneyman/ Supervisor Test Reviewed'by: U. Date /t.// 4 / W Eri ineer/ Supervisor Test Approved by: ; ~
| |
| Date. (2 / /f/N Depar.} ment Head 5
| |
| | |
| 1 .
| |
| i Revision 58 2 October,1994
| |
| ' Page 70 of 76 FIGURE 4 TEMPORARY CHANGE REQUEST
| |
| ; (Page 1 of 2) i A Reference information: (Originator to complete)
| |
| St. Lucie Unit # 0 1. TC # 2- N~337
| |
| ! Procedure
| |
| | |
| ==Title:==
| |
| wee h m -w:.a 0 i b. :.., n a0 Procedure Number: 2 84aeaut Rev. 27 Steps affected: Jn sei.n C,a L. o?.. (#v s m.,:a sr...., % & troch
| |
| ! Reason for change: Dea ,e 2ev (41 . ser.o.zart.r.t.J Originator: 17sav A. As .us a ( Department H(ad or Designee @ M 9 - __
| |
| f Phone: x2ere Date: ' 't // /W B Procedural Controls: (Originator to complete)
| |
| Yes No
| |
| ; O E is this Temporary Change for a one-time use? (If no, the responsible Dept. Head or
| |
| . designee shall ensure a procedure change request. incorporating this TC has been
| |
| , developed, approved and submitted for FRG approval.) This TC may be used up to 90 days.) ,
| |
| j }.
| |
| ! O 5 ls this T.C. for a Q.l.? (If yes. wntten concurrence shall be obtained from the Quality
| |
| ! Manager and wntten approval shall be obtained from the Dept. Head who is
| |
| ; jurisdictionally responsible for the O.1.)
| |
| C Temoorary Chanoe Contents: (originator to complete) l '
| |
| Does this Change:
| |
| Yes No l
| |
| O E Alter the intent of the procedure?
| |
| O E incorporate complex or extensive enanges?
| |
| ; 6 O Modify instrument setpoints?
| |
| d-O E Delete an independent verification?
| |
| O E Alter a 00 holdpoint?
| |
| O 5 Modify a procedural step wnich alters a regulatory requirement as identified in the I procedure?
| |
| O E Alter the first execution of a proceoure? (Preop, LOI)
| |
| O 5 Addition of any enemicals?
| |
| i NOTE If any of the above enteria are markeo yes. prior FRG review is reoutred.
| |
| i I /R58 i
| |
| . ,2.g. H i.
| |
| | |
| 4 = ..s.n.__.
| |
| : Revision 58
| |
| ! October,1994 i' Page 71 of 76 FIGURE 4 i TEMPORARY CHANGE REQUEST l (Page 2 of 2) i j
| |
| : D Does this change: (NPS to complete) -
| |
| I Yes No
| |
| ;_ O Y Compromise the separation of redundant trains of equipment? )
| |
| O B~ Potentially isolate pressure reliefs? )
| |
| f ,_,
| |
| i O Y Defeat automatic signals?
| |
| O [ Defeat mechanical or electncal interlocks?
| |
| ; NOTE 2
| |
| If any of the above enteria are marked yes, discuss possible altematives with the '
| |
| j originator. ,
| |
| 10 CFR 50.59 Screening Yes No )
| |
| : 1. Does the change represent a change to the facility as described in the SAR? Y ]
| |
| j
| |
| : 2. Does the change represent a change to procedures as described in the SAR7 'X ,
| |
| l
| |
| ' i
| |
| : 3. is the change associated with a test or experiment not described in the SAR? X 1
| |
| $ 4. Could the change affect nuclear safety in a way not previously evaluateil in the SAR?
| |
| .- X l J
| |
| 4 1 5. Does the change require a change to the Technical Specifications? A l 4
| |
| 3 NOTE If the answer to & the above 10 CFR 50.59 screening questions are no, (Questions 1 - 5), '
| |
| then a safety evaluation is not reovired.
| |
| STA review bbb b1 M IL / / /N Date STA Sigfiifure E Review: (This change snail have pnor appr6 val by a NPS and one member of the plant management staff.)
| |
| # / /Y / I NPS Signature / Authonzation Date Plant Management Statt Signature C.Ms.u.2r - Date '2 / ? /N l Plant General Manager Approva //)/hbg 6/.-$NMbN Date 13 /h_] W /R58 !
| |
| -~ +
| |
| FRG Number 6 14 This enange shall be reviewed (if prior FRG review is not required) by the Facility Review Group within 14 days of the (PnoyPosL o
| |
| - autnonzation date.
| |
| (NPS/ANPS) Date
| |
| / /
| |
| F Cancellation Authonzation Reason:
| |
| , . . , . , , . ~ - - m ,
| |
| | |
| s O
| |
| .. . l I o i i ST. LUCIE UNIT 2 '
| |
| I & C PROCEDURE NO. 2-1400064L, REVISION 27 INSTALLED PLANT INSTRUMENTATION CAllBRATION (LEVEL) 1-o79 Systeni: Containment Spray Test EquDnient leg No' '
| |
| L cuttio .
| |
| Service: Hesrerine Storese Tank Level t
| |
| Date Started-(*St 2 FJi 92 024 Date Congleted: ;
| |
| . Work Performed by- .
| |
| independent VerlGceton: j ;
| |
| Date Supervisor:
| |
| i l
| |
| ~
| |
| hout Iest f*N 2998 G 22T (13) MA lost Point RIGO 208 ,
| |
| Output et Sit 1 Total Ougsus of: LIS47-9 l Teest i
| |
| L1ADC LT 47-9 Tot *ll/l 1:.8 Vas Accuracy W 25 g og ga Ac arecy W 1 0 ;,,,,,
| |
| Pt % *t l,0 Desired As Found As Left Error Desired As Found As Lok Ener 1 0 .8 4 00 0 2 25 14.3 8 00 10.5 3 50 21 8 12 00 21 0 4 T5 32 3 16 00 31.5 5 800 20 00 42 4 TS -Ns 16 00 31.5 3 50 288 12 00 21.0 8 25 11 3 8 00 10.5 1 0 8 4 00 0 80stallee I urElton AfMMME02908 FITGB 208 Cor.ime:ts.
| |
| Action itequired. CWD 308 Total Ves#y Annunctator Wirukms .
| |
| S-to t o- Alarm
| |
| - 35 1/2" Tot.
| |
| i .4*
| |
| 551/2* = 17.53 :nar 2*p 4 76 msw "! { j j ' y' 33 .
| |
| ^
| |
| Desked As f ound As Left CWD-288 19 95 ll{* . '
| |
| fleset
| |
| * f Action F4equireo i.20 1otsi ; ,
| |
| I o I o A; arm - 2* !
| |
| Tot.
| |
| !4% ,
| |
| ~~
| |
| Deshed As I ourut As left , , _ , , _ , , , , _ _ _
| |
| l ,
| |
| 3* 2
| |
| {
| |
| nose ;q.. e- , , ::y* ,n. .-. t;; ' 2, ,;9 :, , ,, . _ . . g , p,, ,t.;>.
| |
| f y ie<. , ,.
| |
| ?!.1 .?'*''i* /. ;g.. ,. <g . ,.; . 3., , . , , ,; , ..d [
| |
| r.m .:.e.3.:.; . .s ,n .......x..,...,,
| |
| heg.q g ..;
| |
| n a a n.. e ,. . .: : .n 1 l ,,. r ., ..
| |
| hl !! ! !.*.i i f Yli ; I f
| |
| l 1 AiEVECllifr -,_f/ M7 g; g,i,. 3 ,j ,
| |
| .,([g , i j!,
| |
| -..._..___....''..._~.. j 4 j,:
| |
| I
| |
| | |
| . -o t .
| |
| ST. LUCIE UNIT 2
| |
| : y. I I & C PROCEDURE NO. 2-1400064L, REVISION 27 i INSTALLED PLANT INSTRUMENTATION CALIBRATION (LEVEL) !
| |
| l I-07 9 Systeen: Containment Sgpray t oep tio. - Service: Hydrartne Storene Tank Level TW W Tg h i' Date Started- f.2//.3//Y NWWO'~ $ ,~ <5 W I PSI.-2 F.ll,92 024 Date Completed: _ /A.//J'9( /g/eryet #
| |
| / T( y6/
| |
| Wmt Perfumed SY Cor*#w e 3, g .{ gg ,oy4' . *77 3
| |
| /_2//+ 47i Independent VerleceSort > 4<= cAhsm -
| |
| Date I Supervisor:
| |
| i input Iest l' aire 2998 O 22T (lJ) MA test Poire RTOS308 Output of: SH 1 :
| |
| Total Ouqiuset: LISeT-9 Total .
| |
| MADC LT47 9 Tot. '11,0 Tot.
| |
| Vee. Accuracy W 25 g .c4 MA Accesrecy W I.0 a .4 In.
| |
| Pt. % "I f,0 Desired As Found Ao let Ester Desired I As Fossul As Let Enor 1 0 .8 4 00 g (") g , > 0 O 7 c) 2 25 I t.3 8 00 p .9 o / o 10 5 f a. C h ./
| |
| 3 50 28 12 00 ft on o 21.0 U. o , o 4 T5 32 3 1800 & rp t A 4/ 31.5 3 /. f g c) g 5 100 42 8 20 00 g r>, nr / 8 ... 42 r/J. D , O 4 71 ^ 32.3 16 00 /.', . o f
| |
| [ . c)/ 31.5 _ T f .f [ C) t 3 50 21 8 12 00 /,J. cJ o / 9 29.0 Rf . c c) %
| |
| 2 25 II 3 8 00 .T.c)t) > 80.5 fo, Q / I a 0 .e 4 00 y'c)g) <3 0 c) O , l s a Olstat4e f uncean Annunciator f1TG8 208 Comments.
| |
| f Acton fiequired. CWD 306 Total verty Annunctator IMndows to-Alarm S 10 _.,,
| |
| -35 ft2*
| |
| --' ^ Tot.
| |
| 1.4*
| |
| 3$ 112* 3 1.53 ener 2* ,4.75 trd s
| |
| ~{
| |
| ! ['/Y~d3 Deshed As Found As Leh CWD-288 i
| |
| 'rv ?S W . _%.7 :' '+f o Ileset - l-AcGon F4equked- ! . 20 Iotai to Lo Alami . 2* Tol.
| |
| 1.4 % !
| |
| Deshed As I cued As M _ ,,,,, - ,,_,, _ __ ,,_ ,,,_,___.
| |
| I'* 2' 'l . O !. A F 0 * ! * . ., : s ;1. - -
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| l.*Q.D e *iI t < s;*,8 a .- (;;
| |
| * z, ,. I, 7l q. g ,g' t k. .~
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| liesee *.
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| |
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| |
| hfin
| |
| ?, !
| |
| .yq:4,0
| |
| | |
| .)
| |
| later-Office Correspondence i
| |
| To: S. A. Valdes St. Lucie Pla oste: 0) %
| |
| From: D. Denver Department: JP1/JB PSL INFO SVC Nuclear Enginee a
| |
| - subject: ST. LUCIE PLANT UNIT (S) 2, REA/ PROJECT # STAR 2-94080081,1 8 g
| |
| ; TITLE: Setpoint change to the Hydrazine Low Level Alarm (LIS-07-9) DCC PC/M/ FILE i 109-294 Attached for your review, approval, and use is the (EP/MEP) for the subject
| |
| . Plant Change Modification.
| |
| This package provides the details necessary to implement the following modification:
| |
| Chances the setooint for the Hydrazine low level Alarm (LIS-07-9).
| |
| By copy of this letter, Document Control is requested to distribute this package to the normal distribution plus the following:
| |
| l REA Originator: J.P. Honevsett - PSL/0PS j This completes our effort on STAR 2-9408008,1.l If you have any questions, contact Chris P. Chartier at (407) 691-2103.
| |
| DD/cpc y g Attachment c _ .. POST H.L. Fagley/DCC - CS/PSL (w/ Repro)
| |
| S. Kozlin - JDC/JB (w/dwg list.& orig dwgs) F.R.G*
| |
| D.M. Wolf - JPN/JB PSL INFO SVC J.A. Porter - JPN/JB (w/dwg list)
| |
| C.L. Schaeffer - JMC/JB _-
| |
| C.M. Spalter - JPN/JB (w/ orig word doc & copy of dwgs)
| |
| Others: L. Rooers - ICM/PSL ewswowsavow.cos gk 7
| |
| 5.nn ions m.o.e n., m
| |
| | |
| QI 3-PIVPSL-1 f.
| |
| Revisson 30 2=
| |
| ~ February,1994 Page 26 of 39 l },
| |
| - ~ ~ --
| |
| i 4 ATTACHAi M 2 PC/M REVIEW FORM f
| |
| (Page 1 of 3) 1
| |
| ' /o' ~J WM Supplemort Numcor o
| |
| - PCM Nummer wna P5L / L Expiranon Date 4/Z//*I l
| |
| 1 i
| |
| [ - Safety ClasmAcanort
| |
| .r Safety Related Quaisty Rotated Not Safety Related l
| |
| l' Originadng Documore Number:
| |
| j Originator /Orgaruzanon:
| |
| (REA, NCR, RPD, sa:.)
| |
| i
| |
| : 3. P. % vJt +4- 6TA 4. 2. - A 4 o 6 o o b i . I d
| |
| 5 < + pl..* C.h%* 4- A. N d/c b La> tm\
| |
| Title of PCM:
| |
| l ALWm ( I. L 5 - D 'l td ,
| |
| i PCM Descrederc Chqs .rdpo'.4 f% 35 5 * += 3 6 ' "
| |
| i i
| |
| 3
| |
| #^ *
| |
| * d ^\
| |
| * I6**\ eq b.3 A Wdcd S p e cJ.M.
| |
| Need for PCM: + J u '. s is.s" ( c.,4 g)
| |
| (&9'i g ) i s n, & e c. . J c J . C implemenong Documernanon: Cwo #:
| |
| Backfit wortcod
| |
| / Plant wortcod WPS #:
| |
| "I
| |
| 'WOG % N$YlJ400 1 af v 8 5 8 0 5 o Yes or No Descnonon Otner Arelis AG9193: As nor Tis.,s,s C+= ig.ris A=---;.i ;,;.
| |
| Oss,eist "i re Yes Ose . irs PE-:+9=es %s Survedlance Ps_---+m %
| |
| Ms.,ier,&,6 Pe:- --;d'es *Jo
| |
| *= s Psris th 47 9ei 5-t + o eM L .' s + 5RDs? Y /M/ _
| |
| Cr&w ,sL/Tecnncal Manuas '
| |
| FUSAR Chance ,
| |
| Mo
| |
| *J.
| |
| TeuS CTi-i>G.
| |
| Hi,i ,e i F9_197 tJo ERDADS Aft +5+3 4 in-Servce 11= _+:= 6 d.
| |
| CGGG dea
| |
| -- , - , , ~ -
| |
| | |
| n Q13 PR/PSL-1
| |
| !' Revtirn 30 e
| |
| Fcbruary,1994
| |
| , ) Page 27 of 39
| |
| ~ ~-~- - - - - -
| |
| l ATTACHMEAT 2 ~
| |
| PC/M REVIEW FORM l
| |
| (Page 2 of 3) i
| |
| / o 4 - 1 H af _ Supp6emem Number O I PCM Numoer 1
| |
| pm Pst. / L Expuanon Dato . I7-/ 3 I / W l
| |
| t 2 -
| |
| PCM Type: ,
| |
| Physcal Work Required i
| |
| .ARP . As Fall Either or
| |
| ! / Normal
| |
| * i
| |
| $ Techncal Staff Rewow and Cornments: Yes No I
| |
| ' la this PCM Safety Related?
| |
| /
| |
| : 1. /
| |
| : 2. Is the atory to the 10 CFR 5059 screenmg question Yes?
| |
| : 3. Does the PCM requus any physcal work to be performed?
| |
| /
| |
| if the snowere to these questkms are NO, no PRG rewtow le required.
| |
| Safety Evaluation complies vnth 10 CFR 50.59:
| |
| Date / /
| |
| Technmal Staff N/A O^ me #
| |
| PCM Renew Complete:
| |
| //e4 Date / 0 / / L / f't Techncal Staff I
| |
| Maintenance aC Review and Con-s: Lv/g (lg'3{g PCM Rm Comp 6ete.
| |
| L Pi 6103 QC Signature / Dato b I b /
| |
| ~ - /~
| |
| - Plant General Manager Approval:
| |
| Date
| |
| / #b /
| |
| Signature [
| |
| FRG Aoprovat:
| |
| . Date /6 /
| |
| # /
| |
| FRG Number: FRG Secretary
| |
| | |
| Q14-crvecu ,
| |
| R0vcen 30 Fsbrutry,1994
| |
| \
| |
| Page 28 of 39 d, - _ _ _ _ .
| |
| ~%TTACHMENT-2 PC/M REVIEW FORM (Page 3 of 3)
| |
| : 0
| |
| /o9 -2 9v M Supplemer;! Number
| |
| . . PC/M Number i
| |
| Piant/ Unit PW lL i
| |
| 4 i
| |
| - Maintenance QC Closeout Review:
| |
| i a
| |
| Required f Date: / /
| |
| l Not Required Technical Staff i
| |
| l Date: / /
| |
| Approved for Closeout:
| |
| l Maintenance QC 1
| |
| Commenta:
| |
| i,
| |
| ?
| |
| Technical Staff Closeout Review:
| |
| Date: / /
| |
| Approved for Closecut:
| |
| l' Technical Staff
| |
| . Date: / /
| |
| Procedurs Notification Completed:
| |
| Technical Statf
| |
| . Date: / /
| |
| Training Notification Completed:
| |
| Technical Staff Cancellation information:
| |
| Date: / /
| |
| Technical Staff
| |
| | |
| PC/M 109-294 Revision 0 l
| |
| .s Page 1 of 4 I> .
| |
| ..- MINOR ENGINEERING PACKAGE (MEP)
| |
| I PLANT St. Lucie UNIT 2 PC/N NUN 8ER 109-294 _ SUPPL 0 I ORIGINATING DOCUMENT STAR 2-94080081.1 EXPIRATION DATE 12/31/95
| |
| ; PC/N CLASSIFICATION X SR WIS QR ADMIN i TITLE SETPOINT CHANGE TO THE HYDRAZINE LOW LEVEL ALARN (LIS-07-9) i i l
| |
| ] ADDITIONAL REQUIRENENTS/ INSTRUCTIONS YES NO AS-BUILDING TO COMMENCE UPON ISSUANCE OF PACKAGE? _3__
| |
| THIS PACKAGE HAS THE POTENTIAL TO SIGNIFICANTLY X
| |
| ! IMPACT PERSONNEL RADIATION EXPOSURE (See QI 3.13).
| |
| IF YES, JPN FORM 72 IS REQUIRED.
| |
| l, 10CFR50.59 SCREENING YES NO 1
| |
| I) DOES THE CHANGE REPRESENT A CHANGE TO THE .
| |
| 4 FACILITY AS DESCRIBED IN THE SAR7 X t,
| |
| : 2) DOES THE CHANGE REPRESENT A CHANGE T0 d PROCEDURES AS DESCRIBED IN THE SAR? X
| |
| : 3) IS THE CHANGE ASSOCIATED WITH A TEST OR EXPERIMENT NOT DESCRIBED IN THE SAR7 X
| |
| )' 4) COULD THE CHANGE AFFECT NUCLEAR SAFETY IN
| |
| ~
| |
| A WAY NOT PREVIOUSLY EVALUATED IN THE SAR? X
| |
| ! 5) DOES THE CHANGE REQUIRE A CHANGE TO THE 4
| |
| TECHNICAL SPECIFICATIONS? X 1
| |
| , NOTE: IF THE ANSWER TO ANY OF THE ABOVE 10CTR50.59 SCREERING 00ESTIONS IS TES, THE MEP CANNOT BE USED 1 REVIEW / APPROVAL:
| |
| 4 INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL APPROVED
| |
| * INPUT REVIEW N/A numsuunuiumuuuuuuuuuuuuuuuuulu - = 0 Ast l MECH X ELECT X
| |
| !&C X O l- #
| |
| CIVIL X N UC" X ESI X
| |
| * NUC FUEL X
| |
| * For Contractor Evals As Deterurtned By Prof " Review interface As A Minime On All Non-Aetn MEPs FPL PROJECTS APPROVAL:
| |
| , DATE: 96ll
| |
| | |
| . PC/M 109-294 Revision 0 Page 2 of 4 1
| |
| =g ygg.g.gpggg _ _ _ _ _ _ _ _ _ _
| |
| This Minor Engineering Package provides the justification to change the setpoint of level indicatmg switch (11507-9) for f t m IF 7 4 ine storage tank. He followmg will be j modified:
| |
| : 1. De setpoint for level Indicating Switch (LIS-07-9) will be changed from 35.5" to 36.7".
| |
| I
| |
| ! __. 2. The setpoint list and drawings will be repsed accordingly.
| |
| JUSTIFICATION 4
| |
| The design basis for the hydrazine storage tank is to provide controlled amounts of
| |
| ! hydrazine to the containriient spray weter following a loss-of-coolant accident to remove
| |
| ! radio-iodines from the containment atmosphere. The hydrazine storage tank has several
| |
| ; alarmmg serpoints which are used to alert toe operator when the hydrazine level in the j storage tank is reaching a predetermined level.
| |
| 4 i
| |
| Currently, nnmmeintor window S-10 for the hydrazme low level alarm (LIS-07-9) is set at
| |
| ! 35.5" (674 gallons)(Ref. 3). However, a more conservative setpoint for the low level alarm is required, since the existing setpoint is very close to the technical specification required mmimum level of hydrazme (675 gallons)(Ref. 2). A more conservative setpoint can be accomplished by taking the existing setpoint of 35.5" (674 gallons) + .1" (1.6 gallons) = 35.6" (675.6 gallons) + 1.10" (instrument inaccuracies) = 36.7". Calculation PSL-2FJI-92-024 has been reviewed and it has been determined that the new setpoint is acceptable and will envelope the technical specifications minimum requirement for hydrazine levels for the Containment Spray / Iodine Removal Systems.
| |
| This setpoint change does not change the design basis of the Containment Spray System / Iodine Removal System (CSS / IRS) or alter any plant Technical Specification (Ref. 2). This setpoint change does not change the facility as described in the FSAR (Ref.1). While the annunciator window (S-10) is non-safety, this Minor Engineering Package is classified as safety related since the instrumentation associated with the setpoint (LIS-07-9) is classified safety related.
| |
| | |
| . - ..- --- - - .-=-. .-.------ _ . . - _ -
| |
| t PC/M 109-294 !
| |
| Revision 0 Page 3 of 4 f CONCLUSION:
| |
| i i i A design integration review was performed and it has been concluded that this modi 5 cation does not affect nor is it affected by any other designs in progress. This
| |
| { review included the followmg:
| |
| i (1) The computer database PC/M Log as of 9/7/94.
| |
| (2) The computer rintahaw Affected Drawmg 1.ist as of 9/7/94 j (3) De PSL Active Safety Evahi=*ian Ust as of 9/7/94.
| |
| { __. As a result of this design review, no outstantiing designs were identi5ed which would interact with this modification. In addition, there are no Justification for Continued Operation (JCO's) which affect, or are affected by this MEP.
| |
| i 5-The CSS / IRS Systems are described in the FSAR, Section 6.5.2. However, the level j
| |
| indicating switch (US) setpoint for the hydrazine storage tank is not described in the !
| |
| FSAR and it is concluded that the setpoint change from 35.5" to 36.7" is acceptable and has no direct or indirect impact on any safety functions required for analyzed accidents, and does not increase any radiological hazards.
| |
| l The portion of the CSS / IRS System being modi 6ed is safety related, since it is required to meet certain technical speci6 cation levels and is used during a DBA. The CSS / IRS ,
| |
| serves only as an Engineered Safety Function (ESF) and performs no normal operating '
| |
| functions. The annunciator window (S-10) is non-safety and provides additional assurance that the hydrazine level is maintained within the Technical Specification levels. This setpoint change does not alter the CSS / IRS system ability to mitigate or monitor the consequences of an accident. In addition, the modification to the level switch setpoint does not alter any speci5c design, operational or performance requirements for the CSS / IRS System. Furthermore, these changes are not considered a change to the facility as described in the FSAR, Section 6.5.2, nor does this modi 5 cation change or alter the Technical Specification. While the annunciator window (S-10) is non-safety, this modi 5 cation affects a safety related piece of equipment (LIS-07 9), therefore this ;
| |
| package is classified as Safety Related.
| |
| i This conclusion supports the 10CFR50.59 screening results. Thusfore, there is no unreviewed safety question.
| |
| i SPECIAL INS'IRUCTION/ IMPLEMENTATION REOUIREMENTS l
| |
| : 1. Notify operations of work to be performed in the control toom. I
| |
| : 2. Change setpoint for LIS-07-9 from 35.5" to 36.7". See attached setpoint list.
| |
| : 3. Verify operation of loop (new setpoint & annunciator S-10).
| |
| I
| |
| | |
| l PC/M 109-7.94 Revision 0 ;
| |
| Page 4 of 4 l 1
| |
| OTHER AFFECITD DOCUMENTS
| |
| ---.-- ---- Reference Paragraph /Page or. . _ _. ___ i
| |
| " Ed RW Pp Plant to identify any affected procedure which may require revision due to this modification, including the annunciator procedures.
| |
| 4 POST MODIFICATION TESTING ICM shall verify proper operation of loop Ir07-9.
| |
| 4 a
| |
| REFERENCES
| |
| : 1. PSL Unit 2 FSAR, Amendment No. 8
| |
| : 2. PSL Unit 2 Technical Specification, Amendment No. 67 I
| |
| : 3. I&C Calculation PSL-2FJI-92-024, Rev. O " Unit 2 Hydrazine Storage Tank Level"
| |
| : 4. Computer Database Affected Drawing List as of September 09,1994 1
| |
| ; 5. Computer Database PC/M Log as of September 09,1994. >
| |
| : 6. PSL Active Safety Evaluation List dated September 09,1994.
| |
| A'ITACHMENTS Attach Number Descriotion/ Title Number of Panes 1 Setpoint List 1
| |
| l
| |
| :' d , i. i. i.
| |
| : i. i. i. r . i. 1. ..
| |
| l
| |
| ..p_
| |
| + - - - -~ ~ ' -
| |
| +
| |
| . . g 3, g i
| |
| =,s ~ u. -
| |
| 1 v=e i c ..
| |
| l
| |
| %y QL -
| |
| WJ u r
| |
| .I j\ p$b 1
| |
| l
| |
| =
| |
| E s
| |
| f.
| |
| l 4
| |
| J N
| |
| ( e-
| |
| * i 5 3
| |
| ' gg !
| |
| E ag '
| |
| 3 _ := l
| |
| !. Il i i 3 m.y g
| |
| i ! En s a a s
| |
| 2
| |
| = 5= _g 8 .
| |
| * i .
| |
| * 5 : i si r, i b s
| |
| i v g*
| |
| i i !5 a a i
| |
| 95! 3. == c 3. -
| |
| = E k 5* li En s Et :- 5 e*
| |
| . o i $2 1 s*d E EJ h Ed "I
| |
| \ I -
| |
| 11- (
| |
| v
| |
| =gs t 2 . =
| |
| =[
| |
| Eg 8 8 a
| |
| : M a f a= -
| |
| v_ e e e a s : "
| |
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| |
| s " s 3
| |
| ]
| |
| 2 E
| |
| - E
| |
| ~
| |
| ly a
| |
| 5
| |
| =
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| !!gE 5 g
| |
| !!E I t
| |
| E C'
| |
| E l l *g
| |
| = g
| |
| ~
| |
| 1 Is. Wg Im a
| |
| - = 5 w SE -
| |
| = - t -
| |
| 8 a =
| |
| : 2. - E = =
| |
| 5 5- U i !_= 5 EE EE i i 33 ;
| |
| I I! $ I $ X5
| |
| = k
| |
| *3- " *
| |
| * N *
| |
| * I
| |
| = .
| |
| . - 2 I. .
| |
| c*
| |
| 1::gEI.
| |
| _ . r _s
| |
| . . .e e E.
| |
| =.
| |
| I.
| |
| =.
| |
| =.
| |
| = .
| |
| O
| |
| ~~^ _ _
| |
| | |
| l later-Oifice Corresponder
| |
| _-@_ _ _j g MMFO SYC R1
| |
| . A6E_JPN-PSLP-9 3
| |
| 5 j I n r $
| |
| a
| |
| / !? s r.: S. A. Valdes .
| |
| o .. AUG 0 519H occ 4
| |
| St. Lucie Plant -
| |
| ! %. D. J. Denver I o s, JPN/JB l i
| |
| Nuclear Engineering POb, [ l sw. ST. LUCIE UNIT 1 Cmh ' pI' "
| |
| TITLE: ICW/CCW PUMP CONTROL CIRCUITS I PULL-TO-LOCK SWITCHES WITH SLIP CONTACTS PSL lNFO SVC REA/ PROJECT d SLN 93-079-3612.
| |
| SUPPLEMENT f I % j PC/M/ FILE i 182-193 Attached for your review, apprr 4 and use is the subject Engineering Package revision.
| |
| Reason for Revision: Physical wiring connection dia' grams associated with i the 1C ICW and CCW pumps were not revised following an Implementation
| |
| : Review PCM scope change and are corrected in this supplement.
| |
| f l.
| |
| Imoact of Revision Yes (Lo,
| |
| ., 1. Has the design basis or design analysis been affected by X this revision?
| |
| : 2. Has the Safety Evaluaticn been affected by this revision? X
| |
| : 3. Have SRDs been affected by this revision? X 4 Have Start-Up Operations or Maintenance requirements been X affected by this revision?
| |
| Remarks During the initial preparation of PC/M 182-193, a design change was made to accommodate the operation of 2 ICW or 2 CCW pumps on one electrical -
| |
| i train. It was desired to run the 2 pumps on one train for up to 72 hours, as allowed by the Technical Specifications, to provide pump flow to both trains during situations in which a pump on one train is inoperable. This change was correctly incorporated into the control wiring diagrams (CWD's),
| |
| but was not followed through to the connection diagrams. A full re-verification of the entire package has been performed, to ensure completeness.
| |
| F WIS'JOWSPSL*JOW.003 Form tous istocked Rev litt
| |
| :: . )
| |
| 1 JPN-PSLP-94-0478 Pace 2 1._.________._._ _ _ _ _ _ _ _ _ _ _ . _ _.. _
| |
| By copy of this letter, Document Control is requested to distribute this
| |
| , package to the normal distribution plus the following:
| |
| REA Originator W Dean
| |
| ; L Clark ThiscompletesoureffortonREASLN93-079.Ib.
| |
| '7tw If you have any questions, please contact Wiktor Lewinger at (407) 694-
| |
| - -- 3240. <
| |
| DJD/
| |
| Attachments "
| |
| ; Cosmu to: I
| |
| .' H.L. Fagley/DCC - CS/PSL (w/ repro)
| |
| S. Kozlin - JDC/JB (w/dwg list & orig dwgs) i :
| |
| D.M. Wolf - JPN/JB i R.L. Castro - JPN/JB
| |
| : A.S. Suggs - JPN/JB (w/dwg list) :
| |
| .i C.L. Schaeffer - JMC/JB !
| |
| C.M. Spalter - JPN/JB '
| |
| D.M. Stewart - TEC/PSL REA Originator: L. Clark - EM/PSL Others: W. Dean - EM/PSL l
| |
| l l
| |
| i l
| |
| F:\NIS\FOPSASPSL\F075A.003
| |
| | |
| _ . . _ _ _ . . . . . . . . _ . _ _. _ . _ . _ . . - . _ _ _ . . . _ . _ . _ . . _ _ _ _ . _ . _ _ . - ~ .
| |
| !* Ol 3-PR/PSL-1 i Rsvirion 30 I i, February,1994 l . _ _ _ __ . -_ . _ -- -
| |
| _______Page 29 of 39 ;
| |
| ATTACHMENT 3 PC/M SUPPLEMENT FORM (Page 1 of 1) g % PCM NO. PCM Suppement No.
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| Non SM OC Resto lR2-l'f3 l 1-nem item ogsoneman
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| : No.
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| lCd/CCd FUMP CONTROL CitCVnTS PUWTO L 0CK SalTtNLS usTH Slit co+6TAtri
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| .- Suppement C .e.
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| l CoAAECT: set To WiAlec. bMGa4M3 FeA *C' Cb ANo CCW Com0L clRcvers i Reasono for Suppement O Aadmones anon nne iniormsson O omer (Descnoe>
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| l 2 [Moomcanon to Doesgn or Specmceton ONCm O Cnenge m no orememe l O Aoumones venaar insomumen
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| : O Cnense in scope
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| ^
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| j 3
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| 3'''''' ''''A**"'**"
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| iM ACCORbW LJsTri fCH
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| , impemineng Dom.. NPWOs Sht1E At tvMLlttluT O Cwo WPe C.a. anwolveo I
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| kEdstEb ecM bahtdsdVS LISTEb ON AFFECTEh stAL)ls)GS 6
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| Test P - _.-
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| ?ER os 1-0 ATTnCMMG.NT y The onomes PCm fines scope pannese nucmar essety ena ermvanmenen om ment neve oesn reve a sor ow PCm suppiament and evoluenon, 8 IRemam valid suppement provided OA,enoion.orveM. e-ement -
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| Tecnnical Staff Date_.dj_f.fj N M Yes No 9 1. FPL Tecntecal Stoff , jfff A , pf,p/y, x
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| : 2. FPL Plant Quaisty Contrat - fhh *I22, $4 x
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| : 3. FPL Plant Generet Menspor j 4 , .t4 ' ^
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| /
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| * /n/te Approveo for C ,y _
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| Mean m weCC Data fI /M/V
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| ~
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| Tech. Staff - Date '' / ' ' / W 10 Prococure Noencemen Completed:
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| Tecn. Staff Date / /
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| Trainsng Notrlicemon Completed:
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| Tecn. Staff Date' / /
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| d FPL MELEAR FMETMFFETMC 1 --
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| ENGINEERING _RACKAGE _ __ _-_
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| J PC/M NO: 182-193 REY: 1 SUPPL: 1 PLANT: ST. LUCIE UNIT: 01 TITLE: ICW/CCW PUMP CONTROL CIRCUITS PULL-TO-LQCK SWITCHES WITH SL l
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| REVISION DESCRIPTION: CORRECTIONS TO WIRING DIAGRAMS FOR "C" ICW AND CCW LEAD DISCIPLINE: ELECTRICAL EXPIRATION DATE: 12/31/94 i2 e
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| ^ REA NO: SLN 93-079.M DWA N0: N/A PC/M CLASSIFICATION: SR X QR NNS DESIGN ORGANIZATION: PSL/ PEG DISC CHIEF REVIEW REQD? YES NO X
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| : EXTERNAL INTERFACES: NONE DISC CHIEF SIGNATURE: N/A REVIEW / APPROVAL:
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| ,' INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL APPRDVED' INPUT REVIEV N/A
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| ! MECH X
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| : ELECT X 'd h,hy'Nif h ( Y/Op Amt j !&C X h
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| CIVIL X !
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| NuC" '
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| ESI X
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| f)f/)I/Ad X
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| NUC FUEL X
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| * For Contractor Prepared EPs As Determined By Projects " Review Interface As A Minimum Dn All EPs FPL PROJECTS APPROVAL: ._
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| DATE: N/*
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| JPN Form 3. Rev 7/93
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| I 1
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| s PC/M No.182-193 Revision 1
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| , Page 2 of 19 LIST OF EFFECTIVE PAGES PAGE NO.
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| 33 1 1 2 1 3 ,
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| 1 4 0 5 0 6 0 7 0 8 0 9 -
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| 1 10 1 11 0 12 0 13 1 14 1 15 1 16 0 17 1 18 0 '
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| 19 0 l
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| < l i
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| l JPN Fom 3 Rev 7/93
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| 4 PC/M No.182-193 Rovision 1 ;
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| , Page 3 of 19 l
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| ABSTRACT This modification is an alternative to the presently utilized procedural controls to prevent undesirable ICW and CCW pump start conditions when operating the "C" i pump as a replacement for either the "A" or the "B" pump (Reference 5.3). The ;
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| existing control switches and their associated HFA latching relays will be '
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| replaced with control switches having a " pull-to-lock" feature and slip contacts.
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| These switches will perform the latching relay memory function by their slip j contacts and will allow pump lockout (trip) in their " pull-to-lock" position. '
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| '_ Presently, racking out the switchgear' breakers or pulling their control power fuses is required to disable the pump' starting ability.
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| This modification includes the safety related ICW and CCW pump control circuits, therefore, this EP is classified as Safety Related.
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| A safety evaluation of these modifications has been performed in accordance with 10CFR50.59. This evaluation concludes that implementation of this EP does not l involve an unreviewed safety question nor does it require a change to the Technical Specifications and it has no adverse effect on plant safety. Therefore, prior NRC approval is not required. l Revision 1 provides revised wiring diagrams for the "C" ICW and CCW pumps.
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| Originally issued drawings did not reflect the design as presented on CWD's and schematic diagrams. Re-verification of the entire package was performed as part of Revision 1. The revision does not affect the original safety evaluation.
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| 1 i
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| i 1
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| i JPN Fom 3. Rev 7/93 1
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| PC/M Na 182-193 ;
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| ; Rev 0 l
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| ; . Page 4 of 19 l I
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| ! I. DESIGN 1
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| : 1. Structure. System. or Component (SSC) Involved:
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| I ICW Pump 1A, 18, & IC and CCW Pump 1A, 18, & IC control circuits including:
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| . CS-201, 205, 209, 832, 833, & 834; latching relays 4/201, 4/205, 4/209,
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| ! 4/832, 4/833, & 4/834; auxiliary relays 4X/201, 4X/205, 4X/209, 4X/832, 1 - 4X/833, 4X/834, 4YA1/1006, 4YA3/1096, 4YB1/1006, & 4YB3/1006; and time delay -
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| relays 3/201, 3/205, 3/209, 3/832, 3/833, & 3/834. I a ;
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| )
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| 4 2. SSC Puroose/ Function /Desian Basis !
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| The ICW and CCW Systems provide a heat sink for safety related and non i nuclear safety related components under normal operating and emergency i shutdown conditions. The redundant pumps in each system (including the swing i pump IC) are controlled by spring-return-to-auto switches on the RTGB. The
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| ! pump control circuits have latching relays incorporated to provide memory, in
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| ! the event of a LOOP, to restart the applicable pumps. Two pumps in each system are started by an SIAS during a LOCA event. Auxiliary relays are used 4
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| i in the swing pump circuits to detect a failure to start of the primary pump when either (1A or 18) is being backed up by the IC pump. With the present i
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| design, the unused pump must have its breaker racked out or'its control power l fuses removed to prevent the possibility of two pumps starting on one i electrical train (See References 5.3 & 5.4). l i
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| ; 3. Safety Classification: SR X QR NNS
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| ! 4. Reason for Desian Chance This EP is being prepared as requested by the St.
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| ] Lucie Operations Department as an alternative to the existing procedural i controls to prevent undesirable pump start conditions identified in the
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| : Operation Summary as transmitted by letter JPN-PSLP-92-0597 dated June 9,1992 (Reference 5.4). It will remove the HFA latching relays in the pump control i circuits as requested in REA SLN-93-079 (Reference 5.5). It will also eliminate the requirement for the manual resetting of the HFA relays in the Station Blackout procedure (E0P-99, Appendix V).
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| : 5. Desian Chanae Descriotion This EP replaces the existing SBN control switches, (CS-201, CS-205, & CS-209
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| .in RTGB 106) for the CCW pumps and (CS-832, CS-833, & CS-834 in RTGB 102) for the ICW pumps, with SBN control switches having slip contacts and a " pull-to-lock" feature. These switches will perform the latching relays memory function by their slip contact arrangement and allow pump lockout from the Control Room by their " pull-to-lock" feature. These modifications will remove the HFA relays (4/201, 4/205, & 4/209 from RTGB 106 and 4/832, 4/833, & 4/834 from RTGB 102); remove the auxiliary relays (4X/201, 4X/205, 4X/209, from RTGB 106 and 4X/832, 4X/833, & 4X/834 from RTGB 102); and remove the, time delay relays (3/201, 3/205, 3/209 from RTGB 106 and 3/832, 3/833, & 3/834 JPN Forin 3 Rev 7/93
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| l .
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| PC/M No 182-193 Rev 0 i :. _ . ..--. Page 5_ of 19 from RTGB 102). The " pull-to-lock" switches will be used to control the isolation interlock relays between the "1C" swing pumps and the *lA" and "1B" primary pumps. This interlock will prevent the automatic start of two system a
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| pumps on a single electrical train.
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| An evaluation of the performance of the ICW and CCW pump control circuits, after replacement of the latching relays by " pull-to-lock" switches having 4
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| slip contacts, is included as Attachment 4.5. The operational assumption is that during normal operation one pump will not be used and will have its
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| '"_ control switch in the " pull-to-lock" position. During maintenance or testing, l this pump can be operated locally if needed but should be deenergized when l the activity is finished. It should be noted that if a running pump (from j RTGB control) is stopped by local control, it will not respond to a j subsequent SIAS. Therefore, the RTGB control switch would need to be turned l to "Stop" and back to " Auto" to enable the automatic function (See Sectian 11.2). Local stopping of these pumps should be coordinated with the control room operators.'
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| This modification will require a revision to the DBD's regarding the use of the pull-to-lock switches, rather than racking out the switchgear breakers or removing their control power fuses.
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| The only change to the FSAR by this PC/M is the drawings as listed in the Table 1.7-1.
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| 3 I
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| i i
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| l 1
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| l f
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| l l
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| JPN Forn 3. Rn 7/93
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| .- _ = . . .- -- . .
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| PC/M No 182-193 RIv 0 Page !_ of _.11.,
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| i'.____._... ._ _ ___ _ _ _ _ . _ _ . . _ _ . _ _ _ _ _ . . _ _ _ . _ . _ _ . _ _ _ _
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| : 6. Desian Chance Checklist Does the Det.ign Change involve / impact / require justification of:
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| .Y11 NQ REFERENCE Internal / External Flooding X Heavy Load Handling X
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| .- Tornado / Internal Missiles , X Single Failure Criteria X Human Factors X Sec. 8.1 Paging System Audibility X
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| ~~
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| Masonry Block Wall Interaction X
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| ; Environmental Criteria X Plant Security Capability X HELBA Criteria / Analyses X Seismic Qualification _X Sec. 8.2 Seismic Interaction X Electrical Separation Criteria X
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| _Sec. 8.3 Accessibility /Laydown/ Clearance Requirements X Loads Applied to Existing Structures (+ buried) X j
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| EDG/ Battery Loading / Load Sequencing X sec. 8.4
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| , Hydrogen Generation In Conteinment X Heat Sinks in Containment X Emergency Plant Operating Procedures (EOPs/0NOPs) X Sec. 8.5 ASME Code X Emergency Lighting Criteria X
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| Snubber Criteria X Material Compatibility / Hazardous Materials X l
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| Electrical Equipment Grounding X l Cable Tray Seismic Loading X Instrument Setpoints X Hurricane / Tornado Wind Loading X Thermal / Hydraulic Performance X
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| ' Coatings Inside Containment X Emergency Response Data System (ERDS) X Emergency Planning X NML Property Insurance Requirements X
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| ~
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| EnsifohiiidhnllsalifiEatidh X Att. 4.1 Fire;Prdte'ction? Capability ~ X Att. 4.2
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| .Sa fe/Al tern ate jS hu tdownj apj bil,i ty X sec. 8.7 ALARAiEposurejCriteria X Att. 4.3 JPN 76rmi! 3EE3 FEand213 hall; be~;attachedito]usti ff[th;eicon)16siiinifor.;thsii7Jf@
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| JPN form 3, Rev 7/93
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| - . . _ .__.m .
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| ,1 1
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| PC/M No 182-193
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| . Rev 0
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| : l. Page ]_ of _l l,
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| _- _ _ . . _ _ _ _ - . _ _ _ - . . _ . _ _ _ _ _ ~.---.
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| i 7. Desian Evaluation / Justification 2
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| l The design fenction of the ICW and CCW systems is to provide a heat sink for i
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| Safety Related and Non Nuclear Safety components under normal operating and i shutdown conditions. The pump control circuit design utilizes General
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| ; Electric latching relays, 12HFA15422H, where it is important for the plant i operations that the circuit will " remember" its positior ;i.e., energized or
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| ; not) prior -to a loss of power. A number of the HF.. relays have been
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| '_ troublesome in the past by failing to latch. As a result, under a Loss of i Offsite Power (LOOP) condition, the circuits with failed relays could prevent I automatic loading of the affected pump on the Emergency Diesel Generators.
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| 1 These relays are being removed by this design. Their function will be
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| ; performed by the slip contact arrangement of the control switches.
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| l 'The modifications provided in this EP do not adversely affect the ICW or CCW
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| , Safety Related systems' ability to perform their intended Safety Related
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| ! functions. Separation between Safety Related functions and Non Nuclear
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| ! Safety functions has not been affected by this modification.
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| This modification is justified by the following:
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| I
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| * Corrects EDG loading / sequencing, bus voltage drop and system concerns.
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| !
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| * Allows complete control of ICW/CCW put.ps during "C" pump use from the RTG8.
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| * Allows consistency of EDG timing relay settings for both linits pumps.
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| 1
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| * Would allow less accurate EDG timing relays for replacements if needed.
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| 2
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| * Removes the HFA latching relays which have industry wide problems.
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| l
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| * Eliminates time consuming manual steps in the SB0 procedures.
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| ;
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| * Reduces the number of time delay and auxiliary relays in the circuits.
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| f I
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| : 8. Evaluation of any "YES" resoonses in Desian Chanae Checklist l
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| 8.1 Human Factors Engineering j This EP has been designed in accordance with the requirements of NUREG-i 0700. The existing SBN " spring-return-to-Auto" control switches have been l replaced with SBN " pull-to-lock" control switches in the same location on
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| ; the RTGB as the original ones. These swit .nes have the same " spring-4 return-to-Auto" for normal operation e the original ones, and have an 4
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| addititional fourth position beyond trip (Stop) which is maintained by j pulling the pistol grip handle up to the locked position. Switches in the j " pull-to-lock" condition are easily recognized by their handles being in the 90 degree position (horizontal position). This is the only Operator Man-Machine Interface change in this modification. (See section V.3).
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| 8.2 Seismic Qualification The new General Electric SBN switches have been seismically qualified for installation in RTGB's 102 and 106 based on the seismic qualification test report, Reference 5.16.
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| JPN Fom 3. Rev 7/93
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| p PC/M No 182-193 Rev 0 Page g_,of ,R
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| * 1 __ _.._ _ -- . _ _ .
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| < Removal of the relays will result in a weight reduction of approximately 27 lbs for RTGB 102 and 23 lbs for RTGB 106 (References 5.13 & 5.14) The 4
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| weight of the new switches is equivalent to the . existing switches.
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| ' Accordingly, this modification will not affect the seismic qualification
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| , of RTG8's 102 and 106.
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| } 8.3 Electrical Separation Criteria i
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| In accordance with IEEE Std. 279-1971, electrical separation criteria
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| " has been maintained between the wiring of the SA, SB and SA8 sections of the RTGB. The field cabh conduc' tors affected by this EP are being spared
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| {
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| a in place. Therefore, s ectrical separation is not adversely affected. 1 8.4 EDG Loading / Load Sequencing i The EDG load has not been changed by this EP, however, the sequencing timers for all three pumps should be set for the same time delay in each system (ICW pump 1C changed to 9 seconds).
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| 1 j 8.5 Emergency Plant Operating Procedures a
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| i; Emergency Plant Operating Procedure 1-EOP-99 Appendix V shall be revised to delete the HFA relay reset steps (2.8) and add the ICW and CCW pump 1
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| control switches to be in the pull-to-lock position in the step placing the RTG8 control switches for the HPSI, LPSI, and containment spray pumps in the OFF position (2.F).
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| Off-Normal Operating Procedures, ON0P-1-0310030 and ON0P-1-0640030 will be revised to replace the requirement to " remove the trip and close fuses" with " place the control switch in the pull-to-lock position".
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| ! 8.6 Fire Protection Capability As indicated in Attachment 4.2 (JPN Form 3F), this modification does not i l
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| add any combustible materials, does not affect fire protection systems and l does not affect any fire fighting strategies. Therefore, fire protection '
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| capability is not affected. i I
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| j 8.7 Safe / Alternate Shutdown Capability J
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| i As indicated on Attachment 4.2 (JPN Form 3F), this modification provides replacement of control switches and removal of latching relays which control pumps on the Essential Equipment List. The replacements perform i
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| ! the same function as the existing components and will not affect the pumps ability to perform their safety function. Therefore, Safe / Alternate Shutdown Capability is not affected.
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| y
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| : 9. Desian Verification Statement i The design basis for the modification was reviewed to ensure that the overall i design concept meets applicable FSAR, Regulatory Guide, and 10 CFR Part 50 l requirements. The design of the modification was verified by a review of the 4
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| JPN Fom 3. Rev 7/93 I
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| ~_. - . - ._- . - -. .. - . -. .. - _ - - _ .
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| 4
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| ; PC/M No 182-193 Rsv Ai 7A, l Page 9. of 19
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| - 2_ -
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| functional requirements of the system and by the performance of a circuit !
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| analysis to determine if the proposed modifications perfons the functional !
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| i i
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| and safety requirements described in the FSAR. Integration of this modification with other designs in progress and impact on existing safety evaluations was verified by review of the Package Information Tracking System and the Affected Drawings List Databases including the Active Safety Evaluation List. Complete package was re v ,erified during preparation of revision 1. The safety analysis was verified by review of each conclusion statement required to satisfy 10 CFR 50.59 criteria for establishing whether an unreviewed safety question existed.
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| 4 a j II. M
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| : 1. Descriotion and Purpose This Engineering Package covers . modifications to the control circuits of the 1A, IB and IC Component Cooling Water Pumps and the IA,18 and IC Intake i
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| Cooling Water Pumps. Specifically, this PC/M is an alternative to the procedural controls to prevent undesirable pump start conditions when
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| , operating the "C" pump as a replacement for either the "A" or the "B" pump and eliminates the HFA relays which have been troublesome in the past. It will replace the existing control . switches with control switches having a 1
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| " pull-to-lock" feature and remove their associated HFA latching relays. These switches will allow pump lockout of automatic starts by their " pull-to-lock" feature. 1 1
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| : 2. Analysis of Effects on Safety '
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| The design bases for the ICW and CCW systems are described in FSAR Sections 9.2.1 and 9.2.2. This modification will not affect the bases as described in the FSAR and will not result in loss of any protective function nor adversely affect the function of any Safety Related or Non Nuclear Safety structure, )
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| system or component. The replacement " pull-to-lock" switches will function 1 the same as the original switches for normal pump operation and will have no adverse effect on safety. When a pump is out of service, with the control switch in the " pull-to-lock" position, it will not respond .to automatic signals to start. This switch configuration will prevent undesirable starting c'onditions and will therefore enhance the safety functioning of the system.
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| The removal of the HFA latching relays will enhance the reliability of the pumps.
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| 1 A minor change has been made in the local control station operation which will prevent an unwanted start of a pump by an SIAS (real or spurious). This change will only affect a pump that was running by way of a control room start, and is stopped by the local control station. The original design would close the' pump's switchgear breaker, even if it had been stopped at the local control station (intentionally or inadvertently), upon an SIAS start command. This feature could be a personnel safety concern if maintenance was !
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| being performed on the pump. However, with the new design, if the local stop command was unexpected, the control room operator would be alerted by the loss of the pump, and various alarms of flows and temperatures. The control JPN Form 3. Rev # 93
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| PC/M No.182-193 Revision 1 Page 10 of 19_
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| room operator could restart the pump by turning its control switch to "Stop" and then " Start". In addition, if the automatic SIAS start feature was desired after a local control station stop command, the control room operatnr I would turn the RTGB control switch to "Stop" and then back to " Auto" (the l spring return position). The probability of events requiring this action is !
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| expected to be low. The resetting action by use of the control switch is similar to those for the Boric Acid Makeup Pumps.
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| A design integration review has been conducted, and the following sources have been reviewed:
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| PSL Package Information Tracking System, as of July 26, 1994.
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| Nuclear Engineering Drawing Index, as of July 26, 1994.
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| PSL Active Safety Evaluation List, as of July 26, 1994.
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| As a result of this review it has bean concluded that PC/M 200-192, 4W Ground Relay Replacement and PC/M 341.92 ICW Lube Water Piping Removal, will have no impact on this PC/M.
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| Based on the review of the St. Lucie Unit 1 Safety Evaluation List, there are no active safety evaluations issued or in progress which have any effect on, or can be affected by this EP. In addition, there are no Justifications for Continued Operation (JCOs) which affect, or are affected by this EP.
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| : 3. Failure Modes and Effects Analysis (FMEA)
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| The FEMA is provided in the FSAR Sections 9.2.1 and 9.2.2 and in Tables 9.2-2 and 9.2-6. A review of these sections and tables has determined that this modification, which changes the pump control circuits, does not introduce any new potential failure modes to the pumps. The failure modes of the 1ew control switches are the same as the existing ones and since the numbe4 of relays are reduced, the overall reliability is improved. Therefore, the conclusion of the existing FEMA is not changed.
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| : 4. Effect on Technicrl Specifications The ICW and CCW Systen requirements are contained in Sections 3/4 7.3 and 3/4 l 7.4 of the Technical Specifications. A review of the Technical Specifications has determirmd that this modification does not have an affect on, nor require a change to hem.
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| : 5. Unreviewed Safety Ouestion (US0) Determination
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| : 1. Does the proposed activity increase the probability of occurrence of an accident previously evaluated in the SAR?
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| This modification does not affect any equipment whose malfunction is postulated in the FSAR to initiate an accident or prevent an accident from occurring. The modifications performed by this Engineering Package enhance the ability of the pumps to perform as intended during emergency and off-normal conditions. Therefore, the probability of occurrence of an accident JPN Form 3. Rev 7/93
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| PC/M No 182-193 R;v 0 Page 1]_ of 19 previously described in the SAR is not increased by this modification.
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| : 2. Does the proposed activity increase the consequences of an accident previously evaluated in the SAR?
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| This modification does not affect any structures, systems nor components that function to detect the release of radioactivity or to provide post-accident shielding. This modification does not affect the functional operation of the pumps, however, it does enhance the ability to respond to
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| '_ an S80 event. Therefore, the consequences of an accident previously evaluated in the SAR are not intreased by this modification.
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| : 3. Does the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR?
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| The operability of the pumps in this modification is being enhanced by providing operation from the Control Room of functions presutly requiring local actions. Since the reliability of the pump control circuit is being improved by this proposed change, it will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR.
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| : 4. Does the proposed activity increase the consequences of a malfunction of equipment important to safety previously evaluated in the SAR?
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| The operability of these systems is being enhanced by this modification.
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| Since the pumps will continue to perform and satisfy their design basis requirements, the proposed change will not increase the consequences of a malfunction of equipment important to safety previously evaluated in the SAR.
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| : 5. Does the proposed activity create the possibility of an accident of a different type than any previously evaluated in the SAR?
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| This modification does not change the function or design bases of any structure, system or component important to safety as described in the SAR. Since this modification does not affect any equipment whose malfunction is postulated in the SAR to initiate an accident or prevent an accident from occurring, it will not create the possibility of an accident of a different type than any previously evaluated in the SAR.
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| : 6. Does the proposed activity create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the SAR?
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| This modification improves the reliability of the system by eliminating several relays, including HFA relays. It also replaces the SBN control switches with SBN switches having a " pull-to-lock" feature which would have the same malfunction characteristics as the original switches.
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| Therefore, the possibility of a malfunction of equipment important to safety which is of a different type than any previously evaluated in the SAR is not created by this modification.
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| JPN Forn 3. Rev 7/93
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| o PC/M No 182-193 Rev 0 Page J1 of 19
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| : 7. Does the proposed activity reduce the margin of safety as defined in the basis for any Technical Specification?
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| This modification does not affect the operational requirements for the cooling systems as defined by the Technical Specifications Sections 3/4 7.3 and 3/4 7.4. Therefore, the margin of safety as defined in the bases for any Technical Specification is not reduced by this modification. '
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| : 6. Plant Restrictions '
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| This EP can be performed during any mode of operation on one system pump at a time, howeve , due to the RTGB wiring changes, it is reconnended to be implemented during refueling modes 5 or 6. ,
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| l Post modification testing will be required to verify that the control logic with respect to Safety injection Actuation and LOOP has been properly implemented, and that the sequencing time of the pumps is functioning properly.
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| The following plant procedures may need to be revised pursuant to this modification: Maintenance Procedure No. 1-0910055, " Periodic Test of Automatic Load Sequence Relays", and its data sheets, and Operating Procedure No. 1-0400050, " Periodic Test of the Engineered Safety Features". Note that the EDG sequencing time for the "lC" pumps is to be the same as their "1A &
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| IB" pump counterparts.
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| The following Operating Procedures and Off-Normal Operating Procedures should be revised to include the operation of the " pull-to-lock" switches and delete the requirement to remove the trip and close fuses in the switchgear: OP 0310020, OP-1-0640020, ON0P-1-0310030, and ON0P-1-0640030 (References 5.9, 5.10, 5.11, & 5.12).
| |
| : 7. Conclusions The foregoing constitutes, per 10CFR50.59 (b), that the modifications to be performed by this EP do not involve an unreviewed safety question nor a change to the Plant Technical Specifications. Therefore, prior NRC approval for the implementation of these modifications is not required.
| |
| JPN Form 3. Rev 7/93
| |
| | |
| PC/M No.182-193 Revision 1 Page )).,_,of .[1 l
| |
| III. CORRENtNRW
| |
| : l. Affected Document Checklist yJJ !!0_ Reference FSAR X Attachment 4.6 Technical Specifications X TEDB X Attachment 4.4
| |
| '~
| |
| Security Plan X DBDs _f _, Attachment 4.7 Snubber List _ _ _ _ ,
| |
| X ISI/IST Program (if "res . Est revi to r.ouir.c X Code Stress Reports X
| |
| : 2. Affected Drawinos PC/M Dwa # Rev Description / Title Disc Affected Dwas Rev Pr EP Rev JPN-182-193-001 0 Before CCWP 1A Sch I 8770-B-326-201 6 y 0 JPN-182-193-002 0 After CCWP 1A Sch I 8770-B-326-201 6 y 0 JPN-182-193-003 0 Before CCWP 18 Sch I 8770-B-326-205 7 y 0 JPN-182-193-004 0 After CCWP IB Sch I 8770-B-326-205 7 y 0 JPN-182-193-005 0 Before CCWP IC Sch I 8770-8-326-209 7 y 0 JPN-182-193-006 1 After CCWP IC Sch I 8770-8-326-209 7 y 1 JPN-182-193-007 0 Before ICWP 1A Sch I 8770-8-326-832 8 y 0 JPN-182-193-008 0 After ICWP 1A Sch I 8770-8-326-832 8 y 0
| |
| , JPN-182-193-009 0 Before ICWP 18 Sch I 8770-B-326-833 7 y 0 JPN-182-193-010 0 After ICWP 18 Sch I 8770-B-326-833 7 y 0 JPN-182-193-011 0 Before ICWP IC Sch I 8770-B-326-834 7 y 0 JPN-182-193-012 0 After ICWP IC Sch I 8770-8-326-834 7 y 0 JPN-182-193-013 0 Before 3rd Pmp Sch I 8770-B-326-1006 3 y 0 JPN-182-193-014 0 After 3rd Pmp Sch I 8770-B-326-1006 3 y 0 JPN-182-193-015 0 Before CCWP 1A CWD I 8770-B-327-201 15 y 0 JPN-182-193-016 0 After CCWP 1A CWD I 8770-8-327-201 15 y 0 JPN-182-193-017 0 Before CCWP 18 CWD I 8770-B-327-205 17 y 0 JPN-182-193-018 0 After CCWP 18 CWD I 8770-B-327-205 17 y 0 JPN-182-193-019 0 Before CCWP IC CWD I 8770-B-327-209 19 y 0 JPN-182-193-020 1 After CCWP IC CWD I 8770-B-327-209 19 y 1 JPN-182-193-021 0 Before ICWP 1A CWD I 8770-B-327-832 19 y 0 JPN-182-193-022 0 After ICWP 1A CWD I 8770-B-327-832 19 y 0 JPN-182-193-023 0 Before ICWP IB CWD I 8770-B-327-833 16 y 0 JPN-182-193-024 0 After ICWP IB CWD I 8770-B-327-833 16 y 0 JPN-182-193-025 0 Before ICWP IC CWD I 8770-B-327-834 22 y 0 JPN-192-193-026 1 After ICWP IC CWD I 8770-B-327-834 22 y 1 JPN-182-193-027 0 After SWGR 1AB CWD I 8770-B-327-951 9 y 0 JPN-182-193-028 1 Before 3rd Pmp CWD I 6770-8-327-1006 7 y 1 JPN-182-193-029 1 After 3rd Pmp CWD I 8770-B-327-1006 7 y 1 JPN-182-193-030 0 4kV SWGR Rlys Sch I 8770-B-326-951 3 y 0 JM Form 3. hw #93
| |
| | |
| - f PC/M No.182-193 !
| |
| Revision I l Page 14 of- 19_ l PEEf ~ RgE
| |
| ~ ~
| |
| DescNioTion2 Title d ~AIfeh eT Dwas RN ~ [h* [P'Rev JPN-182-193-031 0 Before RTG8 101 I 8770-3324 28 n 0 JPN-182-193-032 1 After RTGB 101 I 8770-3324 28 n 1 JPN-182-193-033. 0 Before RTGB 106 I 8770-3467 17 n 0 JPN-182-193-034 1 After RTGB 106 I 8770-3467 17 n 1 JPN-182-193-035 0 RTG8 102 I 8770-3470 28 n 0 JPN-182-IC 036 0 Before RTG8 102 I 8770-3472 21 n 0 JPN-182-193-037 0 After RTG8 102 I 8770-3472 21 n 0
| |
| ,_ JPN-182-193-038 0 Before RTG8 106 ,I 8770-4464 7 n 0 JPN-182-193-039 1 After RTGB 106 I 8770-4464 7 n 1 JPN-182-193-040 1 RTGB 106 I 8770-4467 14 n 1 JPN-182-193-041 0 Before RTGB 106 I 8770-4468 22 n 0 JPN-182-193-042 0 After RTGB 106 I 8770-4468 22 n 0 JPN-182-193-043 0 Before RTGB 106 I 8770-4468 22 n 0 JPN-182-193-044 1 After RTGB 106 I 8770-4468 22 n 1 JPN-182-193-045 0 Before RTGB 106 I 8770-4469 18 n 0 JPN-182-193-046 0 After RTGB 106 I 8770-4469 18 n 0 JPN-182-193-047 0 RTGB 106 I 8770-4471 12 n 0 JPN-182-193-048 0 Before Cnti & Blk I 8770-B-276-14.28 3 n 0 JPN-182-193-049 1 After Cntl & Blk I 8770-B-276-14.2B 3 n -l JPN-182-193-050 0 Before Cntl & B1k I 8770-B-276-14.2C 3 n 0 JPN-182-193-051 1 After Cntl & Blk I 8770-B-276-14.2C 3 n 1 JPN-182-193-052 0 Before Cntl & Blk I 8770-8-276-14.2D 3 n 0 JPN-182-193-053 1 After Cntl & Blk I 8770-B-276-14.20 3 n 1 JPN-182-193-054 0 Before Cntl & Blk I 8770-B-276-21.1B 3 n 0 JPN-182-193-055 1 After Cntl & Blk I 8770-B-276-21.1B 3 n 1 JPN-18?-193-056 0 Before Cntl & Blk I 8770-B-276-21.lc 3 n 0 .
| |
| JPN-182-193-057 1 After Cntl & B1k I 8770-B-276-RI.1C 3 n 1 JPN-182-193-058 0- Before Cntl & B1k I 8770-B-276-21 lD 3 n 0 <
| |
| JPN-182-193-059 1 After Cnti & Blk I 8770-B-276-21.1D 3 n 1 JPN-182-193-060 0 As-Building Notes I 8770-1638 9 n 1 8770-1548 10 n 8770-1557 9 n 8770-1637 9 n i 8770-1553 12 n 8770-1555 9 n 8770-2175 12 n 8770-2538 15 n
| |
| * Incicate Yes or No if SRD for PSL. Incicate 1 (PDD) 2 (CRD), 3 (MD), 4 (ED), or 5 (other) for PTN.
| |
| : 3. Affected Vendor Manuals Plant Doc No Rev Vendor /Eauio Disc Remarks EP Rev NONE
| |
| : 4. Attachments Paaes JPN Fom 3. Rev 7/93
| |
| | |
| i PC/M No.182-193 {
| |
| Revisien 1 Page 15 of 11.
| |
| --_. ~ ~ ~~ 47At tichmen ts - ~ ~ ~ ~ ~
| |
| - ~ ~ ~ P a g e's
| |
| ]
| |
| 4.1 Environmental Qualification Checklist (Fom 3E) 1 4.2 Fire Protection Review Checklist (Fom 3F) 3 4.3 ALARA Screening (Form 71) 1 4.4 TEDB Change Package 10 4.5 ICW/CCW Pump Control Circutt Evaluation 9 4.6 FSAR Change Package 1 4.7 DBD Change Package 6
| |
| : 5. References 5.1 St. Lucie Unit 1, Final Safety Analysis Report, Amend. 12 5.2 St. Lucie Unit 1, Technical Specification's, Amend. 127 5.3 Engineering Evaluation JPN-PSL-SEEP-92-041, Rev. O, Evaluation of "C" Pump Sta.rt Combinations for ICW, CCW & Charging Pumps.
| |
| 5.4 Letter JPA-PSLP-92-0597 dated June 9,1992, with Operation Summary table attached 5.5 Request fe' Engineering Assistance (REA) number SLN-93-079, approved August 27, 1993 5.6 Plant Operating Procedure 1-EOP-99 Appendix V, SB0 Crosstie, Rev. 9.
| |
| 5.7 Maintenance Procedure 1-0910055, Periodic Test of Automatic Load Sequence Relays, Rev. 5 5.8 Operating Procedure 1-0400050, Periodic Test of the Engineered Safety Features, Rev. 32 5.9 Plant Operating Procedure 1-0310020, CCW System, Rev. 37
| |
| '5.10 Plant Operating Procedure 1-0640020, ICW System, Rev. 38 5.11 Plant Off-Normal Operating Procedure 1-0310030, CCW System, Rev. 25 5.12 Plant Off-Normal Operating Procedure 1-0640030, ICW System, Rev. 17 5.13 GE Protection and Control Products Catalog GEZ-7723A JPN Fom 3. Rev 7/93
| |
| | |
| t<
| |
| PC/M No 182-193 Rev 0 Page 16 of 19
| |
| : 5. References (continued) 5.14 Agastat Catalog EMD-1, December 1989 5.15 GE Selection & Application Guide, GET-6169D, December 1989 l 5.16 Nuclear Logistics Inc. Test Report QR-037003-1, Rev.1, January 1994 1
| |
| IV. MATERIAL l
| |
| : 1. Eauioment and Material I
| |
| 11gm Ouantity Descriotion Reference Pre-Purchased?
| |
| 1 6 General Electric RPA 645003434 Yes Type SBM Control Switches 2 As Wire, switchboard, M&S No. Available in required 1/C #14 AWG 001-28836-9 Stores
| |
| : 2. Soare Parts item Ouantity Descriotion Reference Pre-Purchased?
| |
| 1 1 General Electric RPA 645003434 Yes Type SBM Control Switch l
| |
| l 1
| |
| i
| |
| )
| |
| I l
| |
| i l
| |
| l JM Fors 3. Rev 7/93
| |
| | |
| I PC/M N3.182-193 R;visien 1 l Page 17 of 19 l- -.-- - ... . . - - - --. -. - - - . _ . . _ . - ...
| |
| l V. IMPLEMEWmTION I i
| |
| : 1. Implementation Instructions / Specifications l The Implementor's work scope includes, but is not limited to or confined to a specific order, the following as detailed on the JPN drawings listed in the Affected Drawings Section:
| |
| ~~
| |
| a) Remove and replace the existing SBN control switches CS-201, CS-205, & CS-209 in RTGB 106 with SBN pull-to-lock switches having slip contacts in accordance with appropriate plant procedures and JPN-182-193 drawings as ,
| |
| applicable. !
| |
| b) Remove and return to stores the existing HFA Latching relays 4/201,4/205,
| |
| & 4/209; Auxiliary relays 4X/201, 4X/205, & 4X/209; and Time Delay relays 3/201, 3/205, & 3/209 from RTGB 106 in accordance with applicable JPN-182-193 drawings and plant procedures.
| |
| I c) Re-use the existing conductors between the control switch or relay and the l terminal blocks, when possible. New switchboard wire, if required, is to be run in the existing wireways and conduit without overfilling nor mixing safety trains.
| |
| d) Utilizing switchboard wire, connect jumpers, relays and control switches to associated terminal strips in RTGB 106 as shown in JPN-182-193 drawings.
| |
| Label the connections in accordance with appropriate plant tagging and labelling procedures.
| |
| e) Repeat steps, a) through d) above, for control switches CS-832, CS-833, &
| |
| CS-834 and relays 4/832,4/833,4/834,4X/832,4X/833,4X/834,3/832,3/833,
| |
| & 3/834 in RTGB 102.
| |
| f) Spare in place the three conductors of the following cables, as shown on the CWD's, by determinating and taping at both ends:
| |
| iO2018-SA RB, WB, & GB From RTGB 106 To 4kV SWGR 1A3-6 102058-SB RB, WB, & GB From RTGB 106 To 4kV SWGR IB3-4 10209B-SAB RB, GB, & OB From RTGB 106 To 4kV SWGR 1AB-2 108328-SA RB, WB, & GB From RTGB 102 To 4kV SWGR 1A3-7 10833B-SB RB, WB, & GB From RTGB 102 To 4kV SWGR 1B3-10 10834B-SAB RB, GB, & OB From RTGB 102 To 4kV SWGR 1AB-3 g) Adjust ti- delay relays 2X/TDPU as necessary to comply with this PC/M, especially ICW pump IC at 9 seconds.
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| .PN Form 3. Rev 7/93
| |
| | |
| r PC/M No l82-193 Rev 0
| |
| )
| |
| Page 18 of 19
| |
| : 2. Post-Mod Acceptance Testino i
| |
| Post-modification tests shall be in accordance with approved plant procedures. '
| |
| a) Tesiing shall include verification that operation of the pumps for manual start /st.op commands and in response to a LOOP and an SIAS is in accordance with the operational evaluation and summary in Attachment 4.5.
| |
| b) Testing shall include verification that each pump with its control switch in the " pull-to-lock" position will remain in the tripped condition and not respond to either a LOOP or an S!:iS.
| |
| : 3. Operations and Maintenance Guidelines Operations, Training, and Maintenance should be cognizant of the operational evaluation in section 1.5, Design Change Description,' and Attachment 4.5. The control circuitry modification to be implemented will require that, during Normal Plant Operation, u. pumps will be running with the control switch in the " Auto-after-Start" position and the third pump in "Stop and pull-to-lock" position.
| |
| Under normal operation, two pumps may be in the " Auto-after-Start" position with the third pump's control switch in the "Stop and pull-to-lock" position, the l third pump could be running from the local control station for testing or i maintenance purposes. This operation will not affect the proper response to a '
| |
| LOOP, SIAS, or LOOP /SIAS condition.
| |
| Under abnormal circumstances, two pumps may be running in the " Auto-after-Start" position with the third pump's control switch in the "Stop and pull-to-lock" !
| |
| position, if one running pump is then stopped from the local control station it I
| |
| 'will not respond to a subsequent SIAS (without LOOP) start command, unless the !
| |
| control room switch is turned .to "Stop" and then back to " Auto" (its " spring- !
| |
| return-to-Auto" position). Note, it would respond to a LOOP /SIAS start command.
| |
| Therefore, operations / maintenance procedures should insure that, if c local control station is used to stop a pump which was started from the RTGB, the RTGB control switch must be turned to "Stop" and then back to " Auto" (enabling the SIAS function).
| |
| Plant Operating Procedure 1-0310020 (Reference 5.9) Appendix A, Step 2.C and Appendix C, Step 2.F and Plant Operating Procedure 1-0640020 (Reference 5.10)
| |
| Appendix C, Steps 1.K. 2.K, 3.X, & 4.K, should be revised to replace the requirement to " Remove and tag the trip and close fuses" with " Place the control switch in the pull-to-lock position". '
| |
| Off-Normal Operating Procedures (References 5.11 and 5.12) should be revised as follows:
| |
| JPN Fom 3. Rev 7/93
| |
| | |
| t PC/M N3 182-193 Rev 0 Page 19 of 19
| |
| ; t...______..___.. . _ _ . _ _ _ . . . _ . .
| |
| ! 1 In 1-0310030, Step 5.3 and in 1-0640030, Step 7.2.;, add a note to turn the control switch to "Stop" and then to " Start" in case the pump was stopped from the local control station.
| |
| Revise all steps that " remove the trip and close fuses" , by replacing them with " place the centrol switch in the pull-to-lock position".
| |
| ' ' ~
| |
| Plant procedures (References 5.6, 5.7, & 5.8) should be reviewed for any impact made by this modification in addition'to those discussed in sections I.8.5 and
| |
| , 11.6.
| |
| I 1
| |
| 1
| |
| +
| |
| I I
| |
| l l
| |
| JPN Form 3, Rev 7/93
| |
| | |
| - _ . . . - ~ . - . - - . - -
| |
| 1 i-
| |
| )
| |
| 1_ _ _. _ _ -
| |
| _ latar Offica_Corrasposence__ ,
| |
| : p. . ; :1 - -
| |
| gj ,
| |
| p":53L, , JPN-PSLP-94-0081 E q a r.' ;; . i .. ; O
| |
| ; s
| |
| ~ ~~
| |
| & '.)" d .: i.a 2 *
| |
| .~.,-
| |
| , 1 To: S. A. Valdes o.t.: pg 3 ggg St. Lucie Plant . ;
| |
| l 4
| |
| rrm: J. B. Hosmer c.part nt: JPN/JB
| |
| . Nuclear Engineerin <
| |
| subject: ST. LUCIE PLANT UNIT 1 REA/ PROJECT f SLN-93-079-10 I 1
| |
| TITLE: ICW/CCW PUMP CONTROL CIRCUITS PULL TO LOCK SWITCHES PC/M 182-193. FILE #: REA SLN-93-079 a
| |
| Attached for your review, approval, and use is the EP for the subject Plant i 4
| |
| Change Modification. '
| |
| i This package provides the details necessary to implement the following modification:
| |
| l 4
| |
| Replacement of the existino SBN control switches for the ICW and CCW oumos control circuits with the pull-to-lock switches with slio contacts. The existina HFA latchino relays will be eliminated by this modification.
| |
| By copy of this letter, Document Control is requested to distribute this package to the normal distribution plus the following:
| |
| REA Originator: W Dean This completes the de relay replacement portion of REA SLN-93-079-10. Work is proceeding on the MEP to replace all the ac HFA latching relays.
| |
| If you have any questions, contact W Lewinger at 691-2114.
| |
| LW Attachment Copies to: oOST E
| |
| T**
| |
| * T.M. Biggs - OM/PSL r , i\*"i, b* ,
| |
| H.L. Fagley/DCC - CS/PSL (w/ Repro) A.
| |
| S. Kozlin - JDC/JB (w/dwg list & orig dwgs)
| |
| K.K. Mohindroo - JPN/JB Nig. "
| |
| M.H. Ortega - JPN/JB -
| |
| J.A. Porter - JPN/JB (w/dwg list) _.
| |
| C.L. Schaeffer - JMC/JB -
| |
| C.M. Spalter - JPN/JB (w/ orig word doc & copy of dwgs) , m.r P.
| |
| D.M. Stewart - TEC/PSL #. 1 h V 4(f f'
| |
| 0.L. Smith - JPN/JB / '
| |
| SHELL$\rCRM.016
| |
| /
| |
| | |
| i
| |
| * *~
| |
| 013-PR/PSL-1 l Revision 30 February,1994 Page 26 of 39 l-- . . . _ _ _ _
| |
| j ATTACHMENT 2 PC/M REVIEW FORM (Page 1.of 3) ,
| |
| ! PCM Number /f2-19] Supplement Numoer O Plant / Unit #St./ / Expiration Date /.2;/ /.2.J 2[
| |
| i Safety Classification: .,
| |
| l X Safety Related Quality Related Not Safety Related Originator / Organization: Originatin Document Number:
| |
| NCR, RFD, etc.) j 3_g pfy Stw o79 i
| |
| - l Title of PCM l ZC+/ccw flom/ Gwrwt. C T. w srs Pm s. - G) - La.se s~.srwes l i
| |
| __ fEAAcC*r of IW iMSITW6 38M C*ntet. .%Crmcs Aor- ntt' .2W M CC" l O U*~_ _ W '; flomps (.oumet. Cr$wirt wsnt fwa -Tb -law. .%.sywss wrin y,o m fasrx HfA LAM /AAVE f4 8;M f&rFe. l 1
| |
| //ftp3 fpfavrNNOf.sIAAA4'ECwAn*) CC.w km/ 3 % '~ COWS 0ZITd M ,
| |
| 1 I
| |
| i l
| |
| Implementing Documentation: CWO #: j fj73, 99,,3,3 65 Hlo 140I7stJr '
| |
| Backfit-worked x Plant worked WPS #: 65 No 99004592 6 7320 940n1551 320 ivos7Ft6 No testing required >< Plant tested NPWO #: 4 3ro 9,oenei
| |
| . 65/1310 w ot7ss?
| |
| Otner Areas Attected: Yes or No DesCnDtion Ooorator Trainina Yes As per Trainino Department Reauirements Operatina Proceeures W5 PER SECT 100 E,6 Surveiltance Pfaw*ures A/o Maintenance Procedures Wa Soare Parts Wi Drawinas/Tecnnical Manuals PES SRDs? CD/ N FUSAR Chance yf5 Arrme.1 '/ (
| |
| TEDB Chance YfS A rrwu . t 'l Human Factors yg f ERDADS Affected %
| |
| In Service inspection A4 Others #ssa
| |
| | |
| Q13-PR/PSL-1
| |
| ; R2 vision 30 j, February,1994 l
| |
| . . _ - _ . _ - . . . _ _ _ _ __ _ _ _ _ Page 27 of 39 I 1
| |
| l ATTACHMENT 2 d
| |
| PC/M REVIEW FORM
| |
| : (Page 2 of 3) )
| |
| PC/MWUmber" '/87- S T " ~ Supplenient' Number O' ~
| |
| ; Plant / Unit 80 /l Expwamon Date 12 /.d.) 9'/
| |
| : i d
| |
| PC/M Type:
| |
| ^
| |
| Physcal Work Required ;
| |
| \
| |
| Nonnal ARP As Fail Either or l
| |
| I l Technical Staff Review and Comments: ;
| |
| 1 No l l 1. la this PC/M Safety Related? Ye /s i j 2. Is the answer to the to CFR 50.59 / l screemng queston Yes? )
| |
| : 3. Does the PC/M requwe any physcal j !
| |
| j work to be performed? V l i I If the answere to these questione are NO, no FRG review le required. j l
| |
| 4 Safety Evaluation complies with Cp 50.59:
| |
| Technical Staff Date 2- / 2 t/ / 'y c/
| |
| PC/M Review Complete:
| |
| l Technical Staff Date 8 / 22/ 9Y i
| |
| Maintenance QC Review and Comments:
| |
| i 1
| |
| ' PC/M Review Complete: /
| |
| ! QC Signature A- Date 6 /U /d
| |
| , l i
| |
| Plant General Manager App val-Signatup _ (<Lt r b4- Date b/OW /
| |
| ; //_
| |
| i FRG Approvat:
| |
| j FRG Number: FRG Secretary 'b -
| |
| Date / /
| |
| 7
| |
| | |
| Ol 3-PR/PSL-1 R vizion 30 February,1994 Pace 28 of 39 ATTACHMENT 2 PC/M REVIEW FORM (Page 3 of 3)
| |
| Plant / Unit /#3 ' / /
| |
| Maintenance OC Closecut Review:
| |
| equired Not Required Date: 1- / 2Y / W Technical Staff Approved for Closeout: Date: o / h /3'.L_
| |
| N nance QC Comments:
| |
| Technica! Staff Closecut Review:
| |
| Approved for Closeout: /ld#~ Date: " / #/ +v Technical Staff Procedure Notification Completed: A [--- Date: /L/ /3 / FV Technical Staff Training Notification Completed: 1A N$ Date: .3 //3 /#
| |
| Technical Staff Cancellation Information:
| |
| Technical Staff Date: / /
| |
| | |
| l l
| |
| l FPL NUCLEAR ENGINEERING
| |
| - ~~~~~ )
| |
| ~ ~ ~ ~
| |
| ENGINEERING PA MAGE ~
| |
| l PC/M N0: 182-193' REV: 0 SUPPL: 0 PLANT: ST. LUCIE UNIT: 01 l a
| |
| TITLE: ICW/CCW PUMP CONTROL CIRCUITS Pull.-TO-LOCK SWITCHES WITH SLIP CONTACTS l
| |
| REVISION DESCRIPTION: ISSUED FOR USE LEAD DISCIPLINE: ELECTRICAL EXPIRATION DATE: 12/12/94 REA NO: SLN 93-079-10 DWA N0: N/A PC/M CLASSIFICATION: SR X QR NNS DESIGN ORGANIZATION: PSL/ PEG DISC CHIEF REVIEW REQD? YES NO X EXTERNAL INTERFACES: NONE DISC CHIEF SIGNATURE: N/A REVIEW / APPROVAL:
| |
| INTERFACE TYPE GROUP PREPARED VERIFIED APPROVED FPL APPROVED' INPUT REVIEW N/A MECH X
| |
| = x zw- awM%
| |
| :n x AP G v fhc r. .L N Nlt Mdj
| |
| ::vit x w . 6.c, % 4rh w M. b.
| |
| NUC" X
| |
| [kMe* _
| |
| (St X
| |
| *Ur
| |
| . TU:L I X l
| |
| * ; ::at a:::t ;*e: ares E s as Determ meo Ev :-e:ects " :ev3e. -terf ace As A winimum Cr Al' E8s FPL PROJECTS APPROVAL: M, 4 -
| |
| DATE: $/h fog r - 1. Dev 7/ot
| |
| | |
| i PC/M No 182-193 4
| |
| ;. Rev 0 !
| |
| , - - - _ _ "*" " w **I***-++.-,m .m -
| |
| i I ,
| |
| i LIST OF EFFECTIVE PAGES i
| |
| i PAGE NO. RH 2
| |
| I 0
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| ! 2 0 4
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| ' 3 0
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| < 4 0
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| $ 5 0 6 0 i 7 0 8 0 ;
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| 9 o I 10 0 1 11 0
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| ; 12 0
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| ! 13 0 l '14 0 i 15 0 2 16 0 17 0 18 0 l 19 0 4
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| 5 l
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| 4 4
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| 4 i
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| i n
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| ) '
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| I, -
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| )
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| i e
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| i i
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| i t
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| 4 l
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| *DN fa-. 1 Day 1 tes
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| 1 I
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| PC/M No 182-193 Rev 0 l Page -- of -- - - l I
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| l ABSTRACT l
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| l TMs medification is an alternative to-the-presently utilized procedural controls to prevent undesirable ICW and CCW pump start conditions when operating the "C" pump as a replacement for either the "A" or the "B" pump (Reference 5.3). The existing control switches and their associated HFA latching relays will be replaced with control switches having a " pull-to-lock" feature and slip contacts.
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| . These switches will perform the latcbing relay memory function by their slip contacts and will allow pump lockout (trip) in their " pull-to-lock" position.
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| Presently, racking out the switchgear breakers or pulling their control power fuses is required to disable the pump starting ability.
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| This modification includes the safety related ICW and CCW pump control circuits, therefore, this EP is classified as Safety Related.
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| A safety evaluation of these modifications has been performed in accordance with I 10CFR50.59. This evaluation concludes that implementation of this EP does not i involve an unreviewed safety question nor does -it require a change to the Technical Specifications and it has no adverse effect on plant safety. Therefore, prior NRC approval is not required.
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| PC/M No 182-193
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| I. DESIGN 3 1. Structure. System. or-Component 1SSC) Involved:
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| ICW Pump 1A, 18, & IC and CCW Pump.1A, IB, & IC control circuits including:
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| 4
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| ' CS-201, 205, 209, 832, 833, & 834; latching relays 4/201, 4/205, 4/209, 4/832, 4/833, & 4/834; auxiliary < relays 4X/201, 4X/205, 4X/209, 4X/832,
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| ' 4X/833, 4X/834, 4YA1/1006, 4YA3/1006, 4YBl/1006, & 4YB3/1006; and time delay relays 3/201, 3/205, 3/209, 3/832, 3/833, & 3/834.
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| ! 2. SSC Purpose / Function /Desian Basis The ICW and CCW Systems provide a heat sink for safety related and non nuclear safety related components under normal operating and emergency shutdown conditions. The redundant pumps in each system (including the swing 2
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| pump IC) are . controlled by spring-return-to-auto switches on the RTGB. The pump control circuits have latching relays incorporated to provide memory, in the event of a LOOP, to restart the applicable pumps. Two pumps in each system are started by an SIAS during a LOCA event. Auxiliary relays are used in the swing pump circuits to detect a failure to start of the primary pump when either (lA or IB) is being backed up by the IC pump. With the present i design, the unused pump must have its breaker racked out or its control power fuses removed to prevent the possibility of two pumps starting on one 1
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| electrical train (See References 5.3 & 5.4).
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| : 3. Safety Classification: SR X NNS QR l
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| 4
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| : 4. Reason for Desian Chanae This EP is being prepared as requested by the St.
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| Lucie Operations Department as an alternative to the existing procedural controls to prevent undesirable pump start conditions identified in the Operation Summary as transmitted by letter JPN-PSLP-92-0597 dated June 9,199?
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| (Reference 5.4). It will remove the HFA latching relays in the pump control !
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| circuits as requested in REA SLN-93-079 (Reference 5.5). It will alsa eliminate the requirement for the manual resetting of the HFA relays in the Station Blackout procedure (E0P-99, Appendix V).
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| : 5. Desian Chance Description
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| .This EP replaces the existing SBM control switcr.es, (CS-201, CS-205, & CS-:09 in RRB 106) for the CCW pumps and (CS-832, CS-833, & CS-834 in RTGB 102) for the ICW pumps, with SBM control switches having slip contacts and a " pull-to-lock" feature. These switches will perform the latching relays memory function by their slip contact arrangement and allow pump lockout from the Control Room by their " pull-to-lock" feature. These modifications will remove the HFA relays (4/201, 4/205, & 4/209 from RTGB 106 and 4/832, 4/833, & 4/834 from RTGB 102); remove the auxiliary relays (4X/201, 4X/205, 4X/209, from RTGB 106 and 4X/832, 4X/833, & 4X/834 from RTGB 102); and remove the time delay relays (3/201, 3/205, 3/209 from RTGB 106 and 3/832, 3/833, & 3/834
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| PC/M No 182-193 Rev 0
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| _ _ _ - _ _ _ . . . _ _ _ _ . _ ..._ _ - _.__Page_3 o f. _19 -_ - __ ____ _
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| from RTGB 102). The " pull-to-lock" switches will be used to control the isolation interlock relays between the "1C" swing pumps and the "1A" and "1b" primary pumps. This interlock will prevent the automatic start of two system pumps on a single electrical train.
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| An evaluation of the performance of the ICW and CCW pump control circuits, after replacement of the latching relays by " pull-to-lock" switches having slip contacts, is included as Attachment 4.5. The operational assumption is that during normal operation one gump will not be used and will have its control switch in the " pull-to-lock position. During maintenance or testing, this pump can be operated locally if needed but should be deenergized when
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| 'the activity is finished. It should be noted that if a running pump (from RTGB control) is stopped by local control, it will not respond to a subsequent SIAS. Therefore, the RTGB control switch would need to be turned to "Stop" and back to " Auto" to enable the automatic function (See Section 11.2). Local stopping of these pumps should be coordinated with the control room operators.
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| This modification will require a revision to the DBD's regarding the use of the pull-to-lock switches, rather than rocking out the switchgear breakers or removing their control power fuses.
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| The only change to the FSAR by this PC/M is the drawings as listed in the Table 1.7-1.
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| PC/M No 182-193 Rev 0 Page 5 of 19 _ _ _
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| : 6. Deslan Chanae Checklist !
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| Does.the Design Change involve / impact / require justification of:
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| 4 YES NO REFERENCE 2
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| Internal / External Flooding X Heavy Load Handling X Tornado / Internal Missiles X 4
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| Single Failure Criteria X Human Factors X Sec. 8.1 Paging System Audibility X l
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| ; Masonry Block Wall Interaction X !
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| Environmental Criteria X Plant Security Capability X HELBA Criteria / Analyses X Seismic Qualification X Sec. 8.2 Seismic Interaction X Electrical Separation Criteria X Sec.J 3 Accessibility /Laydown/ Clearance Requirements X Loads Applied to Existing Structures (+ buried) X EDG/ Battery Loading / Load Sequencing X Sec. 8.4 ;
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| Hydrogen Generation In Containment X l
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| Heat Sinks in Containment ~
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| X i Emergency Plant Operating Procedures (E0Ps/0N0Ps) X bet. . 6.5 j ASME Code X :
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| Emergency Lighting Criteria X Snubber Criteria X Material Compatibility / Hazardous Materials X Electrical Equipment Grounding X Cable Tray Seismic Loading X Instrument Setpoints X Hurricane / Tornado Wind Loading X Thermal / Hydraulic Performance X '
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| Coatings Inside Containment X Emergency Response Data System (ERDS) X Emergency Planning X NML Property Insurance Requirements X Environmental' Qualification X Att. 4.1 Fire Protect _ ton Capability X Att. 4.2 ._
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| Safe /AlternateiShutdown Capability X sec. 8.7 ALARA: Exposure Criteria X Att. 4.3 JPN Forms 3E, 3F,-and 71 shall be attached to justify the conclusion for these items.
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| JPN Form 3. Rev 7/93
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| [ . PC/M No 182-193 Rev 0 '
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| l 7. Desian Evaluation / Justification i-t i
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| The design function of the ICW and CCW systems is to provide a heat sink for !i l
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| i Safety Related and Non Nuclear Safety components under normel operating and j
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| shutdown conditions. The pump control circuit design utilizes General i i
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| Electric latching relays,12HFA15422H, where it is important for the plant operations that the circuit will " remember" its position (i.e., energized or ;
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| 4
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| __ not) prior to a loss of power. number of the HFA relays have been troublesome in the past by failing)to latch. As a result, under a Loss Of l
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| : Offsite Power (LOOP) condition, the circuits with failed relays could prevent
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| ; automatic loading of the affected pump on the Emergency Diesel Generators.
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| i These relays are being removed by this design. Their function will be perfomed by the slip contact arrangement of the control switches.
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| I The modifications provided in this EP do not adversely affect the ICW or CCW l l Safety Related systems' ability to perform their intended Safety Related functions. Separation between Safety Related functions and Non Nuclear l Safety functions has not been affected by this modification.
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| [ This modification is justified by the following:
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| * Corrects EDG loading / sequencing, bus voltage drop and system concerns.
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| * Allows complete control of ICW/CCW pumps during "C" pump use from the pTGB.
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| * Allows consistency of EDG timing relay settings for both Units pumps.
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| * Would allow less accurate EDG timing relays for replacements if needed.
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| * Removes the HFA latching relays which have industry wide problems, j
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| * Eliminates time consuming manual step; in the SB0 procedures.
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| * Reduces the number of time delay and auxiliary relays in the circuits.
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| j 8. Evaluation of any "YES" responses in Desian Chance Checklist i f '
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| [ 8.1 Human Factors Engineering' 3
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| ; This EP has been designed in accordance with the requirements of NUREG-0700. The existing SBM " spring-return-to-Auto" control switches hav'e been replaced with SBM " pull-to-lock" control switches in the same location on the RTGB as the original ones. These switches have the same " spring-return-to-Auto" for normal operation as. the original ones, and have an l addititional fourth position beyond trip (Stop) which is maintained by ;
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| i pulling the pistol grip handle up to the locked position. Switches in the i
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| " pull-to-lock" condition are easily recognized by their handles beine in the 90 degree position (horizontal position). This is the only Opera.ar
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| , Man-Machine Interface' change in this modification. (See section V.3).
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| 1 8.2 Seismic Qualification
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| )- The new General Electric SBM switches have been seismic .ly qualified for installation in RTGB's 102 and 106 based on the seismic qualification test
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| ; report, Reference 5.16.
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| 9DII a .eut $ $$p I i
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| PC/M No 182-193
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| . Rev 0
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| ._ - _ _ _ _ _ _ . . . . _ . . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ . _ _ _ _ Page.8_ _of_ 19 Removal of the relays will result in a weight reduction of approximately 27 lbs for RTGB 102 and 23 lbs for RTGB 106 (References 5.13 & 5.14) The weight of the new switches is equivalent to the_ existing switches.
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| Accordingly, this modification will not affect the seismic qualification of RTGB's 102 and 106.
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| 8.3 Electrical Separation Criteria
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| " In accordance with IEEE Std. 279-1971, electrical separation criteria has been maintained between the' wiring of the SA, SB and SAB sections of the RTGB. The field cable conductors affected by this EP are being spared in place. Therefore, electrical separation is not adversely affected.
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| 8.4 EDG Loading / Load Sequencing The EDG load 'has not been changed by this EP, however, the sequencing timers for all three pumps should be set for the same time delay in each system (ICW pump IC changed to 9 seconds).
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| 8.5 Emergency Pla.t Operating Procedures Emergency Plant Operating Procedure 1-E0P-99 Appendix V shall be revised to delete the HFA relay reset steps (2.B) and add the ICW and CCW pump control switches to be in the pull-to-lock position in the step placing the RTGB control switches for the HPSI, LPSI, and containment spray pumps in the OFF position (2.F).
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| Off-Normal Operating Procedures, ONOP-1-0310030 and ONOP-1-0640030 will be revised to replace the requirement to " remove the trip and close fuses" with " place the control switch in the pull-to-lock position".
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| 8.6 Fire Protection Capability As indicated in Attachment 4.2 (JPN Form 3F), this modification does not i add any combustible materials, does not affect fire protection systems and '
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| does not affect any fire fighting strategies. Therefore, fire protection capability is not affected.
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| 8.7 Safe / Alternate Shutdown Capability 1
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| As indicated on Attachment 4.2 (JPN Form 3F), this modification provides replacement of control switches and removal of latching relays which control pumps on the Essential Eo" oment List. The replacements perform the same function as the existing c. ..ponents and will not affect the pu s 1
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| : a. 'ity to perform their safety function. Therefore, Safe /Alterr, e Shutdown Capability is not affected.
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| : 9. Desion Verification Statement c
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| The design basis for the modification was reviewed to ensure tha he overall i design concept meets applicable FSAR, Regulatory Guide, and 10 .fR Part 50 requirements. The design of the modification was verified by a review of the functional requirements of the system and by the performance of a circuit
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| , DN Fem 3. Dev 7/03
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| PC/M No 182-193 ;
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| ~ Rev 0 i Page 9 of '9 ..__. i analysis to determine if the proposed modifications perform the functional !
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| and safety requirements described in the FSAR. Integration of this i modification with other designs in progress and impact on existing safety !
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| evaluations was verified by review of the Package Information Tracking System l and the Affected Drawings List Databases, including the Active Safety i Evaluation List. The safety analysis was verified by review of each conclusion statement required to satisfy 10 CFR 50.59 criteria for !
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| establishing whether an unreviewed safety question existed.
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| l
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| : 11. SAFETY
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| : 1. Description and Purpose l This Engineering Package covers modifications to the control circuits of the IA, 18 and IC Component Cooling Water Pumps and the IA, 1B and IC Intake Cooling Water Pumps. Specifically, this PC/M is an alternative to the i I
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| procedural controls to prevent undesirable pump start conditions when l operating the "C" pump as a replacement for either the "A" or the "B" pump l and eliminates the HFA relays which have been troublesome in the past. It will replace the existing control switches with control switches having a l
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| " pull-to-lock" feature and remove their associated HFA latching relays. These '
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| switches will allow pump lockout of automatic starts by their " pull-to-lock" i feature. '
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| : 2. Analysis of Effects on Safety '
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| The design bases for the ICW and CCW systems are described in FSAR Sections i 9.2.1 and 9.2.2. This modification will not affect the bases as described in I the FSAR and will not result in loss of any ' protective function nor adversely l affect the function of any Safety Related or Non Nuclear Safety structure, system or component. The replacement " pull-to-lock" switches will function the same as the original switches for normal pump operation and will have no adverse effect on safety. When a pump is out of service, with the control switch in the " pull-to-lock" position, it will not respond to automatic signals to start. This switch configuration will prevent undesirable starting conditions and will therefore enhance the safety functioning of the system.
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| The removal of the HFA latching relays will enhance the reliability of the pumps.
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| A minor change has been made in the local control station operation which will prevent an unwanted start of 2 3 ump by an SIAS (real or curious). This change will only affect a pump th was unning by way of I control room start, and is stopped by the loca, con: .i station. The original design would close the pump's switchgear breaker, even if it had been stopped at the local control station (intentionally or inadvertently), upon an SIAS start command. This feature could be a personnel safety concern if maintenance was being performed on the pump. However, with the new design, if the local stop command was unexpected, the control room operator would be alerted by the loss of the pump, and various alarms of flows and temperatures. The control room operator could restart the pump by turning its control switch to "Stop" and then " Start". In addition, if the automatic SIAS start feature was JPN Form 3. Rev 7/93
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| . . _ _ . _ . . _ _ _ _ _ Dage 10- OL 19 - _ _ _
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| desired after a local control station stop command, the control room operator l
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| ' would turn the RTGB control switch to "Stop" and then back to " Auto" (the spring return position). The probability of events requiring this action is ;
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| expected to be low. The resetting action by use of the control switch is l similar to those for the Boric Acid Makeup Pumps. '
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| A design integration review has been conducted, and the following sources ;
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| ; have been reviewed:
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| '~
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| - PSL Package Information Tracking' System, as of Oct. 22, 1993.
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| Nuclear Engineering Drawing Index, as of Oct. 22, 1993.
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| - PSL Active Safety Evaluation List, as of Oct. 22, 1993.
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| As a result of this review it has been concluded that PC/M 200-192, 4kV l' Ground Relay Replacement and PC/M 341-192, ICW Lube Water Piping Removal, will have no impact on this PC/M.
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| Based on the review of the St. Lucie Unit 1 Safety Evaluation List, there are no active safety evaluations issued or in progress which have any effect on, 1 or can be affected by this EP. In addition, there are no Justifications for Continued Operation (JCOs) which affect, or are affected by this EP.
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| : 3. Failure Modes and Effects Analysis (FMEA)
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| The FEMA is provided in the FSAR Sections 9.2.1 and 9.2.2 and in Tables 9.2-2 !
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| and 9.2-6. A review of these sections and tables has determined that this modification, which changes the pump control circuits, does not introduce any new potential failure modes to the pumps. The failure modes of the new control switches are the same as the existing ones and since the number of relays are reduced, the overall reliability is improved. Therefore, the conclusion of the existing FEMA is not changed.
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| : 4. Effect on Technical Soecifications The ICW and CCW System requirements are contained in Sections 3/4 7.3 and 3/4 7.4 of the Technical Specifications. A review of the Technical Specifications has determined that this modification does not have an affect on, nor require a change to them.
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| : 5. Unreviewed Safety Question (US0) Determination 1: Does the proposed activity increase the probability of occurrence of an accident previously evalsated in the SAR?
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| This modification does not affect any equipment whose malfunction is postulated in the FSAR to initiate an accident or prevent an accident from occurring. The modifications performed by this Engineering Package enhance ti:e ability of the pumps to perform as intended during emergency and off-normal conditions. Therefore, the probability of occurrence of an accident previously described in the SAR is not increased by this modification.
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| wm r.,- 3 u, no.
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| * i PC/M No 182-193 Rev 0
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| _ . . _ _ . - . - _ - _ _ _ _ _ _ _ . Dage '! of '9
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| : 2. Does the proposed activity increase the consequences of an accident previously evaluated in the SAR?
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| This modification does not affect any structures. systems nor components that function to detect the release of radioactivity or to provide post-accident shielding. This modification does not affect the functional operation of the pumps, however, it does enhance the ability to respond to an SB0 event. Therefore, the consequences of an accident previously
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| - evaluated in the SAR are not increased <
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| by this modification.
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| : 3. Does the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR?
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| The operability of the pumps in this modification is being enhanced by providing operation from the Control Room of functions presently requiring local actions. Since the reliability of the pump control circuit is being improved by this proposed change, it will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR.
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| : 4. Does the proposed activity increase the consequences of a malfunction of i equipment important to safety previously evaluated in the SAR?
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| The operability of these systems is being enhanced by this modification.
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| Since the pumps will continue to perform and satisfy their design basis requirements, the proposed change will not increase the consequences of a 1 malfunction of equipment important to safety previously evaluated in the !
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| SAR. J
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| : 5. Does the proposed activity create the possibility of an accident of a different type than any previously evaluated in the SAR?
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| i This modification does not change the function or design bases of any l structure, system or component important to safety as described in the SAR. Since this modification does not affect any equipment whose malfunction is postulated in the SAR to initiate an accident or prevent an accident from occurring, it will not create the possibility of an accident ;
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| of a different type than any previously evaluated in the SAR. ;
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| : 6. Does the proposed activity create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the SAR?
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| This modification improves the eliability of the system by eliminating several relays, including HFA relays. It also replaces the SBM control switches with SBM switches having a " pull-to-lock" feature which would have the same malfunction characteristics as the original switches.
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| Therefore, the possibility of a malfunction of equipment important to safety which is of a different type than any previously evaluated in the SAR is not created by this modification.
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| ;pN re m 3, cpy 7/93
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| 1 PC/M No 182-193
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| * Rev 0 Pace !? of 19
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| : 7. Does the proposed activity reduce the margin of safety as defined in the basis for any Technical Specification?
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| This moJification does not affect the operational requirements for the cooling systems as defined by the T6chnical Specifications Sections 3/4 7.3 and 3/4 7.4. Therefore, the margin of safety as defined in the bases for any Technical Specification is not reduced by this modification.
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| : 6. Plant Restrictions '
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| This EP can be performed during any mode of operation on one system pump at a time, however, due to the RTGB wiring changes, it is recommended to be implemented during refueling modes 5 or 6.
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| 1 Post modification testing will be required to verify that the control logic '
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| with respect to Safety injection Actuation and LOOP has been properly implemented, and that the sequencing time of the pumps is functioning properly.
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| The following plant procedures may need to be revised pursuant to this modification: Maintenance Procedure No. 1-0910055, " Periodic Test of Automatic Load Sequence Relays", and its data sheets, and Operating Procedure No. 1-0400050, " Periodic Test of the Engineered Safety Features". Note that the EDG sequencing time for the "lC" pumps is to be the same as their "lA &
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| IB" pump counterparts.
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| The following Operating Procedures and Off-Normal Operating Procedures should be revised to include the operation of the " pull-to-lock" switches and delete the requirement to remove the trip and close fuses in the switchgear: OP 0310020, OP 1-0640020, ON0P-1-0310030, and ONOP-1-0640030 (References 5.9, 5.10, 5.11, & 5.12).
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| : 7. Conclusions The foregoing constitutes, per 10CFR50.59 (b), that the modifications to be !
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| performed by this EP do not involve an unreviewed safety question nor a '
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| change to the Plant Technical Specifications. Therefore, prior NRC approval i for the implementation of these modifications is not required.
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| JPN Fem 3, Rev 7/93
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| I PC/M No JSl 193 Rev 0
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| _ - Page _13__cu 4 9-- _.
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| III. CONFIGURATION
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| ; 1. Affected Document Checklist YJJ N_0 Reference FSAR X Attachment 4.6 Technical Specifications X
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| i TEDB < X Attachment 4.4 !
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| Security Plan X DBDs X Attachment 4.7 i i Snubber List X i
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| ; ISI/IST Program Of 'Yes*, ESI review is required) X l Code Stress Reports X i 2. Affected Drawinas
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| , PC/M Dwo # Rev DescriptioVTitle Disc Affected Dwas Rev Pr' EP Rev JPN-182-193-001 0 Before CCWP 1A Sch I 8770-B-326-201 6 y 0 JPN-182-193-002 0 After CCWP 1A Sch I 8770-B-326-201 6 y 0
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| , JPN-182-lM-003 0 Before CCWP 1B Sch I 8770-B-326-205 7 y 0
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| , JPN-182-193 004 0 After CCWP IB Sch I 8770-B-326-205 7 y 0 JPN-182-193-005 0 Before CCWP IC Sch I 8770-B-326-209 7 y 0 4 JPN-182-193-006 0 After CCWP IC Sch I 8770-B-326-209 7 y 0 l JPN-182-193-007 0 Before ICWP 1A Sch I 8770-B-326-832 8 y 0 l
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| ! JPN-182-193-008 0 After ICWP 1A Sch I 8770-B-326-832 8 y 0
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| ; JPN-182-193-009 0 Before ICWP IB Sch I 8770-B-326-833 7 y 0 l JPN-182-193-010 0 After ICWP IB Sch I 8770-B-326-833 7 y 0 JPN-182-193-Oll 0 Before ICWP IC Sch I 8770-B-326-834 7 y 0 ;
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| 4 JPN-182-193-012 0 After ICWP IC Sch I 8770-B-326-834 7 y 0 i JPN-182-193-013 0 Before 3rd Pmp Sch I 8770-B-326-1006 3 y 0
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| : JPN-182-193-014 0 After 3rd Pmp Sch I 8770-B-326-1006 3 y 0 l JPN-182-193-015 0 Before CCWP 1A CWD I 8770-B-327-201 15 y 0 JPN-182-193-016 0 After CCWP 1A CWD I 8770-B-327-201 15 y 0 JPN-182-193-017 0 Before CCWP IB CWD I 8770-B-327-205 17 y 0 JPN-182-193-018 0 After CCWP IB CWD I 8770-B-327-205 17 y 0 i
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| JPN-182-193-019 0 Before CCWP IC CWD I 8770-B-327-209 19 y 0 JPN-182-193-020 0 After CCWP IC CWD I 8770-B-327-209 19 y 0
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| ; JPN-182-193-021 0 Before ICWP 1A CWD I 8770-B-327-832 19 y 0 i JPN-182-193-022 0 After ICWP 1A CWD I 8770-B-327-832 ~9 y 0
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| : JPN-182'-193-023 0 Before ICWP IB CWD I 8770-B-327-833 46 y 0 3
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| JPN-182-193-024 0 After ICWP IB CWD I 8770-B-327-833 16 y 0 JPN-182-193-025 0 Before ICWP IC CWD I 8770-B-327-834 22 y 0 JPN-182-193-026 0 After ICWP IC CWD I 8770-B-327-834 22 y 0
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| , JPN-182-193-027 0 After SWGR 1AB CWD I 8770-B-327-951 9 y 0 I JPN-182-193-028 0 Before 3rd Pmp CWD I 8770-B-327-1006 7 y 0 JPN-182-193-029 0 After 3rd Pmp CWD I 8770-B-327-1006 7 y 0 JPN-182-193-030 0 4kV SWGR Rlys Sch I 8770-B-326-951 3 y 0
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| %s# F--e 1 Dev 7/01
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| * Rev 0 !
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| : 2. Affected Drawinos (continued)
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| PC/M Dwo # Rev Description / Title Disc Affected Dwas Rev Pr* EP Rev JPN-182-193-031 0 Before RTGB 101 I 8770-3324 28 n 0 ,
| |
| JPN-182-193-032 0 After RTGB 101 I 8770-3324 28 n 0 i JPN-182-193-033 0 Before RTGB 106 I 8770-3467 17 n 0 l JPN-182-193-034 0 After RTGB 106 I 8770-3467 17 n 0 JPN-182-193-035 0 RTGB 102 "I 8770-3470 28 n 0 JPN-182-193-036 0 Before RTGB 102 I 8770-3472 21 n 0 JPN-182-193-037 0 After RTGB 102 I 8770-3472 21 n 0 JPN-182-193-038 0 Before RTGB 106 I 8770-4464 . 7 n 0 JPN-182-193-039 0 After RTGB 106 I 8770-4464 7 n 0 JPN-182-193-040 0 RTGB 106 I 87'/0-4467 14 n 0
| |
| .1PN-182-193-041 0 Before RTGB 106 I 8770-4468 22 n 0 JPN-182-193-042 0 After RTGB 106 I 8770-4468 22 n 0 l JPN-182-193-043 0 Before RTGB 106 I 8770-4468 22 n 0 l JPN-182-193-044 0 After RTGB 106 I 8770-4468 22 n 0 JPN-182-193-045 0 Before RTGB 106 I 8770-4469 18 n 0 JPN-182-193-046 0 After RTGB 106 I 8770-4469 18 n 0 JPN-182-193-047 0 RTGB 106 I 8770-4471 12 n 0 JPN-182-193-048 0 Before Cntl & Blk I 8770-B-276-14.2B 3 n 0 i JPN-182-193-049 0 After Cntl & Blk I 8770-B-276-14.28 3 n 0 ,
| |
| JPN-182-193-050 0 Before Cntl & B1k I 8770-B-276-14.2C 3 n 0 JPN-182-193-051 0 After Cnti & Blk I 8770-B-276-14.2C 3 n 0 JPN-182-193-052 0 Before Cntl & Blk I 8770-B-276-14.2D 3 n 0 JPN-182-193-053 0 After Cntl & Blk I 8770-B-276-14.2D 3 n 0 JPN-182-193-054 0 Before Cntl & Blk I 8770-B-276-21.1B 3 n 0 JPN-182-193-055 0 After Cntl & Blk I 8770-B-276-21.1B 3 n 0 JPN-182-193-056 0 Before Cntl & Blk I 8770-B-276-21.1C 3 n 0 JPN-182-193-057 0 After Cnti & Blk I 8770-B-276-21.lc 3 n 0 JPN-182-193-058 0 Before Cntl & Blk I 8770-B-276-21.1D 3 n 0 JPN-182-193-059 0 After Cnti & Blk I 8770-B-276-21.lD 3 n 0
| |
| * Indicate Yes or No if SRD for PSL. Indicate 1 (POD), 2 (CRD), 3 (MD) 4 (ED). er 5 (other) for PTN.
| |
| : 3. Affected Vendor Manuals Plant Doc No Rev Vendor /Eauio Disc Remarks EP P -
| |
| NONE' JPN Form 3, Rev 7/93
| |
| | |
| . i PC/M No 182-193 '
| |
| Rev 0
| |
| _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - _ - - .. -_. ...._ _ ____._Page.. '" " 'C
| |
| : 4. Attachments Paces 4.1 Environmental Qualification Checklist (Form 3E) 1 4.2 Fire Protection Review Checklist (Form 3F) 3 4.3 ALARA Screening (Form 71) 1 4.4 TEDB Change Package '
| |
| 10 4.5 ICW/CCW Pump Control Circuit Evaluation 9 4.6 FSAR Change Package 1 4.7 DBD Change Package 6
| |
| : 5. References 5.1 St. Lucie Unit 1, Final Safety Analysis Report, Amend. 11 5.2 St. Lucie Unit 1, Technical Specifications, Amend.122 5.3 Engineering Evaluation JPN-PSL-SEEP-92-041, Rev. O, Evaluation of "C" Pump Start Combinations for ICW, CCW & Charging Pumps.
| |
| 5.4 Letter JPN-PSLP-92-0597 dated June 9,1992, with Operation Summary table attached 5.5 Request for Engineering Assistance (REA) number SLN-93-079, approved August 27, 1993 5,6 Plant Operating Procedure 1-E0P-99 Appendix V, SB0 Crosstie, Rev. 8.
| |
| 5.7 Maintenance Procedure 1-0910055, Periodic Test of Automatic Load Sequence Relays, Rev. 5 5.8 Operating Procedure 1-0400050, Periodic Test of the Engineered Safety Features, Rev. 32 5.9. Plant Operating Procedure 1-0310020, CCW System, Rev. 37 l 5.10 P1 ant Operating Procedure 1-0640020, ICW System, Rev. 37 l
| |
| 5.11 Plant Off-Normal Operating Procedure 1-0310030, CCW System, Rev. 23 5.12 Plant Off-Normal Operating Procedure 1-0640030, ICW System, h v. 15 5.13 GE Protection and Control Products Catalog GEZ-7723A m r em 3. % nas
| |
| | |
| PC/M No 182-193 Rev 0
| |
| _. . ___. Page. 16 .. o f.. 19 . _ .
| |
| : 5. References (continued) 5.14 Agastat Catalog EMD-1, December 1989 '
| |
| 5.15 GE Selection & Application Guide, GET-61690, December 1989
| |
| , 5.16 Nuclear Logistics Itic. Test Report QR-037003-1, Rcy.1, January 1994 IV. MATERIAL .
| |
| : 1. Eauipment and Material item Ouantity Description Reference Pre-Purchased?
| |
| I 6 General Electric RPA 645003434 Yes Type SBN !
| |
| Control Switches 2 As Wire, switchboard, M&S No. Available in required 1/C #14 AWG 001-28836-9 Stores a
| |
| : 2. Soare Parts
| |
| : Item Ouantity Description Reference Pre-Purchased?
| |
| 1 I General Electric RPA 645003434 Yes Type SBM Control Switch '
| |
| t l
| |
| I
| |
| ,~,___,...,,o, j
| |
| | |
| PC/M No 182-193 Rev 0 Dage. 17 of 19 i
| |
| V. IMPLEMENTATION
| |
| : 1. Implementation Instructions /Soecifications The Implementor's work scope includes, but is not 1imited to or confined to a i
| |
| specific order, the following as detailed on the JPN drawings listed in the Affected Drawings Section: "
| |
| a) Remove and replace the existing SBM control switches CS-201, CS-205, & CS-209 in RTGB 106 with SBN pull-to-lock switches having slip contacts in accordance with appropriate plant procedures and JPN-182-193 drawings as applicable.
| |
| b) Remove and return to stores the existing HFA Latching relays 4/201,4/205,
| |
| & 4/209; Auxiliary relays 4X/201, 4X/205, & 4X/209; and Time Delay relays 3/201, 3/205, & 3/209 from RTGB 106 in accordance with applicable JPN-182-193 l j drawings and plant procedures.
| |
| ~
| |
| c) Re-use the existing conductors between the control switch or relay and the terminal blocks, when possible. New switchboard wire, if required, is to be
| |
| , run in the existing wireways and conduit without overfilling nor mixing safety trains.
| |
| ! d) Utilizing switchboard wire, connect jumpers, relays and control switches to associated terminal strips in RTGB 106 as shown in JPN-182-193 drawings.
| |
| Label the connections in accordance with appropriate plant tagging and i labelling procedures.
| |
| f e) Repeat steps, a) through d) above, for control switches CS-832, CS-833, &
| |
| CS-834 and relays 4/832, 4/833, 4/834, 4X/832, 4X/833, 4X/834, 3/832, 3/833,
| |
| & 3/834 in RTGB 102.
| |
| f) Spare in place the three conductors of the following cables, as shown on the CWD's, by determinating and taping at both ends:
| |
| i 0201B-SA RB, WB, & GB From RTGB 106 To 4kV SWGR 1A3-6 102058-SB RB, WB, & GB From RTGB 106 To 4kV SWGR 183-4 10209B-SAB RB, WB, & OB From RTGB 106 To 4kV SWGR 1AB-2 10832B-SA RB, WB, & GB From RTGB 102 To 4kV SWGR 1A3 '
| |
| ' 10833B-SB RB, WB, & GB From RTGB 102 To 4kV SWGR 1B3 .3 i
| |
| 10834B-SAB RB, GB, & OB From RTGB 102 To 4kV SWGR 1AB-3 g) Adjust time-delay relays 2X/TDPU as necessary to comply with this PC/M, especially ICW pump IC at 9 seconds. -
| |
| 1 JPN Fem 3 Rev U93
| |
| | |
| PC/M No 182-193
| |
| , Rev 0 Dage 18 p f_ 19 _ . _
| |
| : 2. Post-Mod Acceptance Testina Post-modification tests shall be in accordance with approved plant procedures.
| |
| a) Testing shall include verification that operation of the pumps for manual start /stop comands and in response to a LOOP and an SIAS is in accordance with the operational evaluation and summary in Attachment 4.5.
| |
| a b) Testing shall include verification that each pump with its control switch in the " pull-to-lock" position will remain in the tripped condition and not respond to either a LOOP or an SIAS.
| |
| : 3. Operations and Maintenance Guidelines Operations, Training, and Maintenance should be cognizant of the operational evaluation in section 1.5, Design Change Description, and Attachment 4.5. The control circuitry modification to be implemented will require that, during Normal Plant Operation, two pumps will be running with the control switch in the " Auto-after-Start" position and the third pump in "Stop and pull-to-lock" position.
| |
| Under normal operation, two pumps may be in the " Auto-after-Start" position with l'
| |
| the third pump's control switch in the "Stop and pull-to-lock" position, the third pump could be running from the local control station for testing or maintenance purposes. This operation will not affect the proper response to a LOOP, SIAS, or LOOP /SIAS condition. i Under abnormal circumstances, two pumps may be running in the " Auto-after-Start" position with the third pump's control switch in the "Stop and pull-to-lock" ,
| |
| position, if one running pump is then stopped from the local control station it will not respond to a subsequent SIAS (without LOOP) start command, unless the '
| |
| control room switch is turned to "Stop" and then back to " Auto" (its " spring-return-to-Auto" position). Note, it would respond to a LOOP /SIAS start command.
| |
| Therefore, operations / maintenance procedures should insure that, if a local control station is used to stop a pump which was started from the RTGB, the RTGB control switch must be turned to "Stop" and then back to " Auto" (enabling the SIAS function).
| |
| Plant Operating Procedure 1-0310020 (Reference 5.9) Appendix A, Step 2.C and Appendix C, Step 2.F and Plant Operating procedure 1-0640020 (Reference 5.10)
| |
| Appsndix C, Steps 1.K, 2.K, 3.K, & 4.K, should be revised to replace the requirement to " Remove and tag the trip and close fuses" with " Place the control switch in the pull-to-lock position".
| |
| Off-Normal Operating Procedures (References 5.11 and 5.12) should be reviseo as follows:
| |
| JPN form 3, Rev 7/93
| |
| | |
| ~
| |
| PC/M No 182-193
| |
| * Rev 0 Dage_ 19 qf 19 ,
| |
| In 1-0310030, Step 5.3 and in 1-0640030, Step 7.2.1, add a note to turn the control switch to "Stop" and then to " Start" in case the pump was stopped ,
| |
| from the local control station.
| |
| Revise all steps that " remove the trip and close fuses" , by replacing them with " place the control switch in the pull-to-lock position".
| |
| l Plant procedures (References 5.6,5.7,45.8) should be reviewed for any impact '
| |
| made by this modification in addition to those discussed in sections I.8.5 and 11.6.
| |
| l l
| |
| l
| |
| ]
| |
| l JPN Fem 3. Rev 7/93
| |
| | |
| s
| |
| , Attachment 4.1 PC/M No. --
| |
| 182-193
| |
| . - rec 0~
| |
| Page 1 of 1 ENVIRONMENTAL QUALIFICATION (EQ) CHECKLIST s
| |
| : 1. ELECTRICAL EQUIPMENT YES !LO a) Does the PC/M add, modify or replace electrical /I&C equipment
| |
| -- or affect any EQ Doc Pac? If N0 proceed to Section 2. X _
| |
| b) Is the equipment located in a harsh environment per EQ Doc Pac 1000 (PSL) or 1001 (PTN)? If N0 proceed to Section 2. 1 c) Does the equipment perform a safety related function? _
| |
| OR Does the equipment perform a quality related function such that its failure could mislead an operator or adversely affect any safety related function required to mitigate or monitor an accident? _
| |
| OR Is the equipment classified as Category 1 or 2 by RG 1.97? _
| |
| * If the answer to any question in Section 1.c is YES, then the equipment is subject to 10CFR50.49.and the EP must justify that the equipment is Environmentally Qualified.
| |
| : 2. ENVIRONMENTAL CONDITIONS YES NO a) Does the modification add, relocate, raise flow rate of, or increase radiation levels of any piping containing radioactive liquids such that lifetime or accident exposure of electrical equipment may be increased? 1 b) Does the modification add or reroute any high energy piping, the failure of which could impinge upon electrical equipment or increase the post-break local pressure or temperature? 1 c) Does the modification alter process fluid characteristics such that the post accident pressure, temperature, pH, or boron concentration l to which electrical equipment will be exposed may be changed? 1 ,
| |
| d) Does the modification alter any barriers that shield electrical equipment from high energy lines or radiation exposure? 1 e) Does e modification add equipment .ontainment or increase tte post-LOCA makeup water inventory suc. . hat the design basis Containment Flood Level may be increased? 1
| |
| ** If the answer to any question in Section 2 is YES, then it must be' determined if any enuipment subject to 10CFR50.49 could be impacted and, if so, that its Environmental Qualification is still valid. Document the determination in the EP.
| |
| Prepared by/Date A N b 4 dwn Verified by/Date N L ollSihV b
| |
| | |
| Attacterst 4?
| |
| PC/M 40. !$2-193
| |
| , Page ; of 3 FIRE PROTECTION REVIEW CHECKLIST Ic SAFE SHUTDOWN CAPABILITY YES NO REFERENCE Does the Engineering Package install, relocate, modify, or affect the operation of:
| |
| A. Equipment on the Essential' Equip. List X Sec. I.8.7 B. Safe Shutdown Analyses *
| |
| : 1. Safe Shutdown Circuits X Sec. I.8.7
| |
| : 2. A1 ternate Shutdown X Components
| |
| : 3. Associated Circuits X
| |
| : 4. Manual Actions X II. FIRE PROTECTION SYSTEMS Does the Engineering Package install, modify, or affect the operation of:
| |
| A. Fire Detection Systems X B. Fire Water Stmply System X C. Water Suppression Systems X D. Halon Suppression Systems X E. Standpipes or Hose Stations X F. Portable Fire Extinguishers X III. FIRE RATED ASSEMBLIES Does this Engineering Package install, modify or affe.c+ the function of:
| |
| A. Fire Barriers X B. Fire Doors X
| |
| * If "YES" for PTN EPs, a Safe Shutdown Analysis Change Package (SCP) is required. If "YES" for PSL EPs, a drawing change is required.
| |
| | |
| * - Attacrunent 4.0 PC/m he !!2-19) +
| |
| __ _ _ . . -- _ _ . _ _ _ . . _ _ _ _ _ _ . . . . _ . _ _ _ _ _ __.._.,__1e.___. __ ._..
| |
| Page I of 3
| |
| . III. FIRE RATED ASSEMBLIES (Cont) YES !LO REFERENCE C. Fire Dampers X .
| |
| 4 D. Mechanical Penetration Fire Seals X ,
| |
| i E. HVAC Duct Penetration Fire Seals X F. Cable Tray Fire Stops <
| |
| * X G. Structural Steel Fireproofing X
| |
| ; H. Conduit or Raceway Support Fireproofing X l
| |
| I. Conduit or Raceway Fireproofing ____
| |
| X J. Internal Conduit Fireproofing X (Stuffing)
| |
| IV. EMERGENCY LIGHTING X A. Does the Engineering Package install, modify, or affect the operation of? X B. Does the Engineering Package obstruct i the required light pattern of? _ X__
| |
| C. Does the Engineering Package add or relocate essential equipment or components which ~will require the addition or relocation of? X D. Does the Engineering Package install, relocate, modify, affect, or require the use of hand held emergency lights? X E. Does the Engineering Package relocate, modify, affect, or obstruct the light pattern of perimeter security lighting to equipment requiring manual actions? X V. RCP Olu' COLLECTION Does the Engineering Package install, modify, or affect the operation of? X VI. MISCELLANEOUS A. Does the Engineering Package affect the quantity or protection of insitu combustibles (solids, liquids, or gases) beyond the assumptions in the X FHA?
| |
| | |
| i l
| |
| Attactement 4.2
| |
| 'C/M he. :52-;93
| |
| _ . _ _ _ j_ __ ..
| |
| VI. d!SCELLANE005 (Cont)
| |
| : 8. Does the Engineering Package Cause the YES NO REFERENCE i addition of a large combustible inventory within 50 ft. of essential equipment, components, electrical manholes or structures? X l
| |
| Does this Engineering Package modify.or C.
| |
| affect curbs or dikes used to contain combustible liquid spills? X D. Does this Engineering Package cause the removal of a flame retardant material from non IEEE-383 cables? X E. Does this Engineering Package affect fire pi'otection technical specifications or fire fighting X l
| |
| strategies? I F. Does this Engineering Package install, modify or affect the operation of alternate shutdown communications? X G. Does this Engineering Package install, modify, or affect hydrogen lines (or any combustible gas) in areas of the plant containing safe shutdown equipment or components)' X H. Does this Engineering Pa;kage install, 4 modify, or affect any HVAl. equipment or room heat loads in areas of the plant containing Safe Shutdown equipment or components? X PREPARED BY h4 se,.sb DATE n ho 97 VERIFIED BY bd Nh DATE oi/t / W C
| |
| | |
| I
| |
| . . j a
| |
| Attacrearnt 4.3 i PC/M :52-193 i
| |
| {ew i
| |
| . :~
| |
| -ne \
| |
| ALARA SCREENING i
| |
| i
| |
| : 1. Is this PC/M Administrative only, i.e., no plant hardware is changed.
| |
| e !
| |
| yes, Further ALARA screening is not required. !
| |
| X_ no , Continue screening.
| |
| j 2. Does this PC/M involve a location in the Radiation Controlled Area (RCA)?
| |
| ; yes, Location: Continue screening. ;
| |
| X_ no,- Further ALARA screening is not requireti.
| |
| 3
| |
| : 3. Does the implementation of this PC/M involve any of the foilowing?
| |
| : (Circle all "yes" responses)
| |
| J
| |
| : a. Movement of radioactive material.
| |
| : b. Potential for personnel exposure to a radiation field of > 1r/ hour as a result of ;
| |
| ; implementation, operation or maintenance (assuming current area dose rates).
| |
| s
| |
| : c. A total lifetime estimated dose due to the modification (installation, operation,
| |
| ; maintenance, removal) greater than or equal to one (1) man rem.
| |
| : d. Diving operations associated with systems containing radioactive material.
| |
| {.
| |
| I
| |
| : e. Entrance into containment during power operation for mair.Lenance, surveillance,
| |
| ! etc.
| |
| : f. Movement of, or modifications to, existing permanent radiation shielding.
| |
| : g. Modification of systems containing radioactise fluids or resins such that system
| |
| ; integrity is affected.
| |
| For items (a) thru (g):
| |
| yes, This PC/M has the potential to significantly impact personnel radiation 1 exposure. Complete Form 72 to ensure total radiation dose is minimized by l design.
| |
| i no, This PC/M has little or no impact on personnel radiation exposure. Form 72
| |
| )
| |
| not required, however, normal ALARA precepts should be followed to minimize i radiation exposure. !
| |
| -x u n n n & 5 Prepared by Reviewed) by Note: If the preparer and reviewer are the same as for the PC/M, duplicate signatures are not required.
| |
| 4
| |
| | |
| - ~. - -
| |
| i Facility PSL Unit 01 l
| |
| - _ _ . . _ _ ___.. .._ EC/M ct_DCR.No. _ _ 1 2-193 __
| |
| 1 Attachment No. 4.4 Revision No. O Page 1 of 10 TOTAL EOUIPMENT DATA BASE CHANGE PACKAGE COVER SIEET Description of Change: De existing SBM control switches are being replaced by SBM switches with slip contacts (memory) and a pull-to-lock feature for the fdlowing:
| |
| CS-201, CS-205, CS-209, CS-832, CS-833, & CS-834 ne following relays are DELETED:
| |
| 4/201, 4/205, 4/209, 4/832, 4/833, 4/834. 4X/201, 4X/205. 4X/209. 4X/832. 4X/833, 4X/834 3/201, 3/205, 3/209, 3/832, 3/833. & 3/834.
| |
| Basis for Change: PC/M 182-193
| |
| | |
| ==References:==
| |
| REA - SLN 93-079 Enrineerine Prepared by *l56-C Date n./~> v o y i Verified by - Date O \ / 31/Y Approved I Date (Discipline Supv/ Lead Engineer)
| |
| Conticuration ' ,acement Reviewed by: Date:
| |
| Data Entry by: Date:
| |
| Data Entry Verified by: Date:
| |
| for instructions, see 012.81
| |
| .-..c.._e., r, . . . , .n ,
| |
| | |
| l l
| |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM
| |
| ~ ~'
| |
| FA LT5Y'SELUCIE OMIT Or~-~PCTUDCR N6T82TI93~~~~~~ REV. O ~ ~ ~ ~ ~ ~
| |
| l COMPONENT TAG NO. CS-201 ATTACHMENT 4 4 SUPPL. 0 l ASSOCIATE COMPONENT PAGE OF 10 ADD CHC DM- FTn n IETH DAtt 1.ERT ?
| |
| ca m ageNPTAG 70 imane ce ras y)
| |
| , ED COhfPONENT TAG SO
| |
| ""~
| |
| En REV 3 #
| |
| EO DOC pat' -
| |
| ?
| |
| i SYSTB4 CODE 3 erumme 1 M PT AGR }
| |
| ENG F TERFNCE to N 1 5'M NOTT 4 SPEER I?
| |
| l RC 1.97 fvtN1 I l 30 en ATED t SCEW ^
| |
| X RO t.97 CATEGORY t N C'm Am NO. 4 EO REMARKS ??
| |
| RG 1.97 TYPE 1 r0MPONENT TYPE ?
| |
| COMP St*B-TYPE 4 E&pTTY CitANMRI. 4 C' NET Df3CRIPT10N 65 IDrN CODF/DF.Sc A9 STARTUP SYS CODF 4 MA%i'FArTURER ?o X MODel ?S 1658MD4DooT1FI Pt ALTERN ATE MTR ?o ALTTRN ATE MODEL ?4 DPAW1NG NO 'sHT a n '6 DR AW1NG NO /5HT sn e DRA%1NO NO /SHT to'A DRA%1NG NO /SHT to'A DR$w3No No<sHT inw TTCH MANT' At NO 10 TTrH MA%1' At NO In X ENG v0TT3 $n Pull-To-f a k m tne ENo NnTts <n FOMMFNT% To 7TDB INPt'T rnNTRnt.-
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields.
| |
| | |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM i .
| |
| . -, _. . ..EACILIILST LUCIE __ _ UNIT 01 _ PCM DCR NO. 182-103 _ . _ .REV - 0 _ _ _ _
| |
| COMPONENT TAG NO. CS-205 ATTACHMENT 44 SUPPL. O ASSOCIATE COMPONENT PAGE 1 OF to i Arm caec nr1 FTuf n ffTW NTA 19ft? ?
| |
| ;.y C(RSOMEPT TAG ?O
| |
| ^ N'C . Erwi ?0 EO COMPOVDff 7AO 90 ID REY. 1 w-~ g EO DOC PAC 3 SY3TD4 CODE 1 w 1 SAFETY LTAM 3 4
| |
| ENG RDDLENCE 16 S. GROT? 3 5/M NOTE 1 5 PEER f?
| |
| RC 1 M WIN) t FD11tsf ATyn t SCEW 6 X RC iMi*ATBO(RY 1 N 6
| |
| * am NO. 4
| |
| , EO RFMARKS ?9 10 1 M TYPE 1 COMPONEVT TYPE
| |
| * COMP 5t'B-TYPE 4 EAJ77Y CHANnG1 4 FUNN DFSCRIPT10N A5 IDCN CODF/DF3C A%
| |
| STARTUP SYS CODE 4 MAWFAC1TRER ?O Y MODll ?4 I ASPMDdDrWTIFI Pt ALTERN ATF MFR ?0 ALTTRN ATE MODEL ?5 DP_A%TNG NO 'sHT ' 30 %
| |
| I to/A DRA41NG NO ISHT DRA%1NG NO /SHT to 6 DRA%7NG NO /SHT 10/6 DRA%1NG NO /$HT intA TTCH MANT AL NO to TECH MAVf' AL NO to N ENG NOTT3 to 1%n-To-12% k m sne ENG. NOTT3 50 cOMMFNT4 77 TTDft TNPt'T CONTpnt; OP.!GINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A". (Design) fields.
| |
| | |
| _~. . .- . - - - _ _ . ._. _ _ . _ _ . - .
| |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM
| |
| - -- JACILITY ST, LUCIE ._ . __ _12i1T__. QL _ __ P_CMIDCR NO. t 92-103 . _ REY . O COMPONENT TAG NO. CS-209 ATTACHMENT 44 SUPPL 0 ASSOCIATE COMPONENT PAGE t OF 10 ADD CHC fWT . WWTn ifTIE DATA LNET ?
| |
| EXIMpONEfff TAC 70
| |
| - TC_ MT 20 EO COMPONENT TAG M ED REV. 3 a w ,
| |
| ED DOC PAC $
| |
| SYSTEM CODE 3 l enramuwe t SAFEIY CTAN 3 ENG REFERENCE 16 0-CBot1P 1 StM NOTE 1 5 PEER t?
| |
| RC 1M (YIN) 1 toasTA1Tn 1 SCEW 6 X EG IM cATElc(mY t N i em aese 343; 4 EO REMARK 5 ??
| |
| 10 tM TYPE 1 COMPnNENT TYPE ?
| |
| COMP SUB-1YPE 4 EAFPfY PMA% M 4 FUNCT DEscRWT10N 65 tDcN CODF/DEsc A5 STARTUP SYS CODF 4 MANUF4r fiepyp ?g Y MODEL ?$ I A$PMD4DneTI Ff Pt d
| |
| APIT7N ATE MR ?0 Al. TERN ATE MODF1 ?$
| |
| DRA%1NG NO 'sNT. ?O'A DRA%1NG NO #5HT inta DRA%1NG NO /SHT 10'A DRA41NG NO /5HT 10'A DRA%1NG NO >$HT 90'6 TTCH MANU At. Nn to TECH MANUAL NO to Y ENG NOTTS 50 Pell-T+iM m tnn rNo Nnm sn COMMENTS TO TTDB INPt'T cnVTTOt. _
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields.
| |
| | |
| l TOTAL EQUIPMENT DATA BASE CHANGE FOILM
| |
| _ . . _ _ _ _ _ __ FACH.1TY ST. LUrfF - _ UNIT 01 _PCM.DCRED. 152-103 rey n l
| |
| COMPONENT TAG NO. CS-832 ATTACHMENT 4.4 SUPPL 0 l ASSOCIATE COMPONENT _ PAGE 5 OF 10 l ADD cac Dsi twin 11:TB DATA t.94T ?
| |
| C(RNONENY TAG 70
| |
| - 2:Z_T 70 i l
| |
| EO COMPONENT TAG M I Eo mEv 3
| |
| ' I w ,
| |
| ED Doc PAC 5 SYSTIM CODE 3 I r~ 3 d
| |
| SAFETY CLAN 3 ENO REFUtENCE 16
| |
| . 04"ROUP 3 5/M NOTT 4
| |
| $Pf7R 1?
| |
| RC 1M fYtN) 1 FD metATFD 1 SCEW 6 Y aC1MCA N Y I N l 0 im am W1 4 i EO REMARK 3 79 )
| |
| RC 1M TYPE i COMPONENT TYPE ? ,
| |
| l FOMP SUP-TYPE 4 1ASTW eWA*8@f. 4 FUNCT DE5cRWT10N 65 IDcN CODF/Df30 at STARTUP $YS CODE 4 MANUF AFT 1'PFR ?0 V MODEl. . ?S 1 A$PMD4DooTf FI PI ALTTRNATE MHt ?0 ALTERN ATE MODEL ??
| |
| DRA%1NG NO r5HT 10'6 DR A%1NG NO /5HT 10,6 DRA%1NG NO /SHT 10'6 DRA%1NG NO /sHT 10/6 NR A%1NG NO /SP tora TECH MANT' AL NO in TECH M ANT' At NO to Y ENG NOTES (n Ni.To !2xt m tre.
| |
| ENo sOTr.s sn COMMENTS To TTDR TNPt'T t'ONTRot c ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields.
| |
| | |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM
| |
| . _. IACll.IIY_sT. t_UrfF XNIT 01 PCM/DCR NO.1S2103 REY. 0-COMPONENT TAG NO. Q-833 . ATTACHMENT 4.4 SUPPL 0 I ASSOCIATE COMPONENT PAGE 6 OF 10 (DD ent: DST 91si n tfTH DATA UNtf ? j e ~ J. - T *fAC M
| |
| - Vrr T to EO COMPONEfT TAG M ED REV. 3 e ,
| |
| ED DOC PAC $
| |
| SYSTEM CODr 3 wemmme 1 SAFETY CIAN 9 ENO RDIRFNCE 16
| |
| : 0. CROUP 1 5/VNOW 4 l
| |
| 3 PEDI 1? l mc1.w tven i EDMFTATFh 1 SCEW 6 1
| |
| X RC 1.M CATBG(RY t N I l
| |
| GR AMET NOl A EO REMARKS 78 RD 1.M TYPE 1 COMPONENT TYPE ?
| |
| COMP St'TL1YPE 4 MASPTT enANNFI. 4 RWM DEscRIPT10N 69 1DrN CODF/DEsc 65 START 1*P 9Y5 CODF 4 MA.NTF Ar11'PIR ?o X MODE 1. ?5 1 ASPMD4 Dn0Tt FI Pt ALTERN ATE MTR 20 ALTERN ATE MODEL ?$
| |
| DPA%1NG NO 'SMT 30'6 DRA%1NO NO /SHT 10'6 DRA%1NO NO /SHT 10<6 DRA%1NG NO /SHT in,6 DRA%1%O NO '5HT to/A TFCH MAN 1' AL NO in TFCH MANTAL Nn tn V FNO NOTT.5 to Poli-To-l.wk m trm ENo Nons <n COMMF%T5 TO WDft INN T CONTROL.
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields.
| |
| | |
| l l
| |
| TOTAL EQUIPMENT DATA CASE CHANGE FORM l
| |
| _ .. . _ . FACII_Tr.Y ST. LUCIE _ UNIT 01 _PCM'DCR NO. 182 101 REY. O I COMPONENT TAG NO. CS-834 ATTACHMENT 44 SUPPL. O ASSOCIATE COMPONENT PAGE '
| |
| OF 10 M)D CHO fW1. FRET B ff7W DATA LMIT ?
| |
| CC %- - T TAC M
| |
| , - ,_ g z y EO COMPONENTTAG ?0 ED REY. 3 EO DOC PAC 5 3YSTEM " ODE 3 tyveunt' t BAFETY N 9 ENO RDIRENCE 16 O UROt1P 1 SfM NO17
| |
| * SPEI3t t?
| |
| KC 1M tY!>h 1 30msTATyn 1
| |
| $CEW 6 Y SC iM CATI!CORY 1 N OJR Aw NO.' 4 EO REMARKS ?t 101M TYPF t COMPONENT TYPE ?
| |
| COMP st%-TYPE 4 1AFFTY CHLNNFf. 4 Ft.'NN DESCRIM10N 69 IDCN CODF1DFSC 69 STARTUP SYS CODF 4 MA NTF ACT!*FER ?0 Y MODEL ?5 169B AfD4D00 TIM PI Af TERNATE MFR ?0 ALTEPS ATE MODEL ?$
| |
| DRA%iNG NO r$HT 10'6 DRA%1NG NO /SMT 40/6 DRA%1NG NO /SHT 10/6 Draw 1NG NO 'SHT 10>A DRA%1NG NO 'SHT 10<6 TTCH MANT AL NO In TTCH MANTAL NO in Y ENn NOTE 5 to Pull-To.t eck m tne ENG N OTT_3 50 COMVFNTS TO TTDP TNPt'T PO'JTDOI -
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A"_(Design) fields.
| |
| | |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM 1 FACILITY ST. lucre UNIT 01 Pht/D_CUO. 192-103 _RE V . 0 . _ _ _ .
| |
| COMPONE!G TAG NO. .Sre List Below ATTACHMENT 44 SUPPL 0 ASSOCIATE COMPONENT PAGE S OF 10
| |
| = \
| |
| AIID c1IC IMI FWrT B IETE DATA !
| |
| l tBET ?
| |
| I X 20 r -- _ _ _ m TAC 4/701. 4/705. 4r?00. 4/937. 4'111. 4/tu y
| |
| EO COMPONDrf TAG ?O IK) REY. 1
| |
| . EO DOC PAC 9 SYSTat CODE 3 me 1 SAFETY CIAN 1 ENG RDI3tENCE 16 (Mantir 1 1
| |
| 1/M NO17 3 !
| |
| 3 PEER 1?
| |
| RC1M W!m 1 ROMsTATyn 1 SCEW 6
| |
| , RC 1M CANY t On nw No, 4 1
| |
| ! EO PIMARKS ?8 '
| |
| Rd IMTYPE 1 COM10NENT TYPE ?
| |
| COMP St'B1YPE 4 ,
| |
| . RAFF"Y PWaldNWT. 4
| |
| )
| |
| FUNN DESCRIPTION e5 (AFN CODF/DESC At STARfJP SYS CODE 4 MA NTF AcTYPFP ?O MODEL ?S l
| |
| AL1TRN ATE MF1t ?0 ALTERN ATE MODEL ?S I'RA%1NG NO /SMT 30'6 DRA%1NO NO /$HT M/6 DRA41NG NO /$HT 10'6 DRA%1NO NO /5HT M16 DRA%1NO NO 'SHT M -*
| |
| 1TCH MANTAL NO 16 TECH MANTAL NO to rNG NOns sa enc _ NOTrs so COAN TO TEDP INPt *T cONTRotc ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields. .
| |
| | |
| i 1
| |
| 1 l
| |
| TOTAL EQUIPMENT DATA BASE CHANGE FORM
| |
| . ._ FACILITY ST. LUrfF . ._ UNIT 01 _ PCM/DCR SO. 182-103 REY 0 COMPONENT TAG NO. See List Below ATTACHMENT 4.4 SUPPL. O ASSOCIATE COMPONENT PAGE 9 OF 10 Ano casc nsT. Fun n ifTW DATA INWT ?
| |
| X e --- . i TAC ?O 4Xf?01. 4X/?05. 4Xf'09. 4Xr:17. 4Xis 3 3 4 x 't u
| |
| , y HD COMPONDff TAG 20 E REV 3 m-- ,
| |
| EO DOC PAC $
| |
| SYSTD4 CODE 3 uneuw- 3 i SAFEIY CLAM 1 ENO REM]tENCE 16 4
| |
| (b42ROUP 3 5/M NOTT 3
| |
| )
| |
| 1 S Pf"ER 1? ,.
| |
| I RG 1M fY3te 1 m .n .- ,
| |
| SCEW 6 RC 1.fPCAT M Y t o a aame ND 4 EO REMARKS ?9 101 M TYPE 1 COMPOWENT TYPE ? !
| |
| COMP SffB-TYPE 4 EASTTy PEEA4egl 4 FUNCT DESCR! MON 65 IDCN CODE /DF3C 65 STARTt'P SYS CODE 4 MANTF A N'PER ?O MODEL ?9 ALTERN ATE VFR ?0 ALTERN ATT MODFL ?$
| |
| DRAW 1NG NO 'sHT 10'6 DRA%1NG NO /sHT 10/6 DR.A%1NO NO /5HT 30/6 DRA%1NG NO /5HT 30/6 DR.A%1NG NO iSHT 3 036 TTCH MAN 1' At NO 10 TECH MANT AL NO to ENO NOTT3 %n ENO NOES to COVVFNTS TO TTDB fNN'T rONTRot.
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A";(Design) fields.
| |
| | |
| TOTAL EQUIPMENT DATA CASE CHANGE K)RM
| |
| .-- _ -__.. J.CH ITY ST. LUCIE . UNIT 01 _. PCMIDCILNO. Ic2-to3 _ REY 0__.___
| |
| COMPONENT TAG NO. See List Below ATTACHMENT 44 SUPPL. O ASSOCIATE COMPONENT PAGE 10 OF to ADD CHC Dn. FT51 D IfTH DATA j 1
| |
| UNtf ?
| |
| X e _. _ = TAG 20 1 % t.3 @ 3.3 @ e 3r:1L 1/133. Situ EO COMPOWENT TAG 20 EO REY. 3
| |
| =~ ,
| |
| EO DOC PAC 5 SYS1TM CODE 3 errmac 3 BAFEfY CLAN 3 ENG RDERENCE 16 CMllROUP 1 SIM NOTE i SPEDt t?
| |
| RG 1 M fYtPO 1 30 ast.aTTB 1 SCEW e BC 1.M CATEMRY 1 04AME NO. 4 EO REMARKS ?9 101.97 TYPE I COMPONENT TYPE ? j COMP StP-TYPF 4 RAllTTT P8tAMNF1. 4 Ft'NCT DFSCRIPT10N 65 IDcN CODE /DESC A9 STARTUP SYS CODE 4
| |
| \tA'J1'F Ar"fTPER ?n MODEL ?9 ALTERN ATE MFR ?0 ALTERN ATT MODEL ?9 PPA %7NG NO 'SHT W6 BRA %7NG NO /SHT to;A DRA%1NG NO 15HT 10/4 DRA%1NG NO /SMT tosA DRA%1NG NO /SHT 10' A TECH \tANTAL NO In TECH MANT AL NO 10 rNO NnTts <n ENO NnTES 50
| |
| , COM\fFNTS TO TTDR INPti PONTTrnt.
| |
| ORIGINATED BY INPUT BY APPROVED BY VERIFIED BY VERIFIED BY Shaded fields are "A" (Design) fields.
| |
| | |
| i . .
| |
| l o ,
| |
| ' t
| |
| ~
| |
| Attathment 4.5 {
| |
| PC/M 182-19]l Rev. Os Page I of 9I ST 1.UCIE UNIT I ICW/CCW PUMP CONTROL CIRCUIT OPERATION
| |
| | |
| ==SUMMARY==
| |
| | |
| AFTER LATCillNG RELAYS REPLACED BY PULL TO LOCK SBM SWITCIIES ,
| |
| ICW CCW I. Initial Condition (Bus I AB Aligned to IB) I A START IB START IC STOP 1 A START IB START IC STOP 1.OOP start (9 sec) start (9 sec) no start start (6sec) start (6 sec) no start 1.OCA w/Of fsite Power continue running continue running no start continue running continue running no dtart I.OOP/1 OCA ,
| |
| start (9 sec) start (9 sec) no start start (6 sec) start (6 sec) no art II. Initial Condition (Hus I AB Aligned to IB) I A START IB STOP IC START I A START IB STOP IC S-(ART IOOP start (9 sec) no stant start (9 sec) start (6 sec) no start start (p sec) 1.OCA w/Offsite Power continue running no start continue running continue running no start continue'aunning 1.OOP/LOCA start (9 sec) no start start (9 sec) start (6 sec) no start start (f>sec)
| |
| III. Initial Condition (Hus I AB Aligned to I A) I A START IB START IC STOP I A START IB START IC S*I OP 1.OOP start (9 see) start (9 sec) no start start (6 sec) start (6 sec) no n, tart i OCA w/Offsite Power cimtinue running continue running no start continue running continue running no start i OOP/1.OCA start (9 sec) start (9 sec) no start start (6 sec) start (6 sec) no 5 tart IV. Initial Condition (hu.s I AB Aligned to I A) I A STOP IB START IC START 1 A STOP IB START IC START l .OOP no stait start (9 sec) start (9 sec) no start start (6 sec) start (6 wc) 1.OCA w/Of fsite Power no start continue running continue running no start continue running continue running 1.OOP/LOCA no start start (9 sec) start (9 sec) no start start (6 set-) start (p sec) i
| |
| _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ J
| |
| | |
| I i
| |
| St. IUCIE UNii 1 At tachmerit 4.5 -
| |
| LVAtuATION Of INE PERf 0R9tANCE OF INE CIRWITRY ASSOCIATED WiiN INE ICW AND CEM STSILM PC/M 1H2 193 !
| |
| AFTER IAICNING RtlATS REPLACED SY PULL 10 LOCK Sept SWITCNES Rev. 0 Page 2 lef 9 OPERAll0N/
| |
| CONDIllON ICW PP 1A ICW PP 1C ICW PP IB REMARKS ,
| |
| t BREAKER IS RACKED-IN AND CONTROL BREAKER 15 RACKED-IN AND CONTROL PLANT PROCEDURE OP i ;
| |
| BREAKER AND FUSES POSlll0N P 'kER IS RACKED-IN AND CONTROL ~
| |
| DLCING NORMAL OPERATION. ARE IN PLACE. FUSES ARE IN PL ACE. CONTROL FUSES ARE IN PLACE. 0640020 DOES NOT DEFINE SWITCH CS 834 IS IN THE PULL TMls CONDITION.
| |
| LOCK POSlil0N EXCEPT WHEN THE PUMP IS BEING USED.
| |
| l 4.16 KV I'0WER SUPPLY POWER IS SUPPLIED FROM BUS 1A. POWER CAN BE SUPPLIED FROM EliMER POWER IS S0PPLIED FROM BUS 15. PLANT PROCEDURE OP TRAIN 1A OR TRAIN 18 DEPE W ING 0640020 IN0lCATES iMAI.
| |
| ON THE ALIGNMENT OF THE BUS 1AB. ICWPP1CisNORMALLYl NORMALLY AllGNED TO TRAIN 18. ALIGNED TO NEADER t, ,
| |
| WNICN IS INE DESIGNATE )
| |
| APPENDIX R TRAIN.
| |
| I MAQlAL STARI FROM THE (CWD SH 832) CS-832 CONTACT 1 (CW SH 834) CS-834 CONTACT 1 (CWD SH 833) CS 833 CONTACT 1 PSAR SECil0N 9.2.1.2' CC7TG0t ROOM OR LOCALLY. CLOSES TO CLOSE BREAKER, SPRING CLOSES TO CLOSE BREAKER, SPRING CLOSES TO CLOSE BREAKER, SPRING IslCAIES TNAI "lN THE RETURNS TO OPEN WiiH CONIACT 4, RETURNS TO OPEN, AND CLOSES RETURNS TO OPEN WiiH CONTACT 4, EVENT THAT ElINER PUMP: 1 A AND CLOSES CONTACTS 215. CLOSE CONTACTS 2 1 5. CLOSE COMMAND AND CLOSES CONTACT 2 & 5. CLUSE OR18 FAILS,ICWPP1Cl COMMAND REMAINS THROUGH CS-832 REMAINS THROUGH CS-834 CONTACT 2 COMMAND REMAINS IHROUGH CS-833 MAY SE ALIGNED WiiN !
| |
| CONTACT 2. PUMP CONTINUES 10 RUN. AND THE PROPER BUS ALIGNMENT CONTACT 2. PUMP CONilNUES 70 RUN. EliHER HEADER A OR S OT LOCAL CONTROL CLOSES 8REAKER PERMISSIVES PUMP CONTINUES TO LOCAL CONTROL CLOSES OREAKER POSITIONING Of INE PL84>
| |
| SIRECTLY AND HAS NO RETAINED RUN. LOCAL CONTROL CLOSES DIRECILY AND HAS NO RETAINED DISCNARGE NEADER CROSS' LLOSE COMMAND. BREAKER DIRECTLY. THE START Ct0SE COMMAND. CONNECT VALVE. TME val vE i SIGNAL SYPASSES THE PEPMISSIVE ALIGNMENT REOUIRED 10 THAT VERIFIES AtlGNMENT OF THE CONNECT ICW PP IC 10 BUS 1AB, THE ONLY PERMISSIVE IS NEADER 8 IS SPECIFIED ,1N POWER AVAILABLE ON BUS 1AS. OP-1 0640020. 1 I
| |
| MANUAL STOP FROM THE (CWD SH 832) CS-832 CONIACT 3 (CWD SH 834) CS-834 CONTACT 3 (CWD SH 833) CS-833 CONIACT 3 IECHNICAL SPEClflCAll00tS [
| |
| CONICDL ROOM, 10CALLY OR CLOSES TO TRIP BREAKER AND CLOSES 10 TRIP BREAKER AND CLOSES 10 TRIP BREAKER AND REculRE 2 ICW PUMPS Id BE CONTACIS 2 & 5 OPEN, SPRING CONTACIS 2 & 5 OPEN, SPRING CONTACIS 2 1 5 OPEN, SPRING OPERABLEDURINGMODES(1, DUE TO OVERCURRENT TRIP.
| |
| RLTURNS CONTACTS 2, 3 & 4 OPEN ltETURNS CONTACTS 213 OPEN AND RETURNS CONTACis 2, 3 1 4 OPEN 2, 3 AND 4. I AND CONIACT $ CLOSED. CONIACT 5 CONT ACT 5 CLOSED. CONT ACT 5 AND CONIACT 5 CLOSED. CONIACT 5 l CLOSED ENABLES SIAS START. CS- CLOSED ENABLES SIAS SIART. CS- CLOSED ENA8tES SIAS SIART. CS- l 832 PULL-TO-t0CK TRIPS BREAKER 834 PULL-10 LOCK TRIPS GREAKER BY 833 PULL-10-LOLK TRIPS BREAKER }
| |
| AND ENABLES 1C PUMP PERMISSIVE 8V CONTACT 3 CLOSURE AND THEN AND ENA5tES 1C PUMP PERMISSIVE BY CONTACT 3 & 4 CLOSURE AND THEN INHISITS AUTOMATIC STARTS BY CONTACT 3 1 4 CLOSURE AND INEN INHIBITS AUTOMATIC STARTS 8T OPENING CS 834 CONTACTS 1, 2, 3 INHistiS AUTOMATIC STARIS BY OPENING CS-832 CONIACTS 1, 2, 3, & 5. LOCAL CONTROL IS NORMAL IN OPENING CS-833 CONIACTS 1, 2, 3,
| |
| & 5. LOCAL CONTROL IS NORMAL IN THis MODE. LOCAL STOP OR & 5. LOCAL CONTROL 15 NORMAL IN THIS MODE. LOCAL STOP OR OVERCURRENT TRIP WILL TRIP INIS MODE. LOCAL STOP OR OVERCURRENT IRIP WILL TRIP 3REAKER. ANil-PUMP CIRCUIT, WiiN OVERCURRENT TRIP WILL TRIP BREAKER. ANil-PUMP CIRCUIT, WITH A RETAINED CLOSE CopetAIS, WILL BREAKER. ANil-PUMP circuli, WITN -
| |
| A RETAINED CLOSE COMMAND, WILL PREVENT AUTOMAi!C SKR CLOSURE A RETAINED CLOSE CapetAND, WILL PREVENT ALF0MATIC SKR CLOSURE AFTER AN DVERLOAD TRIP OR LOCAL PREVENT AUTOMAllC SKR CLOSURE AFTER AN OVERLOAD TRIP OR LOCAL STOP. AFTER AN OVERLOAD TRIP OR LOCAL ,
| |
| STOP. STOP. 9 F : \USE RS \Wt DW ARD S\WP \E VAL - NE W.01 f
| |
| | |
| i . .
| |
| I t i ,
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| i '
| |
| St. LUCIE IMIT 1 Attachment' 4.5 LVAIUAll0N OF INE PERf 0RMANCE OF INE CIR(IlliRT ASSOCIATED WITN INE ICW AaB CQf SYSTEM PC/M 182-193 AflER LAICNING RELATS REPLACED BY Pult 10 Lom San SWIICNES Rev. l 0 Page 3 gf 9 0FERAll0N/ . ,
| |
| CONDlil0N ICW PP 1A ICW PP 1C ICW PP 18 REMARKS i i
| |
| i PUMP OPERAll0N TOLLOWING A (CWD SH 832) STRIPPING RELAY 27X- (CW SH 834) ASSlMPil0N 15 THAT (CbD SH 833) STRIPPING RELAT 27X-LOOP. INiilAL CONDITIONS: 7/1A3 TRIPS THE SREAKER AND THE LASI COMMAND TO ICW PP 1C WAS 10/183 TRIPS iME BREAKER AND ICW PPS 1A AND IB RLMNING REMOVES CONTROL POWER TO THE MANUAL STOP AND IN THE PULL-To- REMOVES CONTROL POWER 10 INE AND 1C IN STOP AND PULL- CLOSING circuli UNill BUS 143 IS LOCK POSlil0N. CS 834 CONTACTS CLOSING circuli UNill SUS 193 15 T3-l0CK POSITION. BUS 1AB RE-ENERGlZED BY EDG 1A. CS-832 1, 2, 3, 8 5 AND THE 1A & 15 PUMP RE-ENERGlZED BY EDG 18. CS-833 l ALIGNED TO BUS 18. CONTACT 2 IS CLOSED AND CONTACT 4 INTERLOCK CONIACTS (4TA1 & 4YO17 CONTACT 215 CLOSED AND CONTACT 4 i (1C PLMP INTERLOCK) IS OPEN ARE OPEN INNISITING ALL AUTOMAftC (1C PUMP INTERLOCK) IS OPEN 1 (ASSUMING A PREVIOUS START ST ARTS FROM THE CONTROL ROCM. (ASSUMING A PREVIOUS START COMMAND). UPON POWER RETURN, iHE PUMP REMAINS STOPPED. COMMANO). UPON POWER RETURN, l
| |
| t 27X-7/1A3 RE-ENERGlZES THE 27X-10/183 RE-EMERGlZES IME 1 circuli AND ENABLES TIMER 2X/TDPU circuli AND ENASLES flMER 2X/iOPU ,
| |
| (IWO CONTACTS OF RELAY 3V-7/DG1A (IWO CONTACTS OF RELAY 3T-10/DC15 !
| |
| ARE USED, ONE TO ENERGlZE THE ARE USED, ONE TO ENERGIZE THE {
| |
| TIMER AND ONE 10 BLOCK THE ilMER AND ONE TO stock THE l Cl0SURE OF THE BREAKER tMTIL THE CLOSURE OF INE DREAKER UNTIL INE !
| |
| TIMER CONTACT CLOSES). 9 SEC flMER CONTACT CLOSES). 9 SEC ;
| |
| L ATER CONTACI 2X/TDC CLOSES AND I LATER CONIACT 2M/fDC CLOSES AND THE BREAKER CLOSES. THE BREAKER THE BREAKER CLOSES. THE BREAKER CLOSING COMMAND IS RETAlWED CLOSING COMMAND 15 RETAINED THROUGH CS-832 CONTACT 2. THROUGH CS-833 CONTACT 2.
| |
| PtNP OPERAll0N #0tt0 WING A fruD SH 832) IF SAFETY INJECilC% (CWD SH 834) ASSUMPil0N IS THAT (CWD SH 833) IF SAFEIY INJECil0N SI WIT 31 0FF-Slit POWER . A) TAKES PLACE white ICW PP THE LASI COMMAND TO ICW PP 1C WAS (SIAS 8) TAKES PLACE WHILE ICW PP AVAllABLE. INITIAL 4 WEAKER IS CLOSED, IT WILL NOT MANUAL STOP AND IN THE PULL IB BREAKER IS CLOSED, li WILL CONDlil0NS: ICW PPS 1A AND COMMAND THE BREAKER TO CLOSE, toCK POSill0N. CS-834 CONTACTS NOT COMMAND THE GREAKER 10 CLOSE, l 18 RUN3tNG AND 19 IN STOP SINCE THE CLOSE COMMAND ALREADY 1, 2, 3, & 5 ARE OPEN INM18tilNG SINCE THE CLOSE COMMAND ALREADY l AD Putt - TO-100K POSI TION. EXISTS THROUGH CS-832 CONTACT 2. ALL AUTOMAftc STARTS FROM THE EXISTS THROUGH CS-833 CONTACT 2. I C'JS ILB At IGNED 10 BUS 1B. PUMP CONTINUES 10 RUN. CONTROL ROOM. UPON RECEIPT OF THE PUMP CONilNUES 10 RtM.
| |
| SI AS "A" OR "B" THE CLOSING l
| |
| CIRCulf WILL BE INHIBITED Bf CS- l 834 CONTACT 5 WHICH WILL BE OPEN. I THE PtMP REMAINS STOPPED.
| |
| 8 i
| |
| i t
| |
| I t
| |
| F t \tfSF RWA TCADOMuM( val -M M 01
| |
| | |
| l t
| |
| St. IUCIE UNIT 1 Attachment,4 5 -
| |
| EVAtuAll0N OF THE PERf 0FMANCC OF IME CIR(11tTRY ASSOCI ATED WiiN THE ICW Ale CCW SYSTEM PC/M 182 193 AFIER LAICHlWG REL AVS REPLACCD BY PULL 10 LOCK SBM SWITCHES Rev. l 0 Page 4 of 9 OITRATION/ .
| |
| CONDITION ICW PP 1A ICW PP IC ICV PP 18 REMARKS PUMP OPERATION f0LLOWING A (CWD SH 832) STRIPPING RELAT 27X- (CSD SH 834) ASSUMPil0N IS THAT (CW SH 833) STRIPPING RELAT 27X- '
| |
| LOOP WITH LOCA (SIAS). 7/1A3 TRIPS THE BREAKER Ako THE L AST COMMAND 10 ICW PP 1C WAS 10/183 IRIPS THE BREAKER AND INITIAL Ct*DITIONS: ICW REMOVES CONTROL POWER TO THE MANUAL STOP AND IM THE PULL-TO- REMOVES CONTROL POWER 10 THE PPS 1A AND 18 RUNNING AND CLOSING CIRCUIT Udill BUS 1A3 IS LOCK Postil0N., CS-834 CONTACTS CLOSING CIRCUti UNill BUS 183 IS 1C 10 STOP AND Putt-IO- RE-ENERGl2ED BY EDG 1 A. CS-832 1, 2, 3, & 5 AND THE 1A & 1B PtMP RE-ENERGIZED BY EDG 18. CS-833 LOCK POSillON. BUS 1AB CONTACT 2 15 CLOSED AND CONTACT 4 INTERLOCK CONTACIS (4TA1 & 4Y51) CONTACT 2 15 CLOSED AND CONTACT 4 ,
| |
| ALIGNED 10 BUS 18. (1C PUMP INTERLOCK) IS OPEN ARE OPEN INHl81 TING ALL AUTOMATIC (1C PUMP INTERLOCK) IS OPEN j (ASSUMING A PREVIOUS START STARTS FROM THE CONTROL ROOM. (ASSUMING A PREV 10LFS START .
| |
| COMMAND). UPON POWER RETURN, l COMMAND). UPON POWFR RETURN, UPON RECEIPT OF SISA "A" OR "B" 27x-10/193 RE-ENERGilES THE l 27k-7/1A3 RE-ENERGlZES THE THE CLOSING CIRCUlf WILL BE INHIBITED BY CS-834 CONTACT 5 circuli AND ENABLES flMER 2X/iDPU f CIRCuti AND ENABLES IIMER 2K/iDPU, IHROUGH THE NORMALLY WHICH WILL BE OPEN.iHE PUMP THROUGH THE NORMALLY OPEN CONIACT OPEN CONIACT OF 3Y-7/DG1A (CLOSES REMAINS STOPPED. OF 3Y-10/EDG18 (CLOSES UPON EDG UPON EDG BREAKER CLOSURE), CS-832 BREAKER CLOSURE), CS-833 CONTACT CONTACT 2 OR CS-832 CONTACT 5 AND 2 OR CS-833 CONTACT 5 AND SIAS. ,
| |
| i SIAS. 9 SEC LATER CONTACT 2X/TDC 9 SEC LATER CONTACT 2X/TDC CLOSES AND THE BREAKER CLOSES. THE !
| |
| CLOSES AND THE BREAKER CLOSES.
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| THE BRE AKER CLOSING COMMAND IS BREARER CLOSING COMMAND IS RETAINED THRduGH CS-832 CONIACT RETAINED THROUGH CS-833 CONIACI
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| : 2. 2.
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| PUMP OFE.All0N fotLOWING A D SH 832) STRIPPING REtAY 27X- (CWD SH B34) ASSUMPil0N IS THAT (CWD SH 833) ASSUMPIION IS OfAi LOO. INIllAL CONDITIONS: i A3 TRIPS IME BREAKER AND THE LAST COMMAND TO ICW PP 1C WAS THE LAST COMMAND 10 THE ICW PP 1B ICW PPS 1A AND 1C RUNNING REMOVES CONTROL POWER TO THE MANUAL STARI. UPON LOSS OF POWER WAS TO SIOP AND IN THE Putt AND 18 lN STOP AND Putt- CLOSING CIRCull UNTIL BUS 1 A3 IS STRIPPING REtAY 27x-3/1AB LOCK POSITION. CS 833 CONTACi$
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| TO-t0CK POSITION. BUS 1AB RE-ENERGl2ED BY EDG 14. CS-832 COMMANDS THE BREAKER TO TRIP AND 1, 2, 3, & 5 ARE OPEN INHI8ITING ,
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| I AllGNED 10 BUS 18. CONIACT 2 IS CLOSED AND CONTACT 4 REMOVES THE P0utR 10 THE CLOSING ALL AUTOMAllC STARTS FROM THE (1C FUMP INTERLOCK) IS OPEN CIRCULI. CS-834 CONTACT 2 IS CONTROL ROOM AND CONIACT 4 IS !
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| (ASSUMING A PREVIOUS START CLOSED. UPON REIURN Of POWER TO CLOSED ENASLING 1C PUMP l
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| .OMMAND). UPON POWER RETURN, BUS 1AB, 27x-3/1A8 RE-ENERGIZES PERMISSIVE 4f81/1006 CONIACT. l.
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| 27x-7/1 A3 RE-ENERG12ED THE THE circuli. SINCE BUS 1AB IS THE PUMP REMAINS STOPPED.
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| CIRCult AND ENABLES IIMER 2x/IDPU AtlGNED AND POWEREO FROM BUS 18, ,
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| (TWO CONT ACTS OF REL AY 3Y-7/DGI A THE PERMISSIVE FOR ALIGNMENT ARE USED, ONE 10 ENERG12E THE WB1, 52/MOC 1 AB-183 AND 3TB2 ilMER AND ONE 10 BLOCK THE 1 AB-183) WILL BE CLOSED, WITH ALL CLOSURE Of THE BREAKER UNTIL IHE THE PERMISSIVE SAilSFIED TIMER IIMER CONTACT CLOSES. 9 SEC 2X/IDou ENERGI2ES. 9 SEC LATER LATER CONIACI 2X/iDC CLOSES AND CONIACT 2X/iDC CLOSES AND THE l INE BREAKER CLOSES. THE BRE AKER BREAKER CLOSES. THE BREAKER l
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| CLOSING COMMAND IS RETAINED CLOSING COMMAND is RETAINED THROUGH CS-832 CONTACT 2. THROUGH CS 834 CONIACT 2. ,
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| F :\uSFRSWIItARDS\WP\t val -Nf u.01
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| f i . s 0,
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| 4 ST. LUCIE UNii 1 Attad ment:4.5 EVALUATION of INE PERT 0RnANCE OF TisE CIRQlliRY ASSOCIATED Wlin THE ICW Am CQf SYSitu PC/M 182,-193 AfiER LATCNING RELAYS REPLACED ST PULL 10 LOCK Sal SWITCHES Rev. ' O Page 5 o'i 9 OPERATION / '
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| CONDIll0N ICW PP 1A ICW PP IC ICW PP 18 Rest 4RKS PteeP OPE R All0N FOt TOWING A (CWD SH 832) IF SAFETY INJECilON (CW SH 834) AS$leePfl0N IS INAT (CW SH 833) ASSUe91504 IS TNAT St WIT 2 0FF-SITE POWER (SI AS A) TAKES PLACE WrG E ICW PP INE LAST COMMAND TO ICW PP 1C WAS THE LASI CCNOt4ND TO INE ICW PP 18 LVAILABLE. INiilAL 1 A SREAKER IS CLOSED, n e' WILL NOT MAseUAL START. RECEIPT rF SIAS WAS 10 STOP Am IN iME PULL-TO-CONDITIONS: ICW PPS 14 COMMAND THE BREAKER TO CLOSE, "A" OR "B" Witt is0T FitECT iteE LOCK POSITION. CS-833 CONTACTS AND 1C RUNNING AND 18 IN SINCE THE CLOSE COMMAND ALREADY RUstellNG PUMP SINCE TFJ circuli 1, 2, 3, a 5 ARE OPEN INNitlTING STOP AND PULL-10-toCK EkiSTS THROUGH CS-832 CONTACT 2. ALREADT HAS A CLOSE E19tAND ALL AUTOMATIC SIARIS FROM THE I POSlil0N. BUS 1AB ALIGNED PUMP CONTINUES TO RUN. THROUGM CS-834 CONTACf 2. THE CONTROL ROCWI AND CONTACT 4 15 13 CUS 18. PUMP CONTINUES TO Rust.
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| f CLOSED ENASLING IC PUMP 1 PERMISSIVE 4YB1/1006 CONTACT.
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| UPON RECEIPT OF SIAS S BREAKER CLOSING CIRCUlf 15 INMIOllED ST CS-833 CONTACT 5 AND THE PUMP WILL REMAIN STOPPED.
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| PUMP OPERAll0N FOLLOWING A (CWD SH 832) STRIPFING RELAY 27X- (CW SH 834) ASSUMPil0N IS THAT (CWD SH 833) ASSUMPil00s IS TMAT LOOP WITH 10CA (SIAS). T/1A3 TRIPS THE BREAKER AND THE LAST COMMAND 10 ICW PP 1C WA5 iME LAST CthetAseD TO INE ICW PP 18 INiilAL CONDlil0NS: ICW REMOVES CONTROL POWER TO THE MAseUAL START. UP0el LOSS OF POWER WAS TO STOP AND IN THE PULL-TO-PPS 1A AND IC RUNNING AND CLOSING CIRCUlf UNill BUS 1A3 IS STRIPPING RELAT 27X-3/1A8 LOCK POSlil0ef. CS 833 CONTACTS 18 12 STOP AND PULL-TO- RE-ENERG12ED BY EDG 1A. 05-832 COMMANDS THE BREAKER TO TRIP AND 1, 2, 3, t 5 ARE OPEN INNISITING LOCK POSlil0N. BUS 1A8 CONIACT 2 15 CLOSED A W CONIACT 4 REMOVES THE POWER TO IME CLOSING ALLAUTOMAtlCSTARTSfROMis(
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| AllGNED 10 BUS 16. t PUMP INTERLOCK) IS OPEN circuli. CS 834 COIITACT 2 IS CONTROL ROOM A m CONTACT 4 IS g (A nUMING A PREVIOUS START CLOSED. UPON RETURN OF POWER TO CLOSED ENASLING 1C PtFP COMMAND). UP0el POWER RETURN, BUS 1AB, 2TX-3/1AS RE-EeIERGIZES PERMISSIVE 4Y81/1006 CoseTACT.
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| 27x-7/1A3 RE-ENERGl2ES THE THE circuli. SINCE BUS TAS IS UPON RECEIPT OF SIAS 4 BREAKER circuli AND ENABLES TIMER ALIGNED AND POWERED FROM BUS 18, CLOSING circuli 15 INNIBifED ST a /IDPU, THROUGH THE NORMALLY THE PERMISSIVE FOR ALIGNMENT CS 833 CoseTACT 5 AND iME PUMP OPEN CONTACT OF 3Y-7/DG1A (CLOSES (4YB1, 52/MOC 1AB-183 AND 3f82 WILL REMAlel STOPPED.
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| UPON EDG BREAKER CLOSURE), CS 832 1AS-183) WILL SE CLOSED, AteD CON SCT 2 OR CS-832 CONTACT 5 AND TIMER 2M/IDPU WILL BE STARTED ;
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| Sie. 9 SEC 1ATER C00sTACT 2x/TDC IHROUGH CS-834 C00sTACT 2 OR CS- ,
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| CLOSES AND THE BREAKER CLOSES. 834 CONTACT 5 AND SIAS. 9 SEC THE BREAKER CLOSING COMMAND IS LATER CONTACT 2X/IDC CLOSES AND 8 RETAINED IHROUGH CS-832 CONIACT THE OREAKER CLOSES. THE CLOSE !
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| : 2. COMMAND IS RETAINED THROUGH CS- i 834 CONTACI 2. {
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| f roertracurmsentsiervar -mu n1
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| . s il i St. IUCIE BZli i A t t attunenn 4.5 .
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| IVAIUAllON OF INE PtRIORMANCE OF INC CIRC 1IllRY ASSOCI ATED WITN INC ICW AIS CCW STSIEN PC/M 1BJ 193 AFIER l AICNING REL ATS REPt ACED Of PULL 10 LOCK SWE SWilCIES Rev. O Page 6 of 9 OPERATION /
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| CONOIIION -
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| CCW PP 1A CCW PP 1C CCW PP IB REMARKS BRET.KER AND FUSES POSITION BREAKER IS RACKEO-IN AND CONTROL BREAKER 15 RActED-IN AND CONTROL BREAKER IS RACKED-IN AND CONTROL PLANT PROCEDURE OP Dt21NG NORMAL OPERAtl0N FUSES ARE IN PLACE. FUSES ARE IN PLACE. CONTROL FUSES ARE IN PLACE. 0310020 DOES NOT DEFINE SWITCH CS-209 IS IN THE PULL-TO- Tills CONOITION. !
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| I LOCK POSII!ON EXCEPT WHEN THE PUMP IS BEING USED. i 1
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| 4.16 KV POWER SUPPLY POWER IS SUPPLIED FROM BUS lt. POWER CAN 8E SUPPLIED FROM POWER IS SUPPLIED FROM BUS 18. PLANT PROCEDURE OP EliMER TRAIN 1A OR TRAIN 18, 0310020 INDICATES iMAI LW DEPENDING ON THE ALIGNMENT OF PP IC 15 NORMALLY ALIGW D THE BUS 1AB. NORMALLY ALIGNED TO NEADER 5 WHICH 15 THE 10 TRAIN 18. DESIGNATED APPENDIM R TRAIN.
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| MANUAL STARI FROM THE (CWD SN 201) CS-201 CONTACT 1 (CWD SH 209) C5-209 CONTACT 1 (CWD SN 205) CS 205 CONTACT 1 ESAR SECit0N 9.2.2.2 CONTL'Ot ROOM, OR LOCALL Y. CLOSES 10 CLOSE 8REAKER, SPRING CLOSES TO CLOSE BREAKER, SPRING CLOSES TO CLOSE 3REAKER, SPRING IlmlCATES TNAT "CCW PP {1C REIURNS TO OPEN WiiN CONTACT 4, RETURNS TO OPEN, AND CLOSES RETURNS TO OPEN WITH CONTACT 4, MAT BE ALIGNED WifN EITHER AND CLOSES CONTACIS 2 & 5. CLOSC CONTACTS 2 8 5. CLOSE COPO4AND 15 AND CtOSES CONTACTS 2 & 5. CLOSE HEADER A OR Ba. THE witVE COMMAND IS RETAINED THROUGH CS- RETAINED THROUGH CS-209 CONIACT COMMAND IS RETAINED THROUGN CS- ALIGNMENT REGUIRED 10 !
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| 201 CONIACT 2. PUMP CONTINUES TO 2 AND THE PROPER SUS ALIGNMENT 205 CONIACT 2. PUMP CONilNUES 10 CONNECT CCW PP 1C 10 l RUN. LOCAL CONTROL CLOSES PERMISSIVES. PUMP CONilNUES TO RUN. LOCAL CONTROL CLOSES NEADER 5 IS SPECIFIED IN BREAKER DIRECTLY AND HAS NO RUN. LOCAL CONTROL CLOSES BREAKER DIRECILY AND NAS N0% OP-1 0110020.
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| RETAINED CLOSE COMMAND. BREAKER DIRECILY. INE START RETAINED CLOSE C0pW4AND.
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| SIGNAL BYPASSES THE PERMISSIVE THAT VERIFIES ALIGNMENT OF THE BUS 1AB, THE ONLY PERMISSIVE IS POWER AVAILABLE ON BUS 1AS.
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| MANUAL STOP FROM INE (CWD SH 201) CS-201 CONTACT 3 (CWD SN 209) CS 209 CONIACT 3 (CWD SN 205) CS-205 CONTACT 3 CONTROL ROOM,10CALLY OR TECHNICALSPECIFICAll0h5 CLOSES 10 TRIP BREAKER AND CLOSES TO TRIP BREAKER AND CLOSES 10 TRIP OREAKER AND REQUIRE 2 CCW PUMPS to jBE DUE TO OVERCURRENT TRIP. CONTACTS 2 & 5 OPEN, SPRING CONTACIS 2 & 5 OPEN, SPRING CONTAti$ 2 8 5 OPEN, SPRING OPERAttE DURING MODES 1.
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| RETURNS CONTAtis 2, 3 & 4 OPEN RETURNS CONTACIS 2 & 3 OPEN AND RETURNS CONTACTS 2, 3 & 4 OPEN 2, 3 AND 4.
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| AND CONIACT 5 CLOSED. CONTACT 5 CONTACT 5 CLOSED. CONTACT 5 AND CONIACT 5 CLCSED. CONIACT 5 CLOSED ENABLES SIAS STARI. CS- CLOSED ENABLES SIAS START. CS CLOSED ENASLES SIAS SI ARI. CS-201 PULL-TO-LOCK TRIPS BRE AKER 209 PULL-TO LOCK TRIPS BREAKER 205 PULL-TO-LOCK TRIPS BREAKER AND ENABLES 1C PUMP PERMISSIVE BY BY CONTACT 3 CLOSURE AND INEN AND ENAetES 1C PUMP PERMIS$1VE SY CONTACT 3 & 4 CLOSURE AND THEN INHlBliS AUTOMATIC STARTS 57 CONIACT 3 & 4 CLOSURE AND iMEN INHIBliS AUiOMATIC STARTS BY OPENING CS 209 CONTACTS 1, 2, 3 INHIBITS Aul0MATIC STARis BY OPENING CS 201 CONIACTS 1, 2, 3, & 5. LOCAL CONTROL IS NORMAL IN OPENING CS 205 CONIACTS 1, 2, 3 &
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| E 5. toCAL CONTROL IS NORMAL IN VHl$ MODE. LOCAL STOP OR 5. toCAL CONTROL IS NORMAt IN THIS MODE. LOCAL STOP OR OVERCURRENT TRIP WILL TRIP THl5 MODE. LOCAL SIOP OR OVERCURRENI TRIP WILL TRIP BRE AKER. ANil-PUMP CIRC 11II, WITN OVERCURRENI 1 RIP WILL IRIP BREAKER. ANTI-Pt74P CIRCulf, WiiH A RETAINED CtOSE CapetAND, WILL OREAKER. ANil-PUMP CIRCulf,WilN A A RETAINED CLOSE COMPLAND, WILL PREVENT AuiOMAllC BKR CLOSURE RETAINED CLOSE COMMAND, WILL PREVENT AUTOMATIC BKR CLOSURE AFTER AN OVERLOAD TRIP OR LOCAL PREVENT AUTONAllC OKR CLOSURE AFTER AN OVERLOAD TRIP OR LOCAL STOP. AFTER AN OVERLOAD TRIP OR LOCAL ,
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| STOP. STOP.
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| ]
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| I F : \USE RS\WEDW ARDS\WP \E V AL - NE W. 01
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| St. LUCIE twili 1 Attachment 4.5 EVAtuAll0N OF INE PERIORMANCE OF INE CIROJITRY ASSOCI ATED WITN INE ICW Als CCW SYSIER PC/M 152-193 Af fER L AICHING RELAYS REPLACED BY PULI TO LOCK SWE SWitCIIES Rev. l 0 Page 7 af 9 OPERAll0N/ -
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| CONDlil0N CCW PP 1A CCW PP IC CCW PP 15 REMARets t PtmP OPERAIION F0tt0 WING A (CWD SH 201 STRIPPING RELAY 2Tx- (Ene SH 209) ASSUMPil0N l$ THAT (CW SM 205) STRIPPING RELAY 2TM-LOOP. INiilAL CONDlil0NS: 6/1A3 TRIPS THE BREAKER ANO THE lAST COMMAND TO CCW PP 1C 4/183 TRIPS ileE BREAKER AND CCW PPS 1A AND 1B RUNNING REMOVES CONTROL POWER TO THE WAS MANUAL STOP AND IN PULL-To- REMOVES CONTROL POWER TO TIIE AND 1C IN STOP AND PULL- CLOSING CIRCUIT UNill SUS 173 IS LOCK POSITION. CS-209 CONTACTS CLOSING CIRCult UNTIL OUS 183 IS T3-LOCK Postil0N. BUS 1AB RE-ENERGIZED BY EDG 14. CS-201 1, 2, 3, & 5 AND INE 1A & 18 RE-ENERGIZED BY EDG 15. CS-205 ALIGNED 10 BU$ 18. CONTACT 2 IS CLOSED AND CONTACT PUMP INTERLOCK CONillCTS (4TA3 & CONTACT 2 IS CLOSED AND CONTACT 4 4(IC PtmP INTEttoCK) IS OPEN 4T83) ARE OPEN INMittilNG ALL (1C PUMP INTERLOCK) IS OPEN (ASSUMING A PREVIOUS STARI AUTOMAllC STARIS FROM iME (ASSUMING A PREVIOUS START COMMAND). UPON POWER RETURN, CONTROL ROOM. PUMP REMAINS COPWIAND). UPON POWER RETURN, 2TM 6/1A3 RE-ENERGlZES THE STOPPED. 2TX-4/103 RE-ENERGl2ES THE i CIRCUlf AND ENABLES TIMER 2x/IDPU CIRCUlf AND ENASLES TIMER 2X/IDPU ;
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| (TWO CONTACTS OF RELAY 3Y-6/DG1A (iWO CONTACTS OF RELAY 3f-4/0G1s !
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| ARE USED, ONE 10 ENERGlZE THE ARE USED, ONE TO ENERGlZE THE i TIMER AND ONE TO BLOCK THE TIMER AND ONE TO stock THE l CLOSURE OF THE OREAKER UNTIL THE CLOSURE OF TWE BREAKER UNTIL INE i IIMER CONTACT CLOSES). 6 SEC flMER CONTACT CLOSES). 6 SEC l LATER CONTACT 2x/TDC CLOSES AND LATER CONTACT 2M/IDC CLOSES AND t THE BREAKER CLOSES. THE BREAKER THE BREAKER CLOSES. THE BREAKER CLOSING COMMAND IS RETAlkED CLOSING CapetAND 15 RETAINED THROUGH CS-201 CONIACT 2. THR31GM CS 205 CONTACT 2. ,
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| a i i
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| PUMP OPERAil0N F0tt0 WING A (CWD SH 201) IF SAFETY INJECTION (CWD SH 209) ASSUMPilON IS THAT (CWD SH 205) IF SAFETY INJEttiall SI WiiH OFF-SITE POWER (SIAS A) TAKES PLACE white CCW PP THE LAST COMMAND TO CCW PP 12C (SIAS 8) TAKES PLACE WHILE CCW PP AVAILABLE. INIllAL 1A BREAKER IS CLOSED, II Witt NOT WAS MANUAL STOP AleD IN Pt%L-TO- 15 BRE AKER 15 CLOSED, If WILL NOT U MMAND THE mREAKER 10 CLOSE, LOCK POSIfl0N. CS 209 CONTACTS COMMAND THE BREAKER TO CLOSE, CONDITIONS: CCW PPS 1A
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| $4NCE THE CLOSE COMMAND ALREADY 1, 2, 3, t 5 ARE OPEN INMlBlilNG SINCE THE CLOSE COMMAND ALREADY j l AND 1B RUNNING AND 1C IN STOP AND Putt-TO LOCK EXISTS THROUGH CS-201 CONTACT 2. Att AUTOMATIC STARIS FROM THE ENISTS THROUGH CS-205 CONTACT 2.
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| POSlil0N. BUS 1AB ALIGNED PUMP CONilNUES TO RUN. CONIROL ROOM. UPoll RECElPT OF PUMP CONilNUES TO RUN. t TO 00S 18. SIAS "A" OR "B" THE CLOSING CIRCulf WILL BE INMI8ITED BY CS-209 CONTACT 5 WHICH WILL OE OPEN. THE PUMP REMAINS STOPPED.
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| F :WSE RS\Wf f WARDS %F\(val - Ni W.01
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| __ . _ , . .- .m - ~.__ - _ m . .. . _m. _ _ . _ _ _ _ . _. . . _ . . . _ .
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| f li !
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| St. IUCIE talli 1 AttachmenY, 4.5 EVAtuA110N Of INE PERIORMAllCE Of INE CIRCulIRY ASSOCIATED WITN IIIC ICW AIS CCW SYSIEN PC/M 182 193 AfiER ILAICHIIIG Rit AYS REPL ACED 87 PULL 10 LOCK SSM SWIICHES Rev. ' O Page - 8 s s 9 (N t R AI l(m/ ,
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| f CONDlil0N CCW PP 1A CCW PP IC CCW PP 18 REMARKS l I i PUMP OPERAllON 10tt0 WING A (CW SH 201) STRIPPING REL AY 2TM- (CWD SH 209) ASSUMPil0N IS IMAI (CW SH 205) STRIPPING REL AY 2TM- '
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| LOOP WITH t0CA (SIAS). 6/1A3 IRIPS INE BREAKER AND THE LASY COMMAND TO CCW PP 1C 4/183 TRIPS THE BREAKER AND I' 1%ITIAL Ct*DITIONS: CCW REMOVES CONTROL POWER TO THE WAS MANUAL STOP AND IN iME PULL- REMOVES ColliROL POWER To THE PPS 1A AND 18 RUNNING AND CLOSING circuli UNill BUS 1A3 IS TO-10CK POSITION. CS-209 CLOSIwG CIRCUlf UNilt SUS 183 IS 1C I:0 STOP AND P011 RE-ENERGl2ED BY EDG 1 A. 05-201 CONTACTS 1, 2, 3, & 5 AND THE 1A RE-ENERGIZED Bf EDG 18. CS-205 LOCK POSil10N. BUS 1AB CONIACT 2 IS CLOSED AND CONTACI 4 & 18 PUMP INTERLOCK CONTACTS CONTACT 2 IS CLOSED AND COIITACT 4 ALIGNED 10 BUS 18. (1C PUMP INTERLOCK) 15 OPEN (4fA3 & 4T83) ARE OPEN (1C PUMP INTERLOCK) 15 OPEN j (ASSUMING A PREVIOUS START IPNIBITING ALL AUTOMAllC STARIS (ASSUMING A PREVIOUS START . ,
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| COMMAND). UPON POWER RETURN, FROM THE CONTROL ROOM. UPON COMMAND). UPoll POWER REfuRN, l !
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| 2TX 6/1A3 RE-ENERGl2ES THE RECEIPT OF SIAS "A" OR "O" THE 2TM-4/183 RE-ENERGl2ES THE I CIRCulf AND ENABLES TIMER CloslWG circuli WILL BE CIRCUlf AND ENASLES IIMER l i 2X/IDFU, THROUGH THE NORMALLY INHIBITED SY CS-209 CONTACT 5 2x/TDPU, inROUGH THE NORMALLY OPEN CONI ACT OF 3Y-6/DG1 A (CtOSES WHICH WILL BE OPEN. THE PUMP OPEN CONIACT OF 3Y-4/DG 18 UFON EDG BREAKER CLOSURE), CS- REMAINS STOPPED. (CLOSES UPON EDG SREAKER 201 CONTACT 2 OR CS-201 CoutACI 5 CLOSURE), CS-205 CONTACT 2 OR CS-AND SIAS. 6 SEC LATER CONTACT 205 CONTACT f AsID SIAS. 6 SEC 2X/IDC CLOSES AND THE BREAKER L ATER CONTACT 2K/IDC CLOSES AND Cl0SES. THE BREAKER CLOSING INE SREAKER CLOSES. THE SREAKER COMMAND IS RETAINED IHROUGH CS- CLOSING COMMAND IS RETAINED 201 CONIACI 2. THROUGH CS-205 CONIACT 2. i n .
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| PUMP OPER Al!ON F0t TOWING A (CLU SH 201) STRIFPING REL AY 2TX- (CWD SH 209) ASSUMPil0N ls IHAT (CW SH 205) ASSUMPil0N IS THAT LOOP. INiilAL CONDli!ONS: ' 6/1A3 TRIPS THE BREAKER AND THE L ASI COMMAND TO CCW PP 1C .IHE LAsi COMMAND TO THE CCW PP 18 CCW PPS 1A AND 1C RUNNING REMOVES CONIROL POWER TO THE WAS MANUAL START. UPON LOSS OF WAS TO STOP AND IN THE PULL '
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| AND 1B lN LIOP AND PUL L- Cl0 SING circuli UNill BUS 1A3 IS POWER, STRIPPING RELAY 2TM-2/1A8 LOCK POSlil0N. CS-205 CONIACTS TO-LOCK POSillON. BUS 1AB RE-ENERGIZED BY EDG 1A. CS-201 COMMANDS THE 8REAKER 10 TRIP AND 1, 2, 3, & 5 ARE OPEN INHistilNG ALIGNED 10 BUS 18. CONTACT 2 IS CLOSED AND CONTACI & REMOVES THE POWER TO THE CLO$ LNG Att AUTOMAllC STARIS FROM THE !
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| .IC PUMP INTERLOCK) IS OPEN CIRCulf. CS-209 CONIACT 2 IS CONTROL ROOM AND CONTACT 4 15 l (ASSUMING A PREVIOUS START CL OSED. UPON RETURN OF POWCR TO CLOSED ENASLING IC PUMP
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| * COMMAND). UPON POWER RETURN,' BUS 1A8, 2TX-2/1A8 RE-ENERG12ES PERMISSIVE 4183/1006 CONiaci. l 2TX-6/1 A3 RE-ENERGl2ES THE THE circuli. SINCE BUS 1AB IS PUMP REMAINS STOPPED. i CIREUlf AND ENABLES TIMER 2x/IDPU Allt.NED AND POWERED FROM BUS 18, l (IWO CONiACTS OF REL AY 3Y 6/DG1A THE PERMISSIVE FOR ALIGNMENT
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| * ARE USED, ONE TO ENERGl2E THE (4YB3, 52/MOC 1AB-283 AND 3YB1 TIMER AND ONE 10 BLOCK THE 2A8-183) WILL BE CLOSED, WITH C1050RE OF THE BREAKER UNill IHE ALL IHE PERMIS$1VES SAilSFIED t ilMER CONTACT CLOSES). 6 SEC TIMER 2X/IDPU ENERGl2ED. 6 SEC
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| * i LATER CONIACT 2x/tDC CLOSES AND LATER CONIACT 2X/TDC CLOSES AND .
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| THE BREAKER CtOSES. THE BREAKER THE BREAKER CLOSES. THE BREAKER )
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| CLOSING COMMAND IS RETAINED CLOSING COMMAND 15 RETAINED ;
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| THROUGH CS-201 CONIACT 2. THROUGH CS 209 CONTACI 2. ;
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| t F :\USF R Swi t MARDS WIMIVAt NIu.01
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| SI. LUCIE talli 1 A t t adserit' 4.5 l EVAIHAVION Of INE PERf 0RMAleCL Of IME CIR(11IIRY ASSOCI ATED WIIN INE ICW AliD CCW SYSTE90 PC/M 182-193 l AFTER I ATCNING REl ATS REPLACED BY PULL 10 LOCK SOM SWITCHES Rev. ! O Page 9 df 9 I
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| ortRATION/ .
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| CONDRIION CCW PP 1A CCW PP 1C CCW PP 1B REftARKS PUMP OPER4fl04 FOLLOWING A (CWD SH 201) If SAFETY INJEtil04 (CWD SH 209) ASSUMPil0N IS THAT (C @ SH 205) ASSUMPil0N IS THAT SI WIi2 Off-SITE POWER (SIAS A) TAKES PLACE WHILE CCW PP THE tAST COMMAND TO CCW PP 1C THE LAST CupW44ND TO INE CCW PP 15 i AVAILABLE. INiilAL 1A BREAKER IS CLOSED, li WILL NOT WAS MANUAL START. RECEIPT Of WAS TO STOP AND IN PULL-TO-LOCK CONDlil0NS: CCW PPS 1A COMMAND THE BREAKER 10 CLOSE, SI AS "A" OR "B" WILL IIOT EFFECT POSlil0N. CS-205 CONIACTS 1, 2 AleD IC RUNNING AND 1B IN SINCE THE CLOSE COMMAND A M ?9Y INE RUIINING PUMP SINCE THE CLOSE 3, & 5 ARE Of EN INMlBlilleG Att STOP AND Putt-ID t0CK EXISIS IMROUGH CS-201 CON 18 2. COMMAND ALREADY EXISTS THROUGN AUTOMAllC STARTS FROM THE CONTROL Postil0N. BUS 1AB ALIGNED THE PUMP CONTINUES 10 RUN. CS-209 CONTACT 2. INE PUMP RonM AND CONTACT 4 IS CLOSED .
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| TJ CUS 18. CONilNUES TO RUN. ENAOLING 1C PUMP PERMISSIVE 4Y83/1006 CONTACT. UPON RECEIPT OF SIAS O, BREAKER CLOSING circuli IS IllNIBITED BY CS-205 CONTACT 5 A810 TME PUMP WILL REMAIN STOPPED.
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| PUMP OPER All0N f 0t t0 WING A (CWD SH 201) STRIPPING RELAY 2TX- (CWD SM 209) ASSUMPil0N IS THAT (c m SH 205) ASSUMPil0N IS TMAT LOOP WITH (OCA (SIAS). 6/1A3 TRIPS INE BREAKER AND THE LAST COMMAND 10 CCW PP 1C THE LAST COMMAND 10 THE CCW PP 18 INiilAL Ct*Dli10NS: CCW REMOVES CONTROL POWER TO THE WAS MANUAL START. UPON LDSS OF WAS TO STOP AIID IN PULL-10-LOCK PPS 14 AND 1C RUNNING AND ClostNG CIRCULI UNill BUS 1A3 IS POWER STRIPPING RELAY 2TX-2/iA8 POSlitost. CS-205 CONTACTS 1, 2, 18 113 STOP AND Putt-TO- RE-ENERGlZED BY EDG 1A. CS-201 COMMANDS THE BREAKER TO TalP AND 3, t 5 ARE OPEN INMI8ITING ALL LOCK POSill0N. BUS 1AB CONTACT 2 IS CLOSED AND CONTACT 4 REMOVES THE POWER TO INE CLOSING AUT9MATICSTARTSFROMTHEC0giROL ALIGNED 10 BtlS IB. (1C PtMP INTER 10CK) IS OPEN circuli. CS-209 CONTACT 2 IS ROOM AND CONTACT 4 IS CLOSED CLOSED. UPON RETURN OF POWER 10 ENABLING 1C PUMP PERMIS$1VE !
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| (ASSUMING A FREVIOUS START COMMAND). 13PON POWER RETURN, BUS 1AB, 2TX-2/1At RE-ENERGIZES 4YB3/1006 CONTACT. UPoes RECEIPT 27X-6/1 A3 RE-ENERGlZES THE THE CIRCUII. SINCE BUS 1A8 IS OF SIAS 8, SREAKER CLOSING CIR~JIT AND ENABLES TIMER At it,NED AND POWERED FROM BUS IB, CIRCUIT l$ INHIBliED BY CS-205 2x/IDPU, THROUGH THE NORMALLY THE PERMISSIVE FOR AllG8sMENT CONIACI 5 AND iPE PUMP WILL OPEN CONIACT OF 3Y-6/DGIA (CLOSES (41B3, 52/MOC 1As-183 AND 3YB1 REMAIN STOPPED.
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| UPON EDG BRE AKER CLOSURE), CS-201 1AB-183) WILL BE SATISFIED, CONTACT 2 OR CS-201 CONTACT 5 AND IIMER 2X/IDPU WILL BE STARTED 3 SIAS. 6 SEC L ATER CONTACT 2X/IDC THROUGH CS-209 CONTACT 2 OR CS- l CLOSES AND THE BREAKER CLOSES. 209 CONTACT 5 AND SIAS. 6 SEC THE BREAKER CLOSING COMMAND IS LAftR CONIACT 2X/iDC CLOSES AND I RETAINED THROUGH CS-201 CONIACT THE BRE AKER CLOSES, THE CLOSING '
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| : 2. COMMAND 15 RETAINED THROUGH CS- i 209 CONIACT 2. j t
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| i I
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| F diitfR U tfffCA80 e urntvat oss u 01
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| Attacnmer.t--- A6---- - -
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| Document No. 182-193 Revision 0 Page 1 of I FSAR CHANGE PACKAGE (FCP)
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| Plant ST. LUCIE Unit 1
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| . . FSAR PAGES ATTACHED: ,
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| 3 I
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| l -
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| !"f FSAR FIGURES ATTACHED:
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| i I
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| COMMENTS:
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| ~
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| This PC/M revises drawings JPN-182-193-001 through -031 which are SRD's 4-listed in Table 1.7-1.
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| This FSAR Change Package is provided per this PC/M, Section 111.1.
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| 4 i
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| h f r .nv ' Us *M:' !0 L C1 l3 \ l9 %
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| Prepared by/Date: Verified by :
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| -977% zb /w Approved by/Date:
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| Notes:
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| : 1. All affected FSAR pages and tables are to be marked up and attached. If additional space is required. then additional pages should be provided. New information for inclusion in the FSAR shall also be provided.
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| : 2. The,new or marked up pages are to be ' fibi and 'f sufficient quality tn 5 microfilmed.
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| : 3. If a figure is provided elsewhere in the design package, then it need not be duplicated in the FCP. However, a note should be providet in the comment section referring to its location in .the package. This also applies to new drawings which should be added to the FSAR. If a figure revision is to be included in tne FCP, then a copy of the FSAR figure with a bubble around the affected area is sufficient.
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| ...................,me....--,..
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| l -
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| w w 'h 7 f t ~ I t2- m . H e C **y 2 CG St. Lucie Unit 1 Document No. DBD CCW-1 l
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| - - - - .- COMPONENI COOLING. WATER SYSIEM Revision O_ . _ _ _ _ . . !
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| Design Basis Document Page 38 were running prior to the LOOP are restarted by sequencing relays after the emergency efiesel generator (EDG) breaker closes and reenergizes the essential busses. If prior to a LOCA or LOOP /LOCA, the C_ pump is running as a replacement for the A or B pump, the replaced pump [--- -; - P = h= - - r ;Q sweng # have it's control j;;1 :1--J :f to prevent it from automatically starting on a SIAS. This ens res that three pumps will not be running at the same time (see Source 7). r a LOOP only sce.nario, the replaced pump does not receive an auto start si nal because it wasn't previously running.
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| Wutt TCH IW 7Mi
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| * PULL = 1'O = L.OC}r." P O 3 i T*l0 N-For a LOOP or LdOP/LOCA, the running CCW pump breakers are stripped from their respective busses via the bus under-voltage relays. Then, upon i restoration of power to the essential busses, the CCW pumps are restarted in accordance with EDG load sequencing by individual timing relays. Any pump started by a LOOP signal would stay running upon receipt of a subsequent SIAS.
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| Any CCW pump manually placed in the OFF position, will not start in a LOOP only scenario which is acceptable since only one pump is required for safe shutdown under LOOP only conditions (Source 4). The redundant pump is available for manual start if required.
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| The CCW pumps will start and remove the heat from the containment via the containment fan coolers. Source 3 required the containment fan coolers to be operable within 30 seconds following a LOCA, which is consistent with the
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| .- current emergency diesel generator loading sequence timing, which start the CCW pumps within 16 seconds (10 seconds Diesel Starting Time plus 6 i seconds Load Sequencing Delay).
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| The pump breaker control and protection circuits are powered from the Class 1E 125V DC System via the 4.16 kV Switchgear (See DBD 125 VDC-1). '
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| I I
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| 0.% C BD
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| / 9
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| _ _.. ..Attaehrtent_ 2.' _.
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| Document No. 182-193 Revision 0 Page 1 of 6 i
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| DBD CHANGE PACKAGE (DCP) 1 Plant ST. LUCIE Unit 1
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| - DBD PAGES ATTACHED: DBD-CCW-1 Pages 37 & ,
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| 38 and DBD-ICW-1 Pages 2, 30 & 31 -
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| t DBD FIGURES ATTACHED:
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| COMMENTS:
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| h f dab i n/WT3 Prepared by/Date:
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| N W CI' %\ AV Verified b te: I N eh+
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| Approved by/Date:
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| Notes:
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| : 1. All affected DBD pages and tables are to be marked up and attached. If additional space is required, then additional pages should be provided. New
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| ] information for inclusion in the DBD shall also be provided.
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| : 2. The new or marked up pages are to e legible and of sufficient quality to be microfilmed.
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| : 3. If a figure is provided elsewhere in the design package, then it need not be duplicated in the DCP. However. a note should be provided in .the comment section referring to its location in the package. This also applies to new drawings which should be added to the DBD. If a figure revision is to be included in the DCP. then a copy of the DBD figure with a bubble around the affected area is sufficient.
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| I JPN Form # , Rev.
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| 4 8t\USERSWLDWARDS\WP\ EVAL kEW.01
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| t'* ID-'9 ^h'#
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| A-/faz iw.,a- +. 7 IV 3 'l 0 St. Lucie Unit 1 Document No. DBD-CCW.1
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| -_ _ _.. _.. -OOMPONENECOCUNG3 VATER SYSTEM _
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| . Revision C _ _ - __ _ _ _ _ . . _ _ _ _ ..
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| Design Basis Document Page 37 COMPONENT PARAMETER WORKSHEET Section 7.1.2g Cgmoonent ID Descriotion CCW PP-1 A/B/C , CCW PUMPS A. Parameters See Values i
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| B. Value Controls Manual / Automatic l Actuation Signal LOOP /SIAS l Start Time 30 Seconds I l
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| C. Sources 1. CWD 8770-B 327 Sheets 201, 205, 209 (Ref 10.3.10) l
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| : 2. FSAR Appendix 9.5A (Ref 10.1.1) l
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| : 3. FSAR Table 6.2-6 (Ref 10.1.1) l
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| : 4. FSAR Table 9.2.6 (Ref 10.1.1) l
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| : 5. FSAR Section 7.4.1.4 (Ref 10.1.1) ,
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| : 6. Safety Evaluation JPN-PSL-SECS-92-012, Rev 0 (Ref l 10.3.28) l
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| : 7. FPL Letter JPN-PSLP-92-0597 (Ref 10.3.14)
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| D. Backoround/ Reason for Value The CCW pumps are controlled manually from the control room or, for Appendix "R" alternate shutdown requirements (Sources 1 and 2), from their respective switchgear upon actuation of the normal / isolate transfer switches.
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| Pump on/off status indicating lights are provided at each of these locations.
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| Local control via push-button stations is_also provided at the pump.
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| The following control circuit di cussion pertains to CCW Pumps A and B, as well as CCW Pump C only if i has been aligned as a replacement for CCW Pump A or B as discussed in etion 1.3. In addition to the bus alignments
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| , _ discussed in Section 1.3, CCW Pump # A or BPn g x:" J'O j
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| 'SHOULD ugC.. . =& ve&controg _gy, ..s or'oe: for the ;
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| \ ,.- C pump to operate as a replacement (Source _, m jiTCH IW THE "?VLL'10- Lo CK"hstTsod)
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| During a LOCA, the CCV' pumps remain running if already running, or are started by the SIAS if not running. During a LOOP only, the CCW pumps that
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| ;;W-CBD
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| c>
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| %gg. +. 9 fcw I O - v13. Ke v. C , f4 4 St. Lucie Unit 1 Document No. DBD-lCW-1
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| -- - _ ___JNTAKE_CD_OLING WATER SYSTEM ~ ~ ~ ~ ~ ~
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| Revision O
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| -~ ~ ~ - - - -
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| Design Basis Docurnent Page 2~
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| providing cooling water flow for norma igpyrgngd/orgygrg
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| ,-____ requirements. Normally the _C" pump u 29. - ::- ...:
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| , Mrnou eensWenapFor accident conditions, either train alone is sufficient to supply
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| \ 'the required cooling water flow necessary to mitigate any of the FSAR analyze [l 'gn BasgAcgdg{gggggge start . --_.._ _ , _
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| conditions, the "C" on tne train it is aligned to if that pump wi ~
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| ___.y
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| - train's pu fs4s to start. ,
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| All components associated with the " A" train are powered from safety related
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| " A" power. All components associated with the "B" train are powered from safety related "B" train power. The "C" pump is an installed spare and is powered from the safety related "AB" bus. This bus can be powered from either the "A" or "B" train safety related bus, but is normally powered from the "B" train (on Unit 1), which corresponds to the physical alignment of the l ICW system as discussed earlier. Alignment cf the " AB" bus to the " A" train I can be accomplished manually from the control room via a " dead bus" I transfer. This power swap not only requires the manual re-alignment of the !
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| ICW system cross-tie valves, but the CCW cross-tie valves as well. Since "AB" power can only come from either the "A" or "B" train but not both i simultaneously, the physical alignment of the ICW and CCW systems (" cross- )
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| tie" valve configuration) must be to the same train as the electrical lineup, i This is necessary in order to ensure the proper system configuration exists to the backed up train. This is particularly important when the "C" pump is operating as a replacement for one of the two required pumq- ~ntroi room annunciation will alert the operators if the electrical'- ' lignments are not in agreement. l The Turbine Cooling Water System and Open Blowdown Cooling System are classified as non-nuclear safety related systems and are therefore automatically isolated from the safety related portions of the ICW system upon receipt of a safety injection actuation signal (SIAS). The circulating water pump lube water supply lines are separated from the ICW system by Quality Group C, seismic qualified orifices. This effectively isolates these non-essential tube water supply lines from the essential portions of the ICW system. Thermal overload protection for these SI AS actuated motor operated isolation valves is bypassed for all operations except testing. Isolation of the non-essential portion from the essential portior if the ICW system can also
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| . be accomplished manually either locally or fror. le control room.
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| Automatic temperature control valves (TCVs), located at the outlet of each ICW supplied heat exchanger, will automatically control ICW flow through the heat exchangers. These valves are automatically modulated by the shell side water temperature of the respective heat exchanger. The ICW TCVs that control the CCW temperature will fail to a safe (i.e. " full open") position on a loss of air. The maximum opening of this TCV, along with the downstream installed restriction orifices in each ICW discharge header, will assure enough
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| A ttitc L& +. 7 r% 42-m3 % e rLy 49 St. Lucie Unit 1 Document No. DBD-ICW-1
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| __ ._ __ INTAKE _ COOLING _ WATER SYSTEM _ _ _ _ , _ _ _ Revp on C_ _ _ _ _ _
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| Design Basis Docurnent Page 30 COMPONENT PARAMETER WORKSHEET Section 7.1.2f Comoonent ID Descriotion
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| _ ICW PP 1 A/B/C , ICW Pumps A. Parameters Controls /
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| Actuation /
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| Start Time B. Values Controls Manual / Automatic Actuation Signal LOOP /SIAS Start Time 30 Seconds C. Source 1. CWD 8770-B-327 Sheets 832, 833, 834 (Ref 10.3.12)
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| : 2. FSAR Appendix 9.5A (Ret 10.1.1)
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| : 3. FSAR Table 6.2-6 (Ref 10.1.1)
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| : 4. FSAR Table 9.2-2 (Ref 10.1.1)
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| : 5. FSAR Section 7.4.1.5 (Ref 10.1.1)
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| : 6. Safety Evaluation JPN-PSL-SECS-92-012. Rev 0 (Ref 10.3.15)
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| : 7. FPL Letter JPN-PSLP 92-0597 (Ref 10.3.20)
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| D. Backoround/ Reason for Value The following control circuit discussion pertains to ICW Pumps A, B, and ICW Pump C only if it has been aligned as a replacement for ICW Pump A or B as I discussed in Section 1.3.
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| The ICW pumps are controlled manually from the control room or for Appendix "R" alternate snutdown requirements (Sources 1 and 2), from their respective switchgear upon actuation of the normal / isolate transfer switches. Pump on/off status indicating lights are provided at each of these locations. Local control via pusr .Iton stations is also provided.
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| During a LOCA scenario with off-site power available, the ICW pumps remain running if already running, or are started by the SlAS signal if not running. If prior to the LOCA. the C pump is running as a replacement for the A or B pump, ine replaced pump (if racked in with control power available) will attempt to start upon receipt of the LOCA signal, wnich may result in three ICW oumos running.
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| For this rqson, ICW Pumps A or BM-11. - -- ---- i;r:: D ontrolf - ' ___ p-:r:darde,r for the C Pump to Wpeeenesswer have y , m a e n re u , a n u n e 9
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| AttM % ss 4,7, Pcnm If2- 1 hev IW & 9,!
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| St. Lucie Unit 1 Document No. DBD ICW-1 Reyunon C .
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| f ----4NTAKE COOLING.WATEILSYSTEM Design Basis Document Page 31 operate as a ren:acement as described in Source 7. Souroe 6 addresses the seismic qualification of 4kV Switchgear with breakers in the racked out position.
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| For a LOOP, or LOOP /LOCA, the running ICW pumps are stripped from their l respective busses via the bus under-voltage relays, then upon restoration of EDG supplied AC power to the busses, the ICW pumps are restarted in accordanc_e I
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| - _with EDG load sequence requirem nts (9 seconds for the ICW pumps',1 ..J y
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| " '^ --- 2 'n 'C ?! ;_. , C by individual timing relays. If Mor to a -
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| P/LOCA, the C pitmp was running as a reolacement forJCW C pumps A or 8, the replac_ed pump4(if :::h:d ' Y ' - '-- - __ _. J't:) will attempt to_ l restargtii ^ 0 A , ,d e 1
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| 6, . ..iv, -;,-.; cf buswe D : rr;::::f ;m.) l
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| .m Ln_.--- ..
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| f ~ _~_. _-6~ ~ M7(,~ e ,~ %~u w,,.l,, ',s no r ,a ter "PyaN ro - L o If during a LOOP or a coincidental LOOP /LOCA, off-site power is restored prior to EDG Breaker Closure, the ICW pumps will immediately restart.
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| Any ICW pump manually placed in the OFF position, will not start in a LOOP only scenario which is acceptable since only one pump is required for safe shutdown under LOOP only conditions (Source 4) and the redundant pump is available for manual start if required. >
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| The required start time for the ICW pumps post LOCA is dependent on the containment analysis which is currently being revised. The ICW pumps should start to remove heat from the CCW system which removes heat from the Containment via the Containment Fan Coolers. Source 3 requires the Containment Fan Coolers to be operable within 30 seconds following a LOCA, which is consistent with the current Emergency Diesel Generator loading sequence timing, which start the ICW pumps within 19 seconds (10 seconds Diesel Starting Time plus 9 seconds Load Secuencing Delay)? e'<ce-;; f;- r.; C F2 p, -kick a bri ; ::: ;; ; rep'rce :n: pu,,,p ve,;; i r; ;- 20 m;r.d;-MO recrde O!:;;l C; .; .; TM.; pic; 10 se;;;;d; L;ed Cequer,;bg De!2yb#
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| v The pump breaker control and protection circuits are powered from the Class 1 E 125V DC system via the 4.16 KV Switchgear (See DBD 125V DC-1).
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| 1 i
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| l 1}}
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