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{{#Wiki_filter:SafetyAnalysisGinnaStationUFSARTable6.2-13ChangesRochester GasandElectricCorporation 89EastAvenueRochester, NewYork14649NSL-0000-SA024 Revision1October3,1990Preparedby:NulearEngineerK)-z.-'9QDateReviewedby:NuclerEnginerDateApprovedby:anagr,NuclearSfety&Licensing DatePagei90i0240i'i9 90iOi5PDRADOCK05000244PPDCI RevisionStatusSheetPageLatestRevisionLatestPage'evisionPageLatestRevision789,1014h1516171819202122232425037383940414243444546474812131414a14b14c14d14e14f14g272829303132333435360SafetyAnalysisNSL-0000-SA024 PageiiRevision1Date10390 SafetAnalsis1.02.0fDescritionandScoeThepurposeofthisevaluation istodetermine ifthereareanyunreviewed safetyquestions relatedtoupdatingUFSARTable6.2-13,Containment PipingPenetrations andIsolation Valves.Thisupdateisnecessary toreflectinformation obtainedduringadetailedreviewofthecontainment isolation systemandtheresultofthe1988Inservice Test(IST)Programsubmittal totheNRC.References 2.12.1.12.1.2UpdatedFinalSafetyAnalysisReport,Revision5.Section6.2.4,Containment Isolation System.Table6.2-13,Containment PipingPenetrations andIsolation Valves.2.2R.E.GinnaNuclearPowerPlantTechnical Specifications, datedApril12,1990.2.2.1~~2.2.22.2.32.32.4Section3.6.3,Containment Isolation Valves.Table3.6-1,Containment Isolation Valves.Section3.8.1,Refueling.
{{#Wiki_filter:Safety Analysis Ginna Station UFSAR Table 6.2-13 Changes Rochester Gas and    Electric Corporation 89  East Avenue Rochester,     New  York 14649 NSL-0000-SA024 Revision    1 October 3, 1990 Prepared by:                                                 K) -z.-'9Q Nu  lear Engineer                            Date Reviewed by:
LetterfromJ.E.Maier,RG&E,toD.M.Crutchfield, NRC,
Nucle  r Engine    r                        Date Approved by:
anag  r, Nuclear    S  fety & Licensing   Date Page  i 90i0240i'i9 90iOi5 05000244 PDR  ADOCK P              PDC      I
 
Revision Status Sheet Latest              Latest                    Latest Page      Revision  Page    'evision        Page        Revision 14h                      37 15                      38 16                      39 17                      40 18                      41 19                      42 20            0          43 21                      44 7                    22                      45 8                        23                      46 9                    24                      47
  ,10                    25                      48 12                    27 13                    28 14                    29 14a                  30 14b                  31 14c                  32 14d                  33            0 14e                  34 14f                  35 14g                  36 Safety Analysis                      Revision NSL-0000-SA024 Page ii        Date 1
10 3 90
 
Safet  Anal sis Descri tion and f
1.0                            Sco e The purpose    of this evaluation is to determine are any unreviewed safety questions related to updating if there UFSAR Table 6.2-13, Containment Piping Penetrations and Isolation Valves. This update is necessary to reflect information obtained during a detailed review of the containment isolation system and the result of the 1988 Inservice Test (IST) Program submittal to the NRC.
2.0        References 2.1       Updated Final Safety Analysis Report, Revision 5.
2.1.1      Section 6.2.4, Containment Isolation System.
2.1.2      Table 6.2-13, Containment Piping Penetrations        and Isolation Valves.
2.2        R.E. Ginna Nuclear Power Plant Technical Specifications, dated April 12, 1990.
2.2.1
  ~ ~     Section 3.6.3, Containment Isolation Valves.
2.2.2      Table 3.6-1, Containment Isolation Valves.
2.2.3      Section 3.8.1, Refueling.
2.3      Letter from J.E. Maier,     RG&E, to D.M. Crutchfield,   NRC,


==Subject:==
==Subject:==
SEPTopicVI-4,Containment Isolation Valves(Systems);
SEP  Topic VI-4, Containment Isolation Valves (Systems); dated August 30, 1982.
datedAugust30,1982.LetterfromL.D.White,RG&E,toD.L.Ziemann,NRCg
2.4      Letter from L.D. White,     RG&E, to D.L. Ziemann, NRCg


==Subject:==
==Subject:==
Discussion ofLessonsLearnedShortTermRequirements; datedNovember19,1979.2.52.6LetterfromL.D.White,RG&E,toB.H.Grier,NRC,
Discussion of Lessons Learned Short        Term Requirements;     dated November 19, 1979.
2.5      Letter from L.D. White, RG&E, to      B.H. Grier, NRC,


==Subject:==
==Subject:==
IEBulletins 79-06Aand79-06ARevision1;datedJune22,1979.LetterfromL.D.White,RG&E,toD.L.Ziemann,NRC,
IE Bulletins 79-06A and      79-06A Revision 1; dated June 22, 1979.
2.6      Letter from L.D. White,     RG&E, to D.L. Ziemann, NRC,


==Subject:==
==Subject:==
FollowupActionsResulting fromtheNRCStaffReviewsRegarding theTMIUnit2Accident; datedOctober17,1979.2.7LetterfromD.M.Crutchfield, NRC,toJ.E.Maier,NRC,
Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI Unit 2 Accident; dated October 17, 1979.
2.7      Letter from    D.M. Crutchfield, NRC, to J.E. Maier, NRC,


==Subject:==
==Subject:==
Forwarding FinalEvaluation ReportofSEPTopicVI-4,Containment Isolation SystemfortheGinnaNuclearPowerPlant;datedApril12,1982.SafetyAnalysisNSL-0000-SA024 Page1Revision0 2.82.92.102.112.122.132.142.152.162.172.182.192.19.12.20LetterfromJ.E.Maier,RG&E,toD.M.Crutchfield, NRC,
Forwarding Final Evaluation Report of SEP Topic VI-4, Containment Isolation System for the Ginna Nuclear Power Plant; dated April 12, 1982.
Safety Analysis                                      Revision      0 Page  1 NSL-0000-SA024
 
2.8        Letter from J.E. Maier,   RG&E, to D.M. Crutchfield,   NRC,


==Subject:==
==Subject:==
SEPTopicVI-4,Containment Isolation System;datedDecember30,1981.NUREG-0821, Integrated PlantSafetyAssessment, Systematic Evaluation Program,R.E.GinnaNuclearPowerPlant;datedDecember1982.RG&EInter-Office Correspondence fromG.J.Wrobel,toS.T.Adams,
SEP Topic VI-4, Containment Isolation System; dated December 30, 1981.
2.9        NUREG-0821, Integrated Plant Safety Assessment, Systematic Evaluation Program, R.E. Ginna Nuclear Power Plant; dated December 1982.
2.10      RG&E  Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,  


==Subject:==
==Subject:==
Necessary Clarifications Associated WithTechnical Specification Table3.6-1;datedJuly2,1990.RG&EInter-Office Correspondence fromG.J.Wrobel,toS.T.Adams,
Necessary Clarifications Associated With Technical Specification Table 3.6-1; dated July 2, 1990.
2.11      RG&E  Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,  


==Subject:==
==Subject:==
Containment Isolation ValvesAOV745(Penetration 124a),MOV749A(Penetration 127),andMOV749B(Penetration 128);datedJune22,1990.RG&EInter-Office Correspondence fromG.J.Wrobel,toS.T.Adams,
Containment Isolation Valves AOV 745 (Penetration 124a), MOV 749A (Penetration 127), and MOV 749B (Penetration 128); dated June 22, 1990.
2.12      RG&E  Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,  


==Subject:==
==Subject:==
Technical Specification Interpretation ofContainment Isolation ValvesMOVs749A/B;datedJune21,1990.USNRC,Regulatory Guide1.70,StandardFormatandContentofSafetyAnalysisReportsforNuclearPowerPlants;Revision3,November1978.LetterfromD.D.Di?anni,USNRC,toR.W.Kober,RG&E,
Technical Specification Interpretation of Containment Isolation Valves MOVs 749 A/B; dated June 21, 1990.
2.13      USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants; Revision 3,   November 1978.
2.14      Letter from  D.D. Di?anni, USNRC, to R.W. Kober, RG&E,


==Subject:==
==Subject:==
SEPTopicVI-4,NUREG-0821 Section4.22.2,Containment Isolation Valves;datedJanuary30,1987.NUREG-0800, StandardReviewPlan,Section6.2.4,Revision2,July1981.LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
SEP  Topic VI-4, NUREG-0821 Section 4.22.2, Containment Isolation Valves; dated January 30, 1987.
2.15      NUREG-0800, Standard Review Plan, Section 6.2.4, Revision 2, July 1981.
2.16      Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,


==Subject:==
==Subject:==
Operability ofAOV745andMOVs749A/B;datedJuly9,1990.LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,
Operability of AOV 745 and MOVs 749A/B; dated July  9, 1990.
2.17      Letter from R.C. Mecredy, RG&E, to A.R. Johnson,     NRC,


==Subject:==
==Subject:==
Modification ofContainment Penetration
Modification of Containment Penetration     $ 2; dated March 13, 1990.
$2;datedMarch13,1990.GinnaStationProcedure 0-2.3.1A, Containment ClosureCapability inTwoHoursDuringRCSReducedInventory Operations, Revision5,datedApril28,1990.GinnaStationQualityAssurance Manual.AppendixB,Inservice Inspection ProgramForthe1990-1999Interval, Revision0,datedJanuary1,1990.10CFR50,AppendixJ,PrimaryReactorContainment LeakageTestingforWater-Cooled PowerReactors.
2.18      Ginna Station Procedure 0-2.3.1A, Containment Closure Capability in Two Hours During RCS Reduced Inventory Operations, Revision 5, dated    April 28, 1990.
SafetyAnalysisNSL-0000-SA024 Page2Revision0Date92490 I4II 3.0SafetAnalsis3~13.2Thesystemaffected, bythisUFSARchangeisthecontainment isolation system.Thissystemisdesignedtoisolatenon-essential processlineswhichpenetrate thecontainment toensurethatthetotalleakageofactivitywillbewithindesignlimitsintheeventofanaccident.
2.19      Ginna Station Quality Assurance Manual.
Inaddition, theparentsystems(e.g.,SafetyInjection) ofthecomponents contained inthecontainment isolation systemcanbeconsidered affectedbythisUFSARchange.However,thereisnochangetothecapability ofthesesystemstoperformtheirintendeddesignfunction, onlyanupdateoftheirabilitytoisolatecontainment whenrequired.
2.19.1    Appendix B, Inservice Inspection Program For the 1990-1999 Interval, Revision 0, dated January 1, 1990.
TheupdatedUFSARTable6.2-13ispresented inAttachment A.Duetothesignificant numberofchanges,amarked-up versionofthecurrentUFSARtablewasnotgenerated.
2.20      10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
Instead,Attachment Bprovidesadetailedlistingofallchangesmadetothetable.Attachment Bisdividedintofour(4)subtables.(2)(3)(4)Thefirsttable,providesalistingofglobalnoteswhichwereappliedasapplicable toeliminate redundancy.
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Thesecondtableprovidesalistingofchangesmadetotheformatandoverallstructure oftheUFSARtable.Thethirdtableliststhechangesmadetoeachindividual penetration ontheUFSARtable.Thefourthtableidentifies allchangesmadetotheUFSARtablenotes.However,sincemanymodifications weremadetotheUFSARtable,mostnoteshavebeenrenumbered andrevised.Consequently, toeliminate confusion, achangeassociated withthenotescolumnforaparticular penetration isonlyidentified inTable3ifanotehasbeenaddedordeleted.Thereisnochangeidentified inTable3ifanotenumberhasonlybeenchanged,ifchangesweremadetothenoteitself,orifthenotewasdeletedglobally.
 
Instead,thesechangesareprovidedinTable4.3.3ThechangestoUFSARTable6.2-13fallintothreecategories:
I4 II
(2)(3)clarifications orcorrections oftypographical errorsandomissions,.
 
updatestobetterrepresent actualplantconditions, andupdatesforconsistency betweentheUFSAR,Technical Specifications, andpreviouscommitments madebyRG&E.SafetyAnalysisNSL-0000-SA024 Page3Revision0
3.0        Safet  Anal sis 3~1        The system  affected, by this UFSAR change is the containment  isolation system. This system is designed to isolate non-essential process lines which penetrate the containment to ensure that the total leakage of activity will be within design limits in the event of an accident. In addition, the parent systems (e.g.,
~~s~3.3.13.3.1.1Thecorrection oftypographical errorsandomissions doesnotinvolveanytechnical changetotheUFSARtablenorthefunctionandcapability ofthecontainment isolation system.Allcolumnsandrowsinthetablenowcontaineitherthe'necessary information or"NA".Noblanksor"-"remaininthetable.Inaddition, theclarifications madetotheUFSARtableareminoranddonotinvolveanytechnical changes.Significant clarifications arediscussed below.ThePositionAtPostaccident columnwaschangedtoreflectplantconditions immediately following aContainment Isolation Signal(CIS).Thiscolumnwasmodifiedsincesystemconfigurations canbechangedduringrecoveryoperations.
Safety Injection) of the components contained in the containment isolation system can be considered affected by this UFSAR change. However, there is no change to the capability of these systems to perform their intended design function, only an update of their ability to isolate containment when required.
Ifthiscolumnwasnotmodified, itwouldrequiremostvalvestolist"0/C".Thecolumnnowprovidesaclearlistingofthevalvepositions priortoanyoperatoraction(i.e.,"immediate" postaccident)
3.2        The updated UFSAR Table 6.2-13 is presented in Attachment A. Due to the significant number of changes, a marked-up version of the current UFSAR table was not generated. Instead, Attachment B provides a detailed listing of all changes made to the table.
.3.3.1.2TheNotescolumnwaschangedtoonlysupplement UFSARSection6.2.4.4.2 text.Allduplications ofinformation contained intheUFSARtextwasremovedfromtheNotes.TheNotescolumnnowonlyidentifyexceptions, references, etc.,notcontained intheUFSARtext.3.3.1.3removedfromthetablesincetheydonotprovideanyinformation relevanttotheUFSARTable.Thisinformation canbeobtainedfromothersourcesincluding AppendixBoftheGinnaStationQualityAssurance Manual.Consequently, theinformation contained inthesecolumnsremainsinotherRG&Econtrolled documents.
Attachment B is divided into four (4) sub tables.
3.3.1.4ThePositionIndication InControlRoomcolumnwasmodifiedtoshowthetypeofindication insteadof"Yes/No".
The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy.
Thisisasignificant enhancement sincethetablenowidentifies ifthereisawhitestatuslightorared/green lightassociated withthevalveontheMainControlBoard,orboth.3.3.23.3.2.1TheupdatestotheUFSARtabletobetterrepresent actualplantconditions aredescribed below.Penetration
(2) The second table provides a listing of changes made to the format and overall structure of the UFSAR table.
$2wasaddedtothetable.Thissparepenetration wasmodifiedduringthe1990Refueling Outagetoenhancecontainment closureduringmid-loopoperations.
(3) The third table lists the changes made to each individual penetration on the UFSAR table.
Thepenetration meetsallcurrentcontainment penetration criteria.
(4) The fourth table identifies all changes made to the UFSAR table notes. However, since many modifications were made to the UFSAR table, most notes have been renumbered and revised.
SeeReference 2.17.SafetyAnalysisNSL-0000-SA024 Page4Revision0Date92490
Consequently, to eliminate confusion, a change associated with the notes column for a particular penetration is only identified in Table 3 if a note has been added or deleted.     There is no change identified in Table 3 only been changed, if a note number has if changes were made to the note itself, or  if  the note was deleted globally.
~~~~3.3.2.23.3.2.3Severalvalveshadtheirpositions aslistedunderthePositionAtcolumnsintheUFSARTablechangedtoamoreconservative position.
Instead, these changes are provided in Table 4.
Thatis,thevalvepositionchangedfromeithera"0/C"to"C",nO<rtonCnnpntonLCIrorsrCtttonLCn(SeeTable3ofAttachment Bforadetaileddescription ofthesechangesonapenetration bypenetration basis.)Forthesecases,thevalveisnowidentified asbeinginanisolatedorclosedpositionwhichisthefunctionofacontainment isolation valve.Valves(andpenetration
3.3      The changes to UFSAR Table 6.2-13 fall into three categories:
&#xb9;)inthiscategoryinclude:370B(&#xb9;100),879(&#xb9;110b),371(&#xb9;112),846(&#xb9;120a),539(&#xb9;120b),547(&#xb9;121a),528(121a),508(&#xb9;121b),743(&#xb9;124a),745(&#xb9;124a),1569(&#xb9;124b)g1571(&#xb9;124b)g1572(&#xb9;124b)I1574(&#xb9;124b)I759B(&#xb9;125)I759A(&#xb9;126)I749A(&#xb9;127)749B(&#xb9;128)I1787(&#xb9;129)I1786(&#xb9;129)/7971(&#xb9;132),1076B(&#xb9;202),1084B(&#xb9;202)I1563(&#xb9;203b)I1565(&#xb9;203b)I1566(&#xb9;203b)~1568(&#xb9;203b)I5869(&#xb9;204),966C(&#xb9;205),966B(&#xb9;206a),5735(&#xb9;206b),966A(&#xb9;207a),5736(&#xb9;207b),1080(&#xb9;210),5879(&#xb9;300)g6151(&#xb9;301)g6165(&#xb9;301)~6175(&#xb9;303)6152(&#xb9;303)g1076A(&#xb9;304)I1084A(&#xb9;304)g1554(&#xb9;305c),1556(&#xb9;305c),1557(&#xb9;305c),1559(&#xb9;305c)f1560(&#xb9;305c),1562(&#xb9;305c),7141(&#xb9;310a),921(&#xb9;332c),922(&#xb9;332c),923(&#xb9;332c),and924(&#xb9;332c).Severalvalveshadtheirpositions aslistedunderthePositionAtcolumnsintheUFSARTablechangedtoacomparable position.
clarifications or corrections of typographical errors and omissions,.
Thatis,thevalvepositionchangedfromeithera"0"to"0/C"or"0/C"to"0".(SeeTable3ofAttachment Bforadetaileddescription ofthesechangesonapenetration bypenetration basis.)Forthesecaseswherethevalvewaslistedasopen,thevalveandpenetration wasrequiredtobeevaluated previously assumingthatitwasopensincethiswasthemostconservative position.
(2) updates to better represent actual plant conditions, and (3) updates for consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.
Therefore, changingthevalve'spositionforthesecasesdoesnotnegatively impactthepenetration orcontainment isolation systemsincethevalvewasconservatively evaluated underopenconditions previously.
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Valves(andpenetration
 
&#xb9;)inthiscategoryinclude:1723(&#xb9;107),1728(&#xb9;107),313(&#xb9;108),1789(&#xb9;123bottom),1003A(&#xb9;143),1003B(&#xb9;143)g5869(&#xb9;204)g5735(&#xb9;206b)I5736(&#xb9;207B)5879(&#xb9;300)~4629(&#xb9;308)g4630(&#xb9;311)I4642(&#xb9;312)g4643(&#xb9;315)I4628(&#xb9;316)g4627(&#xb9;319)f4641(&#xb9;320),4644(&#xb9;323),and8418(&#xb9;324).SafetyAnalysisNSL-0000-SA024 Page5Revision0Date92490
~ ~ s ~
~~~~'3.3.2.43.3.2.5Severalvalveshadtheirpositions aslistedunderthePositionAtColdShutdowncolumnintheUFSARTablechangedtoalessconservative position.
3.3.1     The  correction of typographical errors and omissions does not  involve any technical change to the UFSAR table nor the function and capability of the containment isolation system. All columns and rows in the table now contain either the 'necessary information or "NA". No blanks or "-" remain in the table. In addition, the clarifications made to the UFSAR table are minor and do not involve any technical changes.
Thatis,thevalvepositionchangedfromeithera"CntonOnornCntonO/Cn(SeeTable3ofAttachment B=foradetaileddescription ofthesechangesonapenetration bypenetration basis.)However,containment integrity isnotrequiredintheColdShutdowncondition (Technical Specification 3.6.1).Inaddition, duringreducedRCSinventory operations, thepositionofthesevalves(oranautomatic isolation valveinthesameline)isverifiedbyReference 2.18.Thus,thesevalvescanbe'closed ifneeded.Also,duringRefueling Operations, Technical Specification 3.8.1requiresthatall"automatic containment isolation valvesshallbeoperableoratleastonevalveineachlineshallbelockedclosed."Therefore, containment isolation isassuredduringrefueling operations.
Significant clarifications are discussed below.
Consequently, thesechangesdonotnegatively'mpact thepenetration orthecontainment isolation systemsinceadministrative controlsareinplace.Valves(andpenetration 0)inthiscategoryinclude:7970($132),7971($132),5393($310b),7443($317),5738($321),and5737($322).Severalvalveshadtheirpositions aslistedunderthePositionAtNormal0erationandPositionAtImmediate Postaccident columnsintheUFSARTablechangedtoalessconservative position.
3.3.1.1          The Position At Postaccident column was changed to reflect plant conditions immediately following a Containment Isolation Signal (CIS) . This column was modified since system configurations can be changed during recovery operations. If this column was not modified, it would require most valves to list "0/C". The column now provides a clear listing of the valve positions prior to any operator action (i.e., "immediate" post accident) .
Thatis,thevalvepositionchangedeitherfroma"C"to"0/C",or"0"to"LO".(SeeTable3ofAttachment Bforadetaileddescription ofthesechangesonapenetration bypenetration basis.)Therearetwocategories ofvalveswhichmeetthiscriteria(organized byjustification)
3.3.1.2          The Notes column was changed to only supplement UFSAR Section 6.2.4.4.2 text. All duplications of information contained in the UFSAR text was removed from the Notes. The Notes column now  only identify exceptions, references, etc., not contained in the UFSAR text.
.(a)529(g12lb)-Thispenetration hasanautomatic isolation valveinthelinetoperformthenecessary isolation function.
3.3.1.3 removed from the table since they do not provide any information relevant to the UFSAR Table. This information can be obtained from other sources including Appendix B of the Ginna Station Quality Assurance Manual. Consequently, the information contained in these columns remains in other RG&E controlled documents.
Inaddition, sincethischeckvalveseesthesameconditions astheassociated automatic isolation valve,theirpositions shouldbethesame.Consequently, thechangedoesnotnegatively impactthepenetration orthecontainment isolation system.SafetyAnalysisNSL-0000-SA024 Page6Revision0
3.3.1.4          The Position Indication In Control Room column was modified to show the type of indication instead of "Yes/No". This is a significant enhancement since the table now identifies  if there is a white status light or a red/green light associated with the valve on the Main Control Board, or both.
~~(b)4629($308)g4630($311)~4642($312)g4643(f315)~4628($316)g4627($319)g4641($320),4644($323)-Theseessential ServiceWaterSystempenetrations operateatahigherpressurethanthecontainment accidentpressureandaremissileprotected insidecontainment.
3.3.2      The updates to the UFSAR table to better represent actual plant conditions are described below.
Consequently, thelineisnotrequiredtoisolate.SeeUFSARTableNote17.Therefore, thechangeinvalvepositiondoesnotnegatively impactthepenetration orthecontainment isolation system.3.3.2.6a"No"forvalve745($124a).TheMaximumIsolation Timecolumnwasalsochangedfrom"60"to"NA".Thesechangesarejustified perReference 2.16.3.3.2.7Severalpenetrations hadvalvesaddedtothetable,deleted,orboth.Thesearedescribed belowbypenetration number.(a)Penetration 103-Valve5129wasdeletedfromthetableandreplacedbyaBlindFlange.Thischangeenabledtheelimination ofthepreviousnoteof"Nolongerinuse"thatwasassociated withthispenetration.
3.3.2.1          Penetration $ 2 was added to the table. This spare penetration was modified during the 1990 Refueling Outage to enhance containment closure during mid-loop operations. The penetration meets all current containment penetration criteria. See Reference 2.17.
Thepenetration nowreflectsthecurrentconfiguration.
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TheuseoftheBlindFlangeisconsistent withthepreviouslocked-closed manualvalve.(b)Penetration 111-Addedvalve959.Theadditionofthisvalvetothetableensuresthatallvalvesreceiving acontainment isolation signalarelisted.Thisvalvewaspreviously missingfromthetable,butcreditwasnottakenforthevalveduringtheSEP(seeReference 2.7).Consequently, thisisnotconsidered anactualisolation valveandisnottestedperAppendixJ.(c)Penetration 112-Valves204Aand821weredeleted.-andreplacedwithvalves200A,200B,and202.Valve427wasalsoadded.Theadditionofthesevalvesenablesexplicitcompliance withGDC55versustheuseofthetworedundant isolation valves.ThesenewvalvesareincludedinthecurrentISTprogram(seeReference 2.19).(d)123(bottom)-Addedvalve1600A.Seeexplanation for3.3.2.7(b)above.SafetyAnalysisNSL-0000-SA024 Page7Revision0Date92490
 
~~  
~ ~ ~ ~
~~~~(e)Penetration 141-Deletedvalve851Aandaddedvalve1813A.Valve851Adoesnotmeettheselection criteriafor10CFR50AppendixJ,SectionIIH,items1through4.Consequently, thevalvewasdeletedfromthetable.Valve1813Awaspreviously missingfromthetable.Thisvalveislocked-closed withitsbreakerlockedopen.(f)'enetration 142-Deletedvalve851Bandaddedvalve1813B.Seeexplanation for3.3.2.7(e)above.3.3.2.8(g)Penetration 205-Addedvalve955.Seeexplanation for3.3.2.7(b)above.(h)Penetration 206a-Addedvalve953.Seeexplanation for3.3.2.7(b)above.(i)Penetration 207a-Addedvalve951.Seeexplanation for3.3.2.7(b)above.(j)Penetration 210-Addedvalves10214S1and10215S1.Thesevalveswerepreviously missingfromthetable,butreceiveanisolation signal.Penetration 332b-Deletedentirepenetration branchfromthetable.Thispenetration branchcontainsdoubleisolation, fitsthecriteriaasatestconnection, andperformsnoactivefunction.
3.3.2.2         Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a more conservative position. That is, the valve position changed from either a "0/C" to "C",
Therefore, thereisnorequirement totestthevalvesascontainment isolation valves.Consequently, thispenetration branchwasremovedfromthetable.3.3.33.3.3.1SeveralupdatesweremadetotheUFSARtabletoensureconsistency betweentheUFSAR,Technical Specifications, andpreviouscommitments madebyRG&E.Thesechangesaretypically onlyclarifications.
nO<r to nCn      npn to nLCIr or srCtt to nLCn              (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases, the valve is now identified as being in an isolated or closed position which is the function of a containment isolation valve. Valves (and penetration &#xb9;) in this category include: 370B (&#xb9;100), 879 (&#xb9;110b),
Thesignificant changesaredescribed below.Notes7and19wereaddedtoensurethatconsistency ismaintained betweenTechnical Specification Table3.6-1andtheUFSARTable.Thesenotesmainlyprovideclarification anddonotinvolveatechnical change.SafetyAnalysisNSL-0000-SA024 Page8Revision0
371 (&#xb9;112), 846 (&#xb9;120a), 539 (&#xb9;120b), 547 (&#xb9;121a),
~I~~3.3.3.23.3.3.3TheMaximumIsolat'ion Timeofseveralvalveswaschangedtoamoreconservative duration.
528 (121a), 508 (&#xb9;121b), 743 (&#xb9;124a), 745 (&#xb9;124a),
Thatis,thetimewaschangedfrom"NA"toeither"3"secondsforsolenoidvalves,or"60"secondsforAOVsandMOVs.(SeeTable3ofAttachment Bforadetaileddescription ofthesechangesonapenetration bypenetration basis.)TheUFSARTablenowidentifies anisolation timeforallvalvesreceiving acontainment isolation signal.Valves(andpenetration 4)inthiscategoryinclude:1787($129),10211S1($202),10213S1($202),966C($205),966B($206a),5735($206b),966A($207a),5736($207b),10214S($210),10215S1($210)/10205S1($304)g10209S1($304)g1597($305a),1599($305b),and8418($324).TheMaximumIsolation Timeofseveralvalveswaschangedtoalessconservative duration.
1569   (&#xb9;124b) g 1571 (&#xb9;124b) g 1572 (&#xb9;124b) I 1574
Therearethreecategories ofvalveswhichmeetthiscriteria(organized byjustification):
(&#xb9;124b) I 759B (&#xb9; 125) I 759A (&#xb9;126) I 749A (&#xb9;127) 749B (&#xb9; 128) I 1787 (&#xb9;129) I 1786 (&#xb9; 129) / 7971
(a)749A(f127),749B($128)-Thesevalvesdonotreceiveacontainment isolation signal.Consequently, theMaximumIsolation Timewaschangedto"NA"sincethereisnoneedforamaximumisolation time.(b)5869($204)-Thisvalvedoesnotrequireanisolation timesincetheassociated blindflangeactsastheisolation boundary.
(&#xb9;132), 1076B (&#xb9;202), 1084B (&#xb9;202) I 1563 (&#xb9;203b)                 I 1565 (&#xb9;203b) I 1566 (&#xb9;203b)         ~   1568 (&#xb9;203b) I 5869
See,UFSARTableNote19.Consequently, theMaximumIsolation Timewaschangedto"NA"sincethereisnoneedforamaximumisolation time.(c)7970($132),7971($132),7478(f309),and7445(f309)-Theisolation timeforthesebutterfly valveswaschangedfrom"2"secondsto"3"seconds.Technical Specification Table3.6-1allowsfivesecondswithinstrument delay.However,theMaximumIsolation Timecolumndoesnotincludeinstrument delayperNote"b".Theinstrument delaytimeforthesevalvesisapproximately 2seconds.Consequently, thevalveisolation timewaschangedto"3"seconds.3.4AreviewofthedesignbasiseventsanalyzedintheGinnaStationUFSARand,theeventsrequiring analysisasdescribed inUSNRCReg.Guide1.70wasperformed.
(&#xb9;204), 966C (&#xb9;205), 966B (&#xb9;206a), 5735 (&#xb9;206b),
TheeventsrelatedtothisUFSARchangeare:SafetyAnalysisNSL-0000-SA024 Page9Revision0
966A   (&#xb9;207a), 5736 (&#xb9;207b), 1080 (&#xb9;210), 5879
~~3.4.13.4.23.4.3,~~3.4.4(a)Fires(b)SeismicEvents(c)Radiological ReleaseFromaSubsystem orComponent (d)DecreaseinReactorCoolantInventory (e)EventsInitiating aSafetyInjection SignalThechangesasdescribed inSection3.3andAttachment Bdonotaffectthecapability ofthecontainment isolation systemtoperformitsfunctionduringafire.ThechangestotheUFSARTablearemainlyminorclarifications andupdatestoreflectcurrentplantconditions.
(&#xb9;300) g  6151  (&#xb9;301) g  6165    (&#xb9;301) ~   6175   (&#xb9;303) 6152   (&#xb9;303) g  1 07 6A  (&#xb9;304) I  1 084A  ( &#xb9;304) g  1554
Thereisnophysicalmodification toGinnaStationasaresultofthesechanges.Nofirebarriersareaffectedbythesechanges,noristhereanyincreaseinareafireloadings.
(&#xb9;305c), 1556 (&#xb9;305c), 1557 (&#xb9;305c), 1559 (&#xb9;305c)                   f 1560 (&#xb9;305c), 1562 (&#xb9;305c), 7141 (&#xb9;310a), 921
Thechangesasdescribed inSection3.3andAttachment Bdonotaffectthecapability ofthecontainment isolation systemtoperformitsfunctionduringaseismicevent.ThechangestotheUFSARTablearemainlyminorclarifications andupdatestoreflectcurrentplantconditions.
(&#xb9;332c), 922 (&#xb9;332c), 923 (&#xb9;332c), and 924
Nochangesaremadewithrespecttotheseismicdesignoftheaffectedpenetrations.
(&#xb9;332c)   .
Thechangesasdescribed inSection3.3andAttachment Bdonotaffectthecapability ofthecontainment isolation systemtorespondtoaradiological releasewithincontainment.
3.3.2.3        Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a comparable position. That is, the valve position changed from either a "0" to "0/C" or "0/C" to "0". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases where the valve was listed as open, the valve and penetration was required to be evaluated previously assuming that was the most conservative position.
Thecontainment isolation systemwasreviewedindepthduringtheSEPand1988ISTsubmittal.
it  was open since this Therefore, changing the valve's position for these cases does not negatively impact the penetration or containment isolation system since the valve was conservatively evaluated under open conditions previously. Valves (and penetration &#xb9;) in this category include: 1723 (&#xb9;107), 1728 (&#xb9;107), 313
ThechangestotheUFSARTablearemainlyclarifications andupdatestoreflectcurrentplantconditions.
(&#xb9;108), 1789 (&#xb9;123 bottom), 1003A (&#xb9;143), 1003B
Thereisnophysicalmodification toGinnaStationasaresultofthesechanges.Consequently, thecontainment isolation systemisstillwithinitsdesignbasislimits.Thechangesasdescribed inSection3.3andAttachment Bdonotcreatethepotential fortheaffectedpenetrations tocauseadecreaseinRCSinventory (i.e.,aloss-of-coolant-accident)
(&#xb9;1 43) g 5869 (&#xb9;204) g 5735 (&#xb9;206b) I 5736 (&#xb9;207B) 5879 (&#xb9;300) ~ 4629 (&#xb9;308) g 4630 (&#xb9;31 1) I 4642
.Thecontainment isolation systemwasreviewedindepthduringtheSEPand1988ISTsubmittal.
(&#xb9;312) g 4643 (&#xb9;315) I 4628 (&#xb9;316) g 4627 (&#xb9;319) f 4641 (&#xb9;320), 4644 (&#xb9;323), and 8418 (&#xb9;324) .
ThechangestotheUFSARTablearemainlyclarifications andupdatestoreflectcurrentplantconditions.
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Nochangesweremadetocapability oftheparentsystems(e.g.,ResidualHeatRemoval)toperformtheirfunction.
 
Consequently, thecontainment isolation systemandassociated parentsystemsremainwithintheirdesignbasislimits.SafetyAnalysisNSL-0000-SA024 Page10Revision0Date92490 P
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4~~k~3.4.5Eventswhichiniti'ate SafetyInjection alsoresultintheneedforcontainment isolation.
3.3.2.4          Several valves had their positions as listed under the Position At Cold Shutdown column in the UFSAR
ThechangestotheUFSARTabledonotaffectthecapability ofthecontainment isolation systemtoperformitsfunction.
'                        Table changed to a less conservative position.
Allchangeswererev'iewed toensurecontinued compliance withthedesignbasisforthecontainment isolation systemandtheGinnaStationLicensing Basis.4.0Preliminar SafetEvaluation 4.14.2TheproposedUFSARchangeswillnotincreasetheprobability ofoccurrence ofanaccidentpreviously evaluated intheUFSAR.ThechangestotheUFSARTablearetocorrecttypographical errors,provideadditional clarification, andupdatethetabletoreflectactualplantconditions.
That is, the valve position changed from either a "Cn to nOn or nCn to nO/Cn         (See Table 3 of Attachment    B =for a detailed description of these changes on a penetration by penetration basis.)
Allchangesconsidered "lessconservative" areacceptable anddonotincreasetheprobability ofoccurrence asdiscussed inSections3.3.2.4,3.3.2.5,3.3.2.6,and3.3.3.3.Alladditions anddeletions tothetablearealsoacceptable anddonotincreasetheprobability ofoccurrence asdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8.Thus,thereisnochangeinsystemfunction, norareduction insystemreliability.
However, containment integrity is not required in the Cold Shutdown condition (Technical Specification     3.6.1) . In addition, during reduced RCS  inventory  operations, the position of these valves (or an    automatic isolation valve in the same line) is    verified by Reference 2.18. Thus, these valves can be'closed       if  needed.
Thecontainment isolation andparentsystemswillremainwithintheirdesignlimits.TheproposedUFSARchangeswillnotincreasetheconsequences ofanaccidentpreviously evaluated intheUFSAR.Themodification doesnotimpactorincreasethecalculated radiological dosetothegeneralpublicforanyeventevaluated intheUFSAR.Allchangesconsidered "lessconservative" areacceptable anddonotincreasetheconsequences ofanaccidentasdiscussed inSections3.3.2.4,3.3.2.5,3.3.2.'6, and3.3.3.3.Alladditions anddeletions tothetablearealsoacceptable anddonotincreasetheconsequences ofanaccidentasdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8.Thus,-thefunctionandcapability ofthecontainment isolation systemtoisolateanyradiological releasewithincontainment isnotdegraded.
during Refueling Operations, Technical Also, Specification 3.8.1 requires that all "automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed." Therefore, containment isolation is assured during refueling operations.
SafetyAnalysisNSL-0000-SA024 Page11Revision0Date92490
Consequently, these changes do not the penetration or the containment negatively'mpact isolation system since administrative controls are in place. Valves (and penetration 0) in this category include: 7970 ($ 132), 7971 ($ 132), 5393
~~~~
($ 310b),   7443 ($ 317), 5738 ($ 321), and 5737
4.3TheproposedUFSARchangeswillnotincreasetheprobability ofoccurrence ofamalfunction ofequipment important tosafetypreviously evaluated intheUFSAR.Allchangesconsidered "lessconservative" areacceptable anddonotincreasetheprobability ofoccurrence asdiscussed inSections3.3.2.4,3.3.2.5,3.3.2.6,and3.3.3.3.Alladditions anddeletions tothetablearealsoacceptable anddonotincreasetheprobability ofoccurrence asdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8.Thus,thechangesdonotdegradetheperformance ofthecontainment isolation system,northeassociated parentsystems.4.4TheproposedUFSARchangeswillnotincreasetheconsequences ofamalfunction ofequipment important to,.safetypreviously evaluated intheUFSAR.Thechangesdonotimpactorincreasethecalculated radiological dosetothegeneralpublicforanyeventevaluated intheUFSAR.Allchangesconsidered "lessconservative" areacceptable anddonotincreasetheconsequences ofamalfunction ofequipment asdiscussed inSections3.3.2.4,3.3.2.5,3.3.2.6,and3.3.3.3.Alladditions anddeletions tothetablearealsoacceptable anddonotincreasetheconsequences ofamalfunction ofequipment asdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8.Thus,thefunctionandcapability ofthecontainment isolation systemtoisolateanyradiological releasefromcontainment isnotdegraded.
($ 322) .
=4.5TheproposedUFSARchangeswillnotcreatethepossibility ofanaccidentofadifferent typethananypreviously evaluated intheUFSAR.Thesechangesaremainlyclarifications andupdatestoreflectcurrentplantconditions.
3.3.2.5        Several valves had their positions as listed under the Position At Normal 0 eration and Position At Immediate Postaccident columns in the UFSAR Table changed to a less conservative position. That is, the valve position changed either from a "C" to "0/C", or "0" to "LO". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) There are two categories of valves which meet this criteria (organized by justification) .
Allchangesconsidered "lessconservative" areacceptable anddonotincreasetheconsequences ofamalfunction ofequipment asdiscussed inSections3.3.2.4,3.3.2.5,3.3.2.6,and3.3.3.3.Alladditions anddeletions tothetablearealsoacceptable anddonotincreasetheconsequences ofamalfunction ofequipment asdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8.Therearenoadverseaffectsuponothersystems,noranynewfailuremodesinduced.4.6TheproposedUFSARchangeswillnotcreatethepossibility ofadifferent typeofmalfunction ofequipment important tosafetythananypreviously evaluated intheUFSAR.Theadditions anddeletions tothetableareacceptable asdiscussed inSections3.3.1.3,3.3.2.1,3.3.2.7,and3.3.2.8,Thechangesdonotdegradethecontainment isolation orassociated parentsystems.SafetyAnalysisNSL-0000-SA024 Page12Revision92490 k
(a)   529 (g12lb) This    penetration has              an automatic isolation valve in the line to perform the necessary isolation function. In addition, since this check valve sees the same conditions as the associated automatic isolation valve, their positions should be the same. Consequently, the change does not negatively impact the penetration or the containment isolation system.
~~4.74.8TheproposedUFSARchangeswillnotreduceanymarginofsafetyasdefinedinthebasisofanytechnical specification.
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Thefunctions andcharacteristics ofthecontainment isolation systemremainsunchanged.
 
However,changesaremadetovalveisolation timesandthevalveslistedforspecificpenetrations.
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Thesechangeswillbeaddressed intheAmendment RequesttoremoveTable3.6-1fromtheTechnical Specifications andreference thisupdatedUFSARtable.Basedontheaboveanalysis, ithasbeendetermined that:(a)Themarginsofsafetyduringnormaloperation andtransient conditions anticipated duringthelifeoftheplanthasnotbeenreduced,and(b)Theadequacyofstructures, systems,andcomponents providedfortheprevention ofaccidents andforthemitigation oftheconsequences ofaccidents havenotbeenaffected.
(b) 4629   ($ 308) g  4630  ($ 31 1) ~ 4642 ($ 312) g 4643 (f315) 4628 ($ 316)
SafetyAnalysisNSL-0000-SA024 Page13Revision0Date92490 l~/
                                  ~              g  4627  ($ 319) g 4641
Attachment ASafetyAnalysisNSL-0000-SA024 Page14Revision0Date92490 CONTAIANDI2-13PENETRATIONS PIPINC~SsteaPenetration No.ValveNo.ValvePositionValveIndicationPositionOperatorInControlRelativetoNormalPositionAtColdIxaedfateShutdovnPostaccfdent~
($ 320), 4644 ($ 323)     These essential Service Water System penetrations operate at a higher pressure than the containment accident pressure and are missile protected inside containment. Consequently, the line is not required to isolate. See UFSAR Table Note
MaxisansIsolation UFSARNotesSteamCenerator Inspection/
: 17. Therefore, the change in valve position does not negatively impact the penetration or the containment isolation system.
Maintenance BlindFlangesBoth0/CC(add)5I~2FuelTransferTubeChargingLinetoBLoopSafetyInfection PuryIBDischarge Alternate ChargingtoAColdLeg29100101102370B870B889B3838BlindFlangeCheckCheckCheckCheckInsideInsideOutsideOutsideInside0/C00C6'-1356.2-183B6'-153B6'-153B6.2-163B2I3Construction FfreServiceWater103NABlindFlangeNANAInsideCCNA6'-175Containment SprayPusyIAReactorCoolantPuxyhSealWaterInlet105106862A306kCheckCheckNAOutsideCNhInside00NA6'-183B6'-193BSusyhDfschargetoWasteHoldupTankReactorCoolantPumpSealWaterReturnLfneandExcessLetdovntoVCT10710817231728313Diaphraga Dfaphraga AfrhirMotorStatusStatusBothOutsideOutsideOutside000/C0/C0/CCCFCYesFCYesAIYes606.2202606'"20260F2-218,6Containment SprayPuryIB109862BCheckNhNAOutsideCNh6.2223BendAIFallsAsIsAOVAirOperatedValveC~ClosedCIS~Contafnment Isolation SignalCVCheckValveFC~FallsClosedFOFailsOpenLC~LockedClosedMQVMV00/CR/CStatusSOVMoto~rated Valve~ManualValve~OpenOpenorClosed~Red/CreenLightonMainControlBoardWhiteStatusLight,SolenoidOperatedValveReferstopositionfsuediately follovfng receiptofcontainment isolation signalandcontainment ventilation fsolation signal.sThemaxfxaaisolation timedoesnotincludedieselstarttimenorinstrument delaytfme.'eferstoclassesdefinedinSection6.2.6.6.2.
3.3.2.6 a "No"   for valve    745 ($ 124a) . The Maximum Isolation    Time column was also changed from "60" to "NA". These changes are justified per Reference 2.16.
sNotesonlyusedtosupplement Section6.2.6.6.2.
3.3.2.7        Several penetrations had valves added to the table, deleted, or both. These are described below by penetration number.
SafetyAnalysis'I"NSL-'.OO,OO-SA024 Page14aRevision1
(a) Penetration 103 Valve 5129 was deleted from the table and replaced by a Blind Flange.
-13CONTAIPENETRATIONS ANDIPIPING~SatanReactorCoolantPurpBSealNaterInletPenetratfon No.110a(topiValveNo.304BValveCheckPositionValveIndication PositionOperatorInControlRelativetoHomalRoonContafnnent OHeratfon NANhInsMe0PositionAtColdlxxaadfatePaverTriponShutdovnPostaccfdentv FailureCIS0~CNANhMaxixixaIsolation TfxeDFSARNotes6.2-233BSafetyInlectfon TestLfne110b<bottoni879GlobeManualNoOutsideLCLCNA6~2-151ResidualHea'tRenovaltoBColdLeg720959GateGlobeMotorAlrR/CStatusInsideOutsfde00/CAIFC6.2-246.2-243B3B4~7g8I4,1LetdowntoNonregenerative HeatExchanger SafetyIn)ection PuxpIADischarge StandbyAuxfI-faryFeedwater LinetoSteanGenerator lh112113119200A200B202371421810A889A9104A9105AGlobeGloboClobeGlobeGlobeCheckCheckStop-Check CheckAfrAlrAirAirAlrMotorNAR/GR/GR/GBothR/CNANAR/GNhInsideInsideInsideOutsideInsideOutsideOutsideOutsMeInside0/C0/CC00CCCCC00/CCCCCCAINAYesTesYesYesYesNoNh60$060$03B3B6.2-156.2156.2266.2-266~225I$e225I6~22516.2-25I$.2-25I101010NitrogentohccuxaIlators Pressurlxer ReliefTanktoGasAnalyxerNitrogentoPressurixer ReliefTankMakeupRatertoPressurixer ReliefTankContefunestPressureTransnftt@r PT945120a120b121a121b121c8464623539546528547504529PT9451819AGlobeCheckGlobeGlobeCheckGlobeDfaphragn CheckNAGlobeAirNAAirManualNAlanualAirNANAManualBothNASta'xusNoNANoBothNAOutsideInsideOutsideOutsideInsideOutsideOutsideInsideOutsideOutsMeC0/CC0/C0/C'/C,0/C00/COICOICOICCCC0CCFCYesNAFCYesNhNhFCYesNANh60Nh60NA6~2213A$.2-273A6~2-282F2-2426.2-293A$.2293A6~2-303A$.2-303A62-3126.23121213Contafnnent PressureTransxLit'tox'T946 121dF2946NhNANAOutsideNhNA1819BGlobeManualNoOutside006.2-31262-31213StandbyAuxfl-faryI'eedvater LinetoSteanGenerator IB123ltopl9104B91058Stop-Check CheckMotorNhOutsideInsideCCCCAINhNA6.2-26Nh6.2-264SafetyAnalysisNSL-,OOOO-SA024 Page14bRevision1Date10390
This change enabled the elimination of the previous note of "No longer in use" that was associated with this penetration. The penetration now reflects the current configuration. The use of the Blind Flange is consistent with the previous locked-closed manual valve.
(b) Penetration 111 Added valve 959. The addition of this valve to the table ensures that all valves receiving a containment isolation signal are listed. This valve was previously missing from the table, but credit was not taken for the valve during the SEP (see Reference 2.7) . Consequently, this is not considered an actual isolation valve and is not tested per Appendix J.
(c) Penetration 112 - Valves 204A and 821 were deleted .-and replaced with valves 200A, 200B, and 202. Valve 427 was also added.             The addition of these valves enables explicit compliance with GDC 55 versus the use of the two redundant isolation valves. These new valves are included in the current IST program (see Reference 2.19).
(d)   123 (bottom) Added valve 1600A.             See explanation for 3.3.2.7 (b) above.
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(e)   Penetration 141 Deleted valve 851A and added valve 1813A. Valve 851A does not meet the selection criteria for 10CFR50 Appendix J, Section IIH, items 1 through 4.
Consequently, the valve was deleted from the table. Valve 1813A was previously missing from the table. This valve is locked-closed with its breaker locked open.
(f) 'enetration 142 Deleted valve 851B and added valve 1813B. See explanation for 3.3.2.7 (e) above.
(g)   Penetration 205 Added valve 955. See explanation for 3.3.2.7 (b) above.
(h)   Penetration 206a Added valve 953. See explanation for 3.3.2.7 (b) above.
(i)   Penetration 207a Added valve 951. See explanation for 3.3.2.7 (b) above.
(j)   Penetration 210 Added valves 10214S1 and 10215S1. These valves were previously missing from the table, but receive an isolation signal.
3.3.2.8        Penetration 332b Deleted entire penetration branch from the table. This penetration branch contains double isolation, fits the criteria as a test connection, and performs no active function.
Therefore, there is no requirement to test the valves as containment isolation valves.
Consequently, this penetration branch was removed from the table.
3.3.3     Several updates were made to the UFSAR table to ensure consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.
These changes are typically only clarifications. The significant changes are described below.
3.3.3.1        Notes  7 and 19 were added  to ensure that consistency is maintained between Technical Specification Table 3.6-1 and the UFSAR Table.
These notes mainly provide clarification and do not involve a technical change.
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3.3.3.2        The Maximum      Isolat'ion Time of several valves was changed    to  a more conservative    duration. That is, the time    was changed from "NA"     to either "3" seconds for solenoid valves, or "60" seconds for AOVs and MOVs.       (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) The UFSAR Table now identifies an isolation time for all valves receiving a containment isolation signal.
Valves (and penetration 4) in this category include: 1787 ($ 129), 10211S1 ($ 202), 10213S1
($ 202), 966C ($ 205), 966B ($ 206a), 5735 ($ 206b),
966A ($ 207a), 5736 ($ 207b), 10214S ($ 210), 10215S1
($ 210) / 10205S1 ($ 304) g 10209S1 ($ 304) g 1597
($ 305a), 1599 ($ 305b), and 8418 ($ 324) .
3.3.3.3        The Maximum      Isolation  Time of several valves was changed    to  a  less conservative duration. There are three categories of valves which meet this criteria (organized by justification):
(a)   749A   (f127), 749B ($ 128) These valves do not receive a containment isolation signal.
Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.
(b)   5869 ($ 204) This valve does not require an isolation time since the associated blind flange acts as the isolation boundary. See, UFSAR Table Note 19.     Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.
(c)   7970 ($ 132), 7971 ($ 132), 7478 (f309), and 7445 (f309) The isolation time for these butterfly valves was changed from "2" seconds to "3" seconds.     Technical Specification Table 3.6-1 allows    five seconds with instrument delay. However, the Maximum Isolation Time column does not include instrument delay per Note "b". The instrument delay time for these valves is approximately 2 seconds. Consequently, the valve isolation time was changed to "3" seconds.
3.4      A review of the design basis events analyzed in the Ginna Station    UFSAR and,the events requiring analysis as described in USNRC Reg. Guide 1.70 was performed.
The events related to this UFSAR change are:
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(a) Fires (b) Seismic Events (c) Radiological Release  From a Subsystem or Component (d) Decrease in Reactor Coolant Inventory (e) Events Initiating a Safety Injection Signal 3.4.1      The changes as described in Section 3.3 and Attachment B  do not affect the capability of the containment isolation system to perform its function during a fire.
The changes  to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. No fire barriers are affected by these changes, nor is there any increase in area fire loadings.
3.4.2      The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a seismic event. The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. No changes are made with respect to the seismic design of the affected penetrations.
3.4.3,
    ~  ~      The changes  as described in Section 3.3 and Attachment B do  not affect the capability of the containment isolation system to respond to a radiological release within containment. The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. Consequently, the containment isolation system is still within its design basis limits.
3.4.4    The changes as    described in Section 3.3 and Attachment B  do not create  the potential for the affected penetrations to cause a decrease in RCS inventory (i.e., a loss-of-coolant-accident) . The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. No changes were made to capability of the parent systems (e.g., Residual Heat Removal) to perform their function. Consequently, the containment isolation system and associated parent systems remain within their design basis limits.
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3.4.5     Events which  initi'ate Safety Injection also result in the need for containment isolation. The changes to the UFSAR Table do not affect the capability of the containment isolation system to perform its function.
All changes were rev'iewed to ensure continued compliance with the design basis for the containment isolation system and the Ginna Station Licensing Basis.
4.0        Preliminar  Safet  Evaluation 4.1       The proposed UFSAR changes    will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. The changes to the UFSAR Table are to correct typographical errors, provide additional clarification, and update the table to reflect actual plant conditions. All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.
Thus, there is no change in system function, nor a reduction in system reliability. The containment isolation and parent systems will remain within their design  limits.
4.2        The proposed UFSAR changes  will  not increase the consequences of an accident previously evaluated in      the UFSAR. The modification does not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.'6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus,- the function and capability of the containment isolation system to isolate any radiological release within containment is not degraded.
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4.3          The proposed UFSAR changes    will not    increase the probability of occurrence of    a  malfunction of equipment important to safety previously evaluated in the UFSAR.
All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the changes do not degrade the performance of the containment isolation system, nor the associated parent systems.
4.4          The proposed UFSAR changes    will not  increase the consequences of a malfunction      of equipment important to
          ,. safety previously evaluated in the UFSAR. The changes do not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the function and capability of the containment isolation system to isolate any radiological release from containment is not degraded. =
4.5          The proposed UFSAR changes    will not  create the possibility of an accident of a different type than any previously evaluated in the UFSAR. These changes are mainly clarifications and updates to reflect current plant conditions. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.
All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. There are no adverse affects upon other systems, nor any new failure modes induced.
4.6          The proposed UFSAR changes    will not  create the possibility of  a different  type of malfunction of equipment important to safety than any previously evaluated in the UFSAR.     The additions and deletions to the table are acceptable as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8, The changes do not degrade the containment isolation or associated parent systems.
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4.7        The proposed UFSAR changes  will not reduce any margin of safety as defined in the basis of any technical specification. The functions and characteristics of the containment isolation system remains unchanged.
However, changes are made to valve isolation times and the valves listed for specific penetrations. These changes will be addressed in the Amendment Request to remove Table 3.6-1 from the Technical Specifications and reference this updated UFSAR table.
4.8        Based on the above analysis, that:
it has been determined (a)  The margins of safety during normal operation and transient conditions anticipated during the life of the plant has not been reduced, and (b)  The adequacy of structures, systems, and components provided for the prevention of accidents and for the mitigation of the consequences of accidents have not been affected.
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2-13 CONTAI              PENETRATIONS AND I          PIPINC Position                            Position At                            Maxisans Valve    Indication    Position                                                      Isolation Penetration    Valve    Valve      Operator  In Control Relative to    Normal  Cold      Ixaedf ate                                    UFSAR                Notes
~Sstea                  No.         No.                                                             Shutdovn  Postaccfdent~
Steam Cenerator                          Blind Flanges                              Both              0/C            C                                          (add)    5          I~ 2 Inspection/
Maintenance Fuel Transfer            29              Blind Flange                              Inside              0/C                                                    6  '-13    5          2I 3 Tube Charging Line            100        370B      Check                                Inside                                                                      6.2-18    3B to  B Loop Safety                  101        870B      Check                                Outside                            0                                        6  '-15    3B Infection Pury                      889B      Check                                Outside                            0                                        6  '-15    3B IB Discharge Alternate                102        3838      Check                                 Inside                            C                                        6.2-16    3B Charging to A Cold Leg Construction            103          NA  Blind Flange        NA        NA        Inside      C                    C                              NA        6 '-17      5 Ffre Service Water Containment              105        8 62A    Check                      NA        Outside      C                    0                              NA        6 '-18    3B Spray Pusy IA Reactor Coolant          106        306k      Check                      Nh        Inside      0                                                              6 '-19    3B Puxy h Seal Water  Inlet Susy h Dfs              107        1723  Diaphraga        Afr      Status      Outside      0      0/C            C      FC        Yes          60        6.2 20      2 charge to Waste                    1728  Dfaphraga        hir      Status      Outside      0      0/C            C      FC        Yes          60        6 '"20      2 Holdup Tank Reactor Coolant          108        313                    Motor      Both      Outside              0/C                    AI        Yes          60        F  2-21              8,  6 Pump Seal Water Return Lfne and Excess Letdovn to  VCT Containment              109        862B      Check          Nh        NA        Outside      C                                                    Nh        6.2 22    3B Spray Pury IB end AI      Falls As Is                            MQV      Moto~rated      Valve                                                      Refers to position fsuediately follovfng receipt of containment AOV    Air Operated Valve                    MV    ~ Manual Valve                                                                isolation signal and containment ventilation fsolation signal.
C    ~  Closed                                0      ~ Open                                                                      s The maxfxaa  isolation time does not include diesel start time CIS ~  Contafnment Isolation Signal          0/C      Open or Closed                                                            nor instrument delay tfme.
CV      Check Valve                            R/C    ~ Red /  Creen Light on Main Control Board                                'efers    to classes  defined in Section 6.2.6.6.2.
s Notes only used to supplement Section 6.2.6.6.2.
FC  ~  Falls Closed                          Status    White Status Light, FO      Fails Open                            SOV      Solenoid Operated Valve LC  ~ Locked  Closed Safety Analysis                                                                                                                                      Revision                1
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                                                                                                                                                                                              -13 CONTAI              PENETRATIONS AND I          PIPING Position                              Position At                          Maxi xixa Valve  Indication Position                                                          Isolation Penetratfon    Valve    Valve  Operator In Control Relative to  Homal      Cold        lxxaadf ate  Paver
  ~Satan                          No.        No.                        Roon    Contafnnent  OHeratfon Shutdovn    Postaccfdentv Failure Trip  on  Tfxe        DFSAR                Notes CIS Reactor Coolant            110a  (topi  304B    Check    NA        Nh      InsMe        0        0~            C Purp B Seal                                                                                                                        NA    Nh                  6.2-23    3B Nater            Inlet Safety                    110b <bottoni    879    Globe  Manual      No      Outside      LC        LC Inlectfon Test                                                                                                                                      NA      6 ~ 2-15    1 Lfne Residual Hea't                              720      Gate    Motor      R/C        Inside                  0                        AI Renoval            to B                    959    Globe    Alr      Status                                                                                  6.2-24    3B        4 ~ 7g 8 Outs fde                0/C                        FC                        6.2-24 Cold Leg                                                                                                                                                                  3B          4,  1 I
Letdown            to          112      200A      Globe    Afr      R/G        Inside      0/C Nonregenerative                            200B      Globo    Alr      R/G        Inside      0/C C            C                Yes        60      6~  225    I            10 Heat Exchanger                              202    Clobe    Air      R/G        Inside        C C
C C                Tes        $0      $ e2 25    I            10 371    Globe    Air      Both    Outside        0        0 C                Yes        60      6~ 225      1            10 421    Globe    Alr      R/C      Inside        0      0/C C                Yes        $0      6.2-25      I C                Yes                  $ .2-25    I Safety                          113      810A    Check                NA      Outside        C                                                            6.2-15 In)ection            Puxp                889A    Check                NA      Outside        C 3B IA Discharge                                                                                                                                                  6.2 15    3B Standby Auxf I-                  119      9104A  Stop-Check  Motor      R/G      OutsMe                                            AI fary Feedwater                            9105A                                                                                            No                6.2 26 Check    NA        Nh      Inside                                          NA      Nh                6.2-26 Line to Stean Generator lh Nitrogen to                      120a        846    Globe    Air      Both      Outside        C        0/C            C        FC    Yes        60 hccuxaIlators                              4623                                                                                                              6 ~ 2 21  3A Check    NA        NA      Inside      0/C            '/C
                                                                                                                ,          C        NA                Nh      $ .2-27    3A Pressurlxer                      120b        539    Globe    Air    Sta'xus    Outside                0/C Relief            Tank  to                  546    Globe  Manual C        FC    Yes                6 ~ 2-28    2 No      Outside                  0              0        Nh      Nh                F 2-24 Gas            Analyxer                                                                                                                                                    2 Nitrogen to                      121a      528      Check    NA        NA      Inside                0/C                                                  6.2-29 Pressurixer                                547      Globe  lanual      No      Outside                OIC 3A Relief            Tank                                                                                                                                        $ .2 29    3A            12 Makeup            Rater to      121b      504    Dfaphragn  Air      Both      Outside        C        OIC            C Pressurixer                                529 FC    Yes        60      6 ~ 2-30  3A Check    NA        NA        Inside      0/C      OIC            C        NA    Nh                  $ .2-30 Relief            Tank                                                                                                                              NA                  3A Conte funest                      121c      PT945      NA      NA                Outside Pressure                                    1819A    Globe                                                                                                    6 2-31      2            13 Manual              Outs Me                                                                      6.2 31      2 Transnftt@r PT945 Contafnnent                      121d      F2946      Nh      NA        NA      Outside      Nh        NA Pressure                                    1819B    Globe  Manual                                                                                            6.2-31      2            13 No      Outside        0        0                                                  6 2-31    2 TransxLit'tox'T946 Standby              Auxfl-  123  ltopl  9104 B Stop-Check Motor                Outside        C        C                        AI                NA      6.2-26 fary I'eedvater                            91058    Check    Nh                Inside        C        C                        Nh                Nh      6.2-26 Line to Stean                                                                                                                                                              4 Generator IB Safety Analysis                                                                                                                            Revision              1 Page 14b NSL-,OOOO-SA024                                                                                                                              Date            10 3 90
 
)
)
CONTAIAND~2-13~PENETRATION~a PIPIhG~SatcmcPenetration ValveNo.ValvePositionValveIndication PositionOperatorInControlRelativetoHomal~TRocvm,Contafnacent OEeratfon PosftfonAtColdIacaediate PoverTriponShutdovnpostaccfdcntr FailureCI8MaxfaaxaIsolation TilacUFSAR~FireNotesReactorCoolantDrainTanktoGasAnalyzerLineExcessLetdovnBeatExchanger CoolingWaterSupply4ReturnPostaccfdcnt AfrSag>letoCFanComponent CoolingWaterfraaReactorCoolantPump1B123(button)124a124b1251600A1655178974374515691571157215747598GlobeGlobeDiaphragca CheckGlobeDfaphragca Dfsphragca Dfaphragrc Dfaphragal CateSolenoidManualhfrQhirManualManualManualManualHotorNoNoStatusQRIGR/COutsfdeOutsideOutsideInsideOutsideOutsfdeOutsMeOutsideOutsfdeOutside000000/C00/CCCLCIC,LCLCrCrC0CCC0AIYclsNAYesNANoNoNA606.2-326.2-326'-326.2-33.6.2-336'-3456.23456.2-3456.2-3456.2-35414Ccxcponent CoolingWaterfreesReactorCoolantPumpIA126759AGateMotorR/COutside0AINoNh6.2<<36Componen't CoolingNatertoReactorCoolantPumplh127749A750ACateCheckHotorNAOutsideInside00CC00AINAQ6.2-374Q6.2-37Cccmponeat CoolingWatertoReactorCoolant~1BReactorCoolantDrainTankandPressurizer RelistTanktoContainnent VentReader128129749875081713178617871793CateCheckCheckDfaphragal Dfaphragca Dfaphragal MotorNANAhirAirManualNASta'tusS'ta'tuaNoOutsMeInsideOutsideOutsfdeOutsideOutside00C00LCCC0/CCC0/C00CCCLCAINANoNAQ6'-38Q6'-384NANANA6.2-393AFCYes606'-393AFCYes606.2-393ANhNANA6~2-3S3A12Component CoolingWaterfrcxaReactorSupportCooling130-814GateMotorBothOutside0AIYes606.2-404Cc~nentCoolingNatertoReam'torSupportCoolingContainment Nfnf-Purge Exhaust131813CateHotorBothOutside001327970Butterfly hirBothInside0/COIC7971Buttertly AlrBothOutsMeC0/CCCAIYesFCYesFCYes606.2-40436.2-41536.2-415',SafetyAnal'ysis rNSL-0000-SA024 Page14cRevision1
                                                                                                                                                                                ~ 2-13   ~
CONTAI          PENETRATION~a AND        PIPIhG Position                              Posftfon At                                f Max aaxa Valve  Indication Position                                                          Isolation Penetration    Valve    Valve    Operator In Control Relative to Homal        Cold        Iacaediate  Pover              Tilac
~Sat cmc                            No.             ~T          Rocvm, Contafnacent OEeratfon Shutdovn    postaccfdcntr        Trip  on              UFSAR              Notes Failure  CI8                  ~Fi  re Reactor Coolant  123  (button)   1600A    Globe    Solenoid      No      Outsfde        0      0/C Drain Tank to                      1655    Globe    Manual C                Ycls        NA      6.2-32 Analyzer No      Outside        0        0              0                NA                  6.2-32 Gas Line 1789  Diaphragca    hfr    Status    Outside        0      0/C            C                Yes        60      6 '-32 Excess Letdovn        124a          743    Check      Q          Q        Inside        0 Beat Exchanger                      745    Globe      hi r C              C                NA                  6.2-33.
RIG      Outside        0        C              C                No                  6.2-33 Cooling Water                                                                                                                                                                  14 Supply    4 Return Postaccfdcnt          124b        1569 Dfaphragca Afr Sag>le to    C Manual              Outs fde                LC                                                    6 '-34      5 Fan 1571 1572 Dfsphragca Dfaphragrc Manual Manual OutsMe Outside IC,                                                  6.2 34      5 LC                                                    6.2-34      5 1574 Dfaphragal  Manual              Outsfde                  LC                                                    6.2-34      5 r
Component              125        7598    Cate      Hotor      R/C    Outside                  C              0        AI    No                  6.2-35 Cooling Water                                                                                                                                                        4 fraa Reactor                                                                                          r Coolant Pump 1B Ccxcponent              126        759A    Gate      Motor      R/C    Outside        0 Cooling Water                                                                                                                AI      No        Nh      6.2<<36 frees Reactor Coolant Pump IA Componen't             127        749A    Cate      Hotor              Outside        0 Cooling Nater                      750A    Check                          Inside        0 C            0        AI                Q        6.2-37      4 to Reactor                                              NA                                          C            0        NA                Q        6.2-37 Coolant Pump lh Cccmponeat              128        7498    Cate      Motor Cooling Water OutsMe          0        C              0        AI      No        Q        6 '-38 to Reactor Coolant    ~
Reactor Coolant 1B 129 7508 1713 Check Check NA                Inside        0        C              0        NA      NA        Q        6 '-38      4 NA        NA      Outside        C        0/C            C        NA      NA                  6. 2-39 Drain Tank and Pressurizer 1786  Dfaphragal    hir    Sta'tus    Outsfde        0        C              C        FC    Yes NA 60      6 '-39 3A 3A Relist 1787  Dfaphragca    Air    S'ta'tua  Outside        0        C              C        FC    Yes                  6.2-39 Tank to                  1793  Dfaphragal  Manual      No      Outside        LC      0/C            LC 60                  3A Containnent                                                                                                                  Nh      NA        NA      6 ~ 2-3S  3A        12 Vent Reader Component              130        814    Gate      Motor    Both      Outside        0 Cooling Water                                                                                                                AI    Yes        60      6.2-40      4 frcxa Reactor Support Cooling Cc~nent                131          813    Cate      Hotor    Both      Outside        0        0                        AI Cooling Nater                                                                                                                      Yes        60      6.2-40      4 to Ream'tor Support Cooling Containment Nfnf-Purge 132        7970  Butterfly    hir      Both      Inside      0/C      OIC              C        FC    Yes        3        6.2-41    5 Exhaust 7971  Buttertly    Alr      Both      OutsMe        C      0/C              C        FC    Yes        3        6.2-41    5
  ',Safety Anal'ysis                                                                                                                                 Revision            1 r
Page 14c NSL-0000-SA024
 
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213CONTAIPENETRATION<
2 13 CONTAI                  PENETRATION<
ANDI~PIPING~zstenResidualBeatRemovalPumpSuctfonfromAHot,LegPenetration No.140ValveNo.701ValveValveOperatorGateHotorPositionIndication PosftfonInControlRelativetoRoomContainment R/CInsidePositionAtNormalColdImnediate FeverOHeratfon ShutdovnPostaccidcnt'ailure 0CAITriponCISKaxfmsusImoistfonTimeOFSARNotes~FfreClasssSeeendoftable~7i86.2-421ResidualHeatRemovalNo.1PumpSuctionfromSumpB14185th1813ACateCateHotorHotorR/0OutsideCCR/COutsideC0/C0CAINoNh6.2-425AINoNA6.2-425158ResidualHeatRemovalNo.2PumpSuctionfromSu~B142SSOBGateHotorR/COutsideCC1813BGateHotorR/0OutsideC0/CAIAINA6~2-425NA6.2-425158ReactorCoolantDrainTantDischarge LfneReactorCompartment CoolingOnitshandB143201(top)201(bottom)1003A1003B172147574636DIaphragnDiaphragm Diaphragm Butterfly Butterfly AirAfrAlrHanualHanualStatusStatusStatusNoNoOutsideOutsideOutsideOutsideOutside000000/C0
AND I        ~  PIPING Position                              Position At                        Kaxfmsus Valve  Indication Posftfon                                                      Imoist fon Penetration  Valve      Valve      Operator In Control Relative to  Normal    Cold      Imnediate    Fever Trip  on  Time        OFSAR                  Notes
~zs ten                    No.        No.                            Room    Containment OHeratfon Shutdovn    Postaccidcnt'ailure  CIS                ~Ff  re Classs    See end  of table    ~
Residual Beat              140        701      Gate        Hotor      R/C      Inside                0            C        AI                        6.2-42      1            7i    8 Removal Pump Suctfon from    A Hot, Leg Residual Heat              141      85th      Cate        Hotor      R/0    Outside      C        C            0        AI    No        Nh      6.2-42      5              15 Removal No. 1                    1813A      Cate        Hotor      R/C      Outside      C      0/C            C          AI    No        NA      6.2-42      5              8 Pump  Suction from  Sump B Residual Heat              142      SSOB      Gate        Hotor      R/C      Outside      C        C                      AI              NA      6 ~ 2-42    5              15 Removal No. 2                      1813B      Gate        Hotor      R/0      Outside      C      0/C                      AI              NA      6.2-42      5              8 Pump  Suction from Su~    B Reactor Coolant            143      1003A  DIa phragn      Air    Status    Outside      0      0/C            C                Yes        60    '.2-43        2 Drain Tant                          1003B  Diaphragm        Afr    Status    Outside      0      0/C            C                Yes        60      6 ~ 2-43    2 Discharge Lfne                      1721  Diaphragm        Alr    Status    Outside      0        0            C                Yes        60      6.2-42    2 Reactor               


49Penetration 207a-(1)ChangedMaximumIsolation Timefrom"NA"to"60"forvalve966A;(2)Addedvalve951andnecessary information; (3)ChangedPositionIndication inControlRoomfrom"Yes"to"Status"forvalve966A;(4)ChangedPositionAtNormal0erationandPositionAtColdShutdownfrom"0/C"to"C"forvalve966A;(5)GlobalNotes3and4forvalve956F;(6)Reordered penetration valves.(1)Consistency withTechnical Specification Table3.6-1.(2)Valvereceivescontainment isolation signalandwaspreviously missingfromthetable.(3)Minorclarification only.Notechnical change.(4)Updateforbetterrepresentation ofsystemconfiguration.
Removed  notes associated with Technical Specification 4.4.2.4 section a. Deleted Mini-purge valves have been installed so the Technical Specification can be considered reference to section d.         effective. Section d will be removed from Technical Specifications. No technical change.
Samplingsystemnormallyisolated.
: 11. Added steam  generator        Addition of this penetration inspection/maintenance          provides testing criteria similar penetration to Technical        to the equipment hatch and Specification 4.4.2.4           containment air locks.
(5)Notechnical change.(6)Valvesnowinnumericorder.Notechnical change.50.Penetration 207b-(1)ChangedMaximumIsolation Timefrom"NA"to"60"forvalve5736;(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Status"forvalve5736;(3)ChangedPositionAtNormal0erationfrom"0/C"to"0"forvalve5736;(4)ChangedPositionAtColdShutdownfrom"0/C"to"C"forvalve5736;(5)GlobalNotes3and4for5734;(6)Reordered penetration valves.(1)Consistency withTechnical Specification Table3.6-1.(2)Minorclarification only.Notechnical change.(3)(4)Updateforbetterrepresentation ofsystemconfiguration.
section b.
(5)Notechnical change.(6)Valvesnowinnumericorder.Notechnical change.51.Penetration 209top-(1)GlobalNotes3and4;(2)Reordered penetration valves.(1)Notechnical change.(2)Valveordernowconsistent withotherpenetrations.
: 12. Removed Technical              Blind flanges have been installed Specification 4.4.2.4           so the Technical Specification can section d and associated        be considered effective. No note.                           technical change.
Notechnical change.52.Penetration 209bottom
1 3. Changed Reference    from Table Valve  listing remains in a 3.6-1 to UFSAR 6.2-13 in        licensee controlled document under section 4.4.5.1.               10CFR50.59 program.
-(1)GlobalNotes3and4;(2)Reordered penetration valves.(1)Notechnical change.(2)Valveordernowconsistent withotherpenetrations.
: 14. Changed Reference    from Table Valve  listing remains in a 3.6-1 to UFSAR 6.2-13 in        licensee controlled document under section 4.4.6.2.               10CFR50.59 program.
Notechnical change.SafetyAnalysisNSL-0000-SA024 Page32Revision1 53.Penetration 210-(1)Added"A&B"before"Reoombiners" under~3stem;(2)AddedPositionIndication inControlRoomto"Status"forallsolenoidvalves;(3)Added"Yes"under~TrionCISforallsolenoidvalves;(4)Addedvalves10214S1and10215Sandnecessary information; (5)ChangedPositionAtPowerFailurefrom"-"to"FC"forallsolenoidvalves;(6)ChangedPositionAtNormal0erationColdShutdownImmediate Postaccident from"C"to"LC"for1080A;(7)GlobalNotes3and4forvalve1080A;(8)ChangedValveNo.forIV-2AandIV-2Bto10214Sand10215S1,respectively; (9)AddedNote18tosolenoidvalves;(10)ChangedMaximumIsolation Timefrom"NA"to"3"forallsolenoidvalves.(1)Consistency withTechnical Specification Table3.6-1.(2)Minorclarification only.Notechnical change.(3)Correction oftypographical omission.
Notechnical change.(4)Valvereceivecontainment isolation signalandwaspreviously missingfromthetable.(5)Updateforbetterrepresentation ofsystemconfiguration.
Valvesreceivecontainment isolation signal.(6)Consistency withGinnaAdministrative Control.(7)Notechnical change.(8)Updatetonewvalvenumberonly.Notechnical change.(9)Notechnical change.(10)Correction oftypographical error.Notechnical change.-54.Penetration 300-(1)AddedNote19forbothvalveandflange;(2)AddedNote2toBlindFlange;(3)GlobalNote1forBlindFlange;(4)ChangedPositionAtNormal0erationfrom"0/C"to"C"forvalve5879;(5)ChangedPositionAtColdShutdownfrom"0"to"0/C"forvalve5879;(1)Notechnical change.(2)Consistency withTechnical Specifications.
Notechnical change.(3)(4)Updateforbetterrepresentation ofsystemconfiguration.
Penetration onlyusedduringcoldshutdownconditions.
Mini-purge systemnowusedinplaceofpurgesystem.SafetyAnalysisNSL-0000-SA024 Page33Revision0Date092490 55.Penetration 301-(1)GlobalNotes3and4;(2)ChangedPositionAtColdShutdownandPositionAtImmediate Postaccident from"0"to"LC"forbothvalves;(3)AddedNote5tobothvalves.(1)Notechnical change.(2)Consistency withGinnaAdministrative Control.(3)Notechnical change.56.Penetration 303-(1)GlobalNotes3and4;(2)ChangedPositionAtColdShutdownandPositionAtImmediate Postaccident from"0"to"LC"forbothvalves;(3)AddedNote5tobothvalves;(4)Changedbothvalvesfrom"Diaphragm" to"Globe";(5)Reordered penetration valves.(1)Notechnical change.(2)Consistency withGinnaAdministrative Control.(3)Notechnical change.(4)Correction oftypographical error.Notechnical change.(5)Valvesnowinnumericorder.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page34Revision0Date092490 57.Penetration 304-(1)Changedvalves1076Aand1084Afrom"Solenoid" to"Diaphragm";
(2)ChangedPositionAtNormal0erationColdShutdownandImmediate Postaccident from"C"to"LC"forvalves1076Aand1084A;(3)Added"No"underPositionIndication InControlRoomforvalves1076Aand1084A;(4)GlobalNotes3and4forvalves1076Aand1084A;(5)ChangedValveNo.forIV-3AandIV-5Ato10205S1and10209S1,respectively; (6)Added"Status"underPositionIndication inControlRoomforvalves10205Sl&10209S1;(7)ChangedPositionAtPowerFailurefrom"-"to"FC"forvalves10205Sland10209S1;(8)Changed~Tri'nCISfrom"No"to"Yes"forvalve10205S1and10209S1;(9)AddedNote17forvalves10205Sland10209S1;(10)ChangedMaximumIsolation Timefrom"NA"to"3"forvalves10205S1and10209S1;(11)Reordered penetration valves.(1)Correction oftypographical error.Notechnical change.(2)Consistency withGinnaAdministrative Control.(3)Correction oftypographical omission.
Notechnical change.(4)Notechnical change.(5)Updatetonewvalvenumberonly.Notechnical change.(6)Minorclarification only.Notechnical change.(7)(8)Updateforbetterrepresentation ofsystemconfiguration.
Valvesreceivecontainment isolation signal.(9)Notechnical change.(10)Correction oftypographical error.Notechnical change.(11)Valvesnowinnumericorder.Notechnical change.58.Penetration 305a(bottom)-(1)Changed~Sstemto"Containment AirSampleOut";(2)ChangedMaximumIsolation Timefrom"NA"to"60"forvalve1597;(3)Changedvalve1596from"Diaphragm" to"Globe";(4)GlobalNotes3and4forvalve1597;(5)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forvalve1597;(6)Reordered penetration valves.(1)Consistency withUFSARDrawingTitle.Notechnical change.(2)Consistency withTechnical Specification Table3.6-1.(3)Correction oftypographical error.Notechnical change.(4)Notechnical change.(5)Minorclarification only.Notechnical change.(6)Valvesnowinnumericorder.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page35Revision0 59.Penetration 305b(top)-(1)Changed~Sstemto"Containment AirSampleInlet";(2)ChangedMaximumIsolation Timefrom"NA"to"60"forvalve1599;(3)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forvalves1598and1599;(4)Reordered penetration valves.(1)Consistency withUFSARDrawingTitle.(2)Consistency withTechnical Specification Table3.6-1.(3)Minorclarification only.Notechnical change.(4)Valvesnowinnumericorder.Notechnical change.60.Penetration 305c-<1)Changed~Sstemto"Containment AirSamplePostaccident";
forallsixvalves;(3)ChangedPositionAtColdShutdownandPositionAtImmediate Postaccident from"C"to"LC"forallsixvalves;(4)GlobalNotes3and4;(5)Reordered penetration valves.(1)Consistency withUFSARDrawingTitle.(2)Correction oftypographical omission.
Notechnical change.(3)Consistency withGinnaAdministrative Control.(4)Notechnical change.(5)Valvesnowinnumericorder.Notechnical change.61.Penetration 307-(1)SwitchedValveNo.forvalves9227and9229;(2)Added"Gate"-underValve0eratorTeforvalve9227;(3)GlobalNotes1,2,and4forvalve9229;(4)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forvalve9227.(1)Correction oftypographical error.Notechnical change.(2)Correction oftypographical omission.
Notechnical change.(3)Notechnical change.(4)Minorclarification only.Notechnical change.62.Penetration 308-(1)ChangedValveNo.to4629;(2)GlobalNotes3and4;(3)ChangedPositionAtNormal0erationandPositionAtImmediate Postaccident from"0"to"LO";(4)ChangedPositionAtColdShutdownfrom"0"to"0/C"(5)AddedNote17.(1)Correction oftypographical error.Notechnical change.(2)Notechnical change.(3)Consistency withGinnaAdministrative Control.(4)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdown.
(5)Notechnical change.SafetyAnalysisNSL-0000-SA024 Page36Revision0
:,P><><~!~
A.,gyes-.gory
~gg,~:>FQKQ<,.4idsi, 63.Penetration 309-(1)ChangedMaximumIsolation Timefrom"2"to"3"forbothvalves;(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forbothvalves;(3)Reordered penetration valves.(1)Consistency withTechnical Specifications.
Valvedesignallowsclosureasrapidas2(two)seconds.MinimumclosuretimerequiredbyTechnical Specifications is5(five)seconds.(2)Minorclarification only.Notechnical change.(3)Valvesnowinnumericorder.Notechnical change.64.Penetration 310a-(1)Changedvalve7141from"Diaphragm" to"Gate";(2)ChangedPositionAtImmediate Postaccident from"C"to"LC"forvalve7141;(3)GlobalNotes3and4forvalve7141;(4)GlobalNotes1,2,and4forvalve7226;(5)Reordered penetration valves.(1)Correction oftypographical error.Notechnical change.(2)Consistency withGinnaAdministrative Control.(3)(4)Notechnical change.(5)Valvesnowinnumericorder.Notechnical change.65.Penetration 310b-(1)Changedvalve5392from"Diaphragm" to"Globe";(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forvalve5392;(3)ChangedPositionAtColdShutdownfrom"C"to"0"forvalve5393;(4)GlobalNotes1,2,and4for5393;(5)Added"0"underPositionAtColdShutdownforvalve5392;(6)Added"C"underPositionAtImmediate Postaccident forvalve5392;(7)ChangedPositionatPowerFailurefrom"-"to"FC"forvalve5392;(8)Reordered penetration valves.(1)Correction oftypographical error.Notechnical change.(2)Minorclarification only.Notechnical change.(3)Updateforbetterrepresentation ofsystemconfiguration sinceIAisusedduringcoldshutdownconditions.
(4)Notechnical change.(5)(6)(7)Updateforbetterrepresentation ofsystemconfiguration.
Valvereceivescontainment isolation signal.(8)Valvesnowinnumericorder.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page37Revision0Date092490
'I~
Penetration 311-(1)ChangedPositionAtColdShutdownfrom"0"to"0/C";(2)ChangedPositionAtNormal0erationandPositionAtImmediate Postaccident from"0"to"LO";(3)GlobalNotes3and4.(1)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdownconditions.
(2)Consistency withGinnaAdministrative Control.(3)Notechnical change.67.Penetration 312-(1)ChangedPositionAtColdShutdownfrom"0"to"0/C";(2)ChangedPositionAtNormal0erationandPositionAtImmediate Postaccident from"0"to"LO";(3)GlobalNotes3and4~(1)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdownconditions.
(2)Consistency withGinnaAdministrative Control.(3)Notechnical change.68.Penetration 313-(1)Added"Blind"GlobalNotes1,2,and4forBlindFlange;(3)ChangedPositionIndication inControlRoomfrom"Yes"to"Status"from"No"to"Yes"forvalve7444;(5)AddedNote19.(1)Correction oftypographical omission.
Notechnical change.(2)Notechnical change.(3)Minorclarification only.Notechnical change.(4)Correction oftypographical error.Notechnical change.(5)Notechnical change.69.Penetration 315-(1)ChangedPositionAtColdShutdownfrom"0"to"0/C";(2)ChangedPositionAtNormal0erationandPositionAtImmediate Postaccident from"0"to"LO";(3)GlobalNotes3and4.(1)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdownconditions.
(2)Consistency withGinnaAdministrative Control.(3)Notechnical change.SafetyAnalysisNSL-0000-SA024 Page38Revision0Date092490


74.Penetration 320-(1)GlobalNotes3and4;(2)ChangedPositionAtNormalPostaccident from"0"to"LO";(3)ChangedPositionAtColdShutdownfromf!OfftonO/Ctt(1)Notechnical change.(2)Consistency withGinnaAdministrative Control.(3)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdownconditions.
~ ~
75.Penetration 321-(1)GlobalNotes3and4forvalve5701;(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Status"forvalve5738;(3)ChangedPositionAtColdShutdownfrom"C"to"0/C"forvalve5738;(4)Reordered penetration valves.(1)Notechnical change.(2)Minorclarification only.Notechnical.
0}}
change.(3)Updateforbetterrepresentation ofsystemconfiguration.
(4)Valvesnowinnumericorder.Notechnical change.76.Penetration 322-(1)GlobalNotes3and4forvalve5702.(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Status"forvalve5737;(3)ChangedPositionAtColdShutdownfrom"C"to"0/C"forvalve5737;(4)Reordered penetration valves.(1)Notechnical change.(2)Minorclarification only.Notechnical change.(3)Updateforbetterrepresentation ofsystemconfiguration.
(4)Valvesnowinnumericorder.Notechnical change.77.Penetration 323-(1)GlobalNotes3and4;(2)ChangedPositionAtNormalPostaccident from"0"to"LO";(3)ChangedPositionAtColdShutdownfrom"0"to"0/C"(1)Notechnical
'change.(2)Consistency withGinnaAdministrative Control.(3)Updateforbetterrepresentation ofsystemconfiguration sincefancoolersmaybeisolatedformaintenance duringcoldshutdownconditions.
SafetyAnalysisNSL-0000-SA024 Page40Revision1Date10390 78.Penetration 324-(1)Changedvalve8418from"Diaphragm" to"Globe";(2)ChangedPositionAtColdShutdownfrom"0"to"0/C"forvalve8418;(3)ChangedPositionIndication inControlfrom"Yes"to"Both"forvalve8418;(4)GlobalNotes1,2,and4;(5)ChangedMaximumIsolation Timefrom"NA"to"60"forvalve8418;(6)Reordered penetration valves.(1)Correction oftypographical error.Notechnical change.(2)Updateforbetterrepresentation ofsystemconfiguration.
(3)Minorclarification only.Notechnical change.(4)Notechnical change.(5)Correction oftypographical error.Notechnical change.(6)Valvesnowinnumericorder.Notechnical change.79.Penetration 332a-(1)GlobalNote1forpressuretransmitters; (2)Added"Globe"hvalves;(3)GlobalNote3forthemanualvalves;(4)Reordered penetration valves.(1)Notechnical change.(2)Correction oftypographical omission.
Notechnical change.(3)Notechnical change.(4)Valvesnowinnumericorder.Notechnical change.80.Penetration 332b-Deletedentirepenetration fromtable.Penetration hasdoubleisolation andmeetsthecriteria, foratestconnection.
Therefore, thispenetration isnotrequiredtobetestedper10CFR50AppendixJanddoesnotbelongonthetable.81.Penetration 332c-(1)Added"6.2-74"underUFSARFiureforallvalvesotherthan922.(2)ChangedPositionIndication inControlRoomfrom"Yes"to"Both"forallfourvalves;(3)ChangedPositionAtImmediate Postaccident from"0/C"to"C"forallvalves.(1)Correction oftypographical omission.
Notechnical change.(2)Minorclarification only.Notechnical change.(3)Updateforbetterrepresentation ofsystemconfiguration.
Systemisolateduponreceiptofcontainment isolation signal.SafetyAnalysisNSL-0000-SA024 Page41Revision0Date092490 82.Penetration 401-(1)AddedNote11toallvalvesotherthan3517;(2)Changed3517;(3)ChangedPositionIndication inControlRoomfrom"Yes"to"R/G"forvalves3505Aand3517;(4)GlobalNotes1,2,3,4,and5;(5)Reordered penetration valves.(1)Correction oftypographical omission.
Notechnical change.(2)Correction oftypographical error.Notechnical change.(3)Minorclarification only.Notechnical change.(4)Notechnical change.(5)Valvesnowinnumericorder.Notechnical change.83.Penetration 402-(1)AddedNote11toallvalvesotherthan3516and3518;(2)valve3516;(3)ChangedPositionIndication inControlRoomfrom"Yes"to"R/G"forvalves3504Aand3516;(4)GlobalNotes1,2,3,4,and5;(5)Reordered penetration valves.(1)Correction oftypographical omission.
Notechnical change.(2)Correction oftypographical error.Notechnical change.(3)Minorclarification only.Notechnical change.(4)Notechnical change..(5)Valvesnowinnumericorder.Notechnical change.84.Penetration 403-(1)GlobalNotes1,2,3.from"6.2-75"to"6.2-76"forvalve3995;(3)Added"6.2-76"underUFSARFiciureforallvalvesaftervalve3995;(4)AddedNote11toallvalvesotherthanvalve3995;(5)Added"4"underClassforallvalvesotherthan3995;(6)Reordered penetration valves.(1)Notechnical change.(2)Correction oftypographical error.Notechnical change.(3)(4)(5)Correction oftypographical omission.
Notechnical change.(6)Valvesnowinnumericorder.Notechnical change.85.Penetration 404-(1)GlobalNotes1,2,from"6.2-75"to"6.2-76"forvalve3994;(3)AddedNote9toallvalvesotherthan4000D;(4)Reordered penetration valves.(1)Notechnical change.(2)Correction oftypographical error.Notechnical change.(3)Correction oftypographical omission.
Notechnical change.(4)Valvesnowinnumericorder.Notechnical change;SafetyAnalysisNSL-0000-SA024 Page42Revision0 86.Penetration 1000-(1)GlobalNotes1,2,4,and5;(2)Added"Both"toPositionRelativetoContainment; (3)(1)Notechnical change.(2)(3)Correction oftypographical omission.
Notechnical change.87.Penetration 2000-(1)GlobalNotes1,2,4,and5;(2)Added"Both"toPositionRelativetoContainment; (3)"3.8-3IV'1)Notechnical change.(2)(3)Correction oftypographical omission.
Notechnical change.SafetyAnalysisNSL-0000-SA024 Page43Revision0 (1)Deletedlastsentenceof"old"Note1andmoveditto"new"Note2;(2)Renumbered remaining "old"Note1asNote3.(1)(2)Thedeletedsentenceofthenoteisstillappliedtonecessary penetrations.
Notechnical change.2.Deleted"old"Note2.Notewasonlyaduplication oftheUFSARtext.See"new"Note4.Notechnical change.3.Deleted"old"Note3.Notewasonlyaduplication oftheUFSARtext.See"new"Note4.Notechnical change.4.(1)Deletedfirsttwosentences of"old"Note4;(2)Modifiedlastsentencetoreflectsystemconfiguration; (3)Renumbered "old"Note4asNote6.(1)Thesetwosentences onlyduplicated UFSARtext.Notechnical change.(2)Sentencenowaccurately reflectswordingoftheJanuary30,1987letter.(3)Notechnical change.5.Deleted"old"Note5.Notewasonlyaduplication oftheUFSARtext.See"new"Note4.Notechnical change.6.Deleted"old"Note6.Notewasonlyaduplication oftheUFSARtext.See"new"Note4.Notechnical change.7.Deleted"old"Note7.Notewasonlyaduplication oftheUFSARtext.Notechnical change.8.Deleted"old"Note8.Notewasonlyaduplication oftheUFSARtext.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page44Revision0Date092490 9.(1)Modified"old"Note9;(2)Renumbered "old"Note9asNote13.(1)(2)Minorclarification only.Notenowdescribes indetailtheuseofthepressuretransmitter asaboundary.
Notechnical change.10.Deleted"old"Note10.Notewasonlya.duplication oftheUFSARtext.See"new"Note4.Notechnical change.Deleted"old"Note11.Notewasonlyaduplication oftheUFSARtext.See"new"Note4.Notechnical change.12.(1)Modified"old"Note12;(2)Renumbered to"new"Note15.Minorclarification only.change.Notechnical 13.Deleted"old"Note13.Notewasonlyaduplication oftheUFSARtext.Notechnical change.14.(1)Deletedlasttwosentences of"old"Note14andmoveditto"new"Note16;(2)Modifiedremaining "old"Note14;(3)Renumbered "old"Note14asNote17.(1)Thedeletedsentenceofthenoteisstillappliedtonecessary penetrations.
Notechnical change.(2)(3)Minorclarification ofnoteonly.Notechnical change.15.Deleted"old"Note15.Notewasonlyaduplication oftheUFSARtext.Notechnical change.16.Deleted"old"Note16.Noteisincorrect andnolongerapplicable.
17.(1)Modified"old"Note17;(2)Renumbered "old"note17asNote21.(1)(2)Minorclarification ofnoteonly.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page45Revision0 4
32.AddedNote20.Minorclarification only.Noteprovidesadditional information relatedtopenetration's use.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page48Revision0Date092490 18.(1)Modified"old"Note18;(2)Renumbered "old"Note10asNote11.(1)(2)Minorclarification ofnoteonly.Notechnical change.19.AddedNotel.Noteprovidesclarification onuseofthepenetration.
SeeletterfromR.Mecredy,RG&E,toA.Johnson,NRC,datedMarch13,1990.20.AddedNote2.Noteprovidesgenericdescription ofpenetration seals.Noteoriginally partof"old"Note1.Notechnical change.21.AddedNote4.Minorclarification only.Noteoriginally partof"old"Notes2,3,5,6,10,and11.Notenowusedonaglobalbasis.Notechnical change.22.AddedNote5.Minorclarification only.Noteprovidesadditional information relatedtopenetration's use.Notechnical change.23.AddedNote7.Noteprovidesconsistency withTechnical Specification Table3.6-1Note20.Notechnical change.24.AddedNote8.Minorclarification only.Noteprovidesadditional information relatedtoMOVbreakerstatus.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page46Revision0 k
25.AddedNote9.%RP)>h~r..'".'~>Y&Q<<>.v&#xc3;F>N4!jFrvca44AYY+cPc>'~>>@48<44~AAC NK+AA~>~>Y4s.."4%gggg Minorclarification only.Noteprovidesadditional information relatedtofunctionofthevalve.Notechnical change.26.AddedNote10.Minorclarification only.Noteprovidesdetaileddescription ofpenetration valves.Notechnical change.27.AddedNote12.Minorclarification only.Notechnical change.28.AddedNote14.Noteprovidesadditional information relatedtopenetration.
SeeletterfromR.Mecredy,RG&E,toA.Johnson,NRC,datedJuly9,1990.29.AddedNote16.Noteprovidesclarification ofleakagetestrequirements.
Noteoriginally partof"old"Note14.Notechnical change.30.AddedNote18.Minorclarification only.Noteprovidesadditional information relatedtosolenoidstatus.Notechnical change.31.AddedNote19.Noteprovidesconsistency withTechnical Specification Table3.6-1Note22andnotesrelatedtopenetrations 313and317.Notechnical change.SafetyAnalysisNSL-0000-SA024 Page47Revision0 ChanchesTable1Technical Specification ChangesEffectSection3.6.3.1references UFSARTable6.2-13insteadofTechnical Specification Table3.6-1.Notechnical change.2.Table3.6-1removedfromTechnical Specifications andinformation placedinUFSARTable6.2-13.Valvelistingremainsinalicenseecontrolled documentunder10CFR50.59 program.3.4.Revisedinoperable definition ofSection3.6.3.1.Removednoteassociated withTechnical Specification 3.6.5.Notechnical change.Clarification onlyconsistent with10CFR50AppendixJ.Mini-purge valveshavebeeninstalled sotheTechnical Specification canbeconsidered effective.
Notechnical change.5.Added"Pt"andnecessary
~~~~definitions toTechnical Specification 4.4.1.4sectiona.Additionof"Pt"providesclarification oftestingtypeconsistent with10CFR50,AppendixJ.Alltermsin4.4.1.4,sectionanowfullydefined.Notechnical change.7.8.Addedtothedefinition of"Lt"inTechnical Specification 4.4.1.4sectionb.Addeddefinition of"Pa"and"Lam"inTechnical Specification 4.4.1.4sectionc.Addedsteamgenerator inspection/maintenance penetration toTechnical Specification 4.4.1.5sectiona(ii).Addeddefinition "Lt"providesclarification consistent with10CFR50,AppendixJ.Alltermsin4.4.1.4,sectionbnowfullydefined.Notechnical change.Additionof"Pa"and"La"providesclarification consistent with10CFR50,AppendixJ.Alltermsin4.4.1.4,sectioncnowfullydefined.Notechnical change.Additionofthispenetration providestestingcriteriasimilartotheequipment hatchandcontainment airlocks.9.RevisedfirstlineofTechnical Specification 4.4.1.5,sectiona(ii).Minorclarification only.Notechnical change.
Removednotesassociated withTechnical Specification 4.4.2.4sectiona.Deletedreference tosectiond.Mini-purge valveshavebeeninstalled sotheTechnical Specification canbeconsidered effective.
SectiondwillberemovedfromTechnical Specifications.
Notechnical change.11.Addedsteamgenerator inspection/maintenance penetration toTechnical Specification 4.4.2.4sectionb.Additionofthispenetration providestestingcriteriasimilartotheequipment hatchandcontainment airlocks.12.RemovedTechnical Specification 4.4.2.4sectiondandassociated note.Blindflangeshavebeeninstalled sotheTechnical Specification canbeconsidered effective.
Notechnical change.13.ChangedReference fromTable3.6-1toUFSAR6.2-13insection4.4.5.1.14.ChangedReference fromTable3.6-1toUFSAR6.2-13insection4.4.6.2.Valvelistingremainsinalicenseecontrolled documentunder10CFR50.59 program.Valvelistingremainsinalicenseecontrolled documentunder10CFR50.59 program.
~~0}}

Latest revision as of 10:50, 4 February 2020

Rev 1 to Safety Analysis Ginna Station Updated FSAR Table 6.2-13 Changes.
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Text

Safety Analysis Ginna Station UFSAR Table 6.2-13 Changes Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 NSL-0000-SA024 Revision 1 October 3, 1990 Prepared by: K) -z.-'9Q Nu lear Engineer Date Reviewed by:

Nucle r Engine r Date Approved by:

anag r, Nuclear S fety & Licensing Date Page i 90i0240i'i9 90iOi5 05000244 PDR ADOCK P PDC I

Revision Status Sheet Latest Latest Latest Page Revision Page 'evision Page Revision 14h 37 15 38 16 39 17 40 18 41 19 42 20 0 43 21 44 7 22 45 8 23 46 9 24 47

,10 25 48 12 27 13 28 14 29 14a 30 14b 31 14c 32 14d 33 0 14e 34 14f 35 14g 36 Safety Analysis Revision NSL-0000-SA024 Page ii Date 1

10 3 90

Safet Anal sis Descri tion and f

1.0 Sco e The purpose of this evaluation is to determine are any unreviewed safety questions related to updating if there UFSAR Table 6.2-13, Containment Piping Penetrations and Isolation Valves. This update is necessary to reflect information obtained during a detailed review of the containment isolation system and the result of the 1988 Inservice Test (IST) Program submittal to the NRC.

2.0 References 2.1 Updated Final Safety Analysis Report, Revision 5.

2.1.1 Section 6.2.4, Containment Isolation System.

2.1.2 Table 6.2-13, Containment Piping Penetrations and Isolation Valves.

2.2 R.E. Ginna Nuclear Power Plant Technical Specifications, dated April 12, 1990.

2.2.1

~ ~ Section 3.6.3, Containment Isolation Valves.

2.2.2 Table 3.6-1, Containment Isolation Valves.

2.2.3 Section 3.8.1, Refueling.

2.3 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC,

Subject:

SEP Topic VI-4, Containment Isolation Valves (Systems); dated August 30, 1982.

2.4 Letter from L.D. White, RG&E, to D.L. Ziemann, NRCg

Subject:

Discussion of Lessons Learned Short Term Requirements; dated November 19, 1979.

2.5 Letter from L.D. White, RG&E, to B.H. Grier, NRC,

Subject:

IE Bulletins79-06A and 79-06A Revision 1; dated June 22, 1979.

2.6 Letter from L.D. White, RG&E, to D.L. Ziemann, NRC,

Subject:

Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI Unit 2 Accident; dated October 17, 1979.

2.7 Letter from D.M. Crutchfield, NRC, to J.E. Maier, NRC,

Subject:

Forwarding Final Evaluation Report of SEP Topic VI-4, Containment Isolation System for the Ginna Nuclear Power Plant; dated April 12, 1982.

Safety Analysis Revision 0 Page 1 NSL-0000-SA024

2.8 Letter from J.E. Maier, RG&E, to D.M. Crutchfield, NRC,

Subject:

SEP Topic VI-4, Containment Isolation System; dated December 30, 1981.

2.9 NUREG-0821, Integrated Plant Safety Assessment, Systematic Evaluation Program, R.E. Ginna Nuclear Power Plant; dated December 1982.

2.10 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,

Subject:

Necessary Clarifications Associated With Technical Specification Table 3.6-1; dated July 2, 1990.

2.11 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,

Subject:

Containment Isolation Valves AOV 745 (Penetration 124a), MOV 749A (Penetration 127), and MOV 749B (Penetration 128); dated June 22, 1990.

2.12 RG&E Inter-Office Correspondence from G.J. Wrobel, to S.T. Adams,

Subject:

Technical Specification Interpretation of Containment Isolation Valves MOVs 749 A/B; dated June 21, 1990.

2.13 USNRC, Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants; Revision 3, November 1978.

2.14 Letter from D.D. Di?anni, USNRC, to R.W. Kober, RG&E,

Subject:

SEP Topic VI-4, NUREG-0821 Section 4.22.2, Containment Isolation Valves; dated January 30, 1987.

2.15 NUREG-0800, Standard Review Plan, Section 6.2.4, Revision 2, July 1981.

2.16 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Operability of AOV 745 and MOVs 749A/B; dated July 9, 1990.

2.17 Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Modification of Containment Penetration $ 2; dated March 13, 1990.

2.18 Ginna Station Procedure 0-2.3.1A, Containment Closure Capability in Two Hours During RCS Reduced Inventory Operations, Revision 5, dated April 28, 1990.

2.19 Ginna Station Quality Assurance Manual.

2.19.1 Appendix B, Inservice Inspection Program For the 1990-1999 Interval, Revision 0, dated January 1, 1990.

2.20 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.

Safety Analysis Revision 0 Page 2 NSL-0000-SA024 Date 9 24 90

I4 II

3.0 Safet Anal sis 3~1 The system affected, by this UFSAR change is the containment isolation system. This system is designed to isolate non-essential process lines which penetrate the containment to ensure that the total leakage of activity will be within design limits in the event of an accident. In addition, the parent systems (e.g.,

Safety Injection) of the components contained in the containment isolation system can be considered affected by this UFSAR change. However, there is no change to the capability of these systems to perform their intended design function, only an update of their ability to isolate containment when required.

3.2 The updated UFSAR Table 6.2-13 is presented in Attachment A. Due to the significant number of changes, a marked-up version of the current UFSAR table was not generated. Instead, Attachment B provides a detailed listing of all changes made to the table.

Attachment B is divided into four (4) sub tables.

The first table, provides a listing of global notes which were applied as applicable to eliminate redundancy.

(2) The second table provides a listing of changes made to the format and overall structure of the UFSAR table.

(3) The third table lists the changes made to each individual penetration on the UFSAR table.

(4) The fourth table identifies all changes made to the UFSAR table notes. However, since many modifications were made to the UFSAR table, most notes have been renumbered and revised.

Consequently, to eliminate confusion, a change associated with the notes column for a particular penetration is only identified in Table 3 if a note has been added or deleted. There is no change identified in Table 3 only been changed, if a note number has if changes were made to the note itself, or if the note was deleted globally.

Instead, these changes are provided in Table 4.

3.3 The changes to UFSAR Table 6.2-13 fall into three categories:

clarifications or corrections of typographical errors and omissions,.

(2) updates to better represent actual plant conditions, and (3) updates for consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.

Safety Analysis Revision 0 Page 3 NSL-0000-SA024

~ ~ s ~

3.3.1 The correction of typographical errors and omissions does not involve any technical change to the UFSAR table nor the function and capability of the containment isolation system. All columns and rows in the table now contain either the 'necessary information or "NA". No blanks or "-" remain in the table. In addition, the clarifications made to the UFSAR table are minor and do not involve any technical changes.

Significant clarifications are discussed below.

3.3.1.1 The Position At Postaccident column was changed to reflect plant conditions immediately following a Containment Isolation Signal (CIS) . This column was modified since system configurations can be changed during recovery operations. If this column was not modified, it would require most valves to list "0/C". The column now provides a clear listing of the valve positions prior to any operator action (i.e., "immediate" post accident) .

3.3.1.2 The Notes column was changed to only supplement UFSAR Section 6.2.4.4.2 text. All duplications of information contained in the UFSAR text was removed from the Notes. The Notes column now only identify exceptions, references, etc., not contained in the UFSAR text.

3.3.1.3 removed from the table since they do not provide any information relevant to the UFSAR Table. This information can be obtained from other sources including Appendix B of the Ginna Station Quality Assurance Manual. Consequently, the information contained in these columns remains in other RG&E controlled documents.

3.3.1.4 The Position Indication In Control Room column was modified to show the type of indication instead of "Yes/No". This is a significant enhancement since the table now identifies if there is a white status light or a red/green light associated with the valve on the Main Control Board, or both.

3.3.2 The updates to the UFSAR table to better represent actual plant conditions are described below.

3.3.2.1 Penetration $ 2 was added to the table. This spare penetration was modified during the 1990 Refueling Outage to enhance containment closure during mid-loop operations. The penetration meets all current containment penetration criteria. See Reference 2.17.

Safety Analysis Revision 0 Page 4 NSL-0000-SA024 Date 9 24 90

~ ~ ~ ~

3.3.2.2 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a more conservative position. That is, the valve position changed from either a "0/C" to "C",

nO<r to nCn npn to nLCIr or srCtt to nLCn (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases, the valve is now identified as being in an isolated or closed position which is the function of a containment isolation valve. Valves (and penetration ¹) in this category include: 370B (¹100), 879 (¹110b),

371 (¹112), 846 (¹120a), 539 (¹120b), 547 (¹121a),

528 (121a), 508 (¹121b), 743 (¹124a), 745 (¹124a),

1569 (¹124b) g 1571 (¹124b) g 1572 (¹124b) I 1574

(¹124b) I 759B (¹ 125) I 759A (¹126) I 749A (¹127) 749B (¹ 128) I 1787 (¹129) I 1786 (¹ 129) / 7971

(¹132), 1076B (¹202), 1084B (¹202) I 1563 (¹203b) I 1565 (¹203b) I 1566 (¹203b) ~ 1568 (¹203b) I 5869

(¹204), 966C (¹205), 966B (¹206a), 5735 (¹206b),

966A (¹207a), 5736 (¹207b), 1080 (¹210), 5879

(¹300) g 6151 (¹301) g 6165 (¹301) ~ 6175 (¹303) 6152 (¹303) g 1 07 6A (¹304) I 1 084A ( ¹304) g 1554

(¹305c), 1556 (¹305c), 1557 (¹305c), 1559 (¹305c) f 1560 (¹305c), 1562 (¹305c), 7141 (¹310a), 921

(¹332c), 922 (¹332c), 923 (¹332c), and 924

(¹332c) .

3.3.2.3 Several valves had their positions as listed under the Position At columns in the UFSAR Table changed to a comparable position. That is, the valve position changed from either a "0" to "0/C" or "0/C" to "0". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) For these cases where the valve was listed as open, the valve and penetration was required to be evaluated previously assuming that was the most conservative position.

it was open since this Therefore, changing the valve's position for these cases does not negatively impact the penetration or containment isolation system since the valve was conservatively evaluated under open conditions previously. Valves (and penetration ¹) in this category include: 1723 (¹107), 1728 (¹107), 313

(¹108), 1789 (¹123 bottom), 1003A (¹143), 1003B

(¹1 43) g 5869 (¹204) g 5735 (¹206b) I 5736 (¹207B) 5879 (¹300) ~ 4629 (¹308) g 4630 (¹31 1) I 4642

(¹312) g 4643 (¹315) I 4628 (¹316) g 4627 (¹319) f 4641 (¹320), 4644 (¹323), and 8418 (¹324) .

Safety Analysis Revision 0 Page 5 NSL-0000-SA024 Date 9 24 90

~ ~ ~ ~

3.3.2.4 Several valves had their positions as listed under the Position At Cold Shutdown column in the UFSAR

' Table changed to a less conservative position.

That is, the valve position changed from either a "Cn to nOn or nCn to nO/Cn (See Table 3 of Attachment B =for a detailed description of these changes on a penetration by penetration basis.)

However, containment integrity is not required in the Cold Shutdown condition (Technical Specification 3.6.1) . In addition, during reduced RCS inventory operations, the position of these valves (or an automatic isolation valve in the same line) is verified by Reference 2.18. Thus, these valves can be'closed if needed.

during Refueling Operations, Technical Also, Specification 3.8.1 requires that all "automatic containment isolation valves shall be operable or at least one valve in each line shall be locked closed." Therefore, containment isolation is assured during refueling operations.

Consequently, these changes do not the penetration or the containment negatively'mpact isolation system since administrative controls are in place. Valves (and penetration 0) in this category include: 7970 ($ 132), 7971 ($ 132), 5393

($ 310b), 7443 ($ 317), 5738 ($ 321), and 5737

($ 322) .

3.3.2.5 Several valves had their positions as listed under the Position At Normal 0 eration and Position At Immediate Postaccident columns in the UFSAR Table changed to a less conservative position. That is, the valve position changed either from a "C" to "0/C", or "0" to "LO". (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) There are two categories of valves which meet this criteria (organized by justification) .

(a) 529 (g12lb) This penetration has an automatic isolation valve in the line to perform the necessary isolation function. In addition, since this check valve sees the same conditions as the associated automatic isolation valve, their positions should be the same. Consequently, the change does not negatively impact the penetration or the containment isolation system.

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(b) 4629 ($ 308) g 4630 ($ 31 1) ~ 4642 ($ 312) g 4643 (f315) 4628 ($ 316)

~ g 4627 ($ 319) g 4641

($ 320), 4644 ($ 323) These essential Service Water System penetrations operate at a higher pressure than the containment accident pressure and are missile protected inside containment. Consequently, the line is not required to isolate. See UFSAR Table Note

17. Therefore, the change in valve position does not negatively impact the penetration or the containment isolation system.

3.3.2.6 a "No" for valve 745 ($ 124a) . The Maximum Isolation Time column was also changed from "60" to "NA". These changes are justified per Reference 2.16.

3.3.2.7 Several penetrations had valves added to the table, deleted, or both. These are described below by penetration number.

(a) Penetration 103 Valve 5129 was deleted from the table and replaced by a Blind Flange.

This change enabled the elimination of the previous note of "No longer in use" that was associated with this penetration. The penetration now reflects the current configuration. The use of the Blind Flange is consistent with the previous locked-closed manual valve.

(b) Penetration 111 Added valve 959. The addition of this valve to the table ensures that all valves receiving a containment isolation signal are listed. This valve was previously missing from the table, but credit was not taken for the valve during the SEP (see Reference 2.7) . Consequently, this is not considered an actual isolation valve and is not tested per Appendix J.

(c) Penetration 112 - Valves 204A and 821 were deleted .-and replaced with valves 200A, 200B, and 202. Valve 427 was also added. The addition of these valves enables explicit compliance with GDC 55 versus the use of the two redundant isolation valves. These new valves are included in the current IST program (see Reference 2.19).

(d) 123 (bottom) Added valve 1600A. See explanation for 3.3.2.7 (b) above.

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(e) Penetration 141 Deleted valve 851A and added valve 1813A. Valve 851A does not meet the selection criteria for 10CFR50 Appendix J, Section IIH, items 1 through 4.

Consequently, the valve was deleted from the table. Valve 1813A was previously missing from the table. This valve is locked-closed with its breaker locked open.

(f) 'enetration 142 Deleted valve 851B and added valve 1813B. See explanation for 3.3.2.7 (e) above.

(g) Penetration 205 Added valve 955. See explanation for 3.3.2.7 (b) above.

(h) Penetration 206a Added valve 953. See explanation for 3.3.2.7 (b) above.

(i) Penetration 207a Added valve 951. See explanation for 3.3.2.7 (b) above.

(j) Penetration 210 Added valves 10214S1 and 10215S1. These valves were previously missing from the table, but receive an isolation signal.

3.3.2.8 Penetration 332b Deleted entire penetration branch from the table. This penetration branch contains double isolation, fits the criteria as a test connection, and performs no active function.

Therefore, there is no requirement to test the valves as containment isolation valves.

Consequently, this penetration branch was removed from the table.

3.3.3 Several updates were made to the UFSAR table to ensure consistency between the UFSAR, Technical Specifications, and previous commitments made by RG&E.

These changes are typically only clarifications. The significant changes are described below.

3.3.3.1 Notes 7 and 19 were added to ensure that consistency is maintained between Technical Specification Table 3.6-1 and the UFSAR Table.

These notes mainly provide clarification and do not involve a technical change.

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3.3.3.2 The Maximum Isolat'ion Time of several valves was changed to a more conservative duration. That is, the time was changed from "NA" to either "3" seconds for solenoid valves, or "60" seconds for AOVs and MOVs. (See Table 3 of Attachment B for a detailed description of these changes on a penetration by penetration basis.) The UFSAR Table now identifies an isolation time for all valves receiving a containment isolation signal.

Valves (and penetration 4) in this category include: 1787 ($ 129), 10211S1 ($ 202), 10213S1

($ 202), 966C ($ 205), 966B ($ 206a), 5735 ($ 206b),

966A ($ 207a), 5736 ($ 207b), 10214S ($ 210), 10215S1

($ 210) / 10205S1 ($ 304) g 10209S1 ($ 304) g 1597

($ 305a), 1599 ($ 305b), and 8418 ($ 324) .

3.3.3.3 The Maximum Isolation Time of several valves was changed to a less conservative duration. There are three categories of valves which meet this criteria (organized by justification):

(a) 749A (f127), 749B ($ 128) These valves do not receive a containment isolation signal.

Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.

(b) 5869 ($ 204) This valve does not require an isolation time since the associated blind flange acts as the isolation boundary. See, UFSAR Table Note 19. Consequently, the Maximum Isolation Time was changed to "NA" since there is no need for a maximum isolation time.

(c) 7970 ($ 132), 7971 ($ 132), 7478 (f309), and 7445 (f309) The isolation time for these butterfly valves was changed from "2" seconds to "3" seconds. Technical Specification Table 3.6-1 allows five seconds with instrument delay. However, the Maximum Isolation Time column does not include instrument delay per Note "b". The instrument delay time for these valves is approximately 2 seconds. Consequently, the valve isolation time was changed to "3" seconds.

3.4 A review of the design basis events analyzed in the Ginna Station UFSAR and,the events requiring analysis as described in USNRC Reg. Guide 1.70 was performed.

The events related to this UFSAR change are:

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(a) Fires (b) Seismic Events (c) Radiological Release From a Subsystem or Component (d) Decrease in Reactor Coolant Inventory (e) Events Initiating a Safety Injection Signal 3.4.1 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a fire.

The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. No fire barriers are affected by these changes, nor is there any increase in area fire loadings.

3.4.2 The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to perform its function during a seismic event. The changes to the UFSAR Table are mainly minor clarifications and updates to reflect current plant conditions. No changes are made with respect to the seismic design of the affected penetrations.

3.4.3,

~ ~ The changes as described in Section 3.3 and Attachment B do not affect the capability of the containment isolation system to respond to a radiological release within containment. The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. There is no physical modification to Ginna Station as a result of these changes. Consequently, the containment isolation system is still within its design basis limits.

3.4.4 The changes as described in Section 3.3 and Attachment B do not create the potential for the affected penetrations to cause a decrease in RCS inventory (i.e., a loss-of-coolant-accident) . The containment isolation system was reviewed in depth during the SEP and 1988 IST submittal. The changes to the UFSAR Table are mainly clarifications and updates to reflect current plant conditions. No changes were made to capability of the parent systems (e.g., Residual Heat Removal) to perform their function. Consequently, the containment isolation system and associated parent systems remain within their design basis limits.

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3.4.5 Events which initi'ate Safety Injection also result in the need for containment isolation. The changes to the UFSAR Table do not affect the capability of the containment isolation system to perform its function.

All changes were rev'iewed to ensure continued compliance with the design basis for the containment isolation system and the Ginna Station Licensing Basis.

4.0 Preliminar Safet Evaluation 4.1 The proposed UFSAR changes will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. The changes to the UFSAR Table are to correct typographical errors, provide additional clarification, and update the table to reflect actual plant conditions. All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8.

Thus, there is no change in system function, nor a reduction in system reliability. The containment isolation and parent systems will remain within their design limits.

4.2 The proposed UFSAR changes will not increase the consequences of an accident previously evaluated in the UFSAR. The modification does not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.'6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of an accident as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus,- the function and capability of the containment isolation system to isolate any radiological release within containment is not degraded.

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4.3 The proposed UFSAR changes will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR.

All changes considered "less conservative" are acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the probability of occurrence as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the changes do not degrade the performance of the containment isolation system, nor the associated parent systems.

4.4 The proposed UFSAR changes will not increase the consequences of a malfunction of equipment important to

,. safety previously evaluated in the UFSAR. The changes do not impact or increase the calculated radiological dose to the general public for any event evaluated in the UFSAR. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3. All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. Thus, the function and capability of the containment isolation system to isolate any radiological release from containment is not degraded. =

4.5 The proposed UFSAR changes will not create the possibility of an accident of a different type than any previously evaluated in the UFSAR. These changes are mainly clarifications and updates to reflect current plant conditions. All changes considered "less conservative" are acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.2.4, 3.3.2.5, 3.3.2.6, and 3.3.3.3.

All additions and deletions to the table are also acceptable and do not increase the consequences of a malfunction of equipment as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8. There are no adverse affects upon other systems, nor any new failure modes induced.

4.6 The proposed UFSAR changes will not create the possibility of a different type of malfunction of equipment important to safety than any previously evaluated in the UFSAR. The additions and deletions to the table are acceptable as discussed in Sections 3.3.1.3, 3.3.2.1, 3.3.2.7, and 3.3.2.8, The changes do not degrade the containment isolation or associated parent systems.

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4.7 The proposed UFSAR changes will not reduce any margin of safety as defined in the basis of any technical specification. The functions and characteristics of the containment isolation system remains unchanged.

However, changes are made to valve isolation times and the valves listed for specific penetrations. These changes will be addressed in the Amendment Request to remove Table 3.6-1 from the Technical Specifications and reference this updated UFSAR table.

4.8 Based on the above analysis, that:

it has been determined (a) The margins of safety during normal operation and transient conditions anticipated during the life of the plant has not been reduced, and (b) The adequacy of structures, systems, and components provided for the prevention of accidents and for the mitigation of the consequences of accidents have not been affected.

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Attachment A Safety Analysis Revision 0 Page 14 NSL-0000-SA024 Date 9 24 90

2-13 CONTAI PENETRATIONS AND I PIPINC Position Position At Maxisans Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Normal Cold Ixaedf ate UFSAR Notes

~Sstea No. No. Shutdovn Postaccfdent~

Steam Cenerator Blind Flanges Both 0/C C (add) 5 I~ 2 Inspection/

Maintenance Fuel Transfer 29 Blind Flange Inside 0/C 6 '-13 5 2I 3 Tube Charging Line 100 370B Check Inside 6.2-18 3B to B Loop Safety 101 870B Check Outside 0 6 '-15 3B Infection Pury 889B Check Outside 0 6 '-15 3B IB Discharge Alternate 102 3838 Check Inside C 6.2-16 3B Charging to A Cold Leg Construction 103 NA Blind Flange NA NA Inside C C NA 6 '-17 5 Ffre Service Water Containment 105 8 62A Check NA Outside C 0 NA 6 '-18 3B Spray Pusy IA Reactor Coolant 106 306k Check Nh Inside 0 6 '-19 3B Puxy h Seal Water Inlet Susy h Dfs 107 1723 Diaphraga Afr Status Outside 0 0/C C FC Yes 60 6.2 20 2 charge to Waste 1728 Dfaphraga hir Status Outside 0 0/C C FC Yes 60 6 '"20 2 Holdup Tank Reactor Coolant 108 313 Motor Both Outside 0/C AI Yes 60 F 2-21 8, 6 Pump Seal Water Return Lfne and Excess Letdovn to VCT Containment 109 862B Check Nh NA Outside C Nh 6.2 22 3B Spray Pury IB end AI Falls As Is MQV Moto~rated Valve Refers to position fsuediately follovfng receipt of containment AOV Air Operated Valve MV ~ Manual Valve isolation signal and containment ventilation fsolation signal.

C ~ Closed 0 ~ Open s The maxfxaa isolation time does not include diesel start time CIS ~ Contafnment Isolation Signal 0/C Open or Closed nor instrument delay tfme.

CV Check Valve R/C ~ Red / Creen Light on Main Control Board 'efers to classes defined in Section 6.2.6.6.2.

s Notes only used to supplement Section 6.2.6.6.2.

FC ~ Falls Closed Status White Status Light, FO Fails Open SOV Solenoid Operated Valve LC ~ Locked Closed Safety Analysis Revision 1

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" NSL-'.OO,OO-SA024

-13 CONTAI PENETRATIONS AND I PIPING Position Position At Maxi xixa Valve Indication Position Isolation Penetratfon Valve Valve Operator In Control Relative to Homal Cold lxxaadf ate Paver

~Satan No. No. Roon Contafnnent OHeratfon Shutdovn Postaccfdentv Failure Trip on Tfxe DFSAR Notes CIS Reactor Coolant 110a (topi 304B Check NA Nh InsMe 0 0~ C Purp B Seal NA Nh 6.2-23 3B Nater Inlet Safety 110b <bottoni 879 Globe Manual No Outside LC LC Inlectfon Test NA 6 ~ 2-15 1 Lfne Residual Hea't 720 Gate Motor R/C Inside 0 AI Renoval to B 959 Globe Alr Status 6.2-24 3B 4 ~ 7g 8 Outs fde 0/C FC 6.2-24 Cold Leg 3B 4, 1 I

Letdown to 112 200A Globe Afr R/G Inside 0/C Nonregenerative 200B Globo Alr R/G Inside 0/C C C Yes 60 6~ 225 I 10 Heat Exchanger 202 Clobe Air R/G Inside C C

C C Tes $0 $ e2 25 I 10 371 Globe Air Both Outside 0 0 C Yes 60 6~ 225 1 10 421 Globe Alr R/C Inside 0 0/C C Yes $0 6.2-25 I C Yes $ .2-25 I Safety 113 810A Check NA Outside C 6.2-15 In)ection Puxp 889A Check NA Outside C 3B IA Discharge 6.2 15 3B Standby Auxf I- 119 9104A Stop-Check Motor R/G OutsMe AI fary Feedwater 9105A No 6.2 26 Check NA Nh Inside NA Nh 6.2-26 Line to Stean Generator lh Nitrogen to 120a 846 Globe Air Both Outside C 0/C C FC Yes 60 hccuxaIlators 4623 6 ~ 2 21 3A Check NA NA Inside 0/C '/C

, C NA Nh $ .2-27 3A Pressurlxer 120b 539 Globe Air Sta'xus Outside 0/C Relief Tank to 546 Globe Manual C FC Yes 6 ~ 2-28 2 No Outside 0 0 Nh Nh F 2-24 Gas Analyxer 2 Nitrogen to 121a 528 Check NA NA Inside 0/C 6.2-29 Pressurixer 547 Globe lanual No Outside OIC 3A Relief Tank $ .2 29 3A 12 Makeup Rater to 121b 504 Dfaphragn Air Both Outside C OIC C Pressurixer 529 FC Yes 60 6 ~ 2-30 3A Check NA NA Inside 0/C OIC C NA Nh $ .2-30 Relief Tank NA 3A Conte funest 121c PT945 NA NA Outside Pressure 1819A Globe 6 2-31 2 13 Manual Outs Me 6.2 31 2 Transnftt@r PT945 Contafnnent 121d F2946 Nh NA NA Outside Nh NA Pressure 1819B Globe Manual 6.2-31 2 13 No Outside 0 0 6 2-31 2 TransxLit'tox'T946 Standby Auxfl- 123 ltopl 9104 B Stop-Check Motor Outside C C AI NA 6.2-26 fary I'eedvater 91058 Check Nh Inside C C Nh Nh 6.2-26 Line to Stean 4 Generator IB Safety Analysis Revision 1 Page 14b NSL-,OOOO-SA024 Date 10 3 90

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~ 2-13 ~

CONTAI PENETRATION~a AND PIPIhG Position Posftfon At f Max aaxa Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Homal Cold Iacaediate Pover Tilac

~Sat cmc No. ~T Rocvm, Contafnacent OEeratfon Shutdovn postaccfdcntr Trip on UFSAR Notes Failure CI8 ~Fi re Reactor Coolant 123 (button) 1600A Globe Solenoid No Outsfde 0 0/C Drain Tank to 1655 Globe Manual C Ycls NA 6.2-32 Analyzer No Outside 0 0 0 NA 6.2-32 Gas Line 1789 Diaphragca hfr Status Outside 0 0/C C Yes 60 6 '-32 Excess Letdovn 124a 743 Check Q Q Inside 0 Beat Exchanger 745 Globe hi r C C NA 6.2-33.

RIG Outside 0 C C No 6.2-33 Cooling Water 14 Supply 4 Return Postaccfdcnt 124b 1569 Dfaphragca Afr Sag>le to C Manual Outs fde LC 6 '-34 5 Fan 1571 1572 Dfsphragca Dfaphragrc Manual Manual OutsMe Outside IC, 6.2 34 5 LC 6.2-34 5 1574 Dfaphragal Manual Outsfde LC 6.2-34 5 r

Component 125 7598 Cate Hotor R/C Outside C 0 AI No 6.2-35 Cooling Water 4 fraa Reactor r Coolant Pump 1B Ccxcponent 126 759A Gate Motor R/C Outside 0 Cooling Water AI No Nh 6.2<<36 frees Reactor Coolant Pump IA Componen't 127 749A Cate Hotor Outside 0 Cooling Nater 750A Check Inside 0 C 0 AI Q 6.2-37 4 to Reactor NA C 0 NA Q 6.2-37 Coolant Pump lh Cccmponeat 128 7498 Cate Motor Cooling Water OutsMe 0 C 0 AI No Q 6 '-38 to Reactor Coolant ~

Reactor Coolant 1B 129 7508 1713 Check Check NA Inside 0 C 0 NA NA Q 6 '-38 4 NA NA Outside C 0/C C NA NA 6. 2-39 Drain Tank and Pressurizer 1786 Dfaphragal hir Sta'tus Outsfde 0 C C FC Yes NA 60 6 '-39 3A 3A Relist 1787 Dfaphragca Air S'ta'tua Outside 0 C C FC Yes 6.2-39 Tank to 1793 Dfaphragal Manual No Outside LC 0/C LC 60 3A Containnent Nh NA NA 6 ~ 2-3S 3A 12 Vent Reader Component 130 814 Gate Motor Both Outside 0 Cooling Water AI Yes 60 6.2-40 4 frcxa Reactor Support Cooling Cc~nent 131 813 Cate Hotor Both Outside 0 0 AI Cooling Nater Yes 60 6.2-40 4 to Ream'tor Support Cooling Containment Nfnf-Purge 132 7970 Butterfly hir Both Inside 0/C OIC C FC Yes 3 6.2-41 5 Exhaust 7971 Buttertly Alr Both OutsMe C 0/C C FC Yes 3 6.2-41 5

',Safety Anal'ysis Revision 1 r

Page 14c NSL-0000-SA024

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2 13 CONTAI PENETRATION<

AND I ~ PIPING Position Position At Kaxfmsus Valve Indication Posftfon Imoist fon Penetration Valve Valve Operator In Control Relative to Normal Cold Imnediate Fever Trip on Time OFSAR Notes

~zs ten No. No. Room Containment OHeratfon Shutdovn Postaccidcnt'ailure CIS ~Ff re Classs See end of table ~

Residual Beat 140 701 Gate Hotor R/C Inside 0 C AI 6.2-42 1 7i 8 Removal Pump Suctfon from A Hot, Leg Residual Heat 141 85th Cate Hotor R/0 Outside C C 0 AI No Nh 6.2-42 5 15 Removal No. 1 1813A Cate Hotor R/C Outside C 0/C C AI No NA 6.2-42 5 8 Pump Suction from Sump B Residual Heat 142 SSOB Gate Hotor R/C Outside C C AI NA 6 ~ 2-42 5 15 Removal No. 2 1813B Gate Hotor R/0 Outside C 0/C AI NA 6.2-42 5 8 Pump Suction from Su~ B Reactor Coolant 143 1003A DIa phragn Air Status Outside 0 0/C C Yes 60 '.2-43 2 Drain Tant 1003B Diaphragm Afr Status Outside 0 0/C C Yes 60 6 ~ 2-43 2 Discharge Lfne 1721 Diaphragm Alr Status Outside 0 0 C Yes 60 6.2-42 2 Reactor 201 (top) 4757 Butterfly Hanual No Outside 0 0 6.2-44 4 16 Compartment 201 (bottom) 4636 Butterfly Hanual No Outside 0 0 6.2-45 4 17 Cooling Onits h and B B Hydrogen 202 1076B Diaphragm Hanuaf No Outside LC LC LC Nh NA 6. 2-46 Recombiner 1084B Diaphragm Nanuel No Outside LC LC LC NA NA F 2-46 (Pilot and 1021181 Globe Solenoid Status Outside C C C Yes 3 6.2-46 18 Hafn) 1021351 Clobe Solenoid Status Outside C C C Yes 3 6.2-46 18 Containment 2Q3a F2947 NA NA NA Outside NA NA NA 6.2-47 2 13 Pressure PT948 NA Nh Nh Outside NA Nh NA 6.2 47 2 13 Transmitter 1819C Clobe Hanua 1 No Outs Me 0 0 0 6,2 47 2 PT947 and PT948 1819D Globe , Hanual No Outs Ide 0 0 0 6 ~ 2 47 2 PostaccMent 203b 1563 Diaphragm Hanual No Outside 6.2 48 Air 8~le to B 1565 Diaphragm Hanual No Outside 6.2-48 Fan 1566 Diaphragm Hanuel No OutsMe 6.2 48 1568 Diaphragm Hanual No Outside 6.2 48 Purge Supply 204 Blind Flange NA Inside C 0 Nh 6.2 49 2, 19 Duct 5869 Butterfly Afr Both Outside C 0/C FC 6.2 49 19 Hot Leg Loop 205 955 Clobe Air St&'tus Inside C C C Yes NA 6' 50 Sample 956D Globe Hanual No Outside 0 0 0 NA NA 6 ~ 2 50 966C Globe Air Status Outside C C C Yes 60 6.2-50 Pressurizer 206a (top) 953 Globe Alr Status Inside C C C Yes NA 6.2 51 Liquid Space 956E Clobe Manual Outside 0 0 0 6.2-51

~le 966B Globe Alr No S'ta'tus Outside C C C Nh Yes NA 60 6 ~ 2 Sl A Stean 206b (bottom) 5733 Globe Hanual No Outside 0 Nh NA 6~2 52 Cenerator 5735 Globe Alr Status Outsfde C FC 60 6.2 52 Sample Pressurizer 207a (top) 951 Globe Alr Status Inside C C C FC Yes Nh 6.2 S3 1 Steam Space 956F Globe Hanuel No Outside 0 0 0 NA NA NA 6.2-53 I Sample 966A Globe Air Status Outside C C C FC Yes 60 6~ 253 1 ss 3

'Safety Analysis Revise.on 1 Page 14d

'SL-0000-SA024

l 2-13 CONTAIN PENETRA TIGHT AND I N PIPING Position Posftfon At Maxisum Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relative to Normal Cold irumdfate Power Trip on Time UFSAR Notes Mo. No. Roon Containment OBeratfon Shutdovn Postaccfdent'aflur* CIS ~F( re Cla ass See end of table a B Steam 207b (bottom) 5734 Globe Manual No Outside C Nh 6.2-54 Generator 5736 Globe Air Status Outside C 60 6.2-54 Sample Reactor 209 (top) 4635 Butterfly Manual No Outside 6.2-44 16 Cocpartment 209 (bottom) 4758 Butterfly Manual No Outside 6.2-45 17 Cooling Units h and B Oxygen Makeup 210 1080A Globe Manual No Outside LC LC LC Nh 6.2-55 to h 4 B 102145 Clobe Solenoid S'tatus Outside C C C Tes 3 6.2-55 14 Reconbiners 1021481 Globe Solenoid Sta'kus Outs fde C C ~ C Tes 3 6.2 55 14 102158 Globe Solenoid Status Outside C C C Tes 3 6.2-55 14 1021531 Globe Solenoid S'tatus Outside C C C Yes 3 6 '-55 14 Purge Exhaust 300 Nh Blind Flange NA NA Insfde 0 NA 6 '-56 2, 19 Duct 5479 Butterfly Air Both Outs ide OIC Yes F 2-56 19 Auxiliary Steam 301 6151 Globe Manual Outs ide NA 6.2-57 Supply to 6165 Globe Manual Outside NA 6.2-57 Containment Auxiliary Steam 303 6152 Globe Manual No Outside 6.2-57 Condensate 6175 Globe Manual No Ou'teide 6.2-57 Return A Hydrogen 304 1076A Diaphragm Hanual No Outside LC LC LC Nh 6.2-58 Recoebiner 108(A Diaphragm Manual No Outside LC LC LC Nh 6.2-58 (Pilot and 1020551 Globe Solenoid Status Outside C C C Tes 6.2-54 18 Nein) 1020951 Globe Solenoid S'ta'tus Outside C C C Yes 6.2-58 18 Contafnment Alr 305a (bottom) 1596 Globe Manual No Outside NA 6.2 59 2 Saxple Out 1597 Diaphragm Air Both Outside Tes 6 ~ 2 59 2 Containment Air 305b (top} 1598 Diaphragm Air Both Outsfde Tes 60 6.2 60 3A Sarpf e Inlet 1599 Diaphragm Alr Both Outside Tes 60 6' 60 3h Containment Alr 305C 1554 Diaphragm Manual No Outside 6 ~ 2 61 Sa=ple 1556 Die ph rage Manual No Outside 6.2 61 Postaccident 1557 Diaphragm Manual No Outside 6.2 61 1559 Diaphragm Hanual No Outside 6.2-61 1560 Diaphragm Manual No Outside 6.2 61 1562 Diaphragm Manual No Outside 6.2 61 Fire Service 307 9227 Cate Afr Both Outside Tes 60 6.2 62 Mater 9229 Check NA Nh Insfde Nh Nh $ .2-62 Service Mater 308 4629 Butterfly Manual Outside 0/C 6.2 63 to h Fan Cooler Nini-Purge 309 7445 Butterfly hir Both Outsfde OIC Yes 6,2 64 Supply 7474 Butterfly Alr Both Inside OIC Tes 6.2 64 Service Air to 310a (bottcm) 7141 Cata Manual No Outside 0/C 6 ~ 2-65 3A Containment 7226 Check Nh Nh Inside OIC 6.2 65 3A Safety Analysis Revision E

Page 14e

-NSL-0000-SA024 Date 10 3 90

-13 CONTAINNEN PENETRATIONS AND I ON PIPING Position Posftfon ht f Hex sum Valve Indicatfon Position Isolation Penetration Valve Valve Operator In Cont rol Relative to Normal Cold irradiate Trip on Time VFSAR Notes

~Sat em No. Mo, Room Contain>nant OEeratfon Shutdovn Postaccfdent'over Failure CI8 ~Ff re Instrument Air 310b (top) 5392 Globe Both Outside 0 C Yes 60 6.2 66 3A to Contafnmnnt 5393 Check NA Inside 0 C NA IR 6.2-66 3A Service Mater 311 4630 Butterfly Manual Outside 0/C from B Fan 6.2-63 16 Cooler Service Mater 312 4642 Butterfly Hanual Outside 0/C . NA 6.2-63 to D Fan Cooler ~ 17 Leakage Test 313 NA Blind Flange Inside Depressurira- 7444 Butterfly Nh Hotor NA Sta'tus Outsfde C NA NA Q 6.2-67 5 t ion C Al Yes Q 6 ~ 2 67 5 19 Service Mater 315 4643 Butterfly Hanuel Outside 0/C From C I'an > NA NA NA 6.2-63 4 16 Cooler Service Mater 316 4628 Butterfly Hanual No Outside 0/C to B Fan Cooler NA 6.2-63 4 17 Leakage Test 317 NA Blind Flange NA NA Inside Q Supply 7443 Butterfly Hotor Sta'cus NA 6.2 68 5 Outside AI Yes 6.2"68 5 19 Deadveight 31d NA Tes'ter lR NA 20 Service Mater 319 4627 Butterfly Hanual No Outside 0/C from A Fan 6 ~ 2-63 4 16 Cooler Service Mater 320 46li Butter fly Manual No Outside 0/C to C Fan Cooler NA 6.2-63 17 A Steam 321 5701 Globe Hanua1 Outside Generator 5738 Globe Air No Status Outside 0

0 0 NA Q Q 6.2-6S Blovdovn 0/C C FC Yes 60 6 ~ 2 69 B Steam 322 5702 Globe Manual Outside Generator 5737 Globe hir No Status Outside 0 NA Q 6.2-70 Blovdovn 0/C Yes 60 6270 Servfca Mater 323 4644 Butterfly Hanual No Outside fran D I'an 0/C Q 6.2-63 16 Containment Cooler Demineralized Mater to 324 l 4 1d Globe Air Both Outside C 0/C C Yes 60 6. 2-71 5 8l 1 9 Check NA NA Inside C 0/C C NA lVL 6 ~ 2-71 5 Contafment 332a PT944 NA NA NA Outside Q Pressure IVL Nh NA NA NA 6.2-72 2 13 PTS49 NA NA NA Outside IR NA NA Nh Nh IVL 6.2-72 2 Transmitters PT950 Q Nh NA Outside NA NA NA N1L NA IR 6.2-72 13 PT944, F2949> 1819E Globe 2 13 Hanual No Outside 0 0 0 NA . NA NA 6.2-72 2 and PT950 Globe 1419F 18190 Globe Manual Manual No No Outside Outside 0

0 0

0 0 NA NA NA 6 '-72 2 0 NA Nh Nh 6.2-72 2 Safety Analysis Revision 1 Page 14f

. NSL-0000-SA024 Date 10 3 90

2 13 CONTAI 'C PENETRATIONS AND IS ION PIPING Position Position At Maxi sans Valve Indication Position Isolation Penetration Valve Valve Operator In Control Relatfve to Normal Cold Ismedfate Trip on Time CFSAR Notes

~Sstem No. No. Room Contafnvent OBeratfon Shutdovn Postaccfdent'oser Failure CIS ~Ff re Classv See <<nd ot table s Hydrocen 332c 921 Cate Solenoid Both Outside C C C yes 6.2 74 21 Monitor 922 Cate Solenoid Both Outside C C C yes 6.2 74 21 Instrumentatfon 923 Cate Solenoid Both Outside C C C yss 6.2 74 21 Lines 924 Cate Solenoid Both 0 teide C C C Tes 6.2 74 21 Main Steam from 401 3505A Cate Motor R/0 Outside C 0 AI No 6.2 75 11 A Steam 3507 Cate Manual No Outsfde C 0 NA NA 6.2 75 11 Generator 3517 3519 Swine Check Check Air NA R/C NA Outside Outside C

C C

C AI NA No NA 6.2 75 6 ' 75 ll ll 3521 Cate Manual No Outside 0 0 NA NA 6.2 75 ll Main Steam B Steam Iron 402 3504A 3506 Cate Cate Motor Manual R/0 No Outside Outside C

0 C

C 0

0 AI NA No NA 6.2 75 6.2 75 ll ll Generator 3516 Suing Check Air R/0 Outside 0 C C AI No 6.2 75 11 3518 3520 Check Cate NA Manual NA No Outside Outsfde 0

0 C

0 C

0 NA NA NA NA 6 ' 75 6.2"75 ll ll Fcedvater Line 403 3993 Check NA NA Outside 0 C C NA NA 6.2 76 11 to A Steam 3995 Clohe Manual No Outside 0 0 0 NA NA 6.2-76 11 Generator 4008C Check NA NA Outside C C 0 NA NA 6.2 76 11 4083 Check NA NA Outside C C 0 NA NA 6.2-76 11 4885 Globe Manual No Outside 0 0 0 NA NA 6.2-76 11 4011 Globe Manual No Outside 0 0 0 NA NA 6.2-76 11 1'eedvater line 404 3992 Check NA NA Outside 0 C C NA 6.2-76 11 to B Steam 3994 Clohe Manual No Outside 0 0 0 NA 6.2-76 11 Generator 40000 4084 Check Check NA NA NA NA Outside Outside C

C C

C 0

0 NA NA 6.2-76 6.2-76 ll 11 4806 Globe Manual No Outside 0 0 0 'NA 6.2-76 11 4012 Clohe Manual No Outside 0 0 0 NA 6.2-76 11 Personnel Hatch 1080 Both 0/C NA 3.8-31 Equfpcent Hatch 2000 0/C 3.8-30 Safety Analysis Revision Page 14c4 NSL-0000-SA024 Date 10 3 90

13 CONTAINNEN PENETRATIONS'ND IS N PIPING Notes (I) penetration Number 2 was added as a result of ENR 4998 to facflftate steam generator maintenance activities during mfd-loop operation. This penetration is closed by a doubf~asketed blind flange on both ends) however, only one oI the two Ilanges are necessary for containment Integrity purposes.

(2) Thfs penettatfon is provided with redundant seals and fs closed during normal opezatfon.

(3) The end of the tuel transfer tube inside containment fs closed by a doubf~asketed blind flange, to prevent leakage or spent fuel pit. water fnto the contafnment during plant operation.

This flange also serves as protectfon against leakage Izom the containment following a losswfwoofant accident.

(4) This is a closed system outside containment. Verification of this closed system as a contafnment isolation boundary ls accomplished via inservice and/or shutdown leakage checks.

This applfes to the following systems: Safety In)ection, Containment Spray, Charging, Residual Heat Removal, and Component Cooling Hater.

(5) This penetration was only utilized during fnltfal plant construction and fs maintained fnactfvate.

(6) A second isolation barrier is provided by the volume control tank and connectfng piping per letter from D.D. DfIanni, USNRC, to R.N. Kober, RG(E, dated January 30, 1987. This barrier is not required to be tested.

IOCFR50, Appendix J containment leakage testing fs not required per L.D. white Jr. letter to D.L. Fiemann, USNRC, dated September 21, 1978.

(8) MOVs 1813A, 1813B, 720, and 701 are maintained closed at power with their breakers locked off.

(9) This valve receives a contafnsent isolation sfgnal) however, credit is not taken for this function. Therefore, this valve is not sub)ected to J lea'kage testing, nor does ft require a maximum isolation tfme. IOCFR50, Appendix (10) Containment Isolation Signals were added to AOVs 200A. 2008, and 202 since AOV 427 falls open on loss pz power. The Isolation signal for these three valves ls relayed From AOV 427.

(11) The Main Steam, Main Feedwater, and Standby Auxiliary Feedwater isolation valves are not considered contafnmsnt fsolatfon valves. The containsmnt boundary fs the steam generator secondary side and tubes.

I (12) Manual valves 547 and 1793 are locked closed and leak tested to provide equivalent protection for GDC 56 and 57 (see UFSAR 6.2.4.4.1, Class 3A). k (13) The pressure transmitter assexbly, by its design, provides a containment pressure boundary. The fntegrity of this boundary is verified by annual leakage tests.

(14) Operations fs instructed to manually close AOV 745 following a Containment Isolation Signal until an automatic signal 1s installed through the necessary modfficatfon.

(15) Sump ]ines are fn operation and filled with Ifufd foffowfng an accident) therefore. 10CFR50, Appendix J leakage testing is not required for this penetratfon. See L.D. Nhfte Jr. letter to D.L. Ziemann, USNRC, dated September 21, 1978.

(16) This manual valve fs sub)ected to an annual hydrostatic leakage test and fs not sub]ect to 10CFR50. Appendix J leakage testing.

The service Nater System operates at a higher pressure than the contafnment accident pressure and fs missile protected inside containment. Therefore, this manual valve is used for flow control only and fs not sub]ected to 10CFR50 Appendix J leakage testing. See letter from J.E. Mafer, RG(E. to D.M. Czutchfield, hRC, dated August 30, 1982.

(18) Thfs solenoid valve is maintained Inactive in the closed position by removal of fts DC control power.

(19) The Ilanges and associated double seals provide contafnment Isolation and ensure that contafnment Integrity fs maintained Ior all modes of operation above cold shutdown. Nhen the Ilanges are removed, cold shutdovn containment integrity ls provided by the valves. These valves do not require 10CFR50, Appendix J leakage testing, nor a maximum isolation time.

(20) This penetration is decozcdssfoned and weldeci shut.

(21) Acceptable fsolatfon~pabflfty is provided For fnstrument lines by two isolation boundaries outside containment. One of the boundaries outside containment is a Seismic Class I closed system which fs sub)ected to Type C leakage testing under 10CFR50, Appendix J.

Safety Analysis Revision 1 Page 14h NSL-0000-SA024

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Attachment B Safety Analysis Revision 0 Page 15 NSL-0000-SA024 Date 09 24 90

The blanks or "-" within columns were Typographical clarification only. No replaced with "NA". technical change.

2. (1) The blanks or "-" for the Position (1) (2) The valve position and "NA" are At columns were replaced with the more representative of the penetration representative position; (2) The "No" configuration. In addition, listed under Position Indication in consistency is maintained within the Control Room was replaced with "NA". table. No technical change.
3. The "AI" or blank for the Power Failure The "NA" is more representative of the column for manual valves was replaced penetration configuration since a with "NA". manual valve does not receive any motive power. No technical change..
4. The "NA" is more representative of the was replaced with "NA". penetration configuration. In addition, consistency is maintained within the table. No technical change.
5. The blank or "No" for Maximum Isolation The "NA" is more representative of the Time was replaced with "NA". penetration configuration. In addition, consistency is maintained within the table. No technical change.

Safety Analysis Revision 0 Page 16 NSL-0000-SA024 Date 09 24 90

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Added "Cold" to Position At Shutdown Minor clarification for consistency column heading. with Technical Specifications. No technical change.

2. (1) Added "Immediate" to Position At (1) (2) Clarification of column since Postaccident column heading; (2) Added valve position can be potentially Note "a" changed during post accident recovery operations. Column now provides clear definition of penetration configuration following receipt of a CIS.
3. (1) (2) Column did not provide any table; (2) Deleted definitions for "W" information relevant to table. Fluid and "G" from table Legend. type can be inferred from stem

~S column.

4 Column did not provide any information associated Note "c" from table. relevant to table.

5. Added definitions for "AOV", "CV", Correction of typographical omission.

"MOV", "MV", and "SOV" to table Legend. No technical change.

6. (1) Modified Position Indication in (1) (2) The type of control room Control Room column to reflect type of indication is more representative of indication instead of "Yes" and "No"; the system configuration. This is a (2) Added definition for "R/G" and clarification only. No technical "Status" to table Legend. "Both" change.

indicates that a red/green light and status light exists.

7. Moved Table Heading Notes "a", "b", "c", Minor format change only. No technical and "d" to first page of table. change.

Safety Analysis Revision 0 Page 17 NSL-0000-SA024

~ c

8. (1) Renamed Note "a" to "b"; (2) Added (1) (2) Minor clarification- only. Note "nor instrument delay time" to end of is now consistent with Standard Review note. Plan Section 6.2.4. No technical change.
9. Renamed Note "b" to "c". No technical change.
10. Deleted "Line" from ~S stem column No technical change.

heading.

Added Note "d" to Notes column. Minor clarification only. The Notes column is now only used to supplement the UFSAR text which provides more information. No technical change. =

Safety Analysis Revision 0 Page 18 NSL-0000-SA024 Date 09 24 90

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Penetration 2 Added penetration and This spare penetration was modified to necessary information to the table. provide access for steam generator inspection and maintenance cabling during refueling outages to enhance containment closure during midloop operations. No new valves were added.

2. Penetration 29 (1) Global Note 1; (2) (1) (2) No technical change.

Added Note 2.

3. Penetration 100 (1) Global Notes 1, 2, (1) (2) No technical change. (3) Update and 4; (2) Added Note 4; (3) Changed for better representation of system Position At Immediate Postaccident from configuration since the Charging System "0/C" to "C". is isolated upon receipt of a SI signal.

4 ~ Penetration 101 (1) Global Notes 1, 2, (1) (2) No technical change. (3) 4, and 5; (2) Added Note 4; (3) Added Correction of typographical omission.

"3B" under Class for valve 889B; (4) No technical change. (4) Valves now in Reordered penetration valves. numeric order. No technical change.

5. Penetration 102 (1) Global Notes 1, 2, (1) (2) No technical change.

4, and 5; (2) Added Note 4.

6. Penetration 103 Deleted valve 5129 Replaced Note of "No longer in use" to (entire line in table) and replaced with reflect accurate configuration status Blind Flange. of Blind Flange. The use of the Blind Flange is consistent with the previously listed locked-closed manual valve.

Safety Analysis Revision 0 Page 19 NSL-0000-SA024

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7. Penetration 105 (1) Global Notes 1, 2, (1) (2) No technical change.

and 4; (2) Added Note 4.

8. Penetration 106 (1) Global Notes 1, 2, (1) (2) No technical change. (3) Minor and 4; (2) Added Note 4; (3) Changed clarification only. No technical "supply" to "Inlet" under ~S stem. change.
9. Penetration 107 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for both valves; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration.

"0/C" for both valves.

10. Penetration 108 (1) Added "and Excess (1) Consistency with Technical Letdown to VCT" under ~Sstem; (2) Specification Table 3.6-1. (2) Minor Changed Position Indication In Control clarification only. No technical Room from "Yes" to "Both"; (3) change. (3) Update for better At Cold Shutdown from "0" to Changed'osition representation of system configuration "0/C"; (4) Added Note 4; (5) Added Note since this line may or may not be used
6. during cold shutdown conditions. (4)

(5) No technical change.

Penetration 109 (1) Global Notes 1, 2, (1) (2) No technical change.

and 4; (2) Added Note 4.

12. Penetration 110a (1) Global Notes 1, (1) (2) No technical change.

2, and 4; (2) Added Note 4.

Safety Analysis Revision 0 Page 20 NSL-0000-SA024 Date 09 24 90

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13. Penetration 110b (1) Global Notes 3 (1) (2) No technical change. (3) and 4; (2) Added Note 4; (3) Changed Consistency with Ginna Administrative Position At Cold Shutdown and Position Control.

At Immediate Postaccident from "C" to nLCss

14. Penetration 111 (1) Added Note 7 to (1) Consistency with Technical both valves; (2) Added Note 8 to valve Specifications. (2) (3) No technical 720; (3) Added Note 4 to both valves; change. (4) Minor clarification only.

(4) Changed Position Indication In No technical change. (5) Valve Control Room from "Yes" to "R/G" for MOV receives containment isolation signal 720; (5) Added valve 959 and necessary and was previously missing from the information. table.

15. Penetration 112 (1) Deleted valves (1) (2) Present configuration status; 204A and 821 (entire line in table) and the three new valves enable explicit replaced with valves 200A, 200B, and compliance with GDC 55 vs. the use of 202; (2) Added valve 427 and necessary redundant outboard isolation valves.

information; (3) Changed Position The 200A, 200B, 202, and 427 valves Indication In Control Room from "Yes" to have been successfully tested. (3)

"Both" for valve 371; (4) Changed Minor clarification only. No technical Position At Immediate Postaccident from change. (4) Update for better "0" to "C" for valve 371. representation of system configuration since letdown is isolated upon receipt of a SI signal.

Penetration 113 (1) Global Notes 1, 2, (1) (2) No technical change. (3) and 4; (2) Added Note 4 to both valves; Valves now in numeric order. No (3) Reordered penetration valves. technical change.

1 Safety Analysis Revision 0 Page 21 NSL-0000-SA024 Date 09 24 90

17. Penetration 119 (1) Global Notes 1, 2, (1) No technical change. (2) Minor 4, and 5; (2) Changed Position clarification only. No technical Indication In Control Room from "No" -to change. (3) Valves now in numeric "R/G" for valve 9704A; (3) Reordered order. No technical change.

penetration valves.

18. Penetration 120a (1) Global Notes 1, (1) No technical change. (2) 2, and 4 for valve 8623; (2) Changed Correction of typographical error. No valve 846 from "Gate" to "Globe"; (3) technical change. (3) Minor Changed Position Indication In Control clarification only. No technical Room from "Yes" to "Both" for valve 846; change. (4) Update for better (4) Changed Position At Normal 0 eration representation of system configuration.

from "0/C" to "C" for valve 846; (5) This valve remains closed unless the Reordered penetration valves. accumulator nitrogen blanket pressure decreases. (5) Valves now in numeric order. No technical change.

19. Penetration 120b (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for valve 539; (2) Changed better representation of system Position At Normal 0 eration from "0/C" configuration. (3) No technical to "C" for valve 539; (3) Global Notes 3 change.

& 4 for valve 546.

20. Penetration 121a (1) Global Notes 1, (1) No technical change. (2) 2, and 4 for valve 528; (2) Changed Correction of typographical error. No valve 547 from "Diaphragm" to "Globe"; technical change. (3) Consistency with (3) Changed Position At Immediate Ginna Administrative Control. (4)

Postaccident from "0" to "LC" for valve Update for better representation of 547; (4) Changed Position At Normal system configuration. No technical change. (5) No technical change. (6)

(5) Global Notes 3 and 4 for valve 547; Correction of typographical error. No (6) Deleted reference to "old" Note 9; technical change. (7) No technical (7) Added Note 12 to valve 547. change.

Safety Analysis Revision 0 Page 22 NSL-0000-SA024

21. Penetration 121b (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) (3) Update for "Both" for valve 508; (2) Changed better representation of system Position At Normal 0 eration from "0/C" configuration. (4) No technical to "C" for valve 508; (3) Changed change. (5) Valves now in numeric Position At Normal 0 eration from "C" to order. No technical change.

"0/C" for valve 529; (4) Global Notes 1, 2, and 4 for valve 529; (5) Reordered penetration valves.

22. Penetration 121c (1) Global Note 1 for (1) (2) No technical change. (3)

PT945; (2) Global Notes 3 and 4 for Correction of typographical omission.

valve 1819A; (3) Added "Gate" under No technical change.

8 9

23. Penetration 121d (1) Global Note 1 for (1) (2) No technical change.

PT946; (2) Global Notes 3 and 4 for valve 1819B.

24. Penetration 123 (bottom) (1) Added (1) Consistency with Technical "to" before "Gas Analyzer Line" under Specification Table 3.6-1. (2) No

~sstem; (2) Global Notes 3 and 4 for technical change. (3) Correction of 1655; (3) Changed valve 1789 from typographical error. No technical "Globe" to "Diaphragm"; (4) Changed change. (4) Minor clarification only.

Position Indication In Control Room from No technical change. (5) Update for "Yes" to "Status" for valve 1789; (5) better representation of system Changed Position At Normal 0 eration configuration since this line remains from "0/C" to "0" for valve 1789; (6) open. (6) Valve receives containment Added valve 1600A; (7) Reordered isolation signal and was previously penetration valves. missing from the table. (7) Valves now in numeric order. No technical change.

Safety Analysis Revision 0 Page 23 NSL-0000-SA024 Date 09 24 90

25. Penetration 123 (top) (1) Global Notes (1) No technical change. (2) Minor 1, 2, 4, and 5; (2) Changed Position clarification only. No technical Indication In Control Room from "No" to change.

"R/G" for valve 9704B.

26. Penetration 124a (1) Global Notes 1, (1) No technical change. (2) Update 2, and 4 for valve 743; (2) Changed for better representation of system Position At Immediate Postaccident from configuration. Operations is "0" to "C" for valve 743; (3) Changed instructed to manually isolate this Position Indication In Control Room from line following receipt of a containment "Yes" to "R/G" for valve 745; (4) isolation signal. (3) Minor clarification only. No technical for valve 745; (5) Changed Maximum change. (4) (5) Correction of Isolation Time from "60" to "NA" for typographical error. See letter from valve 745; (6) Changed Position At Cold R. Mecredy, RG&E, to A. Johnson, NRC, Shutdown from "0" to "C" for valve 745. dated July 9, 1990. (6) Update representation of system for'etter configuration since excess letdown is not operational during cold shutdown conditions.

Penetration 124b (1) Added "to" before (1) Minor clarification. No technical

27. "C Fan" under ~astern; (2) Added change. (2) Correction of typographical omission. No technical four valves; (3) Changed Position At change. (3) (4) Consistency with Ginna Cold Shutdown from "C" to "LC" for all Administrative Control. (5) No four valves; (4) Changed Position At technical change.

Immediate Postaccident from "0/C" to "LC" for all four valves; (5) Global Notes 3 and 4.

Safety Analysis Revision 0 Page 24 NSL-0000-SA024 Date 09 24 90

28. Penetration 125 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/G"; (2) Changed Position At Cold better representation of system Shutdown from "0" to "C"; (3) Added Note configuration since RCPs are not
4. operating during cold shutdown conditions. (3) No technical change.
29. Penetration 126 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change; (2) Update for "R/G"; (2) Changed Position At Cold better representation of system Shutdown from "0" to "C"; (3) Added Note configuration since RCPs are not
4. operating during cold shutdown conditions. (3) No technical change.
30. Penetration 127 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/B" for valve 749A; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration since RCPs are not "C" for valve 749A; (3) Global Notes 1, operating during cold shutdown 2, and 4 for valve 750A; (4) Changed conditions.. (3) No technical change.

Maximum Isolation Time from "60" to "NA" (4) Correction of typographical error.

for valve 749A. No technical change.

31. Penetration 128 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "R/B" for valve 749B; (2) Changed better representation of system Position At Cold Shutdown from "0" to configuration since RCPs are not "C" for valve 749B; (3) Global Notes 1, operating during cold shutdown 2, and 4 for valve 750B; (4) Changed conditions. (3) No technical change.

Maximum Isolation Time from "60" to "NA" (4) Correction of typographical error.

for valve 749B. No technical change.

Safety Analysis Revision. 0 Page 25 NSL-0000-SA024

32. Penetration 129 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Minor valve 1787; (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valves 1786 and 1787; (3) representation of system configuration.

Changed Position at Cold Shutdown from (4) (5) No technical change. (6) Minor "0" to "C" for valves 1786 and 1787. (4) clarification. No technical change.

Global Notes 1, 2, and 4 for valve 1713; (7) Correction of typographical (5) Global Notes 2, 3, and 4 for valve omission. No technical change. (8) 1793; (6) Deleted "MOV 1793 used for Correction of typographical omission.

long-term isolation" under Notes and No technical change. (9) Valves now in replaced with Note 12; (7) Added "NA" numeric order. No technical change.

>>93:

Added "Outside" under Position Relative To Containment for valve 1793; (9)

Reordered penetration valves.

33. Penetration 130 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Correction of "Both"; (2) Corrected associated valve typographical error. No technical number to 814. change.
34. Penetration 131 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Correction of "Both"; (2) Corrected associated valve typographical error. No technical number to 813. change.

Safety Analysis Revision 0 Page 26 NSL-0000-SA024

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0

35. Penetration 132 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "2" to "3" for both Specifications. Valve design allows valves; (2) Changed Position At Normal closure as rapid as 2 (two) seconds.

Minimum closure time required by (3) Changed Position At Cold

"/'971; Technical Specifications is 5 (five)

Shutdown from "C" to "0/C" for both seconds with instrument delay. (2) (3) valves; (4) Changed Position Indication Update for better representation of In Control Room from "Yes" to "Both" for system configuration. Mini-Purge both valves. system only designed for use during shutdown conditions. (4) Minor clarification only. No technical change.

36. Penetration 140 (1) Added Note 6; (2) (1) Consistency with Technical Added Note 7; (3) Changed Position Specification Table 3.6-1 Note 20. (2)

Indication in Control Room from "Yes" to No technical change. (3) Minor IIR/Gll clarification only. No technical change.

37. Penetration 141 (1) Deleted valve 851A (1) Valve 851A does not meet the (entire line in table); (2) Added valve selection criteria of 10CFR50 Appendix 1813A and necessary information; (3) J, Section IIH, items .1 through 4.

Changed Position Indication In Control Therefore, valve was deleted from Room from "Yes" to "R/G" for valve 850A; table. (2) Valve 1813A was previously (4) Added Note 8 to valve 1813A. missing from table. (3) Minor clarification only. No technical change. (4) No technical change.

Safety Analysis Revision 0 Page 27 NSL-0000-SA024

l

38. Penetration 142 (1) Deleted valve 851B (1) Valve 851B does not meet the (entire line in table); (2) Added valve selection criteria of 10CFR50 Appendix 1813B and necessary information; (3) Jg Section IIH, items 1 through 4.

Changed Position Indication In Control Therefore, valve was deleted from Room from "Yes" to "R/G" for valve 850B; table. (2) Valve 1813B was previously (4) Added Note 8 to valve 1813B. missing from table. (3) Minor clarification only. No technical change. (4) No technical change.

39. Penetration 143 (1) Changed Position (1) Minor clarification only. No Indication In Control Room from "Yes" to technical change. (2) Update for "Status" for all three valves; (2) better representation of system Changed Position At Normal 0 eration configuration. (3) Valves now in from "0/C" to "0" for valves 1003A and numeric order. No technical change.

1003B; (3) Reordered penetration valves.

40. Penetration 201top Global Notes 3 and No technical change.

4.

41. Penetration 20lbottom Global Notes 3 No technical change.

and 4.

Safety Analysis Revision 0 Page 28 NSL-0000-SA024

42. Penetration 202 (1) Changed valves (1) Correction of typographical error.

1076B and 1084B from "Globe" to No technical change. (2) Consistency "Diaphragm"; (2) Changed Position At with Ginna Administrative Control. (3)

Normal 0 eration Cold Shutdown No technical change. (4) Correction Immediate Postaccident from "C" to "LC" of typographical omission. No for valves 1076B and 1084B; (3) Global technical change. (5) Update to new Notes 3 and 4 for valves 1076B and valve number only. No technical 1084B; (4) Added "No" under Position change. (6) Correction of Indication in Control Room for valves typographical omission. No technical 1076B and 1084B; (5) Changed Valve No. change. (7) (8) Update for better for IV-3B and IV-5B to 10211S1 and representation of system configuration.

10213S1, respectively; (6) Added Valves receive containment isolation "Status" under Position Indication in signal. (9) Correction of Control Room for valves 10211S1 & typographical error. No technical 10213S1; (7) Changed Position At Power change. (10) Valves now in numeric Failure from "-" to "FC" for valves order. No technical change.

1021181 and 1021381; (8) Changed ~Tri on CIS from "No" to "Yes" for valves 10211S1 and 10213Sl; (9) Changed Maximum Isolation Time from "NA" to "3" for 10211S1 and 10213Sl; (10) Reordered penetration valves.

43. Penetration 203a (1) Included separate (1) Minor clarification there are two lines in table for valves 1819C and valves. No technical change. (2) (3) 1819D; (2) Added "Outside" to Position Correction of typographical omission.

Relative to Containment for PT947 and No technical change. (4) (5) No PT948; (3) Added "Globe" under Valve technical change.

~T e for valves 1819C and 18190; (4)

Global Note 1 for PT947 and PT948; (5)

Global Notes 3 and 4 for valves 1819C and 1819D.

Safety Analysis Revision 0 Page 29 NSL-0000-SA024

jÃo+g)

44. Penetration 203b (1) Global Notes 3 (1) No technical change. (2) and 4; (2) Added "Diaphragm" under Valve Correction of typographical omission.

~T e for all four valves; (3) Changed No technical change. (3) Consistency Position At Cold Shutdown and Position with Ginna Administrative Control.

At Immediate Postaccident from "C" to "LC" for all four valves.

45. Penetration 204 (1) Added Note 2 to (1) (2) No technical change. (3) Minor Blind Flange; (2) Global Note 1 for clarification only. No technical Blind Flange; (3) Changed Position change. (4) (5) Update for better Indication in Control Room from "Yes" to representation of system configuration.

"Both" for valve 5869; (4) Changed Penetration only used during cold position At Normal 0 eration from "0/C" shutdown conditions. Mini-purge system to "C" for valve 5869; (5) Changed now used in place of purge system. (6)

Position At Cold Shutdown from "0" to The Blind Flange acts as the isolation "0/C" for 5869; (6) Changed Maximum boundary. Therefore, no isolation'time Isolation Time from "5" to "NA" for is required for the valve. (7) No valve 5869; (7) Added Note 19. technical change.

46. Penetration 205 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Valve valve 966C; (2) Added valve 955 and receives containment isolation signal necessary information; (3) Changed and was previously missing from the Position Indication in Control Room from table. (3) Minor clarification only.

"Yes" to "Status" for valve 966C; (4) No technical change. (4) Update for Changed Position At Normal 0 eration and better representation of system Position At Cold Shutdown from "0/C" to configuration. Sampling system "C" for valve 966C; (5) Global Notes 3 normally isolated. (5) No technical and 4 for valve 956D; (6) Reordered change. (6) Valves now in numeric penetration valves. order. No technical change.

Safety Analysis Revision 0 Page 30 NSL-0000-SA024 Date 09 24 90

49 Penetration 207a (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Valve valve 966A; (2) Added valve 951 and receives containment isolation signal necessary information; (3) Changed and was previously missing from the Position Indication in Control Room from table. (3) Minor clarification only.

"Yes" to "Status" for valve 966A; (4) No technical change. (4) Update for Changed Position At Normal 0 eration and better representation of system Position At Cold Shutdown from "0/C" to configuration. Sampling system "C" for valve 966A; (5) Global Notes 3 normally isolated. (5) No technical and 4 for valve 956F; (6) Reordered change. (6) Valves now in numeric penetration valves. order. No technical change.

50. Penetration 207b (1) Changed Maximum (1) Consistency with Technical Isolation Time from "NA" to "60" for Specification Table 3.6-1. (2) Minor valve 5736; (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) (4) Update for better "Status" for valve 5736; (3) Changed representation of system configuration.

Position At Normal 0 eration from "0/C" (5) No technical change. (6) Valves to "0" for valve 5736; (4) Changed now in numeric order. No technical Position At Cold Shutdown from "0/C" to change.

"C" for valve 5736; (5) Global Notes 3 and 4 for 5734; (6) Reordered penetration valves.

51. Penetration 209top (1) Global Notes 3 (1) No technical change. (2) Valve and 4; (2) Reordered penetration valves. order now consistent with other penetrations. No technical change.
52. Penetration 209bottom (1) Global (1) No technical change. (2) Valve Notes 3 and 4; (2) Reordered penetration order now consistent with other valves. penetrations. No technical change.

Safety Analysis Revision 1 Page 32 NSL-0000-SA024

53. Penetration 210 (1) Added "A & B" (1) Consistency with Technical before "Reoombiners" under ~3 stem; (2) Specification Table 3.6-1. (2) Minor Added Position Indication in Control clarification only. No technical Room to "Status" for all solenoid change. (3) Correction of valves; (3) Added "Yes" under ~Tri on typographical omission. No technical CIS for all solenoid valves; (4) Added change. (4) Valve receive containment valves 10214S1 and 10215S and necessary isolation signal and was previously information; (5) Changed Position At missing from the table. (5) Update for Power Failure from "-" to "FC" for all better representation of system solenoid valves; (6) Changed Position At configuration. Valves receive Normal 0 eration Cold Shutdown containment isolation signal. (6)

Immediate Postaccident from "C" to "LC" Consistency with Ginna Administrative for 1080A; (7) Global Notes 3 and 4 for Control. (7) No technical change. (8) valve 1080A; (8) Changed Valve No. for Update to new valve number only. No IV-2A and IV-2B to 10214S and 10215S1, technical change. (9) No technical respectively; (9) Added Note 18 to change. (10) Correction of solenoid valves; (10) Changed Maximum typographical error. No technical Isolation Time from "NA" to "3" for all change.-

solenoid valves.

54. Penetration 300 (1) Added Note 19 for (1) No technical change. (2) both valve and flange; (2) Added Note 2 Consistency with Technical to Blind Flange; (3) Global Note 1 for Specifications. No technical change.

Blind Flange; (4) Changed Position At (3) (4) Update for better representation Normal 0 eration from "0/C" to "C" for of system configuration. Penetration valve 5879; (5) Changed Position At Cold only used during cold shutdown Shutdown from "0" to "0/C" for valve conditions. Mini-purge system now used 5879; in place of purge system.

Safety Analysis Revision 0 Page 33 NSL-0000-SA024 Date 09 24 90

55. Penetration 301 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Cold Shutdown Consistency with Ginna Administrative and Position At Immediate Postaccident Control. (3) No technical change.

from "0" to "LC" for both valves; (3)

Added Note 5 to both valves.

56. Penetration 303 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Cold Shutdown Consistency with Ginna Administrative and Position At Immediate Postaccident Control. (3) No technical change. (4) from "0" to "LC" for both valves; (3) Correction of typographical error. No Added Note 5 to both valves; (4) Changed technical change. (5) Valves now in both valves from "Diaphragm" to "Globe"; numeric order. No technical change.

(5) Reordered penetration valves.

Safety Analysis Revision 0 Page 34 NSL-0000-SA024 Date 09 24 90

57. Penetration 304 (1) Changed valves (1) Correction of typographical error.

1076A and 1084A from "Solenoid" to No technical change. (2) Consistency "Diaphragm"; (2) Changed Position At with Ginna Administrative Control. (3)

Normal 0 eration Cold Shutdown and Correction of typographical omission.

Immediate Postaccident from "C" to "LC" No technical change. (4) No technical for valves 1076A and 1084A; (3) Added change. (5) Update to new valve number "No" under Position Indication In only. No technical change. (6) Minor Control Room for valves 1076A and 1084A; clarification only. No technical (4) Global Notes 3 and 4 for valves change. (7) (8) Update for better 1076A and 1084A; (5) Changed Valve No. representation of system configuration.

for IV-3A and IV-5A to 10205S1 and Valves receive containment isolation 10209S1, respectively; (6) Added signal. (9) No technical change. (10)

"Status" under Position Indication in Correction of typographical error. No Control Room for valves 10205Sl & technical change. (11) Valves now in 10209S1; (7) Changed Position At Power numeric order. No technical change.

Failure from "-" to "FC" for valves 10205Sl and 10209S1; (8) Changed CIS from "No" to "Yes" for valve

~Tri'n 10205S1 and 10209S1; (9) Added Note 17 for valves 10205Sl and 10209S1; (10)

Changed Maximum Isolation Time from "NA" to "3" for valves 10205S1 and 10209S1; (11) Reordered penetration valves.

58. Penetration 305a (bottom) (1) Changed (1) Consistency with UFSAR Drawing

~Sstem to "Containment Air Sample Out"; Title. No technical change. (2)

(2) Changed Maximum Isolation Time from Consistency with Technical "NA" to "60" for valve 1597; (3) Changed Specification Table 3.6-1. (3) valve 1596 from "Diaphragm" to "Globe"; Correction of typographical error. No (4) Global Notes 3 and 4 for valve 1597; technical change. (4) No technical (5) Changed Position Indication in change. (5) Minor clarification only.

Control Room from "Yes" to "Both" for No technical change. (6) Valves now valve 1597; (6) Reordered penetration in numeric order. No technical change.

valves.

Safety Analysis Revision 0 Page 35 NSL-0000-SA024

59. Penetration 305b (top) (1) Changed (1) Consistency with UFSAR Drawing

~S stem to "Containment Air Sample Title. (2) Consistency with Technical Inlet"; (2) Changed Maximum Isolation Specification Table 3.6-1. (3) Minor Time from "NA" to "60" for valve 1599; clarification only. No technical (3) Changed Position Indication in change. (4) Valves now in numeric Control Room from "Yes" to "Both" for order. No technical change.

valves 1598 and 1599; (4) Reordered penetration valves.

60. Penetration 305c <1) Changed ~S stem to (1) Consistency with UFSAR Drawing "Containment Air Sample Postaccident"; Title. (2) Correction of typographical omission. No technical change. (3) for all six valves; (3) Changed Position Consistency with Ginna Administrative At Cold Shutdown and Position At Control. (4) No technical change. (5)

Immediate Postaccident from "C" to "LC" Valves now in numeric order. No for all six valves; (4) Global Notes 3 technical change.

and 4; (5) Reordered penetration valves.

61. Penetration 307 (1) Switched Valve No. (1) Correction of typographical error.

for valves 9227 and 9229; (2) Added No technical change. (2) Correction of "Gate" -under Valve 0 erator T e for typographical omission. No technical valve 9227; (3) Global Notes 1, 2, and 4 change. (3) No technical change. (4) for valve 9229; (4) Changed Position Minor clarification only. No technical Indication in Control Room from "Yes" to change.

"Both" for valve 9227.

62. Penetration 308 (1) Changed Valve No. (1) Correction of typographical error.

to 4629; (2) Global Notes 3 and 4; (3) No technical change. (2) No technical Changed Position At Normal 0 eration and change. (3) Consistency with Ginna Position At Immediate Postaccident from Administrative Control. (4) Update for "0" to "LO"; (4) Changed Position At better representation of system Cold Shutdown from "0" to "0/C" (5) configuration since fan coolers may be Added Note 17. isolated for maintenance during cold shutdown. (5) No technical change.

Safety Analysis Revision 0 Page 36 NSL-0000-SA024

,P><><~!~ A.,gyes-.gory ~gg,~: FQKQ<,.4idsi,
63. Penetration 309 (1) Changed Maximum (1) Consistency with Technical Isolation Time from "2" to "3" for both Specifications. Valve design allows valves; (2) Changed Position Indication closure as rapid as 2 (two) seconds.

in Control Room from "Yes" to "Both" for Minimum closure time required by both valves; (3) Reordered penetration Technical Specifications is 5 (five) valves. seconds. (2) Minor clarification only.

No technical change. (3) Valves now in numeric order. No technical change.

64. Penetration 310a (1) Changed valve (1) Correction of typographical error.

7141 from "Diaphragm" to "Gate"; (2) No technical change. (2) Consistency Changed Position At Immediate with Ginna Administrative Control. (3)

Postaccident from "C" to "LC" for valve (4) No technical change. (5) Valves 7141; (3) Global Notes 3 and 4 for valve now in numeric order. No technical 7141; (4) Global Notes 1, 2, and 4 for change.

valve 7226; (5) Reordered penetration valves.

65. Penetration 310b (1) Changed valve (1) Correction of typographical error.

5392 from "Diaphragm" to "Globe"; (2) No technical change. (2) Minor Changed Position Indication in Control clarification only. No technical Room from "Yes" to "Both" for valve change. (3) Update for better 5392; (3) Changed Position At Cold representation of system configuration Shutdown from "C" to "0" for valve 5393; since IA is used during cold shutdown (4) Global Notes 1, 2, and 4 for 5393; conditions. (4) No technical change.

(5) Added "0" under Position At Cold (5) (6) (7) Update for better Shutdown for valve 5392; (6) Added "C" representation of system configuration.

under Position At Immediate Postaccident Valve receives containment isolation for valve 5392; (7) Changed Position at signal. (8) Valves now in numeric Power Failure from "-" to "FC" for valve order. No technical change.

5392; (8) Reordered penetration valves.

Safety Analysis Revision 0 Page 37 NSL-0000-SA024 Date 09 24 90

'I ~

Penetration 311 (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration and may be isolated for maintenance during Position At Immediate Postaccident from cold shutdown conditions. (2)

"0" to "LO"; (3) Global Notes 3 and 4. Consistency with Ginna Administrative Control. (3) No technical change.

67. Penetration 312 - (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration may be isolated for maintenance during and Position At Immediate Postaccident cold shutdown conditions. (2) from "0" to "LO"; (3) Global Notes 3 and Consistency with Ginna Administrative 4 ~ Control. (3) No technical change.
68. Penetration 313 (1) Added "Blind" (1) Correction of typographical omission. No technical change. (2) No Global Notes 1, 2, and 4 for Blind technical change. (3) Minor Flange; (3) Changed Position Indication clarification only. No technical in Control Room from "Yes" to "Status" change. (4) Correction of typographical error. No technical from "No" to "Yes" for valve 7444; (5) change. (5) No technical change.

Added Note 19.

69. Penetration 315 (1) Changed Position (1) Update for better representation of At Cold Shutdown from "0" to "0/C"; (2) system configuration since fan coolers Changed Position At Normal 0 eration and may be isolated for maintenance during Position At Immediate Postaccident from cold shutdown conditions. (2)

"0" to "LO"; (3) Global Notes 3 and 4. Consistency with Ginna Administrative Control. (3) No technical change.

Safety Analysis Revision 0 Page 38 NSL-0000-SA024 Date 09 24 90

74. Penetration 320 (1) Global Notes 3 and (1) No technical change. (2) 4; (2) Changed Position At Normal Consistency with Ginna Administrative Control. (3) Update for better Postaccident from "0" to "LO"; (3) representation of system configuration Changed Position At Cold Shutdown from since fan coolers may be isolated for f!Off to nO/Ctt maintenance during cold shutdown conditions.
75. Penetration 321 (1) Global Notes 3 and (1) No technical change. (2) Minor 4 for valve 5701; (2) Changed Position clarification only. No technical.

Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valve 5738; (3) Changed representation of system configuration.

Position At Cold Shutdown from "C" to (4) Valves now in numeric order. No "0/C" for valve 5738; (4) Reordered technical change.

penetration valves.

76. Penetration 322 (1) Global Notes 3 and (1) No technical change. (2) Minor 4 for valve 5702. (2) Changed Position clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Status" for valve 5737; (3) Changed representation of system configuration.

Position At Cold Shutdown from "C" to (4) Valves now in numeric order. No "0/C" for valve 5737; (4) Reordered technical change.

penetration valves.

77. Penetration 323 (1) Global Notes 3 and (1) No technical 'change. (2) 4; (2) Changed Position At Normal Consistency with Ginna Administrative Control. (3) Update for better Postaccident from "0" to "LO"; (3) representation of system configuration Changed Position At Cold Shutdown from since fan coolers may be isolated for "0" to "0/C" maintenance during cold shutdown conditions.

Safety Analysis Revision 1 Page 40 NSL-0000-SA024 Date 10 3 90

78. Penetration 324 (1) Changed valve 8418 (1) Correction of typographical error.

from "Diaphragm" to "Globe"; (2) Changed No technical change. (2) Update for Position At Cold Shutdown from "0" to better representation of system "0/C" for valve 8418; (3) Changed configuration. (3) Minor clarification Position Indication in Control from only. No technical change. (4) No "Yes" to "Both" for valve 8418; (4) technical change. (5) Correction of Global Notes 1, 2, and 4; (5) Changed typographical error. No technical Maximum Isolation Time from "NA" to "60" change. (6) Valves now in numeric for valve 8418; (6) Reordered order. No technical change.

penetration valves.

79. Penetration 332a (1) Global Note 1 for (1) No technical change. (2) pressure transmitters; (2) Added "Globe" Correction of typographical omission.

h No technical change. (3) No technical valves; (3) Global Note 3 for the manual change. (4) Valves now in numeric valves; (4) Reordered penetration order. No technical change.

valves.

80. Penetration 332b Deleted entire Penetration has double isolation and penetration from table. meets the criteria, for a test connection. Therefore, this penetration is not required to be tested per 10CFR50 Appendix J and does not belong on the table.
81. Penetration 332c (1) Added "6.2-74" (1) Correction of typographical under UFSAR Fi ure for all valves other omission. No technical change. (2) than 922. (2) Changed Position Minor clarification only. No technical Indication in Control Room from "Yes" to change. (3) Update for better "Both" for all four valves; (3) Changed representation of system configuration.

Position At Immediate Postaccident from System isolated upon receipt of "0/C" to "C" for all valves. containment isolation signal.

Safety Analysis Revision 0 Page 41 NSL-0000-SA024 Date 09 24 90

82. Penetration 401 (1) Added Note 11 to (1) Correction of typographical all valves other than 3517; (2) Changed omission. No technical change. (2)

Correction of typographical error. No 3517; (3) Changed Position Indication in technical change. (3) Minor Control Room from "Yes" to "R/G" for clarification only. No technical valves 3505A and 3517; (4) Global Notes change. (4) No technical change. (5) 1, 2, 3, 4, and 5; (5) Reordered Valves now in numeric order. No penetration valves. technical change.

83. Penetration 402 (1) Added Note 11 to (1) Correction of typographical all valves other than 3516 and 3518; (2) omission. No technical change. (2)

Correction of typographical error. No valve 3516; (3) Changed Position technical change. (3) Minor Indication in Control Room from "Yes" to clarification only. No technical "R/G" for valves 3504A and 3516; (4) change. (4) No technical change. .(5)

Global Notes 1, 2, 3, 4, and 5; (5) Valves now in numeric order. No Reordered penetration valves. technical change.

84. Penetration 403 (1) Global Notes 1, 2, (1) No technical change. (2)
3. Correction of typographical error. No from "6.2-75" to "6.2-76" for valve technical change. (3) (4) (5) 3995; (3) Added "6.2-76" under UFSAR Correction of typographical omission.

Ficiure for all valves after valve 3995; No technical change. (6) Valves now (4) Added Note 11 to all valves other in numeric order. No technical change.

than valve 3995; (5) Added "4" under Class for all valves other than 3995; (6) Reordered penetration valves.

85. Penetration 404 (1) Global Notes 1, 2, (1) No technical change. (2)

Correction of typographical error. No from "6.2-75" to "6.2-76" for valve technical change. (3) Correction of 3994; (3) Added Note 9 to all valves typographical omission. No technical other than 4000D; (4) Reordered change. (4) Valves now in numeric penetration valves. order. No technical change; Safety Analysis Revision 0 Page 42 NSL-0000-SA024

86. Penetration 1000 (1) Global Notes 1, (1) No technical change. (2) (3)

IV'1) 2, 4, and 5; (2) Added "Both" to Correction of typographical omission.

Position Relative to Containment; (3) No technical change.

87. Penetration 2000 (1) Global Notes 1, No technical change. (2) (3) 2, 4, and 5; (2) Added "Both" to Correction of typographical omission.

Position Relative to Containment; (3) No technical change.

"3. 8 3 Safety Analysis Revision 0 Page 43 NSL-0000-SA024

(1) Deleted last sentence of "old" Note (1) (2) The deleted sentence of the 1 and moved it to "new" Note 2; (2)

Renumbered remaining "old" Note 1 as note is still applied to necessary penetrations. No technical change.

Note 3.

2. Deleted "old" Note 2. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
3. Deleted "old" Note 3. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
4. (1) Deleted first two sentences of "old" (1) These two sentences only duplicated Note 4; (2) Modified last sentence to UFSAR text. No technical change. (2) reflect system configuration; (3) Sentence now accurately reflects Renumbered "old" Note 4 as Note 6. wording of the January 30, 1987 letter.

(3) No technical change.

5. Deleted "old" Note 5. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
6. Deleted "old" Note 6. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.
7. Deleted "old" Note 7. Note was only a duplication of the UFSAR text. No technical change.
8. Deleted "old" Note 8. Note was only a duplication of the UFSAR text. No technical change.

Safety Analysis Revision 0 Page 44 NSL-0000-SA024 Date 09 24 90

9. (1) Modified "old" Note 9; (2) (1) (2) Minor clarification only. Note Renumbered "old" Note 9 as Note 13. now describes in detail the use of the pressure transmitter as a boundary. No technical change.
10. Deleted "old" Note 10. Note was only a.duplication of the UFSAR text. See "new" Note 4. No technical change.

Deleted "old" Note 11. Note was only a duplication of the UFSAR text. See "new" Note 4. No technical change.

12. (1) Modified "old" Note 12; (2) Minor clarification only. No technical Renumbered to "new" Note 15. change.
13. Deleted "old" Note 13. Note was only a duplication of the UFSAR text. No technical change.
14. (1) Deleted last two sentences of "old" (1) The deleted sentence of the note is Note 14 and moved it to "new" Note 16; still applied to necessary (2) Modified remaining "old" Note 14; penetrations. No technical change.

(3) Renumbered "old" Note 14 as Note 17. (2) (3) Minor clarification of note only. No technical change.

15. Deleted "old" Note 15. Note was only a duplication of the UFSAR text. No technical change.
16. Deleted "old" Note 16. Note is incorrect and no longer applicable.
17. (1) Modified "old" Note 17; (2) (1) (2) Minor clarification of note Renumbered "old" note 17 as Note 21. only. No technical change.

Safety Analysis Revision 0 Page 45 NSL-0000-SA024

4

32. Added Note 20. Minor clarification only. Note provides additional information related to penetration's use. No technical change.

Safety Analysis Revision 0 Page 48 NSL-0000-SA024 Date 09 24 90

18. (1) Modified "old" Note 18; (2) (1) (2) Minor clarification of note Renumbered "old" Note 10 as Note 11. only. No technical change.
19. Added Note l. Note provides clarification on use of the penetration. See letter from R.

Mecredy, RG&E, to A. Johnson, NRC, dated March 13, 1990.

20. Added Note 2. Note provides generic description of penetration seals. Note originally part of "old" Note 1. No technical change.
21. Added Note 4. Minor clarification only. Note originally part of "old" Notes 2, 3, 5, 6, 10, and 11. Note now used on a global basis. No technical change.
22. Added Note 5. Minor clarification only. Note provides additional information related to penetration's use. No technical change.
23. Added Note 7. Note provides consistency with Technical Specification Table 3.6-1 Note 20. No technical change.
24. Added Note 8. Minor clarification only. Note provides additional information related to MOV breaker status. No technical change.

Safety Analysis Revision 0 Page 46 NSL-0000-SA024

k

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25. Added Note 9. Minor clarification only. Note provides additional information related to function of the valve. No technical change.
26. Added Note 10. Minor clarification only. Note provides detailed description of penetration valves. No technical change.
27. Added Note 12. Minor clarification only. No technical change.
28. Added Note 14. Note provides additional information related to penetration. See letter from R. Mecredy, RG&E, to A. Johnson, NRC, dated July 9, 1990.
29. Added Note 16. Note provides clarification of leakage test requirements. Note originally part of "old" Note 14. No technical change.
30. Added Note 18. Minor clarification only. Note provides additional information related to solenoid status. No technical change.
31. Added Note 19. Note provides consistency with Technical Specification Table 3.6-1 Note 22 and notes related to penetrations 313 and 317. No technical change.

Safety Analysis Revision 0 Page 47 NSL-0000-SA024

Table 1 Technical Specification Changes Chanches Effect Section 3.6.3.1 references No technical change.

UFSAR Table 6.2-13 instead of Technical Specification Table 3.6-1.

2. Table 3.6-1 removed from Valve listing remains in a Technical Specifications and licensee controlled document under information placed in UFSAR 10CFR50.59 program.

Table 6.2-13.

3. Revised inoperable No technical change. Clarification definition of Section only consistent with 10CFR50 3.6.3.1. Appendix J.
4. Removed note associated with Mini-purge valves have been Technical Specification installed so the Technical 3.6.5. Specification can be considered effective. No technical change.
5. Added "Pt" and necessary Addition of "Pt" provides definitions to Technical

~ ~

clarification of testing type Specification 4.4.1.4

~

~ consistent with 10CFR50, Appendix section a. J. All terms in 4.4.1.4, section a now fully defined. No technical change.

Added to the definition of Added definition "Lt" provides "Lt" in Technical clarification consistent with Specification 4.4.1.4 10CFR50, Appendix J. All terms in section b. 4.4.1.4, section b now fully defined. No technical change.

7. Added definition of "Pa" and Addition of "Pa" and "La" provides "Lam" in Technical clarification consistent with 10 Specification 4.4.1.4 CFR 50, Appendix J. All terms in section c. 4.4.1.4, section c now fully defined. No technical change.
8. Added steam generator Addition of this penetration inspection/maintenance provides testing criteria similar penetration to Technical to the equipment hatch and Specification 4.4.1.5 containment air locks.

section a (ii).

9. Revised first line of Minor clarification only. No Technical Specification technical change.

4.4.1.5, section a (ii) .

Removed notes associated with Technical Specification 4.4.2.4 section a. Deleted Mini-purge valves have been installed so the Technical Specification can be considered reference to section d. effective. Section d will be removed from Technical Specifications. No technical change.

11. Added steam generator Addition of this penetration inspection/maintenance provides testing criteria similar penetration to Technical to the equipment hatch and Specification 4.4.2.4 containment air locks.

section b.

12. Removed Technical Blind flanges have been installed Specification 4.4.2.4 so the Technical Specification can section d and associated be considered effective. No note. technical change.

1 3. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.5.1. 10CFR50.59 program.

14. Changed Reference from Table Valve listing remains in a 3.6-1 to UFSAR 6.2-13 in licensee controlled document under section 4.4.6.2. 10CFR50.59 program.

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