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| issue date = 02/07/1990
| issue date = 02/07/1990
| title = Application for Amends to Licenses DPR-58 & DPR-74,deleting Extension Limit,Per Generic Ltr 89-14, Line Item Improvement in Tech Specs-Removal of 3.25 Limit on Extending Surveillance Intervals.
| title = Application for Amends to Licenses DPR-58 & DPR-74,deleting Extension Limit,Per Generic Ltr 89-14, Line Item Improvement in Tech Specs-Removal of 3.25 Limit on Extending Surveillance Intervals.
| author name = ALEXICH M E
| author name = Alexich M
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| addressee name = MURLEY T E
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000315, 05000316
| docket = 05000315, 05000316
Line 14: Line 14:
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 13
| page count = 13
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:.A.CCELKRATED DIBUTfONDEMONSONSYSTEMREGULATOINFORMATION DISTRIBUTION TEM(RIDS)ACCESSION NBR:9002220473 DOC.DATE:
{{#Wiki_filter:. A.CCELKRATED           DI      BUTfON        DEMONS              ON    SYSTEM REGULATO    INFORMATION DISTRIBUTION           TEM (RIDS)
90/02/07NOTARIZED:
ACCESSION NBR:9002220473         DOC.DATE:   90/02/07    NOTARIZED: NO          DOCKET  I FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana                 & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana              a 05000316 AUTH. NAME          AUTHOR AFFILIATION ALEXICH,M.E.         Indiana Michigan Power Co. (formerly Indiana            6 Michigan Ele RECIP.NAME         RECIPIENT AFFILIATION MURLEY,T.E.             Document Control Branch (Document         Control Desk)
NODOCKETIFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Indiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indianaa05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.E.
IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
DocumentControlBranch(Document ControlDesk)


==SUBJECT:==
==SUBJECT:==
Application foramendstoLicensesDPR-58&DPR-74.Amends modTechSpecs4.0.2.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLTITLE:ORSubmittal:
Application for    amends  to Licenses    DPR-58   & DPR-74.Amends mod Tech Specs    4.0.2.
GeneralDistribution NOTES:SIZE:RECIPIENT IDCODE/NAME PD3-1LAGIITTERrJ.
DISTRIBUTION CODE: A001D        COPIES RECEIVED:LTR           ENCL      SIZE:
INTERNAL:
TITLE:   OR  Submittal: General Distribution NOTES:
NRR/DET/ECMB 9HNRR/DST8E2NRR/DST/SICB 7ENUDOCS-ABSTRACT OGC/HDS1RES/DSIR/EIB EXTERNAL:
RECIPIENT          COPIES              RECIPIENT           COPIES ID CODE/NAME       LTTR ENCL        ID CODE/NAME        LTTR ENCL PD3-1 LA                1    1      PD3-1  PD                1    1              h GIITTERrJ.               5    5 INTERNAL: NRR/DET/ECMB 9H            1    1      NRR/DOEA/OTSB11          1    1 NRR/DST        8E2      1    1      NRR/DST/SELB 8D          1    1 NRR/DST/SICB 7E          1    1      NRR/DST/SRXB 8E          1    1 NUDOCS-ABSTRACT         1    1      O~CJ EMB                1    0 OGC/HDS1                1    0        EG  FILE                1    1 RES/DSIR/EIB             1    1 EXTERNAL: LPDR                      1    1      NRC PDR                  1    1 NSIC                    1    1 D
LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DOEA/OTSB11 NRR/DST/SELB 8DNRR/DST/SRXB 8EO~CJEMBEGFILENRCPDRCOPIESLTTRENCL11111111101111hNCTEIOALLrrRZDS>>MKIPIENIS PIZASEHELPUSIOREDUCE%ASTElCGHI'ACI'IHE DOQ3MERI'XÃIBDL DESKRDCNPl-37(EXT.20079)IOEIiQGÃAK%3 RXHtMrrMEPKHDIBTRIBUTI(W LISTSFORDOCQMEHZS RXJDCHITNEEDIDDTOTALNUMBEROFCOPIESREQUIRED:
D NCTE IO ALL rrRZDS>> MKIPIENIS PIZASE HELP US IO REDUCE %ASTEl CGHI'ACI'IHE DOQ3MERI'XÃIBDL DESK RDCN Pl-37 (EXT. 20079) IO EIiQGÃAK%3 RXHt MrrME PKH DIBTRIBUTI(W LISTS FOR DOCQMEHZS RXJ DCHIT NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR            21  ENCL    19
LTTR21ENCL19
~IElIW IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH43216AEP:NRC:1021 GL89-14DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74GENERICLETTER89-14TECHNICAL SPECIFICATION CHANGESU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyFebruary7,1990


==DearDr.Murley:==
      ~ I El I
Thisletteranditsattachments constitute anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldCDCookNuclearPlantUnits1and2.Specifically, weproposetomodifyTechnical Specification
W


==4.0. 2anditsassociated==
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1021 GL 89-14 Donald C. Cook Nuclear Plant Units 1 and      2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 GENERIC LETTER      89-14 TECHNICAL SPECIFICATION  CHANGES U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Attn: T.      E. Murley February 7, 1990
Bases.Technical Specification


==4.0. 2permitssurveillance==
==Dear Dr. Murley:==
intervals tobeextendedupto25percentofthespecified interval.
Italsolimitsextending surveillances sothatthecombinedtimeintervals for'nythreeconsecutive surveillances intervals donotexceed3.25timesthespecified surveillance interval.
Thisapplication foramendment proposestodeletethe3.25extension limitinaccordance withtheguidanceinGenericLetter89-14,"LineItemImprovement inTechnical Specifications-Removal ofthe3.25LimitonExtending Surveillance Intervals."
Ourreasonsfortheproposedchanges,aswellasouranalysesconcerning significant hazardsconsiderations, arecontained inAttachment 1tothisletter.Attachment 2ofthissubmittal containsproposedrevisedT/Spagesthatreflecttheproposedchanges.Inaddition, werequestthattheamendment beissuedbySeptember 1,1990andbeeffective immediately topreventanunnecessary shutdownofCookNuclearPlantUnit1.0olPDRADOCK05000315 Dr.T.E.Murley-2-AEP:NRC'1021 Webelievethattheproposedchangeswillnotresultin(1)significant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
ThesechangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andbytheNuclearSafetyandDesignReviewCommi.ttee.
Incompliance withtherequirements of10CFR50.91(b)(l),
copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporates areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
Sincerely, MP.AlexichVicePresident ehAttachments cc:D.H.Williams, Jr.A.A.Blind-BridgmanR.C.CallenG.CharnoffA.B.DavisNRCResidentInspector
-BridgmanNFEMSectionChief


Attachment 1toAEP:NRC:1021 Reasonsand10CFR50.92AnalysesforChangestotheDonaldC.CookNuclearPlantUnits1and2Technical Specifications Attachment 1toAEP:NRC:1021 Page1DescritionofChaneAssuggested inGenericLetter89-14,thisapplication foramendment proposestoreviseTechnical Specification (T/S)4.0.2byremovingtherequirement thatthecombinedtimeintervalforanythreeconsecutive surveillance intervals shallnotexceed3.25timesthespecified surveillance interval.
This    letter and  its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald      CD Cook Nuclear Plant Units 1 and 2. Specifically, we propose to modify Technical Specification 4.0.2 and its associated Bases.
Additionally, weareproposing tomodifytheassociated TSBases.BackroundTechnical Specification
Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval.       It also limits extending surveillances so that the combined time intervals for'ny three consecutive surveillances intervals do not exceed 3.25 times the specified surveillance interval. This application for amendment proposes to delete the 3.25 extension limit in accordance with the guidance in Generic Letter 89-14, "Line Item Improvement in Technical Specifications-Removal of the 3.25 Limit on Extending Surveillance Intervals."
Our reasons      for the proposed changes, as well as our analyses concerning significant hazards considerations, are contained in Attachment 1 to this letter.
Attachment      2 of this submittal contains proposed revised  T/S pages that reflect the proposed changes.
In addition,     we request that the amendment be issued by September 1, 1990 and be effective immediately to prevent an unnecessary shutdown of Cook Nuclear Plant Unit 1.
0ol PDR      ADOCK    05000315


==4.0. 2permitssurveillance==
Dr. T. E. Murley                                  AEP:NRC'1021 We  believe that the proposed changes    will not result in (1) significant change in the types    of  effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
intervals tobeextendedupto25percentofthespecified interval.
These changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Commi.ttee.
Thisexten-sionfacilitates scheduling activities andallowssurveillances tobepostponed whenplantconditions arenotsuitableforconducting asurveillance.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. R.
Specification
C. Callen of the Michigan Public Service Commission and Mr. G.
Bruchmann of the Michigan Department of Public Health.
This document has been prepared following Corporate procedures that incorporates a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M  P. Alexich Vice President eh Attachments cc:    D. H. Williams, Jr.
A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC  Resident Inspector - Bridgman NFEM  Section Chief
 
Attachment  1 to AEP:NRC:1021 Reasons  and 10 CFR 50.92 Analyses for Changes  to the Donald C. Cook  Nuclear Plant Units  1 and 2  Technical Specifications
 
Attachment    1 to  AEP:NRC:1021                                    Page 1 Descri tion of      Chan e As suggested in Generic Letter 89-14,        this application for amendment proposes to revise Technical        Specification (T/S) 4.0.2 by removing the requirement that        the combined time  interval for any three consecutive surveillance        intervals shall not exceed 3.25 times the specified surveillance interval. Additionally, we are proposing to modify the associated TS Bases.
Back round Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval. This exten-sion facilitates scheduling activities and allows surveillances to be postponed when plant conditions are not suitable for conducting a surveillance.        Specification 4.0.2 also limits extending surveillances so that the combined time interval for any three consecutive time. intervals shall not exceed 3.25 times the specified surveillance interval. On August 21, 1989, the NRC issued Generic Letter 89-14, "Line-Item Improvements in Technical Specifications - Removal of the 3.25 Limit on Extending Surveillance Intervals." The Generic Letter concluded that removal of the 3.25 limit from Specification 4.0.2 results in a "greater benefit to safety than limiting the use of the 25 percent allowance to extend surveillance intervals-.
Im  act on Plant    0  erations Approval of this request        will provide  the following benefits:
: 1. Facilitates scheduling of surveillance activities        and allows surveillances to be postponed when plant conditions are not conducive to the safe conduct of a surveillance.
: 2. Reduces  the potential for unnecessary    forced shutdowns to perform surveillance activities.
: 3. Eliminates the administrative and logistical burden associated with tracking the use of the 25 percent allowance to ensure compliance with the 3.25 limit.
: 4. Minimizes the need      for surveillance interval extension amendments.
Safet    Evaluation Many  surveillances have a specified surveillance interval of 18 months. Generally, an 18-month surveillance interval is intended


==4.0. 2alsolimitsextending==
surveillances sothatthecombinedtimeintervalforanythreeconsecutive time.intervals shallnotexceed3.25timesthespecified surveillance interval.
OnAugust21,1989,theNRCissuedGenericLetter89-14,"Line-Item Improvements inTechnical Specifications
-Removalofthe3.25LimitonExtending Surveillance Intervals."
TheGenericLetterconcluded thatremovalofthe3.25limitfromSpecification 4.0.2resultsina"greaterbenefittosafetythanlimitingtheuseofthe25percentallowance toextendsurveillance intervals-.
ImactonPlant0erationsApprovalofthisrequestwillprovidethefollowing benefits:
1.Facilitates scheduling ofsurveillance activities andallowssurveillances tobepostponed whenplantconditions arenotconducive tothesafeconductofasurveillance.
2.Reducesthepotential forunnecessary forcedshutdowns toperformsurveillance activities.
3.Eliminates theadministrative andlogistical burdenassociated withtrackingtheuseofthe25percentallowance toensurecompliance withthe3.25limit.4.Minimizes theneedforsurveillance intervalextension amendments.
SafetEvaluation Manysurveillances haveaspecified surveillance intervalof18months.Generally, an18-monthsurveillance intervalisintended
~
~
Attachment 1toAEP:NRC:1021 Page2toallowthesurveillance tobeperformed whentheunit'sshutdownduringarefueling outage.Therefore, theactualtimeintervalfortheperformance ofthesesurveillances isdependent onthelengthofafuelcycle,butitcannotexceed18monthsplusthe25percentallowance.
Attachment   1 to AEP:NRC:1021                                 Page 2 to allow the surveillance to be performed when the unit's shutdown during a refueling outage. Therefore, the actual time interval for the performance of these surveillances is dependent on the length of a fuel cycle, but it cannot exceed 18 months plus the 25 percent allowance. The safety benefit of performing these surveillances during a plant shutdown is that systems do not have to be zemoved from service at a time that they are required to be operable. ,This minimizes the amount of time which systems are unavailable during power operation due to surveillance requirements, thereby minimizing the impact on safety, In a few instances, the TS specifically require some surveillances to be performed during a plant shutdown, When a limit is reached on extending an 18-month interval, a forced plant shutdown to perform these surveillances is generally the only alternative short of a license amendment that defers the performance of these surveillances until the end of a fuel cycle.
Thesafetybenefitofperforming thesesurveillances duringaplantshutdownisthatsystemsdonothavetobezemovedfromserviceatatimethattheyarerequiredtobeoperable.
Usually, the length of a fuel cycle would not exceed 18 months by more than the 25 percent allowance, i.e., 4-1/2 months, A more common situation has been to encounter the 3,25 limit on the combined time interval for three consecutive surveillance intervals. The NRC staff has normally approved one-time amendment requests to waive the performance of 18-month surveillances until the end of the fuel cycle when they would exceed the 3.25 limitation on consecutive surveillances yet would not exceed the 25 percent allowance for extending the 18-month surveillance interval. A forced shutdown to perform these surveillances is not
,Thisminimizes theamountoftimewhichsystemsareunavailable duringpoweroperation duetosurveillance requirements, therebyminimizing theimpactonsafety,Inafewinstances, theTSspecifically requiresomesurveillances tobeperformed duringaplantshutdown, Whenalimitisreachedonextending an18-monthinterval, aforcedplantshutdowntoperformthesesurveillances isgenerally theonlyalternative shortofalicenseamendment thatdeferstheperformance ofthesesurveillances untiltheendofafuelcycle.Usually,thelengthofafuelcyclewouldnotexceed18monthsbymorethanthe25percentallowance, i.e.,4-1/2months,Amorecommonsituation hasbeentoencounter the3,25limitonthecombinedtimeintervalforthreeconsecutive surveillance intervals.
  )ustified from a risk standpoint to avoid exceeding the 3.25 limit when extending these surveillances is within the 25 percent allowance. The 18-month surveillances are normally performed during a refueling outage when the plant is in a desirable condition for conducting, these surveillances. As stated in the NRC's Safety Evaluation for Commonwealth Edison's LaSalle Station, the risk of performing some of these surveillances during plant operation has been determined to be greater than the impact on safety of exceeding the 3 '5 limit.
TheNRCstaffhasnormallyapprovedone-timeamendment requeststowaivetheperformance of18-monthsurveillances untiltheendofthefuelcyclewhentheywouldexceedthe3.25limitation onconsecutive surveillances yetwouldnotexceedthe25percentallowance forextending the18-monthsurveillance interval.
In addition to its application to refueling outage surveillances, the use of the  25 percent allowance for extending surveillance intervals can provide a safety benefit when it is used during plant operation, When plant conditions are not suitable for the conduct of suzveillances due to safety systems out-of-service for maintenance oz due to other ongoing activities, safety is enhanced by the use'f the allowance that permits a surveillance interval to be extended, In such cases, the safety benefit of extending a surveillance interval up to 25 percent would exceed the risk reduction derived by conforming to the 3.25 limitation.
Aforcedshutdowntoperformthesesurveillances isnot)ustified fromariskstandpoint toavoidexceeding the3.25limitwhenextending thesesurveillances iswithinthe25percentallowance.
 
The18-monthsurveillances arenormallyperformed duringarefueling outagewhentheplantisinadesirable condition forconducting, thesesurveillances.
, I 4I to  AEP:NRC:1021                                 Page 3 Zn summary,     based on the above considerations, the removal of the 3.25 limit will have an overall positive impact on safety.
AsstatedintheNRC'sSafetyEvaluation forCommonwealth Edison'sLaSalleStation,theriskofperforming someofthesesurveillances duringplantoperation hasbeendetermined tobegreaterthantheimpactonsafetyofexceeding the3'5limit.Inadditiontoitsapplication torefueling outagesurveillances, theuseofthe25percentallowance forextending surveillance intervals canprovideasafetybenefitwhenitisusedduringplantoperation, Whenplantconditions arenotsuitablefortheconductofsuzveillances duetosafetysystemsout-of-service for"maintenance ozduetootherongoingactivities, safetyisenhancedbytheuse'ftheallowance thatpermitsasurveillance intervaltobeextended, Insuchcases,thesafetybenefitofextending asurveillance intervalupto25percentwouldexceedtheriskreduction derivedbyconforming tothe3.25limitation.  
Consequently, we believe there is reasonable assurance that the proposed, change will not adversely affect the health and safety of the public, Si nificant Hazards Considerations Per 10  CFR  50.92, a proposed amendment will not involve a significant      hazards consideration  if the proposed amendment does not:
,I4I Attachment 1toAEP:NRC:1021 Page3Znsummary,basedontheaboveconsiderations, theremovalofthe3.25limitwillhaveanoverallpositiveimpactonsafety.Consequently, webelievethereisreasonable assurance thattheproposed, changewillnotadversely affectthehealthandsafetyofthepublic,SinificantHazardsConsiderations Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.Criterion 1Deletionofthe3.25extension limitation willnotsignificantly affectequipment reliability anddoesnotaffecttheprobability orconsequences ofaccidents previously evaluated intheFSARUpdate.Thesurveillance intervalwillstillbeconstrained bythe25percentintervalextension criteriaofT/S4.0.2.Theriskinvolvedwiththealternative toperform18-monthsurveillances duringplantoperation isgreaterthantheriskinvolvedwithexceeding the3.25limit.Whenplantconditions arenotconducive forthesafeconductofsurveillances duetosafetysystemsbeingout-of-service formaintenance orduetootherongoingsurveillance activities, safetyisenhancedbytheuseoftheallowance thatpermitsasurveillance intervaltobeextended.
(1) involve    a  significant increase in the probability or consequences      of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve    a  significant reduction in  a margin of safety.
Therefore, theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Criterion   1 Deletion of the 3.25 extension limitation will not significantly affect equipment reliability and does not affect the probability or consequences of accidents previously evaluated in the FSAR Update. The surveillance interval will still be constrained by the 25 percent interval extension criteria of T/S 4.0.2. The risk involved with the alternative to perform 18-month surveillances during plant operation is greater than the risk involved with exceeding the 3.25 limit. When plant conditions are not conducive for the safe conduct of surveillances due to safety systems being out-of-service for maintenance or due to other ongoing surveillance activities, safety is enhanced by the use of the allowance that permits a surveillance interval to be extended.
Criterion 2TheproposedrevisiontotheT/Swillnotresultinanyphysicalalteration toanyplantsystem,norwouldtherebeachangeinthemethodbywhichanysafety-related systemperformsitsfunction.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Therefore, theproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Criterion   2 The proposed      revision to the T/S will not result in any physical alteration to      any plant system, nor would there be a change in the method  by which any safety-related system performs its function.
Attachment 1toAEP:NRC:1021 Page4Criterion 3Deletionoftherequirement thatanythreeconsecutive surveillance intervals shallnotexceed3.25timestheintervalwillnotsignificantly affectequipment reliability, ratheritwillreducethepotential tointerrupt normalplantoperations duetosurveillance scheduling, Thisproposedexemption willallowallsurveillance intervals tobeconstrained bythemaximumallowable extension of25percentofthespecified surveillance
Therefore, the proposed change does not create the possibility of a new  or different kind of accident from any accident previously evaluated.
: interval, whichmayenhancesafetywhenusedduringplantoperation, Therefore, theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.Lastly,wenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870) ofamendments considered notlikelytoinvolvesignificant hazardsconsiderations.
to AEP:NRC:1021                               Page 4 Criterion  3 Deletion of the requirement that any three consecutive surveillance intervals shall not exceed 3.25 times the interval will not significantly affect equipment reliability, rather    it will reduce the potential to interrupt normal plant operations due to surveillance scheduling, This proposed exemption will allow all surveillance intervals to be constrained by the maximum allowable extension of 25 percent of the specified surveillance interval, which may enhance safety when used during plant operation, Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreaseintheprobability ofoccurrence orconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofwhichareclearlywithinlimitsestablished asacceptable.
Lastly, we  note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48FR14870) of amendments considered not likely to involve significant hazards considerations. The sixth of these examples refers to changes which may result in some increase in the probability of occurrence or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of which are clearly within limits established as acceptable. The effect of the proposed T/S changes will be to provide deletion of the 3.25 extension limitation found in T/S 4.0.2. The changes, however, are supported, by Generic Letter 89-14. Therefore, we conclude that the example cited is relevant and that the changes should not involve significant hazards considerations.
TheeffectoftheproposedT/Schangeswillbetoprovidedeletionofthe3.25extension limitation foundinT/S4.0.2.Thechanges,however,aresupported, byGenericLetter89-14.Therefore, weconcludethattheexamplecitedisrelevantandthatthechangesshouldnotinvolvesignificant hazardsconsiderations.
 
Attachment 2toAEP:NRC:1021-ProposedRevisedTechnical Specification Changes}}
Attachment 2 to AEP:NRC:1021-Proposed Revised Technical Specification Changes}}

Latest revision as of 00:50, 4 February 2020

Application for Amends to Licenses DPR-58 & DPR-74,deleting Extension Limit,Per Generic Ltr 89-14, Line Item Improvement in Tech Specs-Removal of 3.25 Limit on Extending Surveillance Intervals.
ML17328A569
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/07/1990
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17328A570 List:
References
AEP:NRC:1021, GL-89-14, NUDOCS 9002220473
Download: ML17328A569 (13)


Text

. A.CCELKRATED DI BUTfON DEMONS ON SYSTEM REGULATO INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:9002220473 DOC.DATE: 90/02/07 NOTARIZED: NO DOCKET I FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana a 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to Licenses DPR-58 & DPR-74.Amends mod Tech Specs 4.0.2.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 h GIITTERrJ. 5 5 INTERNAL: NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 O~CJ EMB 1 0 OGC/HDS1 1 0 EG FILE 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D

D NCTE IO ALL rrRZDS>> MKIPIENIS PIZASE HELP US IO REDUCE %ASTEl CGHI'ACI'IHE DOQ3MERI'XÃIBDL DESK RDCN Pl-37 (EXT. 20079) IO EIiQGÃAK%3 RXHt MrrME PKH DIBTRIBUTI(W LISTS FOR DOCQMEHZS RXJ DCHIT NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19

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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1021 GL 89-14 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 GENERIC LETTER 89-14 TECHNICAL SPECIFICATION CHANGES U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley February 7, 1990

Dear Dr. Murley:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald CD Cook Nuclear Plant Units 1 and 2. Specifically, we propose to modify Technical Specification 4.0.2 and its associated Bases.

Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval. It also limits extending surveillances so that the combined time intervals for'ny three consecutive surveillances intervals do not exceed 3.25 times the specified surveillance interval. This application for amendment proposes to delete the 3.25 extension limit in accordance with the guidance in Generic Letter 89-14, "Line Item Improvement in Technical Specifications-Removal of the 3.25 Limit on Extending Surveillance Intervals."

Our reasons for the proposed changes, as well as our analyses concerning significant hazards considerations, are contained in Attachment 1 to this letter.

Attachment 2 of this submittal contains proposed revised T/S pages that reflect the proposed changes.

In addition, we request that the amendment be issued by September 1, 1990 and be effective immediately to prevent an unnecessary shutdown of Cook Nuclear Plant Unit 1.

0ol PDR ADOCK 05000315

Dr. T. E. Murley AEP:NRC'1021 We believe that the proposed changes will not result in (1) significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

These changes have been reviewed by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Commi.ttee.

In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. R.

C. Callen of the Michigan Public Service Commission and Mr. G.

Bruchmann of the Michigan Department of Public Health.

This document has been prepared following Corporate procedures that incorporates a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M P. Alexich Vice President eh Attachments cc: D. H. Williams, Jr.

A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC Resident Inspector - Bridgman NFEM Section Chief

Attachment 1 to AEP:NRC:1021 Reasons and 10 CFR 50.92 Analyses for Changes to the Donald C. Cook Nuclear Plant Units 1 and 2 Technical Specifications

Attachment 1 to AEP:NRC:1021 Page 1 Descri tion of Chan e As suggested in Generic Letter 89-14, this application for amendment proposes to revise Technical Specification (T/S) 4.0.2 by removing the requirement that the combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval. Additionally, we are proposing to modify the associated TS Bases.

Back round Technical Specification 4.0.2 permits surveillance intervals to be extended up to 25 percent of the specified interval. This exten-sion facilitates scheduling activities and allows surveillances to be postponed when plant conditions are not suitable for conducting a surveillance. Specification 4.0.2 also limits extending surveillances so that the combined time interval for any three consecutive time. intervals shall not exceed 3.25 times the specified surveillance interval. On August 21, 1989, the NRC issued Generic Letter 89-14, "Line-Item Improvements in Technical Specifications - Removal of the 3.25 Limit on Extending Surveillance Intervals." The Generic Letter concluded that removal of the 3.25 limit from Specification 4.0.2 results in a "greater benefit to safety than limiting the use of the 25 percent allowance to extend surveillance intervals-.

Im act on Plant 0 erations Approval of this request will provide the following benefits:

1. Facilitates scheduling of surveillance activities and allows surveillances to be postponed when plant conditions are not conducive to the safe conduct of a surveillance.
2. Reduces the potential for unnecessary forced shutdowns to perform surveillance activities.
3. Eliminates the administrative and logistical burden associated with tracking the use of the 25 percent allowance to ensure compliance with the 3.25 limit.
4. Minimizes the need for surveillance interval extension amendments.

Safet Evaluation Many surveillances have a specified surveillance interval of 18 months. Generally, an 18-month surveillance interval is intended

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Attachment 1 to AEP:NRC:1021 Page 2 to allow the surveillance to be performed when the unit's shutdown during a refueling outage. Therefore, the actual time interval for the performance of these surveillances is dependent on the length of a fuel cycle, but it cannot exceed 18 months plus the 25 percent allowance. The safety benefit of performing these surveillances during a plant shutdown is that systems do not have to be zemoved from service at a time that they are required to be operable. ,This minimizes the amount of time which systems are unavailable during power operation due to surveillance requirements, thereby minimizing the impact on safety, In a few instances, the TS specifically require some surveillances to be performed during a plant shutdown, When a limit is reached on extending an 18-month interval, a forced plant shutdown to perform these surveillances is generally the only alternative short of a license amendment that defers the performance of these surveillances until the end of a fuel cycle.

Usually, the length of a fuel cycle would not exceed 18 months by more than the 25 percent allowance, i.e., 4-1/2 months, A more common situation has been to encounter the 3,25 limit on the combined time interval for three consecutive surveillance intervals. The NRC staff has normally approved one-time amendment requests to waive the performance of 18-month surveillances until the end of the fuel cycle when they would exceed the 3.25 limitation on consecutive surveillances yet would not exceed the 25 percent allowance for extending the 18-month surveillance interval. A forced shutdown to perform these surveillances is not

)ustified from a risk standpoint to avoid exceeding the 3.25 limit when extending these surveillances is within the 25 percent allowance. The 18-month surveillances are normally performed during a refueling outage when the plant is in a desirable condition for conducting, these surveillances. As stated in the NRC's Safety Evaluation for Commonwealth Edison's LaSalle Station, the risk of performing some of these surveillances during plant operation has been determined to be greater than the impact on safety of exceeding the 3 '5 limit.

In addition to its application to refueling outage surveillances, the use of the 25 percent allowance for extending surveillance intervals can provide a safety benefit when it is used during plant operation, When plant conditions are not suitable for the conduct of suzveillances due to safety systems out-of-service for maintenance oz due to other ongoing activities, safety is enhanced by the use'f the allowance that permits a surveillance interval to be extended, In such cases, the safety benefit of extending a surveillance interval up to 25 percent would exceed the risk reduction derived by conforming to the 3.25 limitation.

, I 4I to AEP:NRC:1021 Page 3 Zn summary, based on the above considerations, the removal of the 3.25 limit will have an overall positive impact on safety.

Consequently, we believe there is reasonable assurance that the proposed, change will not adversely affect the health and safety of the public, Si nificant Hazards Considerations Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:

(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.

Criterion 1 Deletion of the 3.25 extension limitation will not significantly affect equipment reliability and does not affect the probability or consequences of accidents previously evaluated in the FSAR Update. The surveillance interval will still be constrained by the 25 percent interval extension criteria of T/S 4.0.2. The risk involved with the alternative to perform 18-month surveillances during plant operation is greater than the risk involved with exceeding the 3.25 limit. When plant conditions are not conducive for the safe conduct of surveillances due to safety systems being out-of-service for maintenance or due to other ongoing surveillance activities, safety is enhanced by the use of the allowance that permits a surveillance interval to be extended.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Criterion 2 The proposed revision to the T/S will not result in any physical alteration to any plant system, nor would there be a change in the method by which any safety-related system performs its function.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

to AEP:NRC:1021 Page 4 Criterion 3 Deletion of the requirement that any three consecutive surveillance intervals shall not exceed 3.25 times the interval will not significantly affect equipment reliability, rather it will reduce the potential to interrupt normal plant operations due to surveillance scheduling, This proposed exemption will allow all surveillance intervals to be constrained by the maximum allowable extension of 25 percent of the specified surveillance interval, which may enhance safety when used during plant operation, Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48FR14870) of amendments considered not likely to involve significant hazards considerations. The sixth of these examples refers to changes which may result in some increase in the probability of occurrence or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of which are clearly within limits established as acceptable. The effect of the proposed T/S changes will be to provide deletion of the 3.25 extension limitation found in T/S 4.0.2. The changes, however, are supported, by Generic Letter 89-14. Therefore, we conclude that the example cited is relevant and that the changes should not involve significant hazards considerations.

Attachment 2 to AEP:NRC:1021-Proposed Revised Technical Specification Changes