|
|
(6 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 12/22/1986 | | | issue date = 12/22/1986 |
| | title = Application to Amend Licenses DPR-58 & DPR-74,modifying Tech Spec 5.3.1 to Delete Ref to Max U Weight Per Assembly & to Correct Minor Editorial Changes.Fee Paid | | | title = Application to Amend Licenses DPR-58 & DPR-74,modifying Tech Spec 5.3.1 to Delete Ref to Max U Weight Per Assembly & to Correct Minor Editorial Changes.Fee Paid |
| | author name = ALEXICH M P | | | author name = Alexich M |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = DENTON H R | | | addressee name = Denton H |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ACCESSIONNBR:FACIL:50-31550-31mAUTH.NAI]EALEXICH.N'RECIP.NANEDENTQNpH.R.REGULATORYIFQRNATIONDISTRIBUTIONSYel't(RIDS)8612300253DQC.DATE:86/12/22NOTARIZED:NODOCKET¹DonaldC.CookNuclearPowerPlant.Unit1>Indiana505000315DonaldC.CookNuclearPowerPlantiUnit2>Indiana00500031bAUTHORAFFILIATIONIndiana8cNichiganElectricCo.RECIPIENTAFFILIATIONOfficeofNuclearReactorRegulationtDirector(post851125 | | {{#Wiki_filter:REGULATORY I FQRNATION DISTRIBUTION SY el't (R IDS) |
| | ACCESSION NBR: 8612300253 DQC. DATE: 86/12/22 NOTARIZED: NO DOCKET ¹ FAC IL: 50-315 Donald C. Cook Nuclear Power Plant. Unit 1> Indiana 5 05000315 50-31m Donald C. Cook Nuclear Power Planti Unit 2> Ind iana 0 0500031b AUTH. NAI]E AUTHOR AFFILIATION ALEXICH. N' Indiana 8c Nichigan Electric Co. |
| | RECIP. NANE RECIPIENT AFFILIATION DENTQNp H. R. f Of i ce of Nuclear Reactor Regulationt Direc tor (p ost 851125 SUB JECT: Application to amend Licenses DPR-58 DPR-74> modif ging Tech Zc Spec 5. 3. 1 to delete ref to max U weight per assembly 0 to correct minor editorial changes. Fee paid. |
| | DIBTRIBUTION CODE: AOCID COPTER RECEIVED: LTR ) ENCL Q SIZE: l + ( |
| | TITLE: QR Submittal: General Distribution NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAl'lE LTTR ENCL ID CODE/NANE LTTR ENCL PWR-A EB 1 1 PWR-A EICSB 2 2 PWR-A FOB 1 PWR-A PD4 LA 1 0 PWR-A PD4 PD 01 5 5 WIQQINQTONi D 1 1 PWR-A PSB 1 1 PWR-A RSB 1 1 1E INTERNAL: ADN/LFNB 1 0 ELD/HDS3 1 0 NRR/DHFT/TSCB 1 1 NRR/GRAS 1 0 04 1 1 RQN3 1 1 EXTERNAL: E('@('RUSKE, S 1 LPDR 03 2 2 NRC PDR 02 1 1 NSIC 05 1 48'R( P~gg- g)lyg |
| | <5 aA TOTAL NUl'tBER OF COPIES REQUIRED: LTTR . 2+ ENCL |
|
| |
|
| ==SUBJECT:==
| | t h I 4 I ~ H - t h'I 'l |
| ApplicationtoamendLicensesDPR-58ZcDPR-74>modifgingTechSpec5.3.1todeletereftomaxUweightperassembly0tocorrectminoreditorialchanges.Feepaid.DIBTRIBUTIONCODE:AOCIDCOPTERRECEIVED:LTR)ENCLQSIZE:l+(TITLE:QRSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAl'lEPWR-AEBPWR-AFOBPWR-APD4PD01PWR-APSBINTERNAL:ADN/LFNBNRR/DHFT/TSCB04COPIESLTTRENCL1115511101111RECIPIENTIDCODE/NANEPWR-AEICSBPWR-APD4LAWIQQINQTONiDPWR-ARSB1EELD/HDS3NRR/GRASRQN3COPIESLTTRENCL22101111101011EXTERNAL:E('@('RUSKE,SNRCPDR02111LPDRNSIC030522148'R(P~gg-g)lyg<5aATOTALNUl'tBEROFCOPIESREQUIRED:LTTR.2+ENCL
| | 'K I >>) I HI>>, |
| *thI4I~H-t'KIh'I'l>>)~IHI>>,Hlh4If>>HKI<<1,HhtI'Hdghgfh/1lh'41fl"WHHHJll~,I44IIWIh',
| | ~ H lh 4 If>> HKI |
| INDIANA8MICHIGANELECTRICCOMPANYP,O.BOX16631COLUMBUS,OHIO43216December22,1986AEP:NRC:1016DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74FUELASSEMBLYURANIUMMASSTECHNICALSPECIFICATIONCHANGEMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555
| | <<1, H ht I'H d |
| | gh g fh/ 1 lh' 41 fl" W H |
| | H I , |
| | H ll ~ |
| | J 4 4 II Ih', W |
|
| |
|
| ==DearMr.Denton:== | | INDIANA 8 MICHIGAN ELECTRIC COMPANY P,O. BOX 16631 COLUMBUS, OHIO 43216 December 22, 1986 AEP:NRC:1016 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 FUEL ASSEMBLY URANIUM MASS TECHNICAL SPECIFICATION CHANGE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| ThisletteranditsattachmentsconstituteanapplicationforamendmenttotheTechnicalSpecifications(T/Ss)fortheDonaldC.CookNuclearPlantUnitNos.1and2.Specifically,weproposetomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies)todeletereferencetoamaximumuraniumweightperassemblyandtocorrectminoreditorialchanges'hereasonsfortheproposedchangesandouranalysesconcerningsignificanthazardsconsiderationsarecontainedinAttachment1tothisletter.TheproposedrevisedT/SpagesarecontainedinAttachment2.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee(PNSRC)andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee(NSDRC)attheirnextregularlyscheduledmeeting.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.R.C.CallenoftheMichiganPublicServiceCommissionandMr.G.BruchmannoftheMichiganDepartmentofPublicHealth.Pursuantto10CFR170.12(c),wehaveenclosedanapplicationfeeof$150.00fortheproposedamendments.86i2300253861222~PDR*DOCK05000315('PDR~I, L~~~CI Mr.HaroldR.Denton-2-AEP:NRC:1016ThisdocumenthasbeenpreparedfollowingCorporateprocedureswhichincorporateareasonablesetofcontrolstoinsureitsaccuracyandcompletenesspriortosignaturebytheundersigned.Verytrulyyours,MPA/cmAttachmentsM..AleichVicePresidentIply'll>>cc:JohnE.DolanW.G.Smith,Jr.-BridgmanR.C.CallenG.BruchmannG.CharnoffNRCResidentInspector-Bridgman Attachment1toAEP:NRC:1016Reasonsand10CFR50.92AnalysesforChangestotheDonaldC.CookNuclearPlantUnitNos.1and2TechnicalSpecifications Attachment1toAEP:RC:1016Page1ThislicenseamendmentrequestproposestomodifyT/S5.3.1(DesignFeatures-ReactorCoreFuelAssemblies)forUnits1and2todeletereferencetoamaximumuraniumweightperassembly.BackroundByletterdatedSeptember4,1986(Attachment3),WestinghouseElectricCorporation(Westinghouse)officiallynotifiedusofadiscrepancyinvolvingthemaximumuraniumweightperassemblyspecifiedinT/S5.3.1'orUnit1.Specifically,Westinghouseinformedusthatrecentimprovementstotheirfueldesign(includingchamferedpelletswithareduceddishandanominaldensityincrease)haveincreasedfuelweightslightly.Theweightincreaseshavecausedthemaximumfuelrodweighttoexceedthemaximumvalueof2236gramsspecifiedinUnit1DesignFeaturesT/S5.3.1.WestinghousealsoprovideduswithproposedwordingandjustificationforaT/Schange,aswell,asajustificationforcontinuedoperation.WestinghousehadnotifiedusoftheconditioninformallyinAprilofthisyear.Atthattime,theissuewasdiscussedwithyourstaff,whoinformedustheissuecouldberesolvedbysubmittingrevisedT/Ss.TheapplicabilityofthisissuetoUnit2oftheD.C.CookPlantwasdiscussedwithExxonNuclearCompany(ENC),ourUnit2fuelsupplier.AlthoughtheENCfuelinUnit2doesnotexceedthemaximumuraniumweightperrodspecifiedinUnit2T/S5.3.1,ENCinformedusbyletterdatedOctober15,1986(Attachment4)thatthey"concurwiththegenericWestinghouseevaluationoftheproposedremovalofthemaximumrodweightfromT/S5.3.1."EvaluationTheproposedchangeofTechnicalSpecificationDesignFeaturesSection5.3.1isgiveninAttachment2.ThisistheonlyreferencetofuelroduraniumweightintheTechnicalSpecifications.AsdescribedbyWestinghouseinAttachment3,Althoughanumberofsafetyanalysesareaffectedindirectlybyfuelweight,theanalysesaremoresensitivetofuelconfiguration,length,enrichmentandphysicaldesignwhicharealsospecifiedintheplantTechnicalSpecifications.TheTechnicalSpecificationslimitpowerandpowerdistribution,thuscontrollingthefissionrateandtherateofdecayheatproduction.Fuelrodweightdoesnothaveanydirectbearingonthepowerlimits,poweroperatinglevel,ordecayheatrate.Thecompositionofthefueliscloselymonitoredtoassureacceptablefuelperformance.ThefuelweightchangesthatcouldbemadewithoutaTechnicalSpecificationlimitarenotofsufficientmagnitudetocauseasignificantdifferenceinfuelperformanceasanalyzedbyWestinghouse.Therearenoexpectedobservablechangesinnormaloperationduetothenotedfuelrodweightchanges,andtheremainingfuelparameterslistedintheTechnicalSpecificationsareconsideredintheReloadSafetyEvaluation.
| | |
| 1f~~
| | ==Dear Mr. Denton:== |
| Attachment1toAEP.RC:1016Page2OtherDesignBasisEventswereexaminedtoassesstheeffectsofpossiblechangesinfuelrodweight.Fuelrodweightwillonlychangeasaresultofaspecificchangeinthephysicaldesign,whichisaddressedintheReloadSafetyEvaluation,orwithinthemanufacturingtolerances,inwhichcasethechangesinfuelrodweightarerelativelyinsignificant.Changesinnucleardesignresultingfromfuelrodweightchangesarecontrolledasdiscussedabove.Forthesechanges,theeffectonnewandspentfuelcriticalityandfuel-handlinganalysesremainboundedbytheexistinganalysesandTechnicalSpecificationDesignFeaturelimits.Fuel-handlingequipmentandproceduresarenotaffectedbytheseweightchanges.Seismic/LOCAanalysescontainsufficientconservatismtoboundtheseweightchanges.Otheraccidentanalysesarenotaffectedbyrodweightasadirectparameter,andtheexistinganalysesremainbounding.Asstatedearlier,ENChas(inAttachment4)concurredwiththeWestinghouseevaluationwithregardtoD.C.CookUnit2.BasisforNoSinificantHazardsDeterminationPer10CFR50.92,aproposedamendmentwillinvolveanosignificanthazardsconsiderationiftheproposedamendmentdoesnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyanalyzedorevaluated,or(3)involveasignificantreductioninamarginofsafety.OurevaluationoftheabovecriteriaisbasedoninformationsuppliedtousbyWestinghouse(seeAttachment3).Criterion1Thedeletionofthefuelroduraniumweightlimitdoesnotsignificantlyincreasetheprobabilityorconsequencesofpreviouslyevaluatedaccidents.ThevariationinfuelrodweightthatcanoccurevenwithoutaTechnicalSpecificationlimitissmallbasedonotherfueldesignconstraints,e.g.,roddiameter,gapsize,UO-2densityandactivefuellength,allofwhichprovidesomelimitonthevariationinrodweight.Thecurrentsafetyanalysesarenotbaseddirectlyonfuelrodweight,abutratherondesignparameterssuchaspower-andfueldimensions.Theseparametersareeither(1)notaffectedatallbyfuelrodweight,or(2)areonlyslightlyaffected.However,areviewofdesignparameterswhichmaybeaffectedindicatesthatachangeinfuelweightdoesnotcauseotherdesignparameterstoexceedthevaluesassumedinthevarioussafetyanalyses,ortocauseacceptancecriteriatobeexceeded.Theeffectsarenotsignificantwithrespecttomeasurednuclearparameters(power,powerdistribution,nuclearcoefficients),i.e.,theyremainwithintheirT/Slimits.Thus,itisconcludedthattheT/Smodificationdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofapreviouslyevaluatedaccident.
| | |
| P Attachment1toAEP.C:1016Page3Criterion2Thecreationofanewordifferentkindofaccidentfromanypreviouslyevaluatedaccidentisnotconsideredapossibility.Allofthefuelcontainedinthefuelrodissimilartoanddesignedtofunctionsimilartopreviousfuel.Thus,theexistingnewandspentfuelstoragecriticalityanalysesboundthechangesobserved.Thischangeisconsideredasadministrativeinnatureanddoesnotcreatethepossibilityofanewordifferentkindofaccident.Criterion3Themarginofsafetyismaintainedbyadherencetootherfuel-relatedTechnicalSpecificationlimitsandtheFSARdesignbases.ThedeletionoffuelrodweightlimitsintheTechnicalSpecificationsDesignFeaturesSection5.3.1doesnotdirectlyaffectanysafetysystemorthesafetylimits,andthereforewillnotreducethemarginofsafety.Lastly,wenotethattheNRChasprovidedguidanceconcerningthedeterminationofsignificanthazardsbyprovidingcertainexamples(48FR14870)ofamendmentsconsiderednotlikelytoinvolvesignificanthazardsconsideration.Thesixthoftheseexamplesreferstochangeswhichmayresultinsomeincreasetotheprobabilityofoccurrenceorconsequencesofapreviouslyanalyzedaccidentormayreduceinsomewayasafetymargin,buttheresultsofwhicharewithinacceptablecriteria.DeletingtheT/Slimitformaximumfuelroduraniumweightmaybeperceivedasreducingmarginofsafetyorincreasingtheprobabilityorconsequencesofpreviouslyanalyzedaccidents.However,evaluationsoftheproposedchangeperformedbyWestinghouseandENChavedemonstratedthatapplicablecriteriawithregardstonuclearsafetywouldcontinuetobesatisfied.AdditionalChanesInadditiontothechangesdescribedabove,wealsomadeseveralminoreditorialchangestocorrecttypographicalerrorsintheT/Stext.Specifically,wecorrectedthespellingof"Zircaloy-4"inUnit1T/S5.3.1,andthespellingof"control"inUnit2T/S5.3.2.Thesechangesarepurelyadministrativeinnatureandthereforedonotreduceamarginofsafety,donotincreasetheprobabilityorconsequencesofapreviouslyanalyzedaccident,anddonotintroducethepossibilityofanewaccident.Therefore,webelievethatthesechangesdonotinvolveasignificanthazardsconsiderationasdefinedby10CFR50.92. | | This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Specifically, we propose to modify T/S 5.3.1 (Design Features - Reactor Core Fuel Assemblies) to delete reference to a maximum uranium weight per assembly and to correct minor editorial changes'he reasons for the proposed changes and our analyses concerning significant hazards considerations are contained in Attachment 1 to this letter. The proposed revised T/S pages are contained in Attachment 2. |
| Attachment2toAEP:NRC:1016ProposedRevisedTechnicalSpecificationPages}}
| | We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| | These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meeting. |
| | In compliance with the requirements of 10 CFR 50.91(b)(1), 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. |
| | Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of |
| | $ 150.00 for the proposed amendments. |
| | 86i2300253 861222 PDR *DOCK 05000315(' ~ |
| | P DR~I, |
| | |
| | L ~ |
| | ~ ~ |
| | C I |
| | |
| | Mr. Harold R. Denton AEP:NRC:1016 This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned. |
| | Very truly yours, M. . Ale ich Vice President I ply'll>> |
| | MPA/cm Attachments cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman |
| | |
| | Attachment 1 to AEP:NRC:1016 Reasons and 10 CFR 50.92 Analyses for Changes to the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Technical Specifications |
| | |
| | Attachment 1 to AEP: RC:1016 Page 1 This license amendment request proposes to modify T/S 5.3.1 (Design Features - Reactor Core Fuel Assemblies) for Units 1 and 2 to delete reference to a maximum uranium weight per assembly. |
| | Back round By letter dated September 4, 1986 (Attachment 3), Westinghouse Electric Corporation (Westinghouse) officially notified us of a discrepancy involving the maximum uranium weight per assembly specified in T/S 5.3.1 Unit 1. Specifically, Westinghouse informed us that recent 'or improvements to their fuel design (including chamfered pellets with a reduced dish and a nominal density increase) have increased fuel weight slightly. The weight increases have caused the maximum fuel rod weight to exceed the maximum value of 2236 grams specified in Unit 1 Design Features T/S 5.3.1. Westinghouse also provided us with proposed wording and justification for a T/S change, as well, as a justification for continued operation. Westinghouse had notified us of the condition informally in April of this year. At that time, the issue was discussed with your staff, who informed us the issue could be resolved by submitting revised T/Ss. |
| | The applicability of this issue to Unit 2 of the D. C. Cook Plant was discussed with Exxon Nuclear Company (ENC), our Unit 2 fuel supplier. |
| | Although the ENC fuel in Unit 2 does not exceed the maximum uranium weight per rod specified in Unit 2 T/S 5.3.1, ENC informed us by letter dated October 15, 1986 (Attachment 4) that they "concur with the generic Westinghouse evaluation of the proposed removal of the maximum rod weight from T/S 5.3.1." |
| | Evaluation The proposed change of Technical Specification Design Features Section 5.3.1 is given in Attachment 2. This is the only reference to fuel rod uranium weight in the Technical Specifications. |
| | As described by Westinghouse in Attachment 3, Although a number of safety analyses are affected indirectly by fuel weight, the analyses are more sensitive to fuel configuration, length, enrichment and physical design which are also specified in the plant Technical Specifications. The Technical Specifications limit power and power distribution, thus controlling the fission rate and the rate of decay heat production. Fuel rod weight does not have any direct bearing on the power limits, power operating level, or decay heat rate. |
| | The composition of the fuel is closely monitored to assure acceptable fuel performance. The fuel weight changes that could be made without a Technical Specification limit are not of sufficient magnitude to cause a significant difference in fuel performance as analyzed by Westinghouse. There are no expected observable changes in normal operation due to the noted fuel rod weight changes, and the remaining fuel parameters listed in the Technical Specifications are considered in the Reload Safety Evaluation. |
| | |
| | 1 f |
| | ~ ~ |
| | to AEP. RC:1016 Page 2 Other Design Basis Events were examined to assess the effects of possible changes in fuel rod weight. Fuel rod weight will only change as a result of a specific change in the physical design, which is addressed in the Reload Safety Evaluation, or within the manufacturing tolerances, in which case the changes in fuel rod weight are relatively insignificant. Changes in nuclear design resulting from fuel rod weight changes are controlled as discussed above. For these changes, the effect on new and spent fuel criticality and fuel-handling analyses remain bounded by the existing analyses and Technical Specification Design Feature limits. Fuel-handling equipment and procedures are not affected by these weight changes. |
| | Seismic/LOCA analyses contain sufficient conservatism to bound these weight changes. Other accident analyses are not affected by rod weight as a direct parameter, and the existing analyses remain bounding. |
| | As stated earlier, ENC has (in Attachment 4) concurred with the Westinghouse evaluation with regard to D. C. Cook Unit 2. |
| | Basis for No Si nificant Hazards Determination Per 10 CFR 50.92, a proposed amendment will involve a no 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 analyzed or evaluated, or (3) involve a significant reduction in a margin of safety. |
| | Our evaluation of the above criteria is based on information supplied to us by Westinghouse (see Attachment 3). |
| | Criterion 1 The deletion of the fuel rod uranium weight limit does not significantly increase the probability or consequences of previously evaluated accidents. |
| | The variation in fuel rod weight that can occur even without a Technical Specification limit is small based on other fuel design constraints, e.g., |
| | rod diameter, gap size, UO-2 density and active fuel length, all of which provide some limit on the variation in rod weight. The current safety analyses are not based directly on fuel rod weight, abut rather on design parameters such as power- and fuel dimensions. These parameters are either (1) not affected at all by fuel rod weight, or (2) are only slightly affected. However, a review of design parameters which may be affected indicates that a change in fuel weight does not cause other design parameters to exceed the values assumed in the various safety analyses, or to cause acceptance criteria to be exceeded. The effects are not significant with respect to measured nuclear parameters (power, power distribution, nuclear coefficients), i.e., they remain within their T/S limits. Thus, it is concluded that the T/S modification does not involve a significant increase in the probability or consequences of a previously evaluated accident. |
| | |
| | P Attachment 1 to AEP. C:1016 Page 3 Criterion 2 The creation of a new or different kind of accident from any previously evaluated accident is not considered a possibility. All of the fuel contained in the fuel rod is similar to and designed to function similar to previous fuel. Thus, the existing new and spent fuel storage criticality analyses bound the changes observed. This change is considered as administrative in nature and does not create the possibility of a new or different kind of accident. |
| | Criterion 3 The margin of safety is maintained by adherence to other fuel-related Technical Specification limits and the FSAR design bases. The deletion of fuel rod weight limits in the Technical Specifications Design Features Section 5.3.1 does not directly affect any safety system or the safety limits, and therefore will not reduce the margin of safety. |
| | Lastly, we note that the NRC has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration. The sixth of these examples refers to changes which may result in some increase to 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 within acceptable criteria. |
| | Deleting the T/S limit for maximum fuel rod uranium weight may be perceived as reducing margin of safety or increasing the probability or consequences of previously analyzed accidents. However, evaluations of the proposed change performed by Westinghouse and ENC have demonstrated that applicable criteria with regards to nuclear safety would continue to be satisfied. |
| | Additional Chan es In addition to the changes described above, we also made several minor editorial changes to correct typographical errors in the T/S text. |
| | Specifically, we corrected the spelling of "Zircaloy-4" in Unit 1 T/S 5.3.1, and the spelling of "control" in Unit 2 T/S 5.3.2. These changes are purely administrative in nature and therefore do not reduce a margin of safety, do not increase the probability or consequences of a previously analyzed accident, and do not introduce the possibility of a new accident. |
| | Therefore, we believe that these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92. |
| | |
| | Attachment 2 to AEP:NRC:1016 Proposed Revised Technical Specification Pages}} |
Similar Documents at Cook |
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
REGULATORY I FQRNATION DISTRIBUTION SY el't (R IDS)
ACCESSION NBR: 8612300253 DQC. DATE: 86/12/22 NOTARIZED: NO DOCKET ¹ FAC IL: 50-315 Donald C. Cook Nuclear Power Plant. Unit 1> Indiana 5 05000315 50-31m Donald C. Cook Nuclear Power Planti Unit 2> Ind iana 0 0500031b AUTH. NAI]E AUTHOR AFFILIATION ALEXICH. N' Indiana 8c Nichigan Electric Co.
RECIP. NANE RECIPIENT AFFILIATION DENTQNp H. R. f Of i ce of Nuclear Reactor Regulationt Direc tor (p ost 851125 SUB JECT: Application to amend Licenses DPR-58 DPR-74> modif ging Tech Zc Spec 5. 3. 1 to delete ref to max U weight per assembly 0 to correct minor editorial changes. Fee paid.
DIBTRIBUTION CODE: AOCID COPTER RECEIVED: LTR ) ENCL Q SIZE: l + (
TITLE: QR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAl'lE LTTR ENCL ID CODE/NANE LTTR ENCL PWR-A EB 1 1 PWR-A EICSB 2 2 PWR-A FOB 1 PWR-A PD4 LA 1 0 PWR-A PD4 PD 01 5 5 WIQQINQTONi D 1 1 PWR-A PSB 1 1 PWR-A RSB 1 1 1E INTERNAL: ADN/LFNB 1 0 ELD/HDS3 1 0 NRR/DHFT/TSCB 1 1 NRR/GRAS 1 0 04 1 1 RQN3 1 1 EXTERNAL: E('@('RUSKE, S 1 LPDR 03 2 2 NRC PDR 02 1 1 NSIC 05 1 48'R( P~gg- g)lyg
<5 aA TOTAL NUl'tBER OF COPIES REQUIRED: LTTR . 2+ ENCL
t h I 4 I ~ H - t h'I 'l
'K I >>) I HI>>,
~ H lh 4 If>> HKI
<<1, H ht I'H d
gh g fh/ 1 lh' 41 fl" W H
H I ,
H ll ~
J 4 4 II Ih', W
INDIANA 8 MICHIGAN ELECTRIC COMPANY P,O. BOX 16631 COLUMBUS, OHIO 43216 December 22, 1986 AEP:NRC:1016 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 FUEL ASSEMBLY URANIUM MASS TECHNICAL SPECIFICATION CHANGE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Specifically, we propose to modify T/S 5.3.1 (Design Features - Reactor Core Fuel Assemblies) to delete reference to a maximum uranium weight per assembly and to correct minor editorial changes'he reasons for the proposed changes and our analyses concerning significant hazards considerations are contained in Attachment 1 to this letter. The proposed revised T/S pages are contained in Attachment 2.
We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(1), 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.
Pursuant to 10 CFR 170.12(c), we have enclosed an application fee of
$ 150.00 for the proposed amendments.
86i2300253 861222 PDR *DOCK 05000315(' ~
P DR~I,
L ~
~ ~
C I
Mr. Harold R. Denton AEP:NRC:1016 This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M. . Ale ich Vice President I ply'll>>
MPA/cm Attachments cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman
Attachment 1 to AEP:NRC:1016 Reasons and 10 CFR 50.92 Analyses for Changes to the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Technical Specifications
Attachment 1 to AEP: RC:1016 Page 1 This license amendment request proposes to modify T/S 5.3.1 (Design Features - Reactor Core Fuel Assemblies) for Units 1 and 2 to delete reference to a maximum uranium weight per assembly.
Back round By letter dated September 4, 1986 (Attachment 3), Westinghouse Electric Corporation (Westinghouse) officially notified us of a discrepancy involving the maximum uranium weight per assembly specified in T/S 5.3.1 Unit 1. Specifically, Westinghouse informed us that recent 'or improvements to their fuel design (including chamfered pellets with a reduced dish and a nominal density increase) have increased fuel weight slightly. The weight increases have caused the maximum fuel rod weight to exceed the maximum value of 2236 grams specified in Unit 1 Design Features T/S 5.3.1. Westinghouse also provided us with proposed wording and justification for a T/S change, as well, as a justification for continued operation. Westinghouse had notified us of the condition informally in April of this year. At that time, the issue was discussed with your staff, who informed us the issue could be resolved by submitting revised T/Ss.
The applicability of this issue to Unit 2 of the D. C. Cook Plant was discussed with Exxon Nuclear Company (ENC), our Unit 2 fuel supplier.
Although the ENC fuel in Unit 2 does not exceed the maximum uranium weight per rod specified in Unit 2 T/S 5.3.1, ENC informed us by letter dated October 15, 1986 (Attachment 4) that they "concur with the generic Westinghouse evaluation of the proposed removal of the maximum rod weight from T/S 5.3.1."
Evaluation The proposed change of Technical Specification Design Features Section 5.3.1 is given in Attachment 2. This is the only reference to fuel rod uranium weight in the Technical Specifications.
As described by Westinghouse in Attachment 3, Although a number of safety analyses are affected indirectly by fuel weight, the analyses are more sensitive to fuel configuration, length, enrichment and physical design which are also specified in the plant Technical Specifications. The Technical Specifications limit power and power distribution, thus controlling the fission rate and the rate of decay heat production. Fuel rod weight does not have any direct bearing on the power limits, power operating level, or decay heat rate.
The composition of the fuel is closely monitored to assure acceptable fuel performance. The fuel weight changes that could be made without a Technical Specification limit are not of sufficient magnitude to cause a significant difference in fuel performance as analyzed by Westinghouse. There are no expected observable changes in normal operation due to the noted fuel rod weight changes, and the remaining fuel parameters listed in the Technical Specifications are considered in the Reload Safety Evaluation.
1 f
~ ~
to AEP. RC:1016 Page 2 Other Design Basis Events were examined to assess the effects of possible changes in fuel rod weight. Fuel rod weight will only change as a result of a specific change in the physical design, which is addressed in the Reload Safety Evaluation, or within the manufacturing tolerances, in which case the changes in fuel rod weight are relatively insignificant. Changes in nuclear design resulting from fuel rod weight changes are controlled as discussed above. For these changes, the effect on new and spent fuel criticality and fuel-handling analyses remain bounded by the existing analyses and Technical Specification Design Feature limits. Fuel-handling equipment and procedures are not affected by these weight changes.
Seismic/LOCA analyses contain sufficient conservatism to bound these weight changes. Other accident analyses are not affected by rod weight as a direct parameter, and the existing analyses remain bounding.
As stated earlier, ENC has (in Attachment 4) concurred with the Westinghouse evaluation with regard to D. C. Cook Unit 2.
Basis for No Si nificant Hazards Determination Per 10 CFR 50.92, a proposed amendment will involve a no 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 analyzed or evaluated, or (3) involve a significant reduction in a margin of safety.
Our evaluation of the above criteria is based on information supplied to us by Westinghouse (see Attachment 3).
Criterion 1 The deletion of the fuel rod uranium weight limit does not significantly increase the probability or consequences of previously evaluated accidents.
The variation in fuel rod weight that can occur even without a Technical Specification limit is small based on other fuel design constraints, e.g.,
rod diameter, gap size, UO-2 density and active fuel length, all of which provide some limit on the variation in rod weight. The current safety analyses are not based directly on fuel rod weight, abut rather on design parameters such as power- and fuel dimensions. These parameters are either (1) not affected at all by fuel rod weight, or (2) are only slightly affected. However, a review of design parameters which may be affected indicates that a change in fuel weight does not cause other design parameters to exceed the values assumed in the various safety analyses, or to cause acceptance criteria to be exceeded. The effects are not significant with respect to measured nuclear parameters (power, power distribution, nuclear coefficients), i.e., they remain within their T/S limits. Thus, it is concluded that the T/S modification does not involve a significant increase in the probability or consequences of a previously evaluated accident.
P Attachment 1 to AEP. C:1016 Page 3 Criterion 2 The creation of a new or different kind of accident from any previously evaluated accident is not considered a possibility. All of the fuel contained in the fuel rod is similar to and designed to function similar to previous fuel. Thus, the existing new and spent fuel storage criticality analyses bound the changes observed. This change is considered as administrative in nature and does not create the possibility of a new or different kind of accident.
Criterion 3 The margin of safety is maintained by adherence to other fuel-related Technical Specification limits and the FSAR design bases. The deletion of fuel rod weight limits in the Technical Specifications Design Features Section 5.3.1 does not directly affect any safety system or the safety limits, and therefore will not reduce the margin of safety.
Lastly, we note that the NRC has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration. The sixth of these examples refers to changes which may result in some increase to 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 within acceptable criteria.
Deleting the T/S limit for maximum fuel rod uranium weight may be perceived as reducing margin of safety or increasing the probability or consequences of previously analyzed accidents. However, evaluations of the proposed change performed by Westinghouse and ENC have demonstrated that applicable criteria with regards to nuclear safety would continue to be satisfied.
Additional Chan es In addition to the changes described above, we also made several minor editorial changes to correct typographical errors in the T/S text.
Specifically, we corrected the spelling of "Zircaloy-4" in Unit 1 T/S 5.3.1, and the spelling of "control" in Unit 2 T/S 5.3.2. These changes are purely administrative in nature and therefore do not reduce a margin of safety, do not increase the probability or consequences of a previously analyzed accident, and do not introduce the possibility of a new accident.
Therefore, we believe that these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92.
Attachment 2 to AEP:NRC:1016 Proposed Revised Technical Specification Pages