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| | issue date = 02/22/1996 | | | issue date = 02/22/1996 |
| | title = 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 | | | title = 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 |
| | author name = FITZPATRICK E | | | author name = Fitzpatrick E |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
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| | 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 = 9 | | | page count = 9 |
| | | project = |
| | | stage = Request |
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| {{#Wiki_filter:CATEGORY1EREGULATOhINFORMATIONDISTRIB':TION~TEN(R/DS)ACCESSi.ONNBR:9602280006DOC.DATE:96/02/22NOTARIZED:'YESDOCKET¹FAC'lL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana!;Mi;chigan-EleRECIP.NAMERECIPIENTAFFILIATIONDocumentCont:olBranch(DocumentControlDesk) | | {{#Wiki_filter:CATEGORY 1 E |
| | REGULATOhINFORMATION DISTRIB':TION ~TEN (R/DS) |
| | ACCESSi.ON NBR:9602280006 DOC.DATE: 96/02/22 NOTARIZED: 'YES DOCKET ¹ FAC'lL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana !; Mi;chigan -Ele RECIP.NAME RECIPIENT AFFILIATION Document Cont:ol Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ApplicationforamendstolicensesDPR-58!'PR-74,proposingtoremoverequirementthatOperationsSuperintendentmustholdorhaveheldSOLatplantorsimilarreactor.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRtENCLISIZE:7TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNAL:CH/HICBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOACCOPIESLTTRENCL111j.1111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL1111111111DUENNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIR"'D:LTTR12ENCLll
| | Application for amends to licenses DPR-58 !'PR-74,proposing to remove requirement that Operations Superintendent must hold or have held SOL at plant or similar reactor. |
| -p/.tVf'l~~ | | DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution t ENCL I SIZE: 7 NOTES: |
| ,IndianaMichigan'PowerCompanyPOBox16631Columbus,OH43216hIHQIANAlNlCHlGAMPQWKRFebruary22,1996AEP:NRC:0659AADocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2PROPOSEDAMENDMENTTOTECHNICALSPECIFICATIONSECTION6ADMINISTRATIVECONTROLSThisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/S)forDonaldC.CookNuclearPlantunits1and2.Specifically,weareproposingtoremovetherequirementthattheOperationsSuperintendentmustholdorhaveheldaSeniorOperatorLicenseatCookNuclearPlant,orasimilarreactor.Inaddition,amid-leveloperationsmanagerwillonlyberequiredtoholdaSeniorOperatorLicenseiftheOperationsSuperintendentdoesnotholdone.Attachment1providesadetaileddescriptionoft'eproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.2700709602280006960222,'DRADOCK050003i5,PPDRpji U.S.NuclearRegulatoryCommissionPage2AEP:NRC:0659AAIncompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Sincerely,E.E.FitzpatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS@~~DAYOF1996NteryPulicpitAttachmentsCC:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC:0659AADESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGES~TOTHEDONALDC.COOKNUCLEARPLANTUNIT1AND2TECHNICALSPECIFICATIONS ATTACHMENTTOAEP:NRC:0659AAPage1I.SCOPEThechangetoSection6oftheCookNuclearPlantTechnicalSpecifications,isadministrativeinnatureandaffectsspecifications6.2.2.h,6.3.1and6.5.1.2astheyarerelatedtoOperationSuperintendentqualifications.II.PURPOSEThepurposeofthischangeistoincorporatetheguidancefoundinANSI/ANS3.1-1993Section4.2.2whichdefinesthespecialrequirementsforthepositionofOperationsManager.III'ESCRIPTIONOFCHANGESTheproposedamendmentmakesthefollowingspecificchangestotheCookNuclearPlantUnits1and2TechnicalSpecifications:Theintroductionto6.2.2hasbeenmovedfrompage6-1to6-2.6.2.2.hhasbeenchangedto,.read:h.TheOperationsSuperintendentshallmeetoneofthefollowing:(a)holdaSeniorOperatorLicenseatCookNuclearPlantorsimilarreactor,or(b)haveheldaSeniorOperatorLicenseatCookNuclearPlantorsimilarreactor,or(c)havebeencertifiedforequivalentsenioroperatorknowledge,or(d)haveplantoperationalknowledgeconsistentwiththerequirementsoftheOperationsSuperintendentgob.IftheOperationsSuperintendentdoesnotholdaSeniorOperatorLicense,thenanoperationsmiddlemanagershallholdaSeniorOperatorLicense.6.3.1waschangedtocorrespondtothechangesmadeto6.2.2.h.InTechnicalSpecifications6.5.1.2changethethirdparagraphtoread:PNSRCmembersandalternatesshallmeetorexceedtheminimumqualificationsofANSIN18.1-1971Section4.4forcomparablepositions.ThenuclearpowerplantoperationsindividualshallmeetthequalificationsofSection4.2.2ofANSIN18.1-1971exceptfortherequirementtoholdaSeniorOperatorLicense.Theoperationsindividualshallmeettherequirementsofsection6.2.2.h.ThemaintenanceindividualshallmeetthequalificationsofSection4.2.3ofANSIN18.1-1971. | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 j. |
| <7'jsATTACHMENTTOAEP'NRC'0659AAIV.JUSTIFICATIONFORCHANGEPage2Item(d)ofSection4.2.2ofANSI/ANS3.1-1993providesarelaxationfromtherequirementfortheOperationsManagertoobtainaSeniorOperatorLicenseorcertification.TheANSI/ANSstandardprovidesforequivalent"plantoperationalknowledgeoftheOperationsManager'sjob,"inplaceofobtainingalicenseorcertification.IntheeventtheOperationsManagerdoesnotholdanSRO,amid-leveloperationsmanagerisrequiredtoholdoneperANSI/ANS3.1.Theproposedamendmentisconsistentwiththisrequirement.ThispositionisfurthersupportedinaletterdatedJanuary26,1984,fromStevenA.Varga(NRR)toourMr.JohnDolan,containingtheNRC'sresponsetoourrequesttochangeTechnicalSpecification6.3.Theletterstatedinpart:"VebelievetheOperationsSuperintendent'sknowledgeofplantoperationsshouldremaincurrentbutthatthiscanbedonethrougheffectivetraininganddailyinteractions.SincemaintainingtheSOLwouldrequireconsiderablymoreeffortandmightdetract,fromtheoveralloperationssupervision,wealsobelievetheOperationsSuperintendentneednotmaintaintheSOLbutheshouldhavecapableandlicensedindividualsreportingtohim."InlightoftheNRC'sopinion,andinadditiontothechangesinqualificationrequirementsasputforthinANSI/ANS3.1whichreplacedANSIN18.1,changingtheTechnicalSpecificationwillallowustobettermanagetheplant,andmeettheintentoftheupdatedANS/ANSIrequirements.V.10CFR5092CRITERIAPer10CFR50.92,aproposedchangedoesnotinvolveasignificanthazardsconsiderationifthechangedoesnot:involveasignificantincreaseintheprobabilityofconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety.CriteoTheamendmentrequestdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofaccidentpreviouslyevaluatedbecausetheproposedchangetotheTechnical ATTACHMENTTOAEP:NRC:0659AAPage3Specificationdoesnotaffecttheassumptions,parameters,orresultsofanyUFSARaccidentanalysis.Theproposedamendmentdoesnotmodifyanyexistingequipment.Itisconcludedthatthechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Criterion2Theproposedchangedoesnotinvolvephysicalchangestot'eplantorchangesinplantoperatingconfiguration.TheproposedchangeupdatestherequirementsfortheOperationsSuperintendent.Thus,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.nCriterion3TheproposedchangeupdatestherequirementsforOperationsSuperintendent.Thereisnoreductioninthemarginofsafety. | | INTERNAL: 1 1 NRR/DE/EMCB 1 1 CH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| ATTACHMENT2TOAEP:NRC:0659AACURRENTTECHNICALSPECIFICATIONPAGESWITHCHANGESMARKED}}
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| | N NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIR"'D: LTTR 12 ENCL ll |
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| | ,Indiana Michigan |
| | 'Power Company PO Box 16631 Columbus, OH 43216 IHQIANAl NlCHlGAM PQWKR h |
| | February 22, 1996 AEP:NRC:0659AA Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| | Donald C. Cook Nuclear Plant Units 1 and 2 PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION SECTION 6 ADMINISTRATIVE CONTROLS This letter and its attachments constitute an application for amendment to the technical specifications (T/S) for Donald C. Cook Nuclear Plant units 1 and 2. Specifically, we are proposing to remove the requirement that the Operations Superintendent must hold or have held a Senior Operator License at Cook Nuclear Plant, or a similar reactor. In addition, a mid-level operations manager will only be required to hold a Senior Operator License if the Operations Superintendent does not hold one. |
| | Attachment 1 provides a detailed description of t'e proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment 3 contains the proposed T/S pages. |
| | We believe the proposed changes will not result in (1) a significant change in the types 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 and the Nuclear Safety and Design Review Committee. |
| | 270070 9602280006 050003i5, P |
| | ADOCK 960222,'DR PDR pj i |
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| | U. S. Nuclear Regulatory Commission AEP:NRC:0659AA Page 2 In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health. |
| | Sincerely, E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS@~~ DAY OF 1996 N tery Pu lic pit Attachments CC: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett |
| | |
| | ATTACHMENT 1 TO AEP:NRC:0659AA DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES ~ |
| | TO THE DONALD C. COOK NUCLEAR PLANT UNIT 1 AND 2 TECHNICAL SPECIFICATIONS |
| | |
| | ATTACHMENT TO AEP:NRC:0659AA Page 1 I. SCOPE The change to Section 6 of the Cook Nuclear Plant Technical Specifications, is administrative in nature and affects specifications 6.2.2.h, 6.3.1 and 6.5.1.2 as they are related to Operation Superintendent qualifications. |
| | II. PURPOSE The purpose of this change is to incorporate the guidance found in ANSI/ANS 3.1 - 1993 Section 4.2.2 which defines the special requirements for the position of Operations Manager. |
| | III'ESCRIPTION OF CHANGES The proposed amendment makes the following specific changes to the Cook Nuclear Plant Units 1 and 2 Technical Specifications: |
| | The introduction to 6.2.2 has been moved from page 6-1 to 6-2. |
| | 6.2.2.h has been changed to,.read: |
| | : h. The Operations Superintendent shall meet one of the following: (a) hold a Senior Operator License at Cook Nuclear Plant or similar reactor, or (b) have held a Senior Operator License at Cook Nuclear Plant or similar reactor, or (c) have been certified for equivalent senior operator knowledge, or (d) have plant operational knowledge consistent with the requirements of the Operations Superintendent gob. If the Operations Superintendent does not hold a Senior Operator License, then an operations middle manager shall hold a Senior Operator License. |
| | 6.3.1 was changed to correspond to the changes made to 6.2.2.h. |
| | In Technical Specifications 6.5.1.2 change the third paragraph to read: |
| | PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a Senior Operator License. The operations individual shall meet the requirements of section 6.2.2.h. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971. |
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| | 'js ATTACHMENT TO AEP'NRC'0659AA Page 2 IV. JUSTIFICATION FOR CHANGE Item (d) of Section 4.2.2 of ANSI/ANS 3.1 - 1993 provides a relaxation from the requirement for the Operations Manager to obtain a Senior Operator License or certification. The ANSI/ANS standard provides for equivalent "plant operational knowledge of the Operations Manager's job," in place of obtaining a license or certification. In the event the Operations Manager does not hold an SRO, a mid-level operations manager is required to hold one per ANSI/ANS 3.1. |
| | The proposed amendment is consistent with this requirement. |
| | This position is further supported in a letter dated January 26, 1984, from Steven A. Varga (NRR) to our Mr. John Dolan, containing the NRC's response to our request to change Technical Specification 6.3. The letter stated in part: |
| | "Ve believe the Operations Superintendent's knowledge of plant operations should remain current but that this can be done through effective training and daily interactions. Since maintaining the SOL would require considerably more effort and might detract, from the overall operations supervision, we also believe the Operations Superintendent need not maintain the SOL but he should have capable and licensed individuals reporting to him." |
| | In light of the NRC's opinion, and in addition to the changes in qualification requirements as put forth in ANSI/ANS 3.1 which replaced ANSI N18.1, changing the Technical Specification will allow us to better manage the plant, and meet the intent of the updated ANS/ANSI requirements. |
| | V. 10 CFR 50 92 CRITERIA Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not: |
| | involve a significant increase in the probability of 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. |
| | Crite o The amendment request does not involve a significant increase in the probability or consequences of accident previously evaluated because the proposed change to the Technical |
| | |
| | ATTACHMENT TO AEP: NRC: 0659AA Page 3 Specification does not affect the assumptions, parameters, or results of any UFSAR accident analysis. The proposed amendment does not modify any existing equipment. It is concluded that the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | Criterion 2 The proposed change does not involve physical changes to t'e plant or changes in plant operating configuration. The proposed change updates the requirements for the Operations Superintendent. Thus, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | n Criterion 3 The proposed change updates the requirements for Operations Superintendent. There is no reduction in the margin of safety. |
| | |
| | ATTACHMENT 2 TO AEP:NRC:0659AA CURRENT TECHNICAL SPECIFICATION PAGES WITH CHANGES MARKED}} |
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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
CATEGORY 1 E
REGULATOhINFORMATION DISTRIB':TION ~TEN (R/DS)
ACCESSi.ON NBR:9602280006 DOC.DATE: 96/02/22 NOTARIZED: 'YES DOCKET ¹ FAC'lL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana !; Mi;chigan -Ele RECIP.NAME RECIPIENT AFFILIATION Document Cont:ol Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses DPR-58 !'PR-74,proposing to remove requirement that Operations Superintendent must hold or have held SOL at plant or similar reactor.
DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution t ENCL I SIZE: 7 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 HICKMAN,J 1 j.
INTERNAL: 1 1 NRR/DE/EMCB 1 1 CH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
U E
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIR"'D: LTTR 12 ENCL ll
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,Indiana Michigan
'Power Company PO Box 16631 Columbus, OH 43216 IHQIANAl NlCHlGAM PQWKR h
February 22, 1996 AEP:NRC:0659AA Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION SECTION 6 ADMINISTRATIVE CONTROLS This letter and its attachments constitute an application for amendment to the technical specifications (T/S) for Donald C. Cook Nuclear Plant units 1 and 2. Specifically, we are proposing to remove the requirement that the Operations Superintendent must hold or have held a Senior Operator License at Cook Nuclear Plant, or a similar reactor. In addition, a mid-level operations manager will only be required to hold a Senior Operator License if the Operations Superintendent does not hold one.
Attachment 1 provides a detailed description of t'e proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment 3 contains the proposed T/S pages.
We believe the proposed changes will not result in (1) a significant change in the types 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 and the Nuclear Safety and Design Review Committee.
270070 9602280006 050003i5, P
ADOCK 960222,'DR PDR pj i
U. S. Nuclear Regulatory Commission AEP:NRC:0659AA Page 2 In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.
Sincerely, E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS@~~ DAY OF 1996 N tery Pu lic pit Attachments CC: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett
ATTACHMENT 1 TO AEP:NRC:0659AA DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES ~
TO THE DONALD C. COOK NUCLEAR PLANT UNIT 1 AND 2 TECHNICAL SPECIFICATIONS
ATTACHMENT TO AEP:NRC:0659AA Page 1 I. SCOPE The change to Section 6 of the Cook Nuclear Plant Technical Specifications, is administrative in nature and affects specifications 6.2.2.h, 6.3.1 and 6.5.1.2 as they are related to Operation Superintendent qualifications.
II. PURPOSE The purpose of this change is to incorporate the guidance found in ANSI/ANS 3.1 - 1993 Section 4.2.2 which defines the special requirements for the position of Operations Manager.
III'ESCRIPTION OF CHANGES The proposed amendment makes the following specific changes to the Cook Nuclear Plant Units 1 and 2 Technical Specifications:
The introduction to 6.2.2 has been moved from page 6-1 to 6-2.
6.2.2.h has been changed to,.read:
- h. The Operations Superintendent shall meet one of the following: (a) hold a Senior Operator License at Cook Nuclear Plant or similar reactor, or (b) have held a Senior Operator License at Cook Nuclear Plant or similar reactor, or (c) have been certified for equivalent senior operator knowledge, or (d) have plant operational knowledge consistent with the requirements of the Operations Superintendent gob. If the Operations Superintendent does not hold a Senior Operator License, then an operations middle manager shall hold a Senior Operator License.
6.3.1 was changed to correspond to the changes made to 6.2.2.h.
In Technical Specifications 6.5.1.2 change the third paragraph to read:
PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a Senior Operator License. The operations individual shall meet the requirements of section 6.2.2.h. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.
<7
'js ATTACHMENT TO AEP'NRC'0659AA Page 2 IV. JUSTIFICATION FOR CHANGE Item (d) of Section 4.2.2 of ANSI/ANS 3.1 - 1993 provides a relaxation from the requirement for the Operations Manager to obtain a Senior Operator License or certification. The ANSI/ANS standard provides for equivalent "plant operational knowledge of the Operations Manager's job," in place of obtaining a license or certification. In the event the Operations Manager does not hold an SRO, a mid-level operations manager is required to hold one per ANSI/ANS 3.1.
The proposed amendment is consistent with this requirement.
This position is further supported in a letter dated January 26, 1984, from Steven A. Varga (NRR) to our Mr. John Dolan, containing the NRC's response to our request to change Technical Specification 6.3. The letter stated in part:
"Ve believe the Operations Superintendent's knowledge of plant operations should remain current but that this can be done through effective training and daily interactions. Since maintaining the SOL would require considerably more effort and might detract, from the overall operations supervision, we also believe the Operations Superintendent need not maintain the SOL but he should have capable and licensed individuals reporting to him."
In light of the NRC's opinion, and in addition to the changes in qualification requirements as put forth in ANSI/ANS 3.1 which replaced ANSI N18.1, changing the Technical Specification will allow us to better manage the plant, and meet the intent of the updated ANS/ANSI requirements.
V. 10 CFR 50 92 CRITERIA Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not:
involve a significant increase in the probability of 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.
Crite o The amendment request does not involve a significant increase in the probability or consequences of accident previously evaluated because the proposed change to the Technical
ATTACHMENT TO AEP: NRC: 0659AA Page 3 Specification does not affect the assumptions, parameters, or results of any UFSAR accident analysis. The proposed amendment does not modify any existing equipment. It is concluded that the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2 The proposed change does not involve physical changes to t'e plant or changes in plant operating configuration. The proposed change updates the requirements for the Operations Superintendent. Thus, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
n Criterion 3 The proposed change updates the requirements for Operations Superintendent. There is no reduction in the margin of safety.
ATTACHMENT 2 TO AEP:NRC:0659AA CURRENT TECHNICAL SPECIFICATION PAGES WITH CHANGES MARKED