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| | issue date = 09/06/1988 | | | issue date = 09/06/1988 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74,proposing to Delete Organization Charts from Section 6.0.Fee Paid | | | title = Application for Amends to Licenses DPR-58 & DPR-74,proposing to Delete Organization Charts from Section 6.0.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 = MURLEY T E | | | addressee name = Murley T |
| | addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) | | | addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
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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 = 10 | | | page count = 10 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCESSION NBR:8809190098 DOC.DATE: | | {{#Wiki_filter:ACCESSION NBR:8809190098 DOC.DATE: 88/09/06 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana S 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana S 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk) |
| 88/09/06NOTARIZED: | |
| NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaS0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaS05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
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| IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
| |
| DocumentControlBranch(Document ControlDesk)
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstoLicensesDPR-58SDPR-74,proposing todeleteorganization chartsfromSection6.0.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | Application for amends to Licenses DPR-58 DPR-74,proposing S |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LASTANGiJCOPIESLTTRENCL1011RECIPIENT COPIESIDCODE/NAME LTTR.ENCLPD3-1PD55INTERNAL:
| | to delete organization charts from Section 6.0. |
| ARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DOEA/TSB 11NUDOC-BSTRACTGFE01EXTERNAL: | | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: |
| LPDRNSIC1011111111111111NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8ENRR/PMAS/ILRB12 OGC/HDS1RES/DSIR/EIB NRCPDR111111111"01111TOTALNUMBEROFCOPIESREQUIRED:
| | TITLE: OR Submittal: General Distribution NOTES: |
| LTTR22ENCL19 Indianahlichigan PowerCompanyP.O.Box16631Columbus, OH43216AEP:NRC:06590 DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74GENERICLETTER88-06:REMOVALOFORGANIZATION CHARTSFROMTECHNICAL SPECIFICATION ADMINISTRATIVE CONTROLREQUIREMENTS U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleySeptember 6,1988
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR. ENCL PD3-1 LA 1 0 PD3-1 PD 5 5 STANGiJ 1 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NRR/PMAS/ILRB12 1 1 NUDOC BSTRACT 1 1 OGC/HDS1 1 " |
| | 0 GF E 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19 |
| | |
| | Indiana hlichigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:06590 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 GENERIC LETTER 88-06: REMOVAL OF ORGANIZATION CHARTS FROM TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROL REQUIREMENTS U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley September 6, 1988 |
| | |
| | ==Dear Dr. Murley:== |
| | |
| | This letter is in response .to Generic Let'ter '(GL) 88-06 and constitutes an application for amendment to the Technical Specifications (T/Ss)"for .the Donald C."Cook Nuc1ear'lant'nits 1 and 2. Specifically;,. we, are'. proposin'g- to del'ete-'the organization charts from Section, 6.0 Administrative Controls'as'e'commended by GL 88-06. A detailed description of the proposed chan'ges and our analyses concerning significant hazards considerations are included in Attachment l. Attachment 2 contains the proposed revised T/S pages. |
| | 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 amount of any effluents 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 will be reviewed by the Nuclear Safety and Design Review Committee 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'Commis'sion and I |
| | ~ |
| | Pursuant to 10 CFR 170:12(c),>>: we have'nclosed |
| | ~, >>f>> . '' |
| | Mr.. G. Bruchmann of the Michigan Depart'ment of Public Health: ' |
| | p "an'pplication fee of $ 150.00 for the proposed amendments. |
| | p>>>>o / |
| | 8805'i 90098 PDR ADOCK 880%Oh l 0500031 5 I PNU |
| | |
| | ~ 4 Dr. T. E. Murley AEP:NRC'06590 This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. |
| | Sincerely, M. P. Alexi h Vice President ldp Attachments cc: D. H. Williams, Jr. |
| | W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis -"Region III |
| | |
| | ~~ |
| | ~ |
| | 1 Attachment' to AEP:NRC:06590 Reasons and 10 CFR 50.92 Significant Hazards Evaluation for Changes to the Technical Specifications for Donald C. Cook Units 1 and 2 |
| | |
| | Attachment 1 to AEP:NRC:06590 Page 1 The purpose of this change is to eliminate duplicating and maintaining up-to-date organizational charts in both the FSAR and the technical specifications. We, therefore, are proposing to delete the organization charts from the Section 6.0 administrative controls T/Ss. This proposed change would permit us to implement changes to the structure of the onsite and offsite organizations without first having to obtain NRC approval to update the organization charts in the T/Ss. The NRC previously approved similar changes for the McGuire Nuclear Station, Units 1 and 2, on March 16, 1986, and for the Shearon Harris Nuclear Power Plant, Unit 1, on January'27, 1988. |
| | The content'equired in the administrative controls section of the T/Ss is specified in 10 CFR 50.36C(5). The regulation requires that the T/Ss contain the controls and provisions that are needed to ensure operation of the plant in a safe manner but does not specifically require organizational charts in the T/Ss. |
| | In accordance with the guidance provided in Generic Letter 88-06, we have added general requirements that capture the essential aspects of the organizational structure that are defined by existing organization charts. |
| | Per 10 CFR 50.92, a proposed amendment will not involve a significant not: |
| | hazards consideration if the proposed amendment does (1) involve a significant increase in the probability or consequences of an accident previously analyzed, (2) create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or (3) involve a significan" reduction in a margin of safety. |
| | Our evaluation of the proposed change with respect to these criteria is provided below. |
| | Criterion 1 This proposed change does not involve a significant increase in the probability or consequences of an accident previously analyzed because the deletion of the organization charts from the T/Ss does not change plant operation. We will continue to inform the NRC of organizational changes through other required controls. The Code of Federal Regulations, 10 CFR 50.34(b)(6)(i), requires us to have the organizational structure included in the Final Safety Analysis Report (FSAR). A |
| | |
| | N hg to AEP:NRC:06590 Page 2 description of the organization and detailed organization charts are contained in Chapter 1 of the FSAR. As required by 10 CFR 50.71(e), we submit annual updates to the FSAR. Also 10 CFR 50.54(a)(3) and 10 CFR 50, Appendix B govern changes to the organization as described in the Quality Assurance Program. Some of these changes require NRC approval before they can be made. |
| | Criterion 2 This proposed change does not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated because the proposed change's administrative in nature. There are no physical changes to the plant configuration, the setpoints, or operating parameters to be made as a result of this proposed change. |
| | Criterion 3 This proposed change does not involve a significant reduction in a margin of safety for the reasons stated in Criterion l. |
| | Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve a significant hazards consideration. This change is similar to the first example, which refers to changes that are purely administrative. Based on the above, we believe these changes do not involve a significant hazards consideration as defined in 10 CFR 50.92.' |
| | |
| | Attachment 2 to AEP:NRC:06590 Proposed Revised Technical Specifications Pages |
|
| |
|
| ==DearDr.Murley:==
| |
| >>Thisletterisinresponse.toGenericLet'ter'(GL)88-06andconstitutes anapplication foramendment totheTechnical Specifications (T/Ss)"for
| |
| .theDonaldC."CookNuc1ear'lant'nits 1and2.Specifically;,.
| |
| we,are'.proposin'g-todel'ete-'the organization chartsfromSection,6.0Administrative Controls'as'e'commended byGL88-06.Adetaileddescription oftheproposedchan'gesandouranalysesconcerning significant hazardsconsiderations areincludedinAttachment l.Attachment 2containstheproposedrevisedT/Spages.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofanyeffluents thatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.Incompliance withtherequirements,'of 10'CFR50.91(b)(1),
| |
| copiesofthisletteranditsattachments'.have beentransmitted toMr.R.C.CallenoftheMichiganPublic'Service'Commis'sion andMr..G.Bruchmann oftheMichiganDepart'ment ofPublicHealth:'~~,>>f>>.''.pIPursuantto10CFR170:12(c),>>:
| |
| wehave'nclosed "an'pplication feeof$150.00fortheproposedamendments.
| |
| 8805'i90098880%OhPDRADOCK05000315PNUp>>>>o/lI
| |
| ~4 Dr.T.E.Murley-2-AEP:NRC'06590 Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
| |
| Sincerely, M.P.AlexihVicePresident ldpAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector
| |
| -BridgmanA.B.Davis-"RegionIII
| |
| ~~~1Attachment' toAEP:NRC:06590 Reasonsand10CFR50.92Significant HazardsEvaluation forChangestotheTechnical Specifications forDonaldC.CookUnits1and2 Attachment 1toAEP:NRC:06590 Page1Thepurposeofthischangeistoeliminate duplicating andmaintaining up-to-date organizational chartsinboththeFSARandthetechnical specifications.
| |
| We,therefore, areproposing todeletetheorganization chartsfromtheSection6.0administrative controlsT/Ss.Thisproposedchangewouldpermitustoimplement changestothestructure oftheonsiteandoffsiteorganizations withoutfirsthavingtoobtainNRCapprovaltoupdatetheorganization chartsintheT/Ss.TheNRCpreviously approvedsimilarchangesfortheMcGuireNuclearStation,Units1and2,onMarch16,1986,andfortheShearonHarrisNuclearPowerPlant,Unit1,onJanuary'27, 1988.Thecontent'equired intheadministrative controlssectionoftheT/Ssisspecified in10CFR50.36C(5).
| |
| Theregulation requiresthattheT/Sscontainthecontrolsandprovisions thatareneededtoensureoperation oftheplantinasafemannerbutdoesnotspecifically requireorganizational chartsintheT/Ss.Inaccordance withtheguidanceprovidedinGenericLetter88-06,wehaveaddedgeneralrequirements thatcapturetheessential aspectsoftheorganizational structure thataredefinedbyexistingorganization charts.Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously
| |
| : analyzed, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated, or(3)involveasignifican" reduction inamarginofsafety.Ourevaluation oftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion 1Thisproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzedbecausethedeletionoftheorganization chartsfromtheT/Ssdoesnotchangeplantoperation.
| |
| WewillcontinuetoinformtheNRCoforganizational changesthroughotherrequiredcontrols.
| |
| TheCodeofFederalRegulations, 10CFR50.34(b)(6)(i),
| |
| requiresustohavetheorganizational structure includedintheFinalSafetyAnalysisReport(FSAR).A Nhg Attachment 1toAEP:NRC:06590 Page2description oftheorganization anddetailedorganization chartsarecontained inChapter1oftheFSAR.Asrequiredby10CFR50.71(e),
| |
| wesubmitannualupdatestotheFSAR.Also10CFR50.54(a)(3) and10CFR50,AppendixBgovernchangestotheorganization asdescribed intheQualityAssurance Program.SomeofthesechangesrequireNRCapprovalbeforetheycanbemade.Criterion 2Thisproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated becausetheproposedchange'sadministrative innature.Therearenophysicalchangestotheplantconfiguration, thesetpoints, oroperating parameters tobemadeasaresultofthisproposedchange.Criterion 3Thisproposedchangedoesnotinvolveasignificant reduction inamarginofsafetyforthereasonsstatedinCriterion l.Lastly,wenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolveasignificant hazardsconsideration.
| |
| Thischangeissimilartothefirstexample,whichreferstochangesthatarepurelyadministrative.
| |
| Basedontheabove,webelievethesechangesdonotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.'
| |
| Attachment 2toAEP:NRC:06590 ProposedRevisedTechnical Specifications Pages
| |
| ~f}} | | ~f}} |
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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
ACCESSION NBR:8809190098 DOC.DATE: 88/09/06 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana S 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana S 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58 DPR-74,proposing S
to delete organization charts from Section 6.0.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR. ENCL PD3-1 LA 1 0 PD3-1 PD 5 5 STANGiJ 1 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NRR/PMAS/ILRB12 1 1 NUDOC BSTRACT 1 1 OGC/HDS1 1 "
0 GF E 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19
Indiana hlichigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:06590 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 GENERIC LETTER 88-06: REMOVAL OF ORGANIZATION CHARTS FROM TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROL REQUIREMENTS U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley September 6, 1988
Dear Dr. Murley:
This letter is in response .to Generic Let'ter '(GL) 88-06 and constitutes an application for amendment to the Technical Specifications (T/Ss)"for .the Donald C."Cook Nuc1ear'lant'nits 1 and 2. Specifically;,. we, are'. proposin'g- to del'ete-'the organization charts from Section, 6.0 Administrative Controls'as'e'commended by GL 88-06. A detailed description of the proposed chan'ges and our analyses concerning significant hazards considerations are included in Attachment l. Attachment 2 contains the proposed revised T/S pages.
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 amount of any effluents 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 will be reviewed by the Nuclear Safety and Design Review Committee 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'Commis'sion and I
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Pursuant to 10 CFR 170:12(c),>>: we have'nclosed
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Mr.. G. Bruchmann of the Michigan Depart'ment of Public Health: '
p "an'pplication fee of $ 150.00 for the proposed amendments.
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8805'i 90098 PDR ADOCK 880%Oh l 0500031 5 I PNU
~ 4 Dr. T. E. Murley AEP:NRC'06590 This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. P. Alexi h Vice President ldp Attachments cc: D. H. Williams, Jr.
W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis -"Region III
~~
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1 Attachment' to AEP:NRC:06590 Reasons and 10 CFR 50.92 Significant Hazards Evaluation for Changes to the Technical Specifications for Donald C. Cook Units 1 and 2
Attachment 1 to AEP:NRC:06590 Page 1 The purpose of this change is to eliminate duplicating and maintaining up-to-date organizational charts in both the FSAR and the technical specifications. We, therefore, are proposing to delete the organization charts from the Section 6.0 administrative controls T/Ss. This proposed change would permit us to implement changes to the structure of the onsite and offsite organizations without first having to obtain NRC approval to update the organization charts in the T/Ss. The NRC previously approved similar changes for the McGuire Nuclear Station, Units 1 and 2, on March 16, 1986, and for the Shearon Harris Nuclear Power Plant, Unit 1, on January'27, 1988.
The content'equired in the administrative controls section of the T/Ss is specified in 10 CFR 50.36C(5). The regulation requires that the T/Ss contain the controls and provisions that are needed to ensure operation of the plant in a safe manner but does not specifically require organizational charts in the T/Ss.
In accordance with the guidance provided in Generic Letter 88-06, we have added general requirements that capture the essential aspects of the organizational structure that are defined by existing organization charts.
Per 10 CFR 50.92, a proposed amendment will not involve a significant not:
hazards consideration if the proposed amendment does (1) involve a significant increase in the probability or consequences of an accident previously analyzed, (2) create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or (3) involve a significan" reduction in a margin of safety.
Our evaluation of the proposed change with respect to these criteria is provided below.
Criterion 1 This proposed change does not involve a significant increase in the probability or consequences of an accident previously analyzed because the deletion of the organization charts from the T/Ss does not change plant operation. We will continue to inform the NRC of organizational changes through other required controls. The Code of Federal Regulations, 10 CFR 50.34(b)(6)(i), requires us to have the organizational structure included in the Final Safety Analysis Report (FSAR). A
N hg to AEP:NRC:06590 Page 2 description of the organization and detailed organization charts are contained in Chapter 1 of the FSAR. As required by 10 CFR 50.71(e), we submit annual updates to the FSAR. Also 10 CFR 50.54(a)(3) and 10 CFR 50, Appendix B govern changes to the organization as described in the Quality Assurance Program. Some of these changes require NRC approval before they can be made.
Criterion 2 This proposed change does not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated because the proposed change's administrative in nature. There are no physical changes to the plant configuration, the setpoints, or operating parameters to be made as a result of this proposed change.
Criterion 3 This proposed change does not involve a significant reduction in a margin of safety for the reasons stated in Criterion l.
Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve a significant hazards consideration. This change is similar to the first example, which refers to changes that are purely administrative. Based on the above, we believe these changes do not involve a significant hazards consideration as defined in 10 CFR 50.92.'
Attachment 2 to AEP:NRC:06590 Proposed Revised Technical Specifications Pages
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