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| | issue date = 03/29/1982 | | | issue date = 03/29/1982 |
| | title = Application to Amend Licenses DPR-58 & DPR-74,changing Tech Specs to Incorporate Editorial & Organizational Changes | | | title = Application to Amend Licenses DPR-58 & DPR-74,changing Tech Specs to Incorporate Editorial & Organizational Changes |
| | author name = HUNTER R S | | | author name = Hunter R |
| | 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 |
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| =Text= | | =Text= |
| {{#Wiki_filter:REGULATORY | | {{#Wiki_filter:REGULATORY ~FORMATION DISTRlBUTION SY M (RIDS) |
| ~FORMATION DISTRlBUTION SYM(RIDS)ACCESSION NBR:8204060050'OC | | ACCESSION NBR:8204060050'OC ~ DATE: 82/03/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant~ Unit 1> Indiana 8 05000315 50"316 Donald C ~ Cook Nuclear Power Planti Uni,t 2i Indiana BYNAME 8 05000316 |
| ~DATE:82/03/29NOTARIZED: | | 'AUTH AUTHOR AFFILIATION HUNTERiR ~ ST Indiana 8 Michigan Electric Co. |
| NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant~Unit1>Indiana80500031550"316DonaldC~CookNuclearPowerPlantiUni,t2iIndiana805000316'AUTHBYNAMEAUTHORAFFILIATION HUNTERiR~STIndiana8MichiganElectricCo..RECIP~NAMERECIPIENT AFFILIATION DENTONIH~REOfficeofNuclearReactorRegula'tioni Director
| | .RECIP ~ NAME RECIPIENT AFFILIATION DENTONIH ~ RE Office of Nuclear Reactor Regula'tioni Director |
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| ==SUBJECT:== | | ==SUBJECT:== |
| .Application | | .Application )to amend Licenses DPR-58 8 DPR 74ichanging "Tech Specs to incorporate ediitorial 8 organizational changes. |
| )toamendLicensesDPR-588DPR74ichanging "TechSpecstoincorporate ediitorial 8organizational changes.DISTRIBUTION CODE:A001SCOPIES'RECEIVED:LTR | | DISTRIBUTION CODE: A001S COPIES 'RECEIVED:LTR . ENCL,t, TITLE: General Distribution for after Issuance of, Operating License SIZEe..~ j 5 materially NOTES:I8E:3 copies all materials "0500031'5 I8E:3 copies all 05000316 RECIPIENT COPIES 'ECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NANIE LT~TR ENCL ORB 0 i BC 01 13 13 INTERNAL! ELD 1 0 IE 06 1 NRR/DHFS DEPY08 NRR/DL DIR REG 04 10 1 |
| .ENCL,t,SIZEe..~j5TITLE:GeneralDistribution forafterIssuanceof,Operating LicenseNOTES:I8E:3 copiesallmaterials I8E:3copiesallmaterially "0500031'5 05000316RECIPIENT IDCODE/NAME ORB0iBC01COPIES'ECIPIENT LTTRENCLIDCODE/NANIE 1313COPIESLT~TRENCLINTERNAL! | | 1, 1 |
| ELDNRR/DHFSDEPY08REG04EXTERNAL:
| | 1 NRR/DS I/RAB RGN3 1 |
| ACRS09NRCPDR02NTI'1011101,110101111IENRR/DLDIRNRR/DSI/RABRGN3LPDRNSIC06-030511111112211cgecu(:A3~a.e'a'37TOTALNUMBEROFCOPIESl<EQUIRED
| | 1 1 |
| ~LTTRENCL A111ntn"f'llwiiilffI1ill<'4,1wWIfeaJ(wwwn.c.E'If,W1l,w~WI1~A'IwfPl0~g0'w''w'l'ffNjf''l,t4itww1gl,,l'wflff1n INDIANAIIMICHIGANELECTRICCOMPANYP.O.8OX1880WLINGGREENSTATIONNEWYORK,N.Y.10004March29,1982~AEP:NRC:0659 DonaldC.CookNuclearPlantUnitNos.1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74TECHNICAL SPECIFICATIONS CHANGEREQUESTMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.205556'g9e+~
| | 1 1 |
| | 1 EXTERNAL: ACRS 09 10 10 LPDR -03 2 2 NRC PDR 02 1 1 NSIC 05 1 1 NT I' 1 1 cgecu(: A 3 ~a.e'a |
| | '37 TOTAL NUMBER OF COPIES l<EQUIRED ~ LTTR ENCL |
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| ==DearMr.Denton:== | | A 1 |
| ThisletteranditsAttachments requestseveralchangestotheDonaldC.CookNuclearPlant,UnitNo.1andNo.2AppendixATechnical Specifications.
| | 1 1 n t |
| Attachment No.1tothislettercontainsthedescription ofthechanges.Attachment No.2containstherevisedTechnical Specification pagesforUnitNo.l.andAttachment No.3containstherevisedTechnical Specification pagesforUnitNo.2.Allchangesareindicated byaverticallineontherighthandsideofthepageinAttachment Nos.2and3.TheproposedTechnical Specification changescontained hereinhavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee (PNSRC).ChangeNo.1hasbeenapprovedbytheAEPSCNuclearSafetyandDesignReviewCommittee (NSDRC)andChangeNos.2,3,and4willbepresented totheNSDRCattheirnextmeeting.g/OFourproposedTechnical Specification revisions arecontained inthissubmittal. | | n" f'll w i |
| ChangeNos.2and3areconsidered tobeClassIIamendments
| | iil ill < |
| ($1,200.00feeeach).ClassIduplicate feesalsoapplyforthesechanges.ChangeNos.1and4areeditorial innature.Enclosed, therefore, isacheckinthaamountofg3,200.00 forNRCprocessing of~/t+~theaforementioned requests. | | f f I 1 |
| g/gazoo82040b0050 820329PDRADOCK05000315PDR 41~'tk)I),I:}I))ItII'IttItJtloOI'II'tf'<<}~'I',tII<<I''1Wl,'J"tI*)WW',.P'tIJII.J,(')',"'W""'')I}Ij'I}}"jIl<<)WWII<<ttt}Ih1Wt,.It},I}')'TgP/ktjI,'W'i~IIt Mr.HaroldR.DentonAEP:NRC:0659 Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate areasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned. | | '4,1 wW W |
| Verytrulyyours,R.S.HunterVicePresident
| | 0 IfeaJ(ww wn . c. E I 1 Pl |
| /mdcc:JohnE.Dolan-ColumbusR.W.Jurgensen W.G.Smith,Jr.-BridgmanR.C.CallenG.CharnoffJoeWilliams, Jr.NRCResidentInspector atCookPlant-Bridgman ATTACHMENT NO.1TOAEP:NRC:00659 DESCRIPTION OFPROPOSEDTECHNICAL SPECIFICATION CHANGESFORD.C.COOKUNITNOS~1AND2 ChaneNo.1Unit1;Page3/43-9;Table3.3-1Unit2;Page3/43-8;Table3.3-1,Thischangeiseditorial innature.ForUnitNos.1and2,itisrequested tochangethewords"Turbineimpulsechamberpressure" underDesignation P-7oftheReactorTripSystemInterlocks ofTable3.3-1("ReactorTripSystemInstrumentation" | | 'If, W 1 l, w ~ ~ |
| )tomoreaccurately describethesechannels. | | A |
| ForUnitNo.1,itisrequested thatthesewordsbechangedto"TurbineFirstStagePressure" whichisthecontrolroomnameplate terminology usedforthesechannels.
| | 'I wf ~ |
| ForUnitNo.2,itisrequested tochangethesewordsto"Pressure BeforetheFirstStage"whichisatechnically accuratedescription ofthesechannels.
| | g 0'w ''w'l 'ff jf' N |
| TheUnitNo.2controlroomnameplate terminology willbechangedtocoincidewiththeproposedwording.Theabovechangeswillresultinaccurateandconsistent Technical Specification andcontrolroomnameplate terminology descriptions of-thesechannels.
| | 'l , t 4 it w w 1 g l,, l' w |
| Thesechangeswillnotadversely affectthehealthandsafetyofthegeneralpublic.ChaneNo.2Unit1;Page6-2;Figure6.2-1Unit2;Page6-2;Figure6.2-1Figure6.2-1isthe"OffsiteOrganization forFacilityManagement andTechnical Support".
| | fl 1 |
| ThisFigurehasbeenrevisedtoincorporate themostrecentoffsiteorganizational management changes.TheproposedchangeswillresultinaFigurewhichmoreaccurately describes ourcurrentorganization.
| | ff n |
| Thesechangeswillnotadversely affectthehealthandsafetyofthegeneralpublic.ChaneNo.3Unit1;Page6-3;Figure6.2-2Page6-5;Section6.3Page6-6;Section6.5.1.2Unit2;Page6-3;Figure6.2-2Page6-5;Section6.3Page6-5;Section6.5.1.2Figure6.2-2ofbothUnits'echnical Specifications isthe"Facility Organization" oftheDonaldC.CookNuclearPlant.ThisFigurehasbeenamendedtoshowcurrentpositiontitlesandtheadditionofthefollowing fivesupervisory positions:
| | |
| FireProtection Coordinator ChiefSecuritySupervisor ShiftSecuritySupervisor Environmental Coordinator ShiftTechnical Advisor Threefootnotes havealsobeenaddedtothelegendofthecharttomoreaccurately describethereporting natureoftheQASupervisor andtoindicatetheUnitSupervisor's presentoperating license.Theindicated changeswillmaketheFacilityOrganization chartcurrent.Inaddition, Specification 6.3.2hasbeenaddedunderSpecification 6.3,"Facility StaffQualifications",
| | INDIANA II MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 80 WLING GR E EN STATION NEW YORK, N. Y. 10004 March 29, 1982 |
| ofbothUnits.Specification 6.3.2hasbeenaddedtoaccommodate ournewOperations Superintendent, whodoesnotpresently holdaSeniorReactorOperator's License(SOL).Specification 6.5.1.2,whichidentifies theChairmanandMembersofthePlantNuclearSafetyReviewCommittee (PNSRC),hasbeenamendedtoreflectpresentpositiontitles.Inaddition, theShiftSupervisor andEnvironmental Coordinator havebeenincludedasPNSRCmembers.Thesechangeswillnotadversely affectthehealthandsafetyofthegeneralpublic.ChaneNo.4Unit1;Unit2;Page6-13;Section6.7.1.dPage6-13;Section6.7.1.dSpecification 6.7.l.didentifies to.whomaSafetyLimitViolation Reportshallbesubmitted intheeventaSafetyLimitisviolated.
| | ~ |
| Thischangeiseditorial innatureandservestoreflectthepresentpositiontitleofthepreviousVicePresident,-
| | AEP:NRC:0659 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 TECHNICAL SPECIFICATIONS CHANGE REQUEST Mr. Harold R. Denton, Director 6'g9e+~ |
| NuclearEngineering.
| | Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| Thus,inadditiontotheCommission andtheChairmanoftheNSDRC,aSafetyViolation Reportshallalsobesubmitted totheExecutive VicePresident, Construction andNewYorkEngineering, AEPSC.Thischangewillnotadversely affectthehealthandsafetyofthegeneralpublic. | | |
| ATTACHMENT NO.2TOAEP:NRC:00659 REVISEDTECHNICAL SPECIFICATION PAGESFORD.C.COOKUNITNO.1}} | | ==Dear Mr. Denton:== |
| | |
| | This letter and its Attachments request several changes to the Donald C. Cook Nuclear Plant, Unit No. 1 and No. 2 Appendix A Technical Specifications. Attachment No. 1 to this letter contains the description of the changes. Attachment No. 2 contains the revised Technical Specification pages for Unit No. l. and Attachment No. 3 contains the revised Technical Specification pages for Unit No. 2. All changes are indicated by a vertical line on the right hand side of the page in Attachment Nos. 2 and 3. |
| | The proposed Technical Specification changes contained herein have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC). Change No. 1 has been approved by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) and Change Nos. 2, 3, and 4 will be presented to the NSDRC at their next meeting. g/ |
| | O Four proposed Technical Specification revisions are contained in this submittal. Change Nos. 2 and 3 are considered to be Class II amendments ($ 1,200.00 fee each). Class I duplicate fees also apply for these changes. Change Nos. 1 and 4 are editorial in nature. Enclosed, therefore, is a check in tha amount of g3,200.00 for NRC processing of ~/t+~ |
| | the aforementioned requests. |
| | g/ gazoo 820329 82040b0050 05000315 PDR ADOCK PDR |
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| | Mr. Harold R. Denton AEP:NRC:0659 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, R. S. Hunter Vice President |
| | /md cc: John E. Dolan Columbus R. W. Jurgensen W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff Joe Williams, Jr. |
| | NRC Resident Inspector at Cook Plant Bridgman |
| | |
| | ATTACHMENT NO. 1 TO AEP:NRC:00659 DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGES FOR D. C. COOK UNIT NOS ~ 1 AND 2 |
| | |
| | Chan e No. 1 Unit 1; Page 3/4 3-9; Table 3.3-1 Unit 2; Page 3/4 3-8; Table 3.3-1 |
| | , This change is editorial in nature. For Unit Nos. 1 and 2, it is requested to change the words "Turbine impulse chamber pressure" under Designation P-7 of the Reactor Trip System Interlocks of Table 3.3-1 ("Reactor Trip System Instrumentation" ) to more accurately describe these channels. For Unit No. 1, it is requested that these words be changed to "Turbine First Stage Pressure" which is the control room nameplate terminology used for these channels. For Unit No. 2, it is requested to change these words to "Pressure Before the First Stage" which is a technically accurate description of these channels. The Unit No. 2 control room nameplate terminology will be changed to coincide with the proposed wording. The above changes will result in accurate and consistent Technical Specification and control room nameplate terminology descriptions of- these channels. These changes will not adversely affect the health and safety of the general public. |
| | Chan e No. 2 Unit 1; Page 6-2; Figure 6.2-1 Unit 2; Page 6-2; Figure 6.2-1 Figure 6.2-1 is the "Offsite Organization for Facility Management and Technical Support". This Figure has been revised to incorporate the most recent offsite organizational management changes. |
| | The proposed changes will result in a Figure which more accurately describes our current organization. These changes will not adversely affect the health and safety of the general public. |
| | Chan e No. 3 Unit 1; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-6; Section 6.5.1.2 Unit 2; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-5; Section 6.5.1.2 Figure 6.2-2 of both Units'echnical Specifications is the "Facility Organization" of the Donald C. Cook Nuclear Plant. This Figure has been amended to show current position titles and the addition of the following five supervisory positions: |
| | Fire Protection Coordinator Chief Security Supervisor Shift Security Supervisor Environmental Coordinator Shift Technical Advisor |
| | |
| | Three footnotes have also been added to the legend of the chart to more accurately describe the reporting nature of the QA Supervisor and to indicate the Unit Supervisor's present operating license. The indicated changes will make the Facility Organization chart current. |
| | In addition, Specification 6.3.2 has been added under Specification 6.3, "Facility Staff Qualifications", of both Units. |
| | Specification 6.3.2 has been added to accommodate our new Operations Superintendent, who does not presently hold a Senior Reactor Operator's License (SOL). |
| | Specification 6.5.1.2, which identifies the Chairman and Members of the Plant Nuclear Safety Review Committee (PNSRC), has been amended to reflect present position titles. In addition, the Shift Supervisor and Environmental Coordinator have been included as PNSRC members. |
| | These changes will not adversely affect the health and safety of the general public. |
| | Chan e No. 4 Unit 1; Page 6-13; Section 6. 7. 1. d Unit 2; Page 6-13; Section 6.7.1.d Specification 6.7.l.d identifies to .whom a Safety Limit Violation Report shall be submitted in the event a Safety Limit is violated. This change is editorial in nature and serves to reflect the present position title of the previous Vice President,- Nuclear Engineering. Thus, in addition to the Commission and the Chairman of the NSDRC, a Safety Violation Report shall also be submitted to the Executive Vice President, Construction and New York Engineering, AEPSC. |
| | This change will not adversely affect the health and safety of the general public. |
| | |
| | ATTACHMENT NO. 2 TO AEP:NRC:00659 REVISED TECHNICAL SPECIFICATION PAGES FOR D.C. COOK UNIT NO. 1}} |
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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
REGULATORY ~FORMATION DISTRlBUTION SY M (RIDS)
ACCESSION NBR:8204060050'OC ~ DATE: 82/03/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant~ Unit 1> Indiana 8 05000315 50"316 Donald C ~ Cook Nuclear Power Planti Uni,t 2i Indiana BYNAME 8 05000316
'AUTH AUTHOR AFFILIATION HUNTERiR ~ ST Indiana 8 Michigan Electric Co.
.RECIP ~ NAME RECIPIENT AFFILIATION DENTONIH ~ RE Office of Nuclear Reactor Regula'tioni Director
SUBJECT:
.Application )to amend Licenses DPR-58 8 DPR 74ichanging "Tech Specs to incorporate ediitorial 8 organizational changes.
DISTRIBUTION CODE: A001S COPIES 'RECEIVED:LTR . ENCL,t, TITLE: General Distribution for after Issuance of, Operating License SIZEe..~ j 5 materially NOTES:I8E:3 copies all materials "0500031'5 I8E:3 copies all 05000316 RECIPIENT COPIES 'ECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NANIE LT~TR ENCL ORB 0 i BC 01 13 13 INTERNAL! ELD 1 0 IE 06 1 NRR/DHFS DEPY08 NRR/DL DIR REG 04 10 1
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INDIANA II MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 80 WLING GR E EN STATION NEW YORK, N. Y. 10004 March 29, 1982
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AEP:NRC:0659 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 TECHNICAL SPECIFICATIONS CHANGE REQUEST Mr. Harold R. Denton, Director 6'g9e+~
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
This letter and its Attachments request several changes to the Donald C. Cook Nuclear Plant, Unit No. 1 and No. 2 Appendix A Technical Specifications. Attachment No. 1 to this letter contains the description of the changes. Attachment No. 2 contains the revised Technical Specification pages for Unit No. l. and Attachment No. 3 contains the revised Technical Specification pages for Unit No. 2. All changes are indicated by a vertical line on the right hand side of the page in Attachment Nos. 2 and 3.
The proposed Technical Specification changes contained herein have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC). Change No. 1 has been approved by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) and Change Nos. 2, 3, and 4 will be presented to the NSDRC at their next meeting. g/
O Four proposed Technical Specification revisions are contained in this submittal. Change Nos. 2 and 3 are considered to be Class II amendments ($ 1,200.00 fee each). Class I duplicate fees also apply for these changes. Change Nos. 1 and 4 are editorial in nature. Enclosed, therefore, is a check in tha amount of g3,200.00 for NRC processing of ~/t+~
the aforementioned requests.
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Mr. Harold R. Denton AEP:NRC:0659 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, R. S. Hunter Vice President
/md cc: John E. Dolan Columbus R. W. Jurgensen W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at Cook Plant Bridgman
ATTACHMENT NO. 1 TO AEP:NRC:00659 DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGES FOR D. C. COOK UNIT NOS ~ 1 AND 2
Chan e No. 1 Unit 1; Page 3/4 3-9; Table 3.3-1 Unit 2; Page 3/4 3-8; Table 3.3-1
, This change is editorial in nature. For Unit Nos. 1 and 2, it is requested to change the words "Turbine impulse chamber pressure" under Designation P-7 of the Reactor Trip System Interlocks of Table 3.3-1 ("Reactor Trip System Instrumentation" ) to more accurately describe these channels. For Unit No. 1, it is requested that these words be changed to "Turbine First Stage Pressure" which is the control room nameplate terminology used for these channels. For Unit No. 2, it is requested to change these words to "Pressure Before the First Stage" which is a technically accurate description of these channels. The Unit No. 2 control room nameplate terminology will be changed to coincide with the proposed wording. The above changes will result in accurate and consistent Technical Specification and control room nameplate terminology descriptions of- these channels. These changes will not adversely affect the health and safety of the general public.
Chan e No. 2 Unit 1; Page 6-2; Figure 6.2-1 Unit 2; Page 6-2; Figure 6.2-1 Figure 6.2-1 is the "Offsite Organization for Facility Management and Technical Support". This Figure has been revised to incorporate the most recent offsite organizational management changes.
The proposed changes will result in a Figure which more accurately describes our current organization. These changes will not adversely affect the health and safety of the general public.
Chan e No. 3 Unit 1; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-6; Section 6.5.1.2 Unit 2; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-5; Section 6.5.1.2 Figure 6.2-2 of both Units'echnical Specifications is the "Facility Organization" of the Donald C. Cook Nuclear Plant. This Figure has been amended to show current position titles and the addition of the following five supervisory positions:
Fire Protection Coordinator Chief Security Supervisor Shift Security Supervisor Environmental Coordinator Shift Technical Advisor
Three footnotes have also been added to the legend of the chart to more accurately describe the reporting nature of the QA Supervisor and to indicate the Unit Supervisor's present operating license. The indicated changes will make the Facility Organization chart current.
In addition, Specification 6.3.2 has been added under Specification 6.3, "Facility Staff Qualifications", of both Units.
Specification 6.3.2 has been added to accommodate our new Operations Superintendent, who does not presently hold a Senior Reactor Operator's License (SOL).
Specification 6.5.1.2, which identifies the Chairman and Members of the Plant Nuclear Safety Review Committee (PNSRC), has been amended to reflect present position titles. In addition, the Shift Supervisor and Environmental Coordinator have been included as PNSRC members.
These changes will not adversely affect the health and safety of the general public.
Chan e No. 4 Unit 1; Page 6-13; Section 6. 7. 1. d Unit 2; Page 6-13; Section 6.7.1.d Specification 6.7.l.d identifies to .whom a Safety Limit Violation Report shall be submitted in the event a Safety Limit is violated. This change is editorial in nature and serves to reflect the present position title of the previous Vice President,- Nuclear Engineering. Thus, in addition to the Commission and the Chairman of the NSDRC, a Safety Violation Report shall also be submitted to the Executive Vice President, Construction and New York Engineering, AEPSC.
This change will not adversely affect the health and safety of the general public.
ATTACHMENT NO. 2 TO AEP:NRC:00659 REVISED TECHNICAL SPECIFICATION PAGES FOR D.C. COOK UNIT NO. 1