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| {{#Wiki_filter:Fmxaa.X~rV i(ACCELERATED RIDSPROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9409290181 DOC.DATE: | | {{#Wiki_filter:Fmxaa.X~rV i (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9409290181 DOC.DATE: 94/09/27 NOTARIZED: |
| 94/09/27NOTARIZED: | | YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. |
| YESDOCKETFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
| Rochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | | Project Directorate I-3 |
| ProjectDirectorate I-3
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| ==SUBJECT:== | | ==SUBJECT:== |
| Transmits requested changesto940513LAR,revising TSSection6.0,"Administrative Controls" | | Transmits requested changes to 940513 LAR,revising TS Section 6.0,"Administrative Controls"&ack set of revised TS requirements discussed in LAR which will be reviewed by NRC at this time,per 940803 telcon w/NRC.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL L SIZE: TITLE: OR Submittal: |
| &acksetofrevisedTSrequirements discussed inLARwhichwillbereviewedbyNRCatthistime,per940803telconw/NRC.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLLSIZE:TITLE:ORSubmittal: | | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | 05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERN: FILE CENTER 0 ARCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DE/EELB NRR/DRPW NRR/DS SA/SRXB OC/LFDCB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| 05000244RECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERN:FILECENTER0ARCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS3EXTERNAL:
| | PLEASE HELP US TO REDUCE IVASTE!CONTACT TIIE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT.504-2083)TO ELlih!INATE YOUR NAlIE PRO~I DISTRIBUTION LISTS I'OR DOCI;MENTS YOU DON"I'EED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 12 AND ROCHESTER GAS AND ELECI1C CORPORAT1ON |
| NOACCOPIESLTTRENCL1111111111111011RECIPIENT IDCODE/NAME PD1-3PDNRR/DE/EELB NRR/DRPWNRR/DSSA/SRXBOC/LFDCBNRCPDRCOPIESLTTRENCL111111111011NOTETOALL"RIDS"RECIPIENTS:
| | ~89 EASTAVENUE, ROCHESTER, N.Y 1d6d9-OOOI ROBERT C MECREOY Vice President September 27, 1994 Cinna Nudear Production AREA CODE716 5'.27OO U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555 |
| PLEASEHELPUSTOREDUCEIVASTE!CONTACTTIIEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELlih!INATEYOURNAlIEPRO~IDISTRIBUTION LISTSI'ORDOCI;MENTS YOUDON"I'EED!TOTALNUMBEROFCOPIESREQUIRED:
| |
| LTTR14ENCL12 ANDROCHESTER GASANDELECI1CCORPORAT1ON
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| ~89EASTAVENUE, ROCHESTER, N.Y1d6d9-OOOI ROBERTCMECREOYVicePresident September 27,1994CinnaNudearProduction AREACODE7165'.27OOU.S.NuclearRegulatory Commission DocumentControlDeskAttn:AllenR.JohnsonProjectDirectorate I-3Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseUpgradeofAdministrative ControlsSection6.0Rochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Application for Amendment to Facility Operating License Upgrade of Administrative Controls Section 6.0 Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==References:== | | ==References:== |
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| a.LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC, | | a.Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating License,UpgradeofAdministrative ControlsSection6.0,datedHay13,1994.b.LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC, | | Application for Amendment to Facility Operating License, Upgrade of Administrative Controls Section 6.0, dated Hay 13, 1994.b.Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| Conversion toImprovedTechnical Specifications, datedFebruary28,1994. | | Conversion to Improved Technical Specifications, dated February 28, 1994. |
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| ==DearHr.Johnson,== | | ==Dear Hr.Johnson,== |
| Rochester GasandElectric(RG&E)previously submitted aLicenseAmendment Request(LAR)whichproposedtorevisetheGinnaStationTechnical Specifications (TS)Section6,Administrative Controls(Ref.a).OnAugust3,1994,aconference callwasconducted betweentheNRCandRG&EatwhichtimeseveralchangestotheLARwererequested bytheNRC.Thisdocumenttransmits therequested changesandacknowledges thesetofrevisedTSrequirements discussed intheLARwhichwillbereviewedbytheNRCatthistime.Theremaining TSchangeswillbedeferreduntiltheconversion oftheentireGinnaStationTSduringtheTechnical Specification Improvement Program(Ref.b).Thefollowing changesasdiscussed inAttachment AtoReference aarebeingrequested atthistime:ta.SectionC.1,changeiv(exceptfortheproposeddeletionofGinnaTS6.8.1.f). | | Rochester Gas and Electric (RG&E)previously submitted a License Amendment Request (LAR)which proposed to revise the Ginna Station Technical Specifications (TS)Section 6, Administrative Controls (Ref.a).On August 3, 1994, a conference call was conducted between the NRC and RG&E at which time several changes to the LAR were requested by the NRC.This document transmits the requested changes and acknowledges the set of revised TS requirements discussed in the LAR which will be reviewed by the NRC at this time.The remaining TS changes will be deferred until the conversion of the entire Ginna Station TS during the Technical Specification Improvement Program (Ref.b).The following changes as discussed in Attachment A to Reference a are being requested at this time: t a.Section C.1, change iv (except for the proposed deletion of Ginna TS 6.8.1.f).tt b.Section C.2, changes i, ii (except for the proposed deletion of TS 6.2.2.b and 6.2.2.c), iii, iv, v, vii (revise the submittal of Radiological Effluent Release Report from semiannual to annual only), ix, and x.c.Section C.3, changes iv, vi, and vii.i>pit p P'Q's1409290181 |
| ttb.SectionC.2,changesi,ii(exceptfortheproposeddeletionofTS6.2.2.band6.2.2.c),
| | 'st40927 PDR ADOCK 05000244 p f I Pp%~\~-W I d.Section C.4, change v.e.Section C.7, changes iii and v.These changes are reflected in the enclosed Attachment 8 and C to this letter.Similar to Reference a, Attachment B provides the marked-up Ginna Station TS which documents the requested changes while Attachment C provides the proposed new TS following the changes.Since the above changes are only a subset of those originally requested in Reference a, several additional changes are now necessary to ensure a complete specification. |
| iii,iv,v,vii(revisethesubmittal ofRadiological EffluentReleaseReportfromsemiannual toannualonly),ix,andx.c.SectionC.3,changesiv,vi,andvii.i>pitpP'Q's1409290181 | | These additional changes and their justification are provided in Attachment A.The remaining justification of changes, safety evaluation, and no significant hazards and environmental considerations provided in Attachment A of Reference a remain unchanged. |
| 'st40927PDRADOCK05000244p fIPp%~\~-WI d.SectionC.4,changev.e.SectionC.7,changesiiiandv.Thesechangesarereflected intheenclosedAttachment 8andCtothisletter.SimilartoReference a,Attachment Bprovidesthemarked-up GinnaStationTSwhichdocuments therequested changeswhileAttachment CprovidestheproposednewTSfollowing thechanges.Sincetheabovechangesareonlyasubsetofthoseoriginally requested inReference a,severaladditional changesarenownecessary toensureacompletespecification. | | We request that upon NRC approval, this application should be considered effective immediately and implemented within 60 days, or upon NRC approval and implementation of the gA Program changes, whichever is later.Ver uly yours, Robert C, Mecred Subscribed and sworn to before me on this 27th day of September 1994.N ary ublic MDFX634 Attachments Nsr hRPin es sgs g~~NNROE COUNY@g, xc: Mr.Allen R.Johnson (Mail Stop 14DI)PWR Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector I ll>>II g I'E g E~f..ml4 Nqd aP~ |
| Theseadditional changesandtheirjustification areprovidedinAttachment A.Theremaining justification ofchanges,safetyevaluation, andnosignificant hazardsandenvironmental considerations providedinAttachment AofReference aremainunchanged.
| | Hr.Gene Eckholt Northern States Power Company Prairie Island Nuclear Generating Plant Route 2 Welch, HN 55089 Hr.Thomas Halanowski Wisconsin Electric Power 231 West Michigan Milwaukee, WI 53201 Hs.Sherry Bernhoft Wisconsin Public Service P.O.Box 19002 700 North Adams Green Bay, WI 54307-9002 Mr.Jack Stringfellow Southern Nuclear Operating Company P.O.Box 1295 40 Inverness Center Parkway Birmingham, AL 35201 Hr.Lee Bush Commonwealth Edison Company Zion Nuclear Station 101 Shiloh Boulevard Zion, IL 60099 C~I!5"l Ir ATTACHMENT A Justification of Changes The justification for all changes to the current Ginna Station TS are provided in Attachment A, Section C to the letter from R.C.Mecredy, RGKE, to A.R.Johnson, NRC, |
| WerequestthatuponNRCapproval, thisapplication shouldbeconsidered effective immediately andimplemented within60days,oruponNRCapprovalandimplementation ofthegAProgramchanges,whichever islater.Verulyyours,RobertC,MecredSubscribed andsworntobeforemeonthis27thdayofSeptember 1994.NaryublicMDFX634Attachments NsrhRPinessgsg~~NNROECOUNY@g,xc:Mr.AllenR.Johnson(MailStop14DI)PWRProjectDirectorate I-3Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector Ill>>IIgI'EgE~f..ml4NqdaP~
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| Hr.GeneEckholtNorthernStatesPowerCompanyPrairieIslandNuclearGenerating PlantRoute2Welch,HN55089Hr.ThomasHalanowski Wisconsin ElectricPower231WestMichiganMilwaukee, WI53201Hs.SherryBernhoftWisconsin PublicServiceP.O.Box19002700NorthAdamsGreenBay,WI54307-9002 Mr.JackStringfellow SouthernNuclearOperating CompanyP.O.Box129540Inverness CenterParkwayBirmingham, AL35201Hr.LeeBushCommonwealth EdisonCompanyZionNuclearStation101ShilohBoulevard Zion,IL60099 C~I!5"lIr ATTACHMENT AJustification ofChangesThejustification forallchangestothecurrentGinnaStationTSareprovidedinAttachment A,SectionCtotheletterfromR.C.Mecredy,RGKE,toA.R.Johnson,NRC, | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating License,.UpgradeofAdministrative ControlsSection6.0,datedMay13,1994.Thejustification foradditional changesnotdiscussed intheMay13,1994letterareprovidedbelow:RevisedtheTableofContentstosupporttherequested changes.I2.3.Thefollowing specifications havebeenrevisedtoprovideafootnotewhichallowsforanalternate titletobedesignated forthespecified position: | | Application for Amendment to Facility Operating License,.Upgrade of Administrative Controls Section 6.0, dated May 13, 1994.The justification for additional changes not discussed in the May 13, 1994 letter are provided below: Revised the Table of Contents to support the requested changes.I 2.3.The following specifications have been revised to provide a footnote which allows for an alternate title to be designated for the specified position: a.TS 6.2.l.b, 6.7.b and 6.7.d-Senior Vice President, Production and Engineering. |
| a.TS6.2.l.b,6.7.band6.7.d-SeniorVicePresident, Production andEngineering. | | b.TS 6.4.1-Division Training Manager c.TS 6.13.1-Health Physicist Specifying management positions by title within the technical specifications creates a licensee and NRC burden when titles are changed or responsibilities are shifted.The current Ginna Station TS 6.2.l.a requires that"lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all Plant management positions." The footnote requires that the alternate titles be specified in the Updated Final Safety Analysis Report (UFSAR)and that all the technical specification requirements apply to the alternate title.The title of the Senior Vice President, Production and Engineering has also been revised to Senior Vice President, Customer Operations. |
| b.TS6.4.1-DivisionTrainingManagerc.TS6.13.1-HealthPhysicist Specifying management positions bytitlewithinthetechnical specifications createsalicenseeandNRCburdenwhentitlesarechangedorresponsibilities areshifted.ThecurrentGinnaStationTS6.2.l.arequiresthat"linesofauthority, responsibility, andcommunication shallbeestablished anddefinedfromthehighestmanagement levelsthroughintermediate levelstoandincluding allPlantmanagement positions." | | This is an individual's title change only.This Senior Vice President continues to have corporate responsibility for overall Plant nuclear safety and is chairman of the offsite review function (i.e., Nuclear Safety Audit and Review Board).The footnote for the Senior Vice President, Customer Operations further specifies that the use of an alternate title for this position must be performed in accordance with 10 CFR'0.54(a)(3). |
| Thefootnoterequiresthatthealternate titlesbespecified intheUpdatedFinalSafetyAnalysisReport(UFSAR)andthatallthetechnical specification requirements applytothealternate title.ThetitleoftheSeniorVicePresident, Production andEngineering hasalsobeenrevisedtoSeniorVicePresident, CustomerOperations.
| | The responsibilities of key organization positions, including the Senior Vice President, Production and Engineering are specified in the Ginna Station gA Program.Since changes to the gA Program are controlled by 10 CFR 50.54(a)(3), equivalent control is provided.TS 6.2.2.a and 6.2,2,d and Table,6.2-1 were removed from the technical specifications since they duplicate current regulations as specified in 10 CFR 50.54(k), (1), and (m).However, the following shift crew requirements as specified in TS Table 6.2-1 are not contained within the current regulations and must be added to TS 6.2.2: a.An auxiliary operator with fuel in the reactor, b.A second auxiliary operator above Cold Shutdown, and.9409290181 I (ii, 4, 5.c.A Shift Technical Advisor (STA)above Cold Shutdown.In addition, the exception provided in TS Table, 6.2-1 with respect to unexpected absences of on-duty shift crew members was also added to TS 6.2.2.Also, TS 6.2.2.b and 6.2.2.c are revised consistent with NUREG-1431 (ITS 5.2.2.b).TS 6.13.1 was revised to replace"health physicist" with"radiation protection" in those places where health physicist was a generic reference since this department is currently identified as radiation protection. |
| Thisisanindividual's titlechangeonly.ThisSeniorVicePresident continues tohavecorporate responsibility foroverallPlantnuclearsafetyandischairmanoftheoffsitereviewfunction(i.e.,NuclearSafetyAuditandReviewBoard).ThefootnotefortheSeniorVicePresident, CustomerOperations furtherspecifies thattheuseofanalternate titleforthispositionmustbeperformed inaccordance with10CFR'0.54(a)(3).
| | Specific functions performed by a health physicist were not revised.This is not a technical change.A submittal date of Hay 1 of each year was selected for the Radioactive Effluent Release Report since 10 CFR 50.36a only requires an annual submittal but does not identify a specific submittal date.The last RGEE submittal. |
| Theresponsibilities ofkeyorganization positions, including theSeniorVicePresident, Production andEngineering arespecified intheGinnaStationgAProgram.SincechangestothegAProgramarecontrolled by10CFR50.54(a)(3),
| | of this report was on August 30, 1994.Therefore, the next report on May 1, 1995 is less than the required annual submittal frequency and is consistent with the submittal date of the Annual Radiological Environmental Operation Report (TS 6.9.1.3).A cross reference to the justification of each proposed change is provided in the left margin of each Ginna Station TS that has been changed by use of a circle containing section numbers from either Attachment A, Section C of the Hay 13, 1994 letter (e.g., C.l.iv)or the above justifications (e.g., A.1).}} |
| equivalent controlisprovided. | |
| TS6.2.2.aand6.2,2,dandTable,6.2-1 wereremovedfromthetechnical specifications sincetheyduplicate currentregulations asspecified in10CFR50.54(k),
| |
| (1),and(m).However,thefollowing shiftcrewrequirements asspecified inTSTable6.2-1arenotcontained withinthecurrentregulations andmustbeaddedtoTS6.2.2:a.Anauxiliary operatorwithfuelinthereactor,b.Asecondauxiliary operatoraboveColdShutdown, and.9409290181 I(ii, 4,5.c.AShiftTechnical Advisor(STA)aboveColdShutdown. | |
| Inaddition, theexception providedinTSTable,6.2-1withrespecttounexpected absencesofon-dutyshiftcrewmemberswasalsoaddedtoTS6.2.2.Also,TS6.2.2.band6.2.2.carerevisedconsistent withNUREG-1431(ITS5.2.2.b).
| |
| TS6.13.1wasrevisedtoreplace"healthphysicist" with"radiation protection" inthoseplaceswherehealthphysicist wasagenericreference sincethisdepartment iscurrently identified asradiation protection.
| |
| Specificfunctions performed byahealthphysicist werenotrevised.Thisisnotatechnical change.Asubmittal dateofHay1ofeachyearwasselectedfortheRadioactive EffluentReleaseReportsince10CFR50.36aonlyrequiresanannualsubmittal butdoesnotidentifyaspecificsubmittal date.ThelastRGEEsubmittal.
| |
| ofthisreportwasonAugust30,1994.Therefore, thenextreportonMay1,1995islessthantherequiredannualsubmittal frequency andisconsistent withthesubmittal dateoftheAnnualRadiological Environmental Operation Report(TS6.9.1.3).Acrossreference tothejustification ofeachproposedchangeisprovidedintheleftmarginofeachGinnaStationTSthathasbeenchangedbyuseofacirclecontaining sectionnumbersfromeitherAttachment A,SectionCoftheHay13,1994letter(e.g.,C.l.iv)ortheabovejustifications (e.g.,A.1).}}
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Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999
Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
ML17265A7651999-10-0808 October 1999
Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request
ML17265A7631999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000
ML17265A7641999-10-0505 October 1999
Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel
ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7461999-08-31031 August 1999
Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
ML17265A7401999-08-26026 August 1999
Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A7411999-08-26026 August 1999
Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
ML17250B3021999-08-23023 August 1999
Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
ML17265A7451999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d)
ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
ML17265A7061999-07-22022 July 1999
Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A7191999-07-21021 July 1999
Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
ML17265A7141999-07-21021 July 1999
Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view] |
Text
Fmxaa.X~rV i (ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9409290181 DOC.DATE: 94/09/27 NOTARIZED:
YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Transmits requested changes to 940513 LAR,revising TS Section 6.0,"Administrative Controls"&ack set of revised TS requirements discussed in LAR which will be reviewed by NRC at this time,per 940803 telcon w/NRC.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL L SIZE: TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERN: FILE CENTER 0 ARCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DE/EELB NRR/DRPW NRR/DS SA/SRXB OC/LFDCB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE IVASTE!CONTACT TIIE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT.504-2083)TO ELlih!INATE YOUR NAlIE PRO~I DISTRIBUTION LISTS I'OR DOCI;MENTS YOU DON"I'EED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 12 AND ROCHESTER GAS AND ELECI1C CORPORAT1ON
~89 EASTAVENUE, ROCHESTER, N.Y 1d6d9-OOOI ROBERT C MECREOY Vice President September 27, 1994 Cinna Nudear Production AREA CODE716 5'.27OO U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555
Subject:
Application for Amendment to Facility Operating License Upgrade of Administrative Controls Section 6.0 Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
References:
a.Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License, Upgrade of Administrative Controls Section 6.0, dated Hay 13, 1994.b.Letter from R.C.Hecredy, RG&E, to A.R.Johnson, NRC,
Subject:
Conversion to Improved Technical Specifications, dated February 28, 1994.
Dear Hr.Johnson,
Rochester Gas and Electric (RG&E)previously submitted a License Amendment Request (LAR)which proposed to revise the Ginna Station Technical Specifications (TS)Section 6, Administrative Controls (Ref.a).On August 3, 1994, a conference call was conducted between the NRC and RG&E at which time several changes to the LAR were requested by the NRC.This document transmits the requested changes and acknowledges the set of revised TS requirements discussed in the LAR which will be reviewed by the NRC at this time.The remaining TS changes will be deferred until the conversion of the entire Ginna Station TS during the Technical Specification Improvement Program (Ref.b).The following changes as discussed in Attachment A to Reference a are being requested at this time: t a.Section C.1, change iv (except for the proposed deletion of Ginna TS 6.8.1.f).tt b.Section C.2, changes i, ii (except for the proposed deletion of TS 6.2.2.b and 6.2.2.c), iii, iv, v, vii (revise the submittal of Radiological Effluent Release Report from semiannual to annual only), ix, and x.c.Section C.3, changes iv, vi, and vii.i>pit p P'Q's1409290181
'st40927 PDR ADOCK 05000244 p f I Pp%~\~-W I d.Section C.4, change v.e.Section C.7, changes iii and v.These changes are reflected in the enclosed Attachment 8 and C to this letter.Similar to Reference a, Attachment B provides the marked-up Ginna Station TS which documents the requested changes while Attachment C provides the proposed new TS following the changes.Since the above changes are only a subset of those originally requested in Reference a, several additional changes are now necessary to ensure a complete specification.
These additional changes and their justification are provided in Attachment A.The remaining justification of changes, safety evaluation, and no significant hazards and environmental considerations provided in Attachment A of Reference a remain unchanged.
We request that upon NRC approval, this application should be considered effective immediately and implemented within 60 days, or upon NRC approval and implementation of the gA Program changes, whichever is later.Ver uly yours, Robert C, Mecred Subscribed and sworn to before me on this 27th day of September 1994.N ary ublic MDFX634 Attachments Nsr hRPin es sgs g~~NNROE COUNY@g, xc: Mr.Allen R.Johnson (Mail Stop 14DI)PWR Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector I ll>>II g I'E g E~f..ml4 Nqd aP~
Hr.Gene Eckholt Northern States Power Company Prairie Island Nuclear Generating Plant Route 2 Welch, HN 55089 Hr.Thomas Halanowski Wisconsin Electric Power 231 West Michigan Milwaukee, WI 53201 Hs.Sherry Bernhoft Wisconsin Public Service P.O.Box 19002 700 North Adams Green Bay, WI 54307-9002 Mr.Jack Stringfellow Southern Nuclear Operating Company P.O.Box 1295 40 Inverness Center Parkway Birmingham, AL 35201 Hr.Lee Bush Commonwealth Edison Company Zion Nuclear Station 101 Shiloh Boulevard Zion, IL 60099 C~I!5"l Ir ATTACHMENT A Justification of Changes The justification for all changes to the current Ginna Station TS are provided in Attachment A, Section C to the letter from R.C.Mecredy, RGKE, to A.R.Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License,.Upgrade of Administrative Controls Section 6.0, dated May 13, 1994.The justification for additional changes not discussed in the May 13, 1994 letter are provided below: Revised the Table of Contents to support the requested changes.I 2.3.The following specifications have been revised to provide a footnote which allows for an alternate title to be designated for the specified position: a.TS 6.2.l.b, 6.7.b and 6.7.d-Senior Vice President, Production and Engineering.
b.TS 6.4.1-Division Training Manager c.TS 6.13.1-Health Physicist Specifying management positions by title within the technical specifications creates a licensee and NRC burden when titles are changed or responsibilities are shifted.The current Ginna Station TS 6.2.l.a requires that"lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all Plant management positions." The footnote requires that the alternate titles be specified in the Updated Final Safety Analysis Report (UFSAR)and that all the technical specification requirements apply to the alternate title.The title of the Senior Vice President, Production and Engineering has also been revised to Senior Vice President, Customer Operations.
This is an individual's title change only.This Senior Vice President continues to have corporate responsibility for overall Plant nuclear safety and is chairman of the offsite review function (i.e., Nuclear Safety Audit and Review Board).The footnote for the Senior Vice President, Customer Operations further specifies that the use of an alternate title for this position must be performed in accordance with 10 CFR'0.54(a)(3).
The responsibilities of key organization positions, including the Senior Vice President, Production and Engineering are specified in the Ginna Station gA Program.Since changes to the gA Program are controlled by 10 CFR 50.54(a)(3), equivalent control is provided.TS 6.2.2.a and 6.2,2,d and Table,6.2-1 were removed from the technical specifications since they duplicate current regulations as specified in 10 CFR 50.54(k), (1), and (m).However, the following shift crew requirements as specified in TS Table 6.2-1 are not contained within the current regulations and must be added to TS 6.2.2: a.An auxiliary operator with fuel in the reactor, b.A second auxiliary operator above Cold Shutdown, and.9409290181 I (ii, 4, 5.c.A Shift Technical Advisor (STA)above Cold Shutdown.In addition, the exception provided in TS Table, 6.2-1 with respect to unexpected absences of on-duty shift crew members was also added to TS 6.2.2.Also, TS 6.2.2.b and 6.2.2.c are revised consistent with NUREG-1431 (ITS 5.2.2.b).TS 6.13.1 was revised to replace"health physicist" with"radiation protection" in those places where health physicist was a generic reference since this department is currently identified as radiation protection.
Specific functions performed by a health physicist were not revised.This is not a technical change.A submittal date of Hay 1 of each year was selected for the Radioactive Effluent Release Report since 10 CFR 50.36a only requires an annual submittal but does not identify a specific submittal date.The last RGEE submittal.
of this report was on August 30, 1994.Therefore, the next report on May 1, 1995 is less than the required annual submittal frequency and is consistent with the submittal date of the Annual Radiological Environmental Operation Report (TS 6.9.1.3).A cross reference to the justification of each proposed change is provided in the left margin of each Ginna Station TS that has been changed by use of a circle containing section numbers from either Attachment A, Section C of the Hay 13, 1994 letter (e.g., C.l.iv)or the above justifications (e.g., A.1).
