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| {{#Wiki_filter:CATEGORYj.REGULAT.INFORMATION DISTRIBUTION YSTEM(RIDS)ACCESSION | | {{#Wiki_filter:CATEGORY j.REGULAT.INFORMATION DISTRIBUTION YSTEM (RIDS)ACCESSION)%BR:9605310028 DOC.DATE:'96/05/29 NOTARIZED: |
| )%BR:9605310028 DOC.DATE:'96/05/29 NOTARIZED: | | YES FACIL:56-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NM4E.AUTHOR AFFILIATION MECREDY,R.C. |
| YESFACIL:56-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GAUTH.NM4E
| | Rochester Gas 6 Electric Corp.RECXP.NAME RECIPXENT AFFILIATION UISSXNGPG.S. |
| .AUTHORAFFILIATION MECREDY,R.C. | |
| Rochester Gas6ElectricCorp.RECXP.NAME RECIPXENT AFFILIATION UISSXNGPG.S. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardspagesof960508LARthathavebeenchangedasresultof960528&29telcons.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLSIZE:TITLE:ORSubmittal:
| | Forwards pages of 960508 LAR that have been changed as result of 960528&29 telcons.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
| | General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| DOCKET05000244T05000244RECIPIENT IDCODE/NAME PDl-1LAVISSINGIG.INTERN:LECENTERCNRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | DOCKET 05000244 T 05000244 RECIPIENT ID CODE/NAME PDl-1 LA VISSING I G.INTERN: LE CENTER C NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES.LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDQCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS: |
| NOACCOPIES.LTTRENCL11111111111011RECIPIENT IDCODE/NAME PD1-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDQCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111DNOTETOALL"RIDS"RECIPIENTS:
| | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES'EQUIRED:. |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
| | LTTR 12 ENCL'l AND t ROCHESTER'R GAS AND EIECTRIC CORPORATION |
| 415-2083) | | ~89 EASTAVENIJE, ROCHESTER N.Y Irt649-0001 AREA CODE716%f6-2700 ROBERT C.MECREDY Vice President Nudear Operations May 29, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIES'EQUIRED:.
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| LTTR12ENCL'l ANDtROCHESTER'R GASANDEIECTRICCORPORATION
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| ~89EASTAVENIJE, ROCHESTER N.YIrt649-0001 AREACODE716%f6-2700ROBERTC.MECREDYVicePresident NudearOperations May29,1996U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| Application forAmendment toFacilityOperating LicenseUpdatetoCorrection ofTypographical ErrorsRequestRochester Gas&ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | Application for Amendment to Facility Operating License Update to Correction of Typographical Errors Request Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==References:== | | ==References:== |
| | | (a)Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC, |
| (a)LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC, | |
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| ==Subject:== | | ==Subject:== |
| Application forAnrendment toFacilityOperating License,Correction ofTypographical Jrrrors,datedMay8,1996.(b)LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC, | | Application for Anrendment to Facility Operating License, Correction of Typographical Jr rrors, dated May 8, 1996.(b)Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC, |
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| ==Subject:== | | ==Subject:== |
| Application forAmendinent torr'acility Operating License,Correction ofTypographical Errors,ReqrtestforExigentConsideration, datedMay10,1996. | | Application for Amendinent to rr'acility Operating License, Correction of Typographical Errors, Reqrtest for Exigent Consideration, dated May 10, 1996. |
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| ==DearMr.Vissing,== | | ==Dear Mr.Vissing,== |
| ByReference (a),RG&Esubmitted alicenseamendment request(LAR)tocorrectseveraltypographical errorswithintheGinnaStationImprovedTechnical Specifications (ITS).Subsequently, RG&Erequested thatthisLARbeconsidered onanexigentbasisduetothepotential todelayaplannedstartup(Reference (b)).OnMay28thand29th,conference callswereheldbetweenRG&EandNRCStaffconcerning thisLAR.Asaresultofthesecalls,severalminorchangeswererequested bytheNRCandagreeduponbyRG&E.Thesechangeswerenottechnical andwereonlyrequested toprovideadditional clarityandconsistency withinthetechnical specifications.
| | By Reference (a), RG&E submitted a license amendment request (LAR)to correct several typographical errors within the Ginna Station Improved Technical Specifications (ITS).Subsequently, RG&E requested that this LAR be considered on an exigent basis due to the potential to delay a planned startup (Reference (b)).On May 28th and 29th, conference calls were held between RG&E and NRC Staff concerning this LAR.As a result of these calls, several minor changes were requested by the NRC and agreed upon by RG&E.These changes were not technical and were only requested to provide additional clarity and consistency within the technical specifications. |
| Inaddition, itwasnotedthatRG&EnowexpectsthatMODE2willbeenteredlateonJune3rdinsteadofJune2ndaswasoriginally documented inReference 2.'tt605310028 960529PDRADOCK05000244.,
| | In addition, it was noted that RG&E now expects that MODE 2 will be entered late on June 3rd instead of June 2nd as was originally documented in Reference 2.'tt605310028 960529 PDR ADOCK 05000244., P P DR~I I Therefore, the purpose of this letter is provide those pages of the LAR submitted by Reference (a)that have been changed as a result of the conference call.All other pages of Reference (a), including the no significant hazards consideration, are unaffected by this submittal. |
| PPDR~I I Therefore, thepurposeofthisletterisprovidethosepagesoftheLARsubmitted byReference (a)thathavebeenchangedasaresultoftheconference call.AllotherpagesofReference (a),including thenosignificant hazardsconsideration, areunaffected bythissubmittal.
| | Very truly yours, Robert C.Mecred Subscribed and sworn to before me on this 29th day of May 1996.a, ti~T1~ftNObWXiR@k8<ER Notary Public rn the State of New Yorft MONROE COUNTY Conunission Expires Dec.12.1924 MDF7856 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Guy Vissing (Mail Stop 14C7)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.F.William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253 0 l I f I Attachment A Instructions: |
| Verytrulyyours,RobertC.MecredSubscribed andsworntobeforemeonthis29thdayofMay1996.a,ti~T1~ftNObWXiR@k8<ER NotaryPublicrntheStateofNewYorftMONROECOUNTYConunission ExpiresDec.12.1924MDF7856Attachments xc:U.S.NuclearRegulatory Commission Mr.GuyVissing(MailStop14C7)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector Mr.F.WilliamValentine, President NewYorkStateEnergy,Research, andDevelopment Authority 2Rockefeller PlazaAlbany,NY12223-1253 0lIfI Attachment AInstructions:
| | Remove pages 2 and 3 and replace with attached pages 2 and 3 3.LCO 3.3.1'I The Note for Required Action R.1 was revised to provide consistency with NUREG-1431 (see LCO 3.3.1, Required Action Q.1)and the current bases.Several errors in the f(d)input into the Overtemperature zT and Overpower zT equations for Table 3.3.1-1 were corrected. |
| Removepages2and3andreplacewithattachedpages2and3 3.LCO3.3.1'ITheNoteforRequiredActionR.1wasrevisedtoprovideconsistency withNUREG-1431 (seeLCO3.3.1,RequiredActionQ.1)andthecurrentbases.Severalerrorsinthef(d)inputintotheOvertemperature zTandOverpower zTequations forTable3.3.1-1werecorrected.
| | These include: a.The"Q>" in the f(d)discussion for Overtemperature aT was changed to"q>" based on the equations presented below this text.The description of when to set f(~1)=0 was changed to"when q,-q>is<+13%RTP" versus when">+13%RTP." The error with respect to the.~sign is readily apparent since the same"when q,-qis>+13%RTP" text is used in the next line for when f(zI)must be shifted.The correction of this error is based on the"old" TS, page 2.3-2.c.The values for certain constants were revised to provide necessary units to ensure that the equation is mathematically correct and consistent with all defined values.4..LCO 3.3.2 The Note prior to the Surveillance Requirements in LCO 3.3.2 was revised to remove the plural application of"note" and to delete the"1" preceding the note consistent with the NUREG-1431 format for single notes.This change also affects the bases.5.LCO 3.3.3 The titles of all steam generator (SG)related instrumentation listed in Table 3.3.3-1 were changed since the current wording implies that these are instrumentation |
| Theseinclude:a.The"Q>"inthef(d)discussion forOvertemperature aTwaschangedto"q>"basedontheequations presented belowthistext.Thedescription ofwhentosetf(~1)=0waschangedto"whenq,-q>is<+13%RTP"versuswhen">+13%RTP."Theerrorwithrespecttothe.~signisreadilyapparentsincethesame"whenq,-qis>+13%RTP"textisusedinthenextlineforwhenf(zI)mustbeshifted.Thecorrection ofthiserrorisbasedonthe"old"TS,page2.3-2.c.Thevaluesforcertainconstants wererevisedtoprovidenecessary unitstoensurethattheequationismathematically correctandconsistent withalldefinedvalues.4..LCO3.3.2TheNotepriortotheSurveillance Requirements inLCO3.3.2wasrevisedtoremovethepluralapplication of"note"andtodeletethe"1"preceding thenoteconsistent withtheNUREG-1431 formatforsinglenotes.Thischangealsoaffectsthebases.5.LCO3.3.3Thetitlesofallsteamgenerator (SG)relatedinstrumentation listedinTable3.3.3-1werechangedsincethecurrentwordingimpliesthattheseareinstrumentation
| | >a given SG.As such, the text was revised to reflect that the instrumentation is frrm a given SG.6.LCO 3.3.5 The title for Table 3.3.5-1 Function 4 was changed to"Containment Spray-Manual Initiation" versus"Manual Isolation" per Table 3.3.2-1, Function 2.a and the bases for LCO 3.3.5. |
| >agivenSG.Assuch,thetextwasrevisedtoreflectthattheinstrumentation isfrrmagivenSG.6.LCO3.3.5ThetitleforTable3.3.5-1Function4waschangedto"Containment Spray-ManualInitiation" versus"ManualIsolation" perTable3.3.2-1,Function2.aandthebasesforLCO3.3.5. | | I 0 B.BACKGROUND On February 24, 1996, RG8cE implemented the Improved Technical Specifications at Ginna Station per Amendment No.61.Since that time, upon use of the new TS, several typographical errors have been discovered. |
| I 0B.BACKGROUND OnFebruary24,1996,RG8cEimplemented theImprovedTechnical Specifications atGinnaStationperAmendment No.61.Sincethattime,uponuseofthenewTS,severaltypographical errorshavebeendiscovered. | | The majority of these errors are readily evident upon discovery and do not impact any operational activities. |
| Themajorityoftheseerrorsarereadilyevidentupondiscovery anddonotimpactanyoperational activities.
| | However, the errors described above with respect to LCO 3.3.1 could provide confusion and potential incorrect application of the necessary requirement. |
| However,theerrorsdescribed abovewithrespecttoLCO3.3.1couldprovideconfusion andpotential incorrect application ofthenecessary requirement. | | Therefore, this LAR proposes to correct these errors.Since Ginna Station is currently in a defueled condition in support of the steam generator replacement project, the errors are not currently a problem.However, RG&E expects that Ginna Station will enter MODE 2 conditions late on June 3rd at which time, the Overtemperature aT and Overpower zT reactor trip functions must be OPERABLE.Therefore, the corrections to the f(d)descriptions for these functions must be corrected prior to entering MODE 2.The remaining error within LCO 3.3.1 only applies to specific surveillances of reactor trip functions at power which will not become limiting until several weeks later.C.JUSTIFICATION OP CHANGES This section provides the justification for all changes described in Section A above and shown in Attachment II.The justifications are organized based on whether the change is: more restrictive (M), less restrictive (L), administrative (A), or the requirement is relocated C.l~A A.1 The proposed changes described in Section A above do not involve any technical issues.Instead, the changes relate to minor errors (e.g., page numbering and titles), providing consistency within the TS (e.g., note formats), correction of equations that were incorrectly translated from the"old" TS, and providing consistency with NUREG-1431 as was originally intended by Amendment No.61.The changes to the Overpower and Overtemperature |
| Therefore, thisLARproposestocorrecttheseerrors.SinceGinnaStationiscurrently inadefueledcondition insupportofthesteamgenerator replacement project,theerrorsarenotcurrently aproblem.However,RG&EexpectsthatGinnaStationwillenterMODE2conditions lateonJune3rdatwhichtime,theOvertemperature aTandOverpower zTreactortripfunctions mustbeOPERABLE. | | ~T equations are strictly editorial and are required to ensure that the penalty for f(d)is correctly applied and that the equations have the correct units.The proposed change results in an, equation which is mathematically identical to the"old" TS and was confirmed by Westinghouse as being appropriate and acceptable. |
| Therefore, thecorrections tothef(d)descriptions forthesefunctions mustbecorrected priortoenteringMODE2.Theremaining errorwithinLCO3.3.1onlyappliestospecificsurveillances ofreactortripfunctions atpowerwhichwillnotbecomelimitinguntilseveralweekslater.C.JUSTIFICATION OPCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated C.l~AA.1Theproposedchangesdescribed inSectionAabovedonotinvolveanytechnical issues.Instead,thechangesrelatetominorerrors(e.g.,pagenumbering andtitles),providing consistency withintheTS(e.g.,noteformats), | | The remaining errors were introduced during last minute changes to the TS prior to NRC issuance of Amendment No.61.This is further confirmed in that only one bases page is affected by these changes.Therefore, the correction of these errors is administrative only.There are not any more restrictive (M), less restrictive (L), or relocated (R)changes associated with this LAR. |
| correction ofequations thatwereincorrectly translated fromthe"old"TS,andproviding consistency withNUREG-1431 aswasoriginally intendedbyAmendment No.61.ThechangestotheOverpower andOvertemperature | | 0~I'l W,}} |
| ~Tequations arestrictlyeditorial andarerequiredtoensurethatthepenaltyforf(d)iscorrectly appliedandthattheequations havethecorrectunits.Theproposedchangeresultsinan,equationwhichismathematically identical tothe"old"TSandwasconfirmed byWestinghouse asbeingappropriate andacceptable. | |
| Theremaining errorswereintroduced duringlastminutechangestotheTSpriortoNRCissuanceofAmendment No.61.Thisisfurtherconfirmed inthatonlyonebasespageisaffectedbythesechanges.Therefore, thecorrection oftheseerrorsisadministrative only.Therearenotanymorerestrictive (M),lessrestrictive (L),orrelocated (R)changesassociated withthisLAR.
| |
| 0~I'lW,}} | |
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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
CATEGORY j.REGULAT.INFORMATION DISTRIBUTION YSTEM (RIDS)ACCESSION)%BR:9605310028 DOC.DATE:'96/05/29 NOTARIZED:
YES FACIL:56-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NM4E.AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.RECXP.NAME RECIPXENT AFFILIATION UISSXNGPG.S.
SUBJECT:
Forwards pages of 960508 LAR that have been changed as result of 960528&29 telcons.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL SIZE: TITLE: OR Submittal:
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET 05000244 T 05000244 RECIPIENT ID CODE/NAME PDl-1 LA VISSING I G.INTERN: LE CENTER C NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES.LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDQCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES'EQUIRED:.
LTTR 12 ENCL'l AND t ROCHESTER'R GAS AND EIECTRIC CORPORATION
~89 EASTAVENIJE, ROCHESTER N.Y Irt649-0001 AREA CODE716%f6-2700 ROBERT C.MECREDY Vice President Nudear Operations May 29, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
Subject:
Application for Amendment to Facility Operating License Update to Correction of Typographical Errors Request Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244
References:
(a)Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC,
Subject:
Application for Anrendment to Facility Operating License, Correction of Typographical Jr rrors, dated May 8, 1996.(b)Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC,
Subject:
Application for Amendinent to rr'acility Operating License, Correction of Typographical Errors, Reqrtest for Exigent Consideration, dated May 10, 1996.
Dear Mr.Vissing,
By Reference (a), RG&E submitted a license amendment request (LAR)to correct several typographical errors within the Ginna Station Improved Technical Specifications (ITS).Subsequently, RG&E requested that this LAR be considered on an exigent basis due to the potential to delay a planned startup (Reference (b)).On May 28th and 29th, conference calls were held between RG&E and NRC Staff concerning this LAR.As a result of these calls, several minor changes were requested by the NRC and agreed upon by RG&E.These changes were not technical and were only requested to provide additional clarity and consistency within the technical specifications.
In addition, it was noted that RG&E now expects that MODE 2 will be entered late on June 3rd instead of June 2nd as was originally documented in Reference 2.'tt605310028 960529 PDR ADOCK 05000244., P P DR~I I Therefore, the purpose of this letter is provide those pages of the LAR submitted by Reference (a)that have been changed as a result of the conference call.All other pages of Reference (a), including the no significant hazards consideration, are unaffected by this submittal.
Very truly yours, Robert C.Mecred Subscribed and sworn to before me on this 29th day of May 1996.a, ti~T1~ftNObWXiR@k8<ER Notary Public rn the State of New Yorft MONROE COUNTY Conunission Expires Dec.12.1924 MDF7856 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Guy Vissing (Mail Stop 14C7)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.F.William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253 0 l I f I Attachment A Instructions:
Remove pages 2 and 3 and replace with attached pages 2 and 3 3.LCO 3.3.1'I The Note for Required Action R.1 was revised to provide consistency with NUREG-1431 (see LCO 3.3.1, Required Action Q.1)and the current bases.Several errors in the f(d)input into the Overtemperature zT and Overpower zT equations for Table 3.3.1-1 were corrected.
These include: a.The"Q>" in the f(d)discussion for Overtemperature aT was changed to"q>" based on the equations presented below this text.The description of when to set f(~1)=0 was changed to"when q,-q>is<+13%RTP" versus when">+13%RTP." The error with respect to the.~sign is readily apparent since the same"when q,-qis>+13%RTP" text is used in the next line for when f(zI)must be shifted.The correction of this error is based on the"old" TS, page 2.3-2.c.The values for certain constants were revised to provide necessary units to ensure that the equation is mathematically correct and consistent with all defined values.4..LCO 3.3.2 The Note prior to the Surveillance Requirements in LCO 3.3.2 was revised to remove the plural application of"note" and to delete the"1" preceding the note consistent with the NUREG-1431 format for single notes.This change also affects the bases.5.LCO 3.3.3 The titles of all steam generator (SG)related instrumentation listed in Table 3.3.3-1 were changed since the current wording implies that these are instrumentation
>a given SG.As such, the text was revised to reflect that the instrumentation is frrm a given SG.6.LCO 3.3.5 The title for Table 3.3.5-1 Function 4 was changed to"Containment Spray-Manual Initiation" versus"Manual Isolation" per Table 3.3.2-1, Function 2.a and the bases for LCO 3.3.5.
I 0 B.BACKGROUND On February 24, 1996, RG8cE implemented the Improved Technical Specifications at Ginna Station per Amendment No.61.Since that time, upon use of the new TS, several typographical errors have been discovered.
The majority of these errors are readily evident upon discovery and do not impact any operational activities.
However, the errors described above with respect to LCO 3.3.1 could provide confusion and potential incorrect application of the necessary requirement.
Therefore, this LAR proposes to correct these errors.Since Ginna Station is currently in a defueled condition in support of the steam generator replacement project, the errors are not currently a problem.However, RG&E expects that Ginna Station will enter MODE 2 conditions late on June 3rd at which time, the Overtemperature aT and Overpower zT reactor trip functions must be OPERABLE.Therefore, the corrections to the f(d)descriptions for these functions must be corrected prior to entering MODE 2.The remaining error within LCO 3.3.1 only applies to specific surveillances of reactor trip functions at power which will not become limiting until several weeks later.C.JUSTIFICATION OP CHANGES This section provides the justification for all changes described in Section A above and shown in Attachment II.The justifications are organized based on whether the change is: more restrictive (M), less restrictive (L), administrative (A), or the requirement is relocated C.l~A A.1 The proposed changes described in Section A above do not involve any technical issues.Instead, the changes relate to minor errors (e.g., page numbering and titles), providing consistency within the TS (e.g., note formats), correction of equations that were incorrectly translated from the"old" TS, and providing consistency with NUREG-1431 as was originally intended by Amendment No.61.The changes to the Overpower and Overtemperature
~T equations are strictly editorial and are required to ensure that the penalty for f(d)is correctly applied and that the equations have the correct units.The proposed change results in an, equation which is mathematically identical to the"old" TS and was confirmed by Westinghouse as being appropriate and acceptable.
The remaining errors were introduced during last minute changes to the TS prior to NRC issuance of Amendment No.61.This is further confirmed in that only one bases page is affected by these changes.Therefore, the correction of these errors is administrative only.There are not any more restrictive (M), less restrictive (L), or relocated (R)changes associated with this LAR.
0~I'l W,
