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| | issue date = 12/21/1995 | | | issue date = 12/21/1995 |
| | title = Forwards Rev 22 to QA Program for Station Operation, Incorporating Organization Related Changes Associated W/ Restructuring of Corporation | | | title = Forwards Rev 22 to QA Program for Station Operation, Incorporating Organization Related Changes Associated W/ Restructuring of Corporation |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = JOHNSON A R | | | addressee name = Johnson A |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY1REGUDRTOO~INFORMATION'DISTRIBUTION | | {{#Wiki_filter:CATEGORY 1 REGUDRTOO~INFORMATION'DISTRIBUTION %STEM (RIDE) |
| %STEM(RIDE)ACCESSION NBR:9601020057 DOC.DATE: | | ACCESSION NBR:9601020057 DOC.DATE: 95/12/21 NOTARIZED: NO 'OCKET I FACIL:50-244 Robert "Emmet,Ginna kQclear. Plant', Unit j., Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas '& Electric Corp. |
| 95/12/21NOTARIZED: | | RECIP.NAME RECIPIENT=AFFILIATION |
| NO'OCKETIFACIL:50-244 Robert"Emmet,Ginna kQclear.Plant',Unitj.,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION MECREDY,R.C. | | .JOHNSON,A.R. |
| Rochester Gas'&ElectricCorp.RECIP.NAME RECIPIENT=AFFILIATION | |
| .JOHNSON,A.R. | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsRev22to"QAProgram'forStationOperation,"
| | Forwards Rev 22 to "QA Program 'for Station Operation," |
| incorporating organization relatedchangesassociated w/C>>'restructuring ofcorporation.' | | incorporating organization related changes associated w/ C |
| DISTRIBUTION CODE:Q004DCOPIESRECEIVED:LTR ENCLUSIZE:TITLE:QATopicalReport,Change,Amendment, orCorrespondence (ocketUtiliNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | >>'restructuring of corporation.' |
| 05000244EEXTRNANRRDRCH/HQMB OC/LFDCBDMB/OSSNRCPDRRECIPIENT IDCODE/NAME JOHNSON,A INTERNAL:
| | DISTRIBUTION CODE: Q004D TITLE: |
| DRS/RGNl3ILECECOPIES.LTTRENCL1"1111122111111'1RECIPIENT IDCODE/NAME DRS/RGN2DRS/RGN4NRR/DISP/IMS NUDOCS-ABSTRACT RGN1FILEIHSCOPIESLTTRENCL11111111111.1D0CUENOTETOALL"RZDS"RECZPZENTS: | | COPIES RECEIVED:LTR Topical Report, Change, ENCL U Amendment, or Correspondence SIZE: |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
| | ocket Utili QA ( |
| 415-2083) | | NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES. RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JOHNSON,A 1 "1 INTERNAL: DRS/RGNl 1 1 DRS/RGN2 1 1 3 1 1 DRS/RGN4 1 1 ILE CE 2 2 NRR/DISP/IMS 1 1 NRR DRCH/HQMB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 1 RGN1 FILE 1 1 EXT RNA DMB/OSS 1 1 ' |
| TOELZMZNATE YOURNAMEFROMDZSTRZBUTZON LZSTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | IHS 1 .1 NRC PDR 1 D |
| LTTR,'.15ENCL."15I liA!;0>1Cf4~~l~"p' 4NDIROCHESTER GASANDEIECIIIIC CORPORATION | | 0 C |
| ~89EASTAY&IUf, ROCHESlER, N.YIrIiQ9-0001 AREACODE716546-27MROBERTC.MECREDYVicePresident NuclearOperations December21,1995U.S.NuclearRegulatory Commission DocumentControlDeskAttn:'llenR.JohnsonProjectDirectorate I-1Washington, D.C.20555 | | U E |
| | NOTE TO ALL "RZDS" RECZPZENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR, '. |
| | 15 ENCL. "15 I |
| | |
| | li A |
| | ;0 |
| | >1 C |
| | f 4 |
| | ~ ~l~"p' |
| | |
| | 4ND I |
| | ROCHESTER GAS AND EIECIIIICCORPORATION ~ 89 EASTAY&IUf,ROCHESlER, N. Y IrIiQ9-0001 AREA CODE716 546-27M ROBERT C. MECREDY Vice President Nuclear Operations December 21, 1995 U.S. Nuclear Regulatory Commission Document Attn: 'llen Control Project Desk R. Johnson Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| RevisedSubmittal ofQualityAssurance ProgramforStationOperation Rochester Gas6ElectricCorporation R.E.GinnaNuclearPowerPlantDocketNo.50-244
| | Revised Submittal of Quality Assurance Program for Station Operation Rochester Gas 6 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
| | |
| | ==Dear Mr. Johnson,== |
| | |
| | In accordance with 10CFR50.54(a)(3), enclosed is revision 22 to the Quality Assurance Program for Station Operation (QAPSO). Revision 22 incorporates organization related changes associated with the restructuring of the corporation. Our effectiveness review concluded that these changes do not impact commitments in the quality assurance program description previously approved by the Nuclear Regulatory Commission (NRC) and therefore do not require prior NRC approval. |
| | The changes are described in the attached Synopsis of Changes (Attachment 1) and in the enclosed program revision. Attachment 1 also provides the basis for concluding that the revised program continues to satisfy the 10CFR50, Appendix B criteria and does not reduce the scope of the quality assurance program. Changes made to revision 21 of the Quality Assurance Program for Station Operation are denoted by a single revision bar in the left margin. |
| | Attachment 2 is a copy of the QAPSO with changes denoted by highlighting or strike-out. |
| | These QA Program changes are considered effective immediately. |
| | Ver truly yours, Robert C. ecr dy GAH'It413 Attachments 1 and 2 Enclosure 1: QA Program for Station Operation Revision 22 |
| | 'st601020057 951221 PDR ADOCK 05000244 P PDR OO( |
| | 02003I |
| | |
| | xc: Mr. Allen R. Johnson (Mail Stop 14B2) |
| | 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 |
| | |
| | ATTACHMENT 1 S no sis of Chan es Or anization and Position Title Chan es The following organization titles and position titles have been changed: |
| | "Senior Vice President, Customer Operations" to "Senior Vice President, Energy Operations" "Vice President, Nuclear Operations" to "Vice President, Nuclear Operations Group" "Division Manager, Support Services" to "Group Manager, Support Services" "Division Manager,'nergy Delivery" to "Group Manager, Energy Delivery" "Division Manager, Information Services" to "Group Manager, Information Services" "Nuclear Division Training" to "Nuclear Training" These changes are reflected throughout the revised document and are not identified at each occurrence in the following summary. |
| | 17.1 MANAGEMENT 17.1.1 Methodolo Paragraph 3 Last sentence was revised to be consistent with the phrase used on the "RGRE Corporate Statement of QA Policy" Table 17.1.1-1. |
| | Paragraph 4 Reference to ANSI N18.2-1973 is removed as been superseded by ANSI/ANS 51.1-1983. |
| | it has Paragraph 5 - This paragraph has been rewritten to clarify |
| | ,RGEE's method of applying a graded QA Program to items which are not classified as "Safety Related". |
| | |
| | ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.) |
| | 17.1.2 Or anization The following organization changes were made and are reflected throughout the text of the document and on the Figure 17.1.2-1 Organization Chart: |
| | The Senior Vice President, Energy Operations reports directly to the Chairman of the Board, President, and Chief Executive Officer. The Executive Vice President position no longer exists. |
| | ~ Information Services now reports to the Energy Services vice Energy Operations. However, their functions in supporting the QA Program have remained the same. |
| | A new position, the Director, Operating Experience, has been assigned the responsibility of supporting root cause investigations and corrective action for significant conditions adverse to quality, and for evaluating and disseminating industry experience information. These responsibilities were previously assigned to the Manager, Nuclear Assurance. |
| | Plant Manager, "Procurement" was added to list of Ginna Station responsibilities for clarification. |
| | Department Manager, "Technical Support" for Ginna Operations Nuclear Engineering was revised for clarification. |
| | Services Manager, Revised to eliminate redundancy in text. |
| | Quality Assurance Manager, Revised to remove responsibilities now Nuclear Assurance assigned to the Director, Operating Experience and to add responsibility for trending and analysis of corrective action program data. |
| | Group Manager, Revised to clarify responsibility for Support Services calibration of M6TE reference standards. |
| | Group Manager, Revised to clarify responsibility for Information Services calibration of installed electric meters. |
| | Group Manager, Revised to eliminate redundancy in text. |
| | Energy Delivery |
| | |
| | ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT 17.1.2 Or anization Cont. |
| | Review and Audit Organizations |
| | ~ Nuclear Safety Audit and. Review Board Removed reference to the QA/QC Subcommittee of the NSARB. |
| | Plant Operations Review Committee Paragraph 2 Removed last sentence. This sentence does not discuss the primary responsibilities of the PORC and is unnecessary. |
| | 'I Paragraph 7 Removed requirement for PORC to provide written meeting minutes to the Vice President, Nuclear Operations Group and the Chairman, NSARB. These meeting minutes are retained as a record by Records Management. |
| | Dele ation of Work Paragraph was revised to provide clarification of QA Program requirements for external organizations. |
| | 17.1.5 Personnel Trainin and uglification Paragraph was revised to provide clarification of requirements for training of personnel in QA policies and instructions. |
| | 17.1.6 Corrective Action Paragraph was revised to provide clarification of requirements for identifying adverse trends in performance. |
| | |
| | ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.) |
| | Table 17.1.1-2 Su lementar Glossar Commitment Revised to be consistent with definition used in the Nuclear Policy Manual. |
| | Heavy Load Revised to include specific plant information. |
| | Off the Shelf Deleted. Old term is no longer used. |
| | Safety Related Revised for clarification SSCs Safety Significant Revised for clarification SSCs Table 17.1.7-1 Conformance of Ginna Station Pro ram to ualit Assurance Standards Re uirements and Guides Regulatory Guide 1.26 Reference to ANSI N18.2-1973 is removed as superseded by ANSI/ANS 51.1-1983. |
| | it has been ANSI/ANS 3.1-1987, Section 4.7. |
| | Revised to clarify that qualification requirements apply to NSARB members only as addressed by this standard. |
| | 17.2 PERFORMANCE/VERIFICATION 17.2.1 Methodolo Paragraph 1 Revised for clarification and consistency with 10CFR50 Appendix B. |
| | 17.2.2 Desi n Control Paragraph 7 - Revised for clarification. |
| | |
| | ATTACHMENT 1 S no sis of Chan es 17.2 PERFORMANCE/VERIFICATION (Cont.) |
| | 17.2.4 Procurement Control Acceptance of Items and Services Revised for clarification and to allow for the use of methods such as sampling. |
| | 17.2.5 Procurement Verification Paragraph 5 - Revised for clarification and to allow for the use of post installation testing as a means of item acceptance. |
| | 17.2.8 Test Control Paragraph 6 - Revised for clarification. |
| | 17.2.11 S ecial Process Control Paragraph 4 - Revised for clarification of responsibility changed in previous submittal (Rev. 21). |
| | 17.2.14 Document Control Paragraph 1 Revised for clarification. |
| | Paragraph 3 Revised for clarification of method used to approve temporary procedure changes at Ginna Station. Temporary procedure changes receive the same level of review as permanent changes, and in addition receive approval by the Shift Supervisor. |
| | Temporary procedure changes are approved by the Plant Manager or designee prior to implementation. |
| | 17.2.15 Records Paragraph 1 Revised for clarification. |
|
| |
|
| ==DearMr.Johnson,==
| | ATTACHMENT 1 S no sis of Chan es 17.3 ASSESSMENT 17.3.1 Methodolo Paragraph 3 Revised to remove reference to the QA/QC Subcommittee. Provides clarification of "Operational Assessment" as an assessment type and "Operating Experience" as an organization which performs this assessment. |
| Inaccordance with10CFR50.54(a)(3),
| | 17.3.2 Assessment Operational Assessment The responsibility for reviewing NRC Information Notices has been reassigned to Nuclear Safety and Licensing. |
| enclosedisrevision22totheQualityAssurance ProgramforStationOperation (QAPSO).Revision22incorporates organization relatedchangesassociated withtherestructuring ofthecorporation.
| | The revised program, as described above, continues to satisfy the 10CFR50 criteria and does not reduce the scope of the quality assurance program. These changes do not require NRC approval prior to implementation.}} |
| Oureffectiveness reviewconcluded thatthesechangesdonotimpactcommitments inthequalityassurance programdescription previously approvedbytheNuclearRegulatory Commission (NRC)andtherefore donotrequirepriorNRCapproval.
| |
| Thechangesaredescribed intheattachedSynopsisofChanges(Attachment 1)andintheenclosedprogramrevision.
| |
| Attachment 1alsoprovidesthebasisforconcluding thattherevisedprogramcontinues tosatisfythe10CFR50,AppendixBcriteriaanddoesnotreducethescopeofthequalityassurance program.Changesmadetorevision21oftheQualityAssurance ProgramforStationOperation aredenotedbyasinglerevisionbarintheleftmargin.Attachment 2isacopyoftheQAPSOwithchangesdenotedbyhighlighting orstrike-out.
| |
| TheseQAProgramchangesareconsidered effective immediately.
| |
| Vertrulyyours,RobertC.ecrdyGAH'It413 Attachments 1and2Enclosure 1:QAProgramforStationOperation Revision22'st601020057 951221PDRADOCK05000244PPDR02003IOO(
| |
| xc:Mr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector ATTACHMENT 1SnosisofChanesOranization andPositionTitleChanesThefollowing organization titlesandpositiontitleshavebeenchanged:"SeniorVicePresident, CustomerOperations" to"SeniorVicePresident, EnergyOperations" "VicePresident, NuclearOperations" to"VicePresident, NuclearOperations Group""Division Manager,SupportServices" to"GroupManager,SupportServices" "Division Manager,'nergy Delivery" to"GroupManager,EnergyDelivery" "Division Manager,Information Services" to"GroupManager,Information Services" "NuclearDivisionTraining" to"NuclearTraining" Thesechangesarereflected throughout thereviseddocumentandarenotidentified ateachoccurrence inthefollowing summary.17.1MANAGEMENT 17.1.1Methodolo Paragraph 3-Lastsentencewasrevisedtobeconsistent withthephraseusedonthe"RGRECorporate Statement ofQAPolicy"-Table17.1.1-1.
| |
| Paragraph 4-Reference toANSIN18.2-1973 isremovedasithasbeensuperseded byANSI/ANS51.1-1983.
| |
| Paragraph 5-Thisparagraph hasbeenrewritten toclarify,RGEE'smethodofapplyingagradedQAProgramtoitemswhicharenotclassified as"SafetyRelated". | |
| ATTACHMENT 1SnosisofChanes17.1MANAGEMENT (Cont.)17.1.2Oranization Thefollowing organization changesweremadeandarereflected throughout thetextofthedocumentandontheFigure17.1.2-1Organization Chart:TheSeniorVicePresident, EnergyOperations reportsdirectlytotheChairmanoftheBoard,President, andChiefExecutive Officer.TheExecutive VicePresident positionnolongerexists.~Information ServicesnowreportstotheEnergyServicesviceEnergyOperations.
| |
| However,theirfunctions insupporting theQAProgramhaveremainedthesame.Anewposition, theDirector, Operating Experience, hasbeenassignedtheresponsibility ofsupporting rootcauseinvestigations andcorrective actionforsignificant conditions adversetoquality,andforevaluating anddisseminating industryexperience information.
| |
| Theseresponsibilities werepreviously assignedtotheManager,NuclearAssurance.
| |
| PlantManager,GinnaStation"Procurement" wasaddedtolistofresponsibilities forclarification.
| |
| Department Manager,NuclearEngineering Services"Technical Support"forGinnaOperations wasrevisedforclarification.
| |
| Manager,QualityAssurance Revisedtoeliminate redundancy intext.Manager,NuclearAssurance Revisedtoremoveresponsibilities nowassignedtotheDirector, Operating Experience andtoaddresponsibility fortrendingandanalysisofcorrective actionprogramdata.GroupManager,SupportServicesRevisedtoclarifyresponsibility forcalibration ofM6TEreference standards.
| |
| GroupManager,Information ServicesRevisedtoclarifyresponsibility forcalibration ofinstalled electricmeters.GroupManager,EnergyDeliveryRevisedtoeliminate redundancy intext.
| |
| ATTACHMENT 1SnosisofChanes17.1MANAGEMENT 17.1.2Oranization Cont.ReviewandAuditOrganizations
| |
| ~NuclearSafetyAuditand.ReviewBoardRemovedreference totheQA/QCSubcommittee oftheNSARB.PlantOperations ReviewCommittee Paragraph 2Paragraph 7Removedlastsentence.
| |
| Thissentencedoesnotdiscusstheprimaryresponsibilities ofthePORCandisunnecessary.
| |
| 'IRemovedrequirement forPORCtoprovidewrittenmeetingminutestotheVicePresident, NuclearOperations GroupandtheChairman, NSARB.ThesemeetingminutesareretainedasarecordbyRecordsManagement.
| |
| DeleationofWorkParagraph wasrevisedtoprovideclarification ofQAProgramrequirements forexternalorganizations.
| |
| 17.1.5Personnel Traininanduglification Paragraph wasrevisedtoprovideclarification ofrequirements fortrainingofpersonnel inQApoliciesandinstructions.
| |
| 17.1.6Corrective ActionParagraph wasrevisedtoprovideclarification ofrequirements foridentifying adversetrendsinperformance.
| |
| ATTACHMENT 1SnosisofChanes17.1MANAGEMENT (Cont.)Table17.1.1-2SulementarGlossarCommitment HeavyLoadRevisedtobeconsistent withdefinition usedintheNuclearPolicyManual.Revisedtoincludespecificplantinformation.
| |
| OfftheShelfSafetyRelatedSSCsDeleted.Oldtermisnolongerused.Revisedforclarification SafetySignificant SSCsRevisedforclarification Table17.1.7-1Conformance ofGinnaStationProramtoualitAssurance Standards Reuirements andGuidesRegulatory Guide1.26Reference toANSIN18.2-1973 isremovedasithasbeensuperseded byANSI/ANS51.1-1983.
| |
| ANSI/ANS3.1-1987, Section4.7.Revisedtoclarifythatqualification requirements applytoNSARBmembersonlyasaddressed bythisstandard.
| |
| 17.2PERFORMANCE/VERIFICATION 17.2.1Methodolo Paragraph 1-Revisedforclarification andconsistency with10CFR50AppendixB.17.2.2DesinControlParagraph 7-Revisedforclarification.
| |
| ATTACHMENT 1SnosisofChanes17.2PERFORMANCE/VERIFICATION (Cont.)17.2.4Procurement ControlAcceptance ofItemsandServicesRevisedforclarification andtoallowfortheuseofmethodssuchassampling.
| |
| 17.2.5Procurement Verification Paragraph 5-Revisedforclarification andtoallowfortheuseofpostinstallation testingasameansofitemacceptance.
| |
| 17.2.8TestControlParagraph 6-Revisedforclarification.
| |
| 17.2.11SecialProcessControlParagraph 4-Revisedforclarification ofresponsibility changedinprevioussubmittal (Rev.21).17.2.14DocumentControlParagraph 1-Revisedforclarification.
| |
| Paragraph 3Revisedforclarification ofmethodusedtoapprovetemporary procedure changesatGinnaStation.Temporary procedure changesreceivethesamelevelofreviewaspermanent changes,andinadditionreceiveapprovalbytheShiftSupervisor.
| |
| Temporary procedure changesareapprovedbythePlantManagerordesigneepriortoimplementation.
| |
| 17.2.15RecordsParagraph 1-Revisedforclarification.
| |
| ATTACHMENT 1SnosisofChanes17.3ASSESSMENT 17.3.1Methodolo Paragraph 3Revisedtoremovereference totheQA/QCSubcommittee.
| |
| Providesclarification of"Operational Assessment" asanassessment typeand"Operating Experience" asanorganization whichperformsthisassessment.
| |
| 17.3.2Assessment Operational Assessment Theresponsibility forreviewing NRCInformation Noticeshasbeenreassigned toNuclearSafetyandLicensing. | |
| Therevisedprogram,asdescribed above,continues tosatisfythe10CFR50criteriaanddoesnotreducethescopeofthequalityassurance program.ThesechangesdonotrequireNRCapprovalpriortoimplementation.}}
| |
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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
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
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
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
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
CATEGORY 1 REGUDRTOO~INFORMATION'DISTRIBUTION %STEM (RIDE)
ACCESSION NBR:9601020057 DOC.DATE: 95/12/21 NOTARIZED: NO 'OCKET I FACIL:50-244 Robert "Emmet,Ginna kQclear. Plant', Unit j., Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas '& Electric Corp.
RECIP.NAME RECIPIENT=AFFILIATION
.JOHNSON,A.R.
SUBJECT:
Forwards Rev 22 to "QA Program 'for Station Operation,"
incorporating organization related changes associated w/ C
>>'restructuring of corporation.'
DISTRIBUTION CODE: Q004D TITLE:
COPIES RECEIVED:LTR Topical Report, Change, ENCL U Amendment, or Correspondence SIZE:
ocket Utili QA (
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES. RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JOHNSON,A 1 "1 INTERNAL: DRS/RGNl 1 1 DRS/RGN2 1 1 3 1 1 DRS/RGN4 1 1 ILE CE 2 2 NRR/DISP/IMS 1 1 NRR DRCH/HQMB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 1 RGN1 FILE 1 1 EXT RNA DMB/OSS 1 1 '
IHS 1 .1 NRC PDR 1 D
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NOTE TO ALL "RZDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR, '.
15 ENCL. "15 I
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4ND I
ROCHESTER GAS AND EIECIIIICCORPORATION ~ 89 EASTAY&IUf,ROCHESlER, N. Y IrIiQ9-0001 AREA CODE716 546-27M ROBERT C. MECREDY Vice President Nuclear Operations December 21, 1995 U.S. Nuclear Regulatory Commission Document Attn: 'llen Control Project Desk R. Johnson Directorate I-1 Washington, D.C. 20555
Subject:
Revised Submittal of Quality Assurance Program for Station Operation Rochester Gas 6 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
In accordance with 10CFR50.54(a)(3), enclosed is revision 22 to the Quality Assurance Program for Station Operation (QAPSO). Revision 22 incorporates organization related changes associated with the restructuring of the corporation. Our effectiveness review concluded that these changes do not impact commitments in the quality assurance program description previously approved by the Nuclear Regulatory Commission (NRC) and therefore do not require prior NRC approval.
The changes are described in the attached Synopsis of Changes (Attachment 1) and in the enclosed program revision. Attachment 1 also provides the basis for concluding that the revised program continues to satisfy the 10CFR50, Appendix B criteria and does not reduce the scope of the quality assurance program. Changes made to revision 21 of the Quality Assurance Program for Station Operation are denoted by a single revision bar in the left margin.
Attachment 2 is a copy of the QAPSO with changes denoted by highlighting or strike-out.
These QA Program changes are considered effective immediately.
Ver truly yours, Robert C. ecr dy GAH'It413 Attachments 1 and 2 Enclosure 1: QA Program for Station Operation Revision 22
'st601020057 951221 PDR ADOCK 05000244 P PDR OO(
02003I
xc: Mr. Allen R. Johnson (Mail Stop 14B2)
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
ATTACHMENT 1 S no sis of Chan es Or anization and Position Title Chan es The following organization titles and position titles have been changed:
"Senior Vice President, Customer Operations" to "Senior Vice President, Energy Operations" "Vice President, Nuclear Operations" to "Vice President, Nuclear Operations Group" "Division Manager, Support Services" to "Group Manager, Support Services" "Division Manager,'nergy Delivery" to "Group Manager, Energy Delivery" "Division Manager, Information Services" to "Group Manager, Information Services" "Nuclear Division Training" to "Nuclear Training" These changes are reflected throughout the revised document and are not identified at each occurrence in the following summary.
17.1 MANAGEMENT 17.1.1 Methodolo Paragraph 3 Last sentence was revised to be consistent with the phrase used on the "RGRE Corporate Statement of QA Policy" Table 17.1.1-1.
Paragraph 4 Reference to ANSI N18.2-1973 is removed as been superseded by ANSI/ANS 51.1-1983.
it has Paragraph 5 - This paragraph has been rewritten to clarify
,RGEE's method of applying a graded QA Program to items which are not classified as "Safety Related".
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)
17.1.2 Or anization The following organization changes were made and are reflected throughout the text of the document and on the Figure 17.1.2-1 Organization Chart:
The Senior Vice President, Energy Operations reports directly to the Chairman of the Board, President, and Chief Executive Officer. The Executive Vice President position no longer exists.
~ Information Services now reports to the Energy Services vice Energy Operations. However, their functions in supporting the QA Program have remained the same.
A new position, the Director, Operating Experience, has been assigned the responsibility of supporting root cause investigations and corrective action for significant conditions adverse to quality, and for evaluating and disseminating industry experience information. These responsibilities were previously assigned to the Manager, Nuclear Assurance.
Plant Manager, "Procurement" was added to list of Ginna Station responsibilities for clarification.
Department Manager, "Technical Support" for Ginna Operations Nuclear Engineering was revised for clarification.
Services Manager, Revised to eliminate redundancy in text.
Quality Assurance Manager, Revised to remove responsibilities now Nuclear Assurance assigned to the Director, Operating Experience and to add responsibility for trending and analysis of corrective action program data.
Group Manager, Revised to clarify responsibility for Support Services calibration of M6TE reference standards.
Group Manager, Revised to clarify responsibility for Information Services calibration of installed electric meters.
Group Manager, Revised to eliminate redundancy in text.
Energy Delivery
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT 17.1.2 Or anization Cont.
Review and Audit Organizations
~ Nuclear Safety Audit and. Review Board Removed reference to the QA/QC Subcommittee of the NSARB.
Plant Operations Review Committee Paragraph 2 Removed last sentence. This sentence does not discuss the primary responsibilities of the PORC and is unnecessary.
'I Paragraph 7 Removed requirement for PORC to provide written meeting minutes to the Vice President, Nuclear Operations Group and the Chairman, NSARB. These meeting minutes are retained as a record by Records Management.
Dele ation of Work Paragraph was revised to provide clarification of QA Program requirements for external organizations.
17.1.5 Personnel Trainin and uglification Paragraph was revised to provide clarification of requirements for training of personnel in QA policies and instructions.
17.1.6 Corrective Action Paragraph was revised to provide clarification of requirements for identifying adverse trends in performance.
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)
Table 17.1.1-2 Su lementar Glossar Commitment Revised to be consistent with definition used in the Nuclear Policy Manual.
Heavy Load Revised to include specific plant information.
Off the Shelf Deleted. Old term is no longer used.
Safety Related Revised for clarification SSCs Safety Significant Revised for clarification SSCs Table 17.1.7-1 Conformance of Ginna Station Pro ram to ualit Assurance Standards Re uirements and Guides Regulatory Guide 1.26 Reference to ANSI N18.2-1973 is removed as superseded by ANSI/ANS 51.1-1983.
it has been ANSI/ANS 3.1-1987, Section 4.7.
Revised to clarify that qualification requirements apply to NSARB members only as addressed by this standard.
17.2 PERFORMANCE/VERIFICATION 17.2.1 Methodolo Paragraph 1 Revised for clarification and consistency with 10CFR50 Appendix B.
17.2.2 Desi n Control Paragraph 7 - Revised for clarification.
ATTACHMENT 1 S no sis of Chan es 17.2 PERFORMANCE/VERIFICATION (Cont.)
17.2.4 Procurement Control Acceptance of Items and Services Revised for clarification and to allow for the use of methods such as sampling.
17.2.5 Procurement Verification Paragraph 5 - Revised for clarification and to allow for the use of post installation testing as a means of item acceptance.
17.2.8 Test Control Paragraph 6 - Revised for clarification.
17.2.11 S ecial Process Control Paragraph 4 - Revised for clarification of responsibility changed in previous submittal (Rev. 21).
17.2.14 Document Control Paragraph 1 Revised for clarification.
Paragraph 3 Revised for clarification of method used to approve temporary procedure changes at Ginna Station. Temporary procedure changes receive the same level of review as permanent changes, and in addition receive approval by the Shift Supervisor.
Temporary procedure changes are approved by the Plant Manager or designee prior to implementation.
17.2.15 Records Paragraph 1 Revised for clarification.
ATTACHMENT 1 S no sis of Chan es 17.3 ASSESSMENT 17.3.1 Methodolo Paragraph 3 Revised to remove reference to the QA/QC Subcommittee. Provides clarification of "Operational Assessment" as an assessment type and "Operating Experience" as an organization which performs this assessment.
17.3.2 Assessment Operational Assessment The responsibility for reviewing NRC Information Notices has been reassigned to Nuclear Safety and Licensing.
The revised program, as described above, continues to satisfy the 10CFR50 criteria and does not reduce the scope of the quality assurance program. These changes do not require NRC approval prior to implementation.
