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| | number = ML17265A684 | | | number = ML17265A684 |
| | issue date = 06/21/1999 | | | issue date = 06/21/1999 |
| | title = 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 | | | title = 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 |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | 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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| | page count = 6 | | | page count = 6 |
| | project = | | | project = |
| | stage = Other | | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:glACCESSIONNBRFACIL:50-244AUTE.NAMEMECRgDY,R.C.RECIP.NAMEVISSING;G.S.REGULAYINFORMATIONDISTRIBUTIONYSTEM(RIDS)'I:9906290269DOC.DATE:99/06/2X"NOTARIZED:NODOCKET0.RobertEmmetGinnaNuclearPlant,Unit1,RochesterG05000244AUTHORAFFILIATIONRochesterGas8ElectricCorp.RECIPIENTAFFILIATION | | {{#Wiki_filter:gl REGULA Y INFORMATION DISTRIBUTION YSTEM (RIDS) |
| | 'I ACCESSION NBR :9906290269 DOC.DATE: 99/06/2X" NOTARIZED: NO DOCKET 0 FACIL:50-244 .Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTE. NAME AUTHOR AFFILIATION MECRgDY,R.C. Rochester Gas 8 Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION VISSING; G. S. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| InformsutilwishestoamendextentofalternateexamsprovidedforreliefrequestreISIprogramASMESectionXIrecpxireexamsforfirst10-Yrintervalforcontainment.DISTRIBUTIONCODE:A047DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:Inservice/Testing/RelieffromASMECode-GL-09-04NOTES:LicenseExp'dateinaccordancewith10CFR2,2.109(9/19/72).05000244ERECIPIENT,IDCODE/NAMELPD1-1LAVISSING,G.INTERNAL:cRXLECENTER01NUDOCS-ABSTRACTRES/DET/EIBEXTERNAL:LITCOANDERSONNRCPDRCOPIESLTTRENCL11111111111111RECIPIENTIDCODE/NAMELPD1-1PDNRR/DE/EMEBOGC/HDS3RES/DET/EMMEBNOACCOPIESLTTRENCL11111011110RDPEmR~Lt,~<g~'ENOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE."TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11 ANDROCHESTERGASANDELEClÃICCORPORAVON~89EASTAYENUE,ROCHESrERN.YId6r19-0001AREACODE716&f6-2700ROBERTC.MECREDYVicePresidentNuclearOperationsJune21,1999U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:GuyS.VissingProjectDirectorateI-1Washington,D.C.20555
| | Informs util wishes to amend extent of alternate exams provided for relief request re ISI program ASME Section XI recpxire exams for first 10-Yr interval for containment. |
| | DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: |
| | TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-09-04 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 0 LPD1-1 LA 1 1 LPD1-1 PD 1 1 VISSING,G. 1 1 R INTERNAL: cRXLE CENTER 01 1 1 NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D |
| | PEmR~Lt,~<g~ |
| | 'E NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE."TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 |
| | |
| | AND ROCHESTER GASANDELEClÃICCORPORAVON ~ 89EASTAYENUE, ROCHESrER N. Y Id6r19-0001 AREA CODE716 &f6-2700 ROBERT C. MECREDY Vice President Nuclear Operations June 21, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| InserviceInspectionProgramASMESectionXIRequiredExaminationsforFirst10-YearIntervalforContainment(IWEandIWL)RequestforReliefNo.40R.E.GinnaNuclearPowerPlantDocketNo.50/244
| | Inservice Inspection Program ASME Section XI Required Examinations for First 10-Year Interval for Containment (IWE and IWL) |
| | Request for Relief No. 40 R.E. Ginna Nuclear Power Plant Docket No. 50/244 |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | RG&E provided the NRC with the subject relief request on January 11, 1999. As a result of a telecon with NRC staff on June 16, 1999, RG&E wishes to amend the extent of the alternate examinations provided for in that relief request. |
| | In addition to the testing to be conducted in accordance with 10CFR 50 Appendix J, RGB E will perform an IWE detailed visual examination of the repaired or replaced area (VT-1). A replacement page of the attachment to our January 11, 1999 relief request is provided. |
| | Very truly yours, Robert C. Mecredy 9906290269 990b2'i POR ADQCK 0500024%i |
| | |
| | xc: Mr. Guy S. Vissing (Mail Stop 8C2) |
| | Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector |
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| | r T |
| | I h |
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| | Collection systems, as required during the conduct of a system pressure test. In addition, personnel performing VT-2 examinations are required to be qualified in accordance with Subarticle IWA-2300 of ASME Section XI. |
| | For repairs, replacements or modifications that are performed under ASME Section XI Code, applicable Construction Code (or Installation Code) non-destructive examinations (NDE) are performed and must meet the acceptance criteria of the Construction / |
| | Installation Code. In addition to the Construction Code NDE, applicable ASME Section XI NDE pre-service NDE are also performed. These Construction Code and Section XI pre-service NDE requirements provide additional assurances that the repairs, replacements or modifications are sound and leak-tight. |
| | Table IWE-2500-1, Examination Category E-P, identifies the examination method of 10 CFR 50, Appendix J and does not specifically identify a VT-2 visual examination. 10 CFR 50, Appendix J provides requirements for testing as well as acceptable leakage criteria. These tests are performed by Appendix J "Test" personnel and utilize calibrated equipment to determine acceptability. Additionally, 10 CFR 50.55a (b) (2) (x) (E) requires a general visual examination of the containment each period that would identify any structural degradation that may contribute to leakage. A "VT-2"visual examination willnot provide additional assurance of safety beyond that of current Appendix J practices. |
| | Relief is requested in accordance with 10 CFR 50.55a (a) (3) (I). The proposed alternative (pressure testing in accordance with 10 CFR 50, Appendix J) willprovide and acceptable level of quality and safety. |
| | The reference to paragraph IWA-5240 has been removed in the 1997 Addenda of ASME Section XI. This addenda has been approved by the ASME Main Committee and should be published in 1998. |
| | Alternate Examinations: |
| | Testing shall be conducted in accordance with 10 CFR 50, Appendix J, in lieu of Paragraph IWE-5240 of ASME Section XI, as well as performing an IWE detailed visual examination of the repaired or replaced area (VT-l). |
| | Request for Relief No. 40 Attachment Page 2 of 3 |
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| ==DearMr.Vissing:==
| | 4 rr od}} |
| RG&EprovidedtheNRCwiththesubjectreliefrequestonJanuary11,1999.AsaresultofateleconwithNRCstaffonJune16,1999,RG&Ewishestoamendtheextentofthealternateexaminationsprovidedforinthatreliefrequest.Inadditiontothetestingtobeconductedinaccordancewith10CFR50AppendixJ,RGBEwillperformanIWEdetailedvisualexaminationoftherepairedorreplacedarea(VT-1).AreplacementpageoftheattachmenttoourJanuary11,1999reliefrequestisprovided.Verytrulyyours,RobertC.Mecredy9906290269990b2'iPORADQCK0500024%i xc:Mr.GuyS.Vissing(MailStop8C2)ProjectDirectorateI-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555RegionalAdministrator,RegionIU.S.NuclearRegulatoryCommission475AllendaleRoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector rITh Collectionsystems,asrequiredduringtheconductofasystempressuretest.Inaddition,personnelperformingVT-2examinationsarerequiredtobequalifiedinaccordancewithSubarticleIWA-2300ofASMESectionXI.Forrepairs,replacementsormodificationsthatareperformedunderASMESectionXICode,applicableConstructionCode(orInstallationCode)non-destructiveexaminations(NDE)areperformedandmustmeettheacceptancecriteriaoftheConstruction/InstallationCode.InadditiontotheConstructionCodeNDE,applicableASMESectionXINDEpre-serviceNDEarealsoperformed.TheseConstructionCodeandSectionXIpre-serviceNDErequirementsprovideadditionalassurancesthattherepairs,replacementsormodificationsaresoundandleak-tight.TableIWE-2500-1,ExaminationCategoryE-P,identifiestheexaminationmethodof10CFR50,AppendixJanddoesnotspecificallyidentifyaVT-2visualexamination.10CFR50,AppendixJprovidesrequirementsfortestingaswellasacceptableleakagecriteria.ThesetestsareperformedbyAppendixJ"Test"personnelandutilizecalibratedequipmenttodetermineacceptability.Additionally,10CFR50.55a(b)(2)(x)(E)requiresageneralvisualexaminationofthecontainmenteachperiodthatwouldidentifyanystructuraldegradationthatmaycontributetoleakage.A"VT-2"visualexaminationwillnotprovideadditionalassuranceofsafetybeyondthatofcurrentAppendixJpractices.Reliefisrequestedinaccordancewith10CFR50.55a(a)(3)(I).Theproposedalternative(pressuretestinginaccordancewith10CFR50,AppendixJ)willprovideandacceptablelevelofqualityandsafety.ThereferencetoparagraphIWA-5240hasbeenremovedinthe1997AddendaofASMESectionXI.ThisaddendahasbeenapprovedbytheASMEMainCommitteeandshouldbepublishedin1998.AlternateExaminations:Testingshallbeconductedinaccordancewith10CFR50,AppendixJ,inlieuofParagraphIWE-5240ofASMESectionXI,aswellasperforminganIWEdetailedvisualexaminationoftherepairedorreplacedarea(VT-l).RequestforReliefNo.40AttachmentPage2of3 od4rr}}
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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
gl REGULA Y INFORMATION DISTRIBUTION YSTEM (RIDS)
'I ACCESSION NBR :9906290269 DOC.DATE: 99/06/2X" NOTARIZED: NO DOCKET 0 FACIL:50-244 .Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTE. NAME AUTHOR AFFILIATION MECRgDY,R.C. Rochester Gas 8 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING; G. S.
SUBJECT:
Informs util wishes to amend extent of alternate exams provided for relief request re ISI program ASME Section XI recpxire exams for first 10-Yr interval for containment.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-09-04 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 0 LPD1-1 LA 1 1 LPD1-1 PD 1 1 VISSING,G. 1 1 R INTERNAL: cRXLE CENTER 01 1 1 NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D
PEmR~Lt,~<g~
'E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE."TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11
AND ROCHESTER GASANDELEClÃICCORPORAVON ~ 89EASTAYENUE, ROCHESrER N. Y Id6r19-0001 AREA CODE716 &f6-2700 ROBERT C. MECREDY Vice President Nuclear Operations June 21, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Inservice Inspection Program ASME Section XI Required Examinations for First 10-Year Interval for Containment (IWE and IWL)
Request for Relief No. 40 R.E. Ginna Nuclear Power Plant Docket No. 50/244
Dear Mr. Vissing:
RG&E provided the NRC with the subject relief request on January 11, 1999. As a result of a telecon with NRC staff on June 16, 1999, RG&E wishes to amend the extent of the alternate examinations provided for in that relief request.
In addition to the testing to be conducted in accordance with 10CFR 50 Appendix J, RGB E will perform an IWE detailed visual examination of the repaired or replaced area (VT-1). A replacement page of the attachment to our January 11, 1999 relief request is provided.
Very truly yours, Robert C. Mecredy 9906290269 990b2'i POR ADQCK 0500024%i
xc: Mr. Guy S. Vissing (Mail Stop 8C2)
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
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Collection systems, as required during the conduct of a system pressure test. In addition, personnel performing VT-2 examinations are required to be qualified in accordance with Subarticle IWA-2300 of ASME Section XI.
For repairs, replacements or modifications that are performed under ASME Section XI Code, applicable Construction Code (or Installation Code) non-destructive examinations (NDE) are performed and must meet the acceptance criteria of the Construction /
Installation Code. In addition to the Construction Code NDE, applicable ASME Section XI NDE pre-service NDE are also performed. These Construction Code and Section XI pre-service NDE requirements provide additional assurances that the repairs, replacements or modifications are sound and leak-tight.
Table IWE-2500-1, Examination Category E-P, identifies the examination method of 10 CFR 50, Appendix J and does not specifically identify a VT-2 visual examination. 10 CFR 50, Appendix J provides requirements for testing as well as acceptable leakage criteria. These tests are performed by Appendix J "Test" personnel and utilize calibrated equipment to determine acceptability. Additionally, 10 CFR 50.55a (b) (2) (x) (E) requires a general visual examination of the containment each period that would identify any structural degradation that may contribute to leakage. A "VT-2"visual examination willnot provide additional assurance of safety beyond that of current Appendix J practices.
Relief is requested in accordance with 10 CFR 50.55a (a) (3) (I). The proposed alternative (pressure testing in accordance with 10 CFR 50, Appendix J) willprovide and acceptable level of quality and safety.
The reference to paragraph IWA-5240 has been removed in the 1997 Addenda of ASME Section XI. This addenda has been approved by the ASME Main Committee and should be published in 1998.
Alternate Examinations:
Testing shall be conducted in accordance with 10 CFR 50, Appendix J, in lieu of Paragraph IWE-5240 of ASME Section XI, as well as performing an IWE detailed visual examination of the repaired or replaced area (VT-l).
Request for Relief No. 40 Attachment Page 2 of 3
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