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| | number = ML17265A509 | | | number = ML17265A509 |
| | issue date = 01/11/1999 | | | issue date = 01/11/1999 |
| | title = Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section Xi of ASME B&PV Code for ISI Program.Relief Request 41 Encl | | | title = Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 41 Encl |
| | 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 = 7 | | | page count = 7 |
| | project = | | | project = |
| | stage = Other | | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY1REGULA'1RYINFORMATION DISTRIBUTI wSYSTEM(RIDS)ACCESSION NBR:9901200387 DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 REGULA'1 RY INFORMATION DISTRIBUTI w SYSTEM (RIDS) |
| 99/01/11NOTARIZED: | | ACCESSION NBR:9901200387 DOC.DATE: 99/01/11 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas E Electric Corp. |
| NODOCKET¹FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION MECREDY,R.C.
| | RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. |
| Rochester GasEElectricCorp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Requestsreliefper10CFR50.55a(a)(3)(ii) fromcertainrequirements ofSectionXIofASMEBSPVCodeforISIprogram.Reliefrequest41encl.DISTRIBUTION CODE:A047DCOPIESRECEIVED:LTR ENCSIZE:TITLE:ORSubmittal:
| | Requests relief per 10CFR50.55a(a)(3)(ii) from certain requirements of Section XI of ASME BSPV Code for ISI program. Relief request 41 encl. |
| Inservice/Testing/Relief fromASMECode-GL-89-04NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENC SIZE: |
| 0500024kQRECIPIENT IDCODE/NAME PD1-1LAVISSING,G.
| | TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 0500024k Q |
| INTERNAL: | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 VISSING,G. 1 1 R INTERNAL: AEOD/SPD/RAB 1 1 FILE CENTER 0 1 1 NRR/DE/ECGB 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 |
| AEOD/SPD/RAB NRR/DE/ECGB NUDOCS-ABSTRACT RES/DET/EIB EXTERNAL: | | N NOTE TO ALL "RZDSn RECZPZENTS, PLEASE HELP US TO REDUCE WASTE TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRZBUTION 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 14 ENCL 13 |
| LITCOANDERSONNRCPDRCOPIESLTTRENCL1111111111111111RECIPIENT IDCODE/NAME PD1-1PDFILECENTER0NRRDEEMEBOGC/HDS3RES/DET/EMMEB NOACCOPIESLTTRENCL111111101111RDNNOTETOALL"RZDSnRECZPZENTS, PLEASEHELPUSTOREDUCEWASTETOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDZSTRZBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR14ENCL13 4ND0ROCHESTER GASANDELECTRICCORPORATION
| | 4ND 0 |
| ~89FASTAVENUf, ROCHESTER, N.YId&f9-0001 AREACODE7165'-2700ROBERTC.MECREDYVicePresident NvctearOperations January11,1999U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555 | | ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FASTAVENUf, ROCHESTER, N. Y Id&f9-0001 AREA CODE716 5'-2700 ROBERT C. MECREDY Vice President Nvctear Operations January 11, 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:== |
| | Inservice Inspection Program ASME Section XI Required Examinations for First 10-Year Interval for Containment (IWE and IWL) |
| | Request for Relief No. 41 R.E. Ginna Nuclear Power Plant Docket No. 50/244 |
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| ==References:== | | ==References:== |
| | EPRI "Containment Inspection Program Guide" GC-110698, September 1998, and selected Relief Request: |
| | (1) Calvert Cliffs Relief Request L-1 |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | In the Federal Register, dated August 8, 1996 (61 FR 41303), the NRC amended its regulations to incorporate by reference the 1992 Edition and Addenda of Subsections IWE and IWL of Section XI of the ASME Code. Subsections IWE and IWL give the requirements for inservice inspection (ISI) of Class MC (metallic containment) and Class CC (concrete containment). These requirements are now applicable for R. E. Ginna Nuclear Power Plant. |
| | The purpose of this letter is to request relief pursuant to 10 CFR 50.55a(a)(3)(ii) from certain requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Rochester Gas and Electric is a participant in the Electric Power Research Institute (EPRI) project for the'reparation of a Generic IWE/IWL Program and Industry Guide. This program was described to the NRC in a meeting on October 23, 1997r between the NRC, EPRI, and NEI, and several utilities. As a result from these meetings as well as the publication of the EPRI "Containment Inspection Program Guide" GC-110698, dated September 1998, Rochester Gas and Electric is submitting this relief request. Relief Request Number 41 is based on a generic relief request contained in the EPRI "Containment Inspection Program Guide". |
| | tt l 990i200387 9'ttOi PDR ADQCK ii 05000244 q |
| | 6 '"'DR I,g*'' |
| | I |
| | |
| | Relief Request Number 41 requests relief from Section XI of the ASME Code, 1992 Edition, 1992 Addenda, Subarticle IWA-2210, "Visual Examination," which lists requirements for minimum illumination and maximum direct examination distance of Class CC components under paragraph IWL-2310, "Visual Examination and Personnel Qualification." When remotely performing the visual examinations required by Subsection IWL, Paragraph IWL-2510, the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the techniques are qualified to detect the required conditions and indications. |
| | The Relief Request, justification, and the proposed alternatives are included in the attachment to this letter. This relief request will be included in the Inservice Inspection Program for R.E. Ginna Nuclear Power Plant, for the Third Interval Program (which ends December 31, 1999) and the Fourth Interval Program (which begins January 1, 2000). NRC approval of this relief request is desired before the end of June, 1999, to ensure these programs are in compliance with NRC requirements before the end of the Third Interval. |
| | Very truly yours, Robert C. Mecr Attachment xc: Mr. Guy S. Vissing (Mail Stop 14B2) |
| | 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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| Inservice Inspection ProgramASMESectionXIRequiredExaminations forFirst10-YearIntervalforContainment (IWEandIWL)RequestforReliefNo.41R.E.GinnaNuclearPowerPlantDocketNo.50/244EPRI"Containment Inspection ProgramGuide"GC-110698,September 1998,andselectedReliefRequest:(1)CalvertCliffsReliefRequestL-1 | | ATTACHMENT Rochester Gas and Electric Corporation Ginna Station Docket No. 50/244 First 10-Year Interval for Containment Inspection Program Request for Relief No. 41 Containment Inspection Remote VT of Class CC System/Component(s) for Which Relief is Requested: |
| | All components subject to the rules and requirements for Inservice Inspection of Class CC Concrete Components, Examination Category L-A, Concrete, Item L. l. 11 as applicable to IWL-2310, Visual Examination and Personnel Qualification and IWA-2210, Visual Examinations. |
| | II. Code Requirement: |
| | ASME Section XI, 1992 Edition, 1992 Addenda, IWL-2310, Visual Examination and Personnel Qualification and IWA-2210, Visual Examinations requires specific minimum illumination and maximum direct examination distance for all concrete surfaces. |
| | III. Code Requirement from Which Relief is Requested: |
| | Relief is requested from Paragraph IWA-2210, Visual Examination Requirements for minimum illumination and maximum direct examination distance of Class CC components under Paragraph IWL-2310. |
| | IV. Basis for Relief: |
| | 10 CFR 50.55a was amended in the Federal Register (61 FR 41303) to require the use of the 1992 Edition, 1992 Addenda, of Section XI when performing containment examinations. In addition to the requirements of Subsection IWL, the rulemaking also imposes the requirements of Subsection IWA of the 1992 Edition, 1992 Addendum, of ASME Section XI for minimum illumination and maximum direct examination distance of Class CC components, specifically for the examination of concrete under Paragraph IWL-2510. When remotely performing the visual examinations required by Subsection IWL Paragraph IWL-2510, the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased. |
| | Request for Relief No. 41 Attachment Page 1 of 3 |
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| ==DearMr.Vissing:==
| | IWA-2210 allows for remote examination as long as the remote examination procedure is demonstrated to resolve the selected test chart characters. The Registered Professional Engineer (RPE) will identify minimum size of indications of interest. For remote visual examination, the procedure and equipment to be used will be demonstrated capable of resolving these minimum indications to the satisfaction of the RPE and the Authorized Nuclear Insurance Inspector (ANII)( as allowed in IWA-2240, "Alternative Examinations." |
| IntheFederalRegister, datedAugust8,1996(61FR41303),theNRCamendeditsregulations toincorporate byreference the1992EditionandAddendaofSubsections IWEandIWLofSectionXIoftheASMECode.Subsections IWEandIWLgivetherequirements forinservice inspection (ISI)ofClassMC(metallic containment) andClassCC(concrete containment).
| | The record of demonstration will be available to Regulatory Authorities. |
| Theserequirements arenowapplicable forR.E.GinnaNuclearPowerPlant.Thepurposeofthisletteristorequestreliefpursuantto10CFR50.55a(a)(3)(ii) fromcertainrequirements ofSectionXIoftheAmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCode.Rochester GasandElectricisaparticipant intheElectricPowerResearchInstitute (EPRI)projectforthe'reparation ofaGenericIWE/IWLProgramandIndustryGuide.Thisprogramwasdescribed totheNRCinameetingonOctober23,1997rbetweentheNRC,EPRI,andNEI,andseveralutilities.
| | Accessibility to higher portions of the dome and the containment building itself make it a hardship to obtain the maximum direct examination distance and minimum illumination requirements. The installation of extensive temporary scaffold systems or a climbing scaffold system to access these portions of the containment would be necessary. These scaffolds would provide limited access due to containment geometry restrictions as well as structural and equipment interferences. The installation and removal of these scaffolds would increase both worker radiation exposure and personnel safety in order to meet Paragraph IWA-2210 requirements. |
| Asaresultfromthesemeetingsaswellasthepublication oftheEPRI"Containment Inspection ProgramGuide"GC-110698, datedSeptember 1998,Rochester GasandElectricissubmitting thisreliefrequest.ReliefRequestNumber41isbasedonagenericreliefrequestcontained intheEPRI"Containment Inspection ProgramGuide".990i200387 9'ttOiiiPDRADQCK05000244I6'"'DRI,g*''qttl
| | staff received The NRC into Public Comment g 2.3 in Part III that seven comments were consolidated of Attachment 6A to SECY-96-080. The Staff response to these concerns is as follows: |
| | "Comments received from ASME members on the containment committees indicate that the newer, more stringent requirements of IWA-2210 were not intended to be used for the examination of containments and were inadvertently included in Subsection IWL. The NRC agrees that remote examinations are the only practica'l method for inspecting much of the containment surface area. g 50.55a(b) (2) (x) (B) has been added to the final rule which contains alternative lighting and resolution requirements which may be used in lieu of the requirements contained in IWA-2210-1." |
| | However, as specified within 10 CFR 50.55a(b)(2)(x)(B) of the final rule, this alternative applies only to Subsection IWE, and not to Subsection IWL. |
| | Relief is requested in accordance with 10 CFR 50.55a(a)(3) |
| | (ii). Compliance with the original requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | Request for Relief No. 41 Attachment Page 2 of 3 |
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| |
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| ReliefRequestNumber41requestsrelieffromSectionXIoftheASMECode,1992Edition,1992Addenda,Subarticle IWA-2210, "VisualExamination,"
| | V. Alternate Examinations: |
| whichlistsrequirements forminimumillumination andmaximumdirectexamination distanceofClassCCcomponents underparagraph IWL-2310, "VisualExamination andPersonnel Qualification."
| | When performing remotely the visual examinations required by Subsection IWL, Paragraph IWL-2510 , the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination. |
| Whenremotelyperforming thevisualexaminations requiredbySubsection IWL,Paragraph IWL-2510, themaximumdirectexamination distancespecified inTableIWA-2210-1 maybeextended, andtheminimumillumination requirements specified inTableIWA-2210-1 maybedecreased providedthatthetechniques arequalified todetecttherequiredconditions andindications.
| | VI. Justification for the Granting of Relief: |
| TheReliefRequest,justification, andtheproposedalternatives areincludedintheattachment tothisletter.ThisreliefrequestwillbeincludedintheInservice Inspection ProgramforR.E.GinnaNuclearPowerPlant,fortheThirdIntervalProgram(whichendsDecember31,1999)andtheFourthIntervalProgram(whichbeginsJanuary1,2000).NRCapprovalofthisreliefrequestisdesiredbeforetheendofJune,1999,toensuretheseprogramsareincompliance withNRCrequirements beforetheendoftheThirdInterval.
| | This Relief Request is similar to Relief Request L-1 submitted by Calvert Cliffs as one of the EPRI "Containment Inspection Program Guide" Pilot Plant Relief Requests. |
| Verytrulyyours,RobertC.MecrAttachment xc:Mr.GuyS.Vissing(MailStop14B2)ProjectDirectorate I-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555RegionalAdministrator, RegionIU.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector ATTACHMENT Rochester GasandElectricCorporation GinnaStationDocketNo.50/244First10-YearIntervalforContainment Inspection ProgramRequestforReliefNo.41Containment Inspection RemoteVTofClassCCSystem/Component(s) forWhichReliefisRequested:
| | Relief Request L-1 (for Calvert Cliffs) was subsequently approved by the NRC. Refer to a letter from the NRC (S. |
| Allcomponents subjecttotherulesandrequirements forInservice Inspection ofClassCCConcreteComponents, Examination CategoryL-A,Concrete, ItemL.l.11asapplicable toIWL-2310, VisualExamination andPersonnel Qualification andIWA-2210, VisualExaminations.
| | Bajwa) to Baltimore Gas and Electric (C. Cruse), dated November 16, 1998 (Docket No. 50-317/318). This Relief Request will minimize Ginna operating and maintenance cost without decreasing the level of quality and safety. |
| II.CodeRequirement:
| | VII. Implementation Schedule: |
| ASMESectionXI,1992Edition,1992Addenda,IWL-2310, VisualExamination andPersonnel Qualification andIWA-2210, VisualExaminations requiresspecificminimumillumination andmaximumdirectexamination distanceforallconcretesurfaces.
| | Relief is requested for the first inspection interval for the IWL Containment Inspection Program (1996 2008). Note that this interval overlaps the Third and Fourth 10-Year Interval inspections of the Ginna Inservice Inspection Program. |
| III.CodeRequirement fromWhichReliefisRequested:
| | Request for Relief No. 41 Attachment Page 3 of 3}} |
| Reliefisrequested fromParagraph IWA-2210, VisualExamination Requirements forminimumillumination andmaximumdirectexamination distanceofClassCCcomponents underParagraph IWL-2310.
| |
| IV.BasisforRelief:10CFR50.55awasamendedintheFederalRegister(61FR41303)torequiretheuseofthe1992Edition,1992Addenda,ofSectionXIwhenperforming containment examinations.
| |
| Inadditiontotherequirements ofSubsection IWL,therulemaking alsoimposestherequirements ofSubsection IWAofthe1992Edition,1992Addendum, ofASMESectionXIforminimumillumination andmaximumdirectexamination distanceofClassCCcomponents, specifically fortheexamination ofconcreteunderParagraph IWL-2510.
| |
| Whenremotelyperforming thevisualexaminations requiredbySubsection IWLParagraph IWL-2510, themaximumdirectexamination distancespecified inTableIWA-2210-1 maybeextended, andtheminimumillumination requirements specified inTableIWA-2210-1 maybedecreased.
| |
| RequestforReliefNo.41Attachment Page1of3 IWA-2210allowsforremoteexamination aslongastheremoteexamination procedure isdemonstrated toresolvetheselectedtestchartcharacters.
| |
| TheRegistered Professional Engineer(RPE)willidentifyminimumsizeofindications ofinterest.
| |
| Forremotevisualexamination, theprocedure andequipment tobeusedwillbedemonstrated capableofresolving theseminimumindications tothesatisfaction oftheRPEandtheAuthorized NuclearInsurance Inspector (ANII)(asallowedinIWA-2240, "Alternative Examinations."
| |
| Therecordofdemonstration willbeavailable toRegulatory Authorities.
| |
| Accessibility tohigherportionsofthedomeandthecontainment buildingitselfmakeitahardshiptoobtainthemaximumdirectexamination distanceandminimumillumination requirements.
| |
| Theinstallation ofextensive temporary scaffoldsystemsoraclimbingscaffoldsystemtoaccesstheseportionsofthecontainment wouldbenecessary.
| |
| Thesescaffolds wouldprovidelimitedaccessduetocontainment geometryrestrictions aswellasstructural andequipment interferences.
| |
| Theinstallation andremovalofthesescaffolds wouldincreasebothworkerradiation exposureandpersonnel safetyinordertomeetParagraph IWA-2210requirements.
| |
| TheNRCstaffreceivedsevencommentsthatwereconsolidated intoPublicCommentg2.3inPartIIIofAttachment 6AtoSECY-96-080.
| |
| TheStaffresponsetotheseconcernsisasfollows:"Comments receivedfromASMEmembersonthecontainment committees indicatethatthenewer,morestringent requirements ofIWA-2210werenotintendedtobeusedfortheexamination ofcontainments andwereinadvertently includedinSubsection IWL.TheNRCagreesthatremoteexaminations aretheonlypractica'l methodforinspecting muchofthecontainment surfacearea.g50.55a(b)
| |
| (2)(x)(B)hasbeenaddedtothefinalrulewhichcontainsalternative lightingandresolution requirements whichmaybeusedinlieuoftherequirements contained inIWA-2210-1."
| |
| However,asspecified within10CFR50.55a(b)(2)(x)(B) ofthefinalrule,thisalternative appliesonlytoSubsection IWE,andnottoSubsection IWL.Reliefisrequested inaccordance with10CFR50.55a(a)(3)
| |
| (ii).Compliance withtheoriginalrequirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityandsafety.RequestforReliefNo.41Attachment Page2of3 V.Alternate Examinations:
| |
| Whenperforming remotelythevisualexaminations requiredbySubsection IWL,Paragraph IWL-2510,themaximumdirectexamination distancespecified inTableIWA-2210-1 maybeextended, andtheminimumillumination requirements specified inTableIWA-2210-1 maybedecreased providedthattheconditions orindications forwhichthevisualexamination isperformed canbedetectedatthechosendistanceandillumination.
| |
| VI.Justification fortheGrantingofRelief:ThisReliefRequestissimilartoReliefRequestL-1submitted byCalvertCliffsasoneoftheEPRI"Containment Inspection ProgramGuide"PilotPlantReliefRequests. | |
| ReliefRequestL-1(forCalvertCliffs)wassubsequently approvedbytheNRC.RefertoaletterfromtheNRC(S.Bajwa)toBaltimore GasandElectric(C.Cruse),datedNovember16,1998(DocketNo.50-317/318).
| |
| ThisReliefRequestwillminimizeGinnaoperating andmaintenance costwithoutdecreasing thelevelofqualityandsafety.VII.Implementation Schedule:
| |
| Reliefisrequested forthefirstinspection intervalfortheIWLContainment Inspection Program(1996-2008).NotethatthisintervaloverlapstheThirdandFourth10-YearIntervalinspections oftheGinnaInservice Inspection Program.RequestforReliefNo.41Attachment Page3of3}}
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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
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 REGULA'1 RY INFORMATION DISTRIBUTI w SYSTEM (RIDS)
ACCESSION NBR:9901200387 DOC.DATE: 99/01/11 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas E Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Requests relief per 10CFR50.55a(a)(3)(ii) from certain requirements of Section XI of ASME BSPV Code for ISI program. Relief request 41 encl.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENC SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 0500024k Q
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 VISSING,G. 1 1 R INTERNAL: AEOD/SPD/RAB 1 1 FILE CENTER 0 1 1 NRR/DE/ECGB 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
N NOTE TO ALL "RZDSn RECZPZENTS, PLEASE HELP US TO REDUCE WASTE TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRZBUTION 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 14 ENCL 13
4ND 0
ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FASTAVENUf, ROCHESTER, N. Y Id&f9-0001 AREA CODE716 5'-2700 ROBERT C. MECREDY Vice President Nvctear Operations January 11, 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. 41 R.E. Ginna Nuclear Power Plant Docket No. 50/244
References:
EPRI "Containment Inspection Program Guide" GC-110698, September 1998, and selected Relief Request:
(1) Calvert Cliffs Relief Request L-1
Dear Mr. Vissing:
In the Federal Register, dated August 8, 1996 (61 FR 41303), the NRC amended its regulations to incorporate by reference the 1992 Edition and Addenda of Subsections IWE and IWL of Section XI of the ASME Code. Subsections IWE and IWL give the requirements for inservice inspection (ISI) of Class MC (metallic containment) and Class CC (concrete containment). These requirements are now applicable for R. E. Ginna Nuclear Power Plant.
The purpose of this letter is to request relief pursuant to 10 CFR 50.55a(a)(3)(ii) from certain requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Rochester Gas and Electric is a participant in the Electric Power Research Institute (EPRI) project for the'reparation of a Generic IWE/IWL Program and Industry Guide. This program was described to the NRC in a meeting on October 23, 1997r between the NRC, EPRI, and NEI, and several utilities. As a result from these meetings as well as the publication of the EPRI "Containment Inspection Program Guide" GC-110698, dated September 1998, Rochester Gas and Electric is submitting this relief request. Relief Request Number 41 is based on a generic relief request contained in the EPRI "Containment Inspection Program Guide".
tt l 990i200387 9'ttOi PDR ADQCK ii 05000244 q
6 '"'DR I,g*
I
Relief Request Number 41 requests relief from Section XI of the ASME Code, 1992 Edition, 1992 Addenda, Subarticle IWA-2210, "Visual Examination," which lists requirements for minimum illumination and maximum direct examination distance of Class CC components under paragraph IWL-2310, "Visual Examination and Personnel Qualification." When remotely performing the visual examinations required by Subsection IWL, Paragraph IWL-2510, the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the techniques are qualified to detect the required conditions and indications.
The Relief Request, justification, and the proposed alternatives are included in the attachment to this letter. This relief request will be included in the Inservice Inspection Program for R.E. Ginna Nuclear Power Plant, for the Third Interval Program (which ends December 31, 1999) and the Fourth Interval Program (which begins January 1, 2000). NRC approval of this relief request is desired before the end of June, 1999, to ensure these programs are in compliance with NRC requirements before the end of the Third Interval.
Very truly yours, Robert C. Mecr Attachment xc: Mr. Guy S. Vissing (Mail Stop 14B2)
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
ATTACHMENT Rochester Gas and Electric Corporation Ginna Station Docket No. 50/244 First 10-Year Interval for Containment Inspection Program Request for Relief No. 41 Containment Inspection Remote VT of Class CC System/Component(s) for Which Relief is Requested:
All components subject to the rules and requirements for Inservice Inspection of Class CC Concrete Components, Examination Category L-A, Concrete, Item L. l. 11 as applicable to IWL-2310, Visual Examination and Personnel Qualification and IWA-2210, Visual Examinations.
II. Code Requirement:
ASME Section XI, 1992 Edition, 1992 Addenda, IWL-2310, Visual Examination and Personnel Qualification and IWA-2210, Visual Examinations requires specific minimum illumination and maximum direct examination distance for all concrete surfaces.
III. Code Requirement from Which Relief is Requested:
Relief is requested from Paragraph IWA-2210, Visual Examination Requirements for minimum illumination and maximum direct examination distance of Class CC components under Paragraph IWL-2310.
IV. Basis for Relief:
10 CFR 50.55a was amended in the Federal Register (61 FR 41303) to require the use of the 1992 Edition, 1992 Addenda, of Section XI when performing containment examinations. In addition to the requirements of Subsection IWL, the rulemaking also imposes the requirements of Subsection IWA of the 1992 Edition, 1992 Addendum, of ASME Section XI for minimum illumination and maximum direct examination distance of Class CC components, specifically for the examination of concrete under Paragraph IWL-2510. When remotely performing the visual examinations required by Subsection IWL Paragraph IWL-2510, the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased.
Request for Relief No. 41 Attachment Page 1 of 3
IWA-2210 allows for remote examination as long as the remote examination procedure is demonstrated to resolve the selected test chart characters. The Registered Professional Engineer (RPE) will identify minimum size of indications of interest. For remote visual examination, the procedure and equipment to be used will be demonstrated capable of resolving these minimum indications to the satisfaction of the RPE and the Authorized Nuclear Insurance Inspector (ANII)( as allowed in IWA-2240, "Alternative Examinations."
The record of demonstration will be available to Regulatory Authorities.
Accessibility to higher portions of the dome and the containment building itself make it a hardship to obtain the maximum direct examination distance and minimum illumination requirements. The installation of extensive temporary scaffold systems or a climbing scaffold system to access these portions of the containment would be necessary. These scaffolds would provide limited access due to containment geometry restrictions as well as structural and equipment interferences. The installation and removal of these scaffolds would increase both worker radiation exposure and personnel safety in order to meet Paragraph IWA-2210 requirements.
staff received The NRC into Public Comment g 2.3 in Part III that seven comments were consolidated of Attachment 6A to SECY-96-080. The Staff response to these concerns is as follows:
"Comments received from ASME members on the containment committees indicate that the newer, more stringent requirements of IWA-2210 were not intended to be used for the examination of containments and were inadvertently included in Subsection IWL. The NRC agrees that remote examinations are the only practica'l method for inspecting much of the containment surface area. g 50.55a(b) (2) (x) (B) has been added to the final rule which contains alternative lighting and resolution requirements which may be used in lieu of the requirements contained in IWA-2210-1."
However, as specified within 10 CFR 50.55a(b)(2)(x)(B) of the final rule, this alternative applies only to Subsection IWE, and not to Subsection IWL.
Relief is requested in accordance with 10 CFR 50.55a(a)(3)
(ii). Compliance with the original requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Request for Relief No. 41 Attachment Page 2 of 3
V. Alternate Examinations:
When performing remotely the visual examinations required by Subsection IWL, Paragraph IWL-2510 , the maximum direct examination distance specified in Table IWA-2210-1 may be extended, and the minimum illumination requirements specified in Table IWA-2210-1 may be decreased provided that the conditions or indications for which the visual examination is performed can be detected at the chosen distance and illumination.
VI. Justification for the Granting of Relief:
This Relief Request is similar to Relief Request L-1 submitted by Calvert Cliffs as one of the EPRI "Containment Inspection Program Guide" Pilot Plant Relief Requests.
Relief Request L-1 (for Calvert Cliffs) was subsequently approved by the NRC. Refer to a letter from the NRC (S.
Bajwa) to Baltimore Gas and Electric (C. Cruse), dated November 16, 1998 (Docket No. 50-317/318). This Relief Request will minimize Ginna operating and maintenance cost without decreasing the level of quality and safety.
VII. Implementation Schedule:
Relief is requested for the first inspection interval for the IWL Containment Inspection Program (1996 2008). Note that this interval overlaps the Third and Fourth 10-Year Interval inspections of the Ginna Inservice Inspection Program.
Request for Relief No. 41 Attachment Page 3 of 3
