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| | number = ML18018A934 | | | number = ML18018A934 |
| | issue date = 06/08/1978 | | | issue date = 06/08/1978 |
| | title = Nine Mile Point, Unit 2 - Letter Responding to the May 9, 1978 Letter Requesting Additional Information Required to Continue Review of the Mark Ii Containment Program and Advising That the Information Will Be Addressed in Revision I of the | | | title = Letter Responding to the May 9, 1978 Letter Requesting Additional Information Required to Continue Review of the Mark II Containment Program and Advising That the Information Will Be Addressed in Revision I of the Load Assess |
| | author name = Rhode G K | | | author name = Rhode G |
| | author affiliation = Niagara Mohawk Power Corp | | | author affiliation = Niagara Mohawk Power Corp |
| | addressee name = Case E G | | | addressee name = Case E |
| | addressee affiliation = NRC/NRR | | | addressee affiliation = NRC/NRR |
| | docket = 05000410 | | | docket = 05000410 |
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| | document type = Letter, Response to Request for Additional Information (RAI) | | | document type = Letter, Response to Request for Additional Information (RAI) |
| | page count = 10 | | | page count = 10 |
| | | project = |
| | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:gREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS>DISTRIBUTIONFORINCOMINGMATERIAL50-410REC:CASEEGORG:RHODEGKDOCDATE:-06/08/78NRCNIAGARAMOHAWKPWRDATERCVD:06/13/784DQCTYPE:LETTER-NOTARIZED:NOCOPIESRECEIVEDSUBJECT.'TR1ADVISINGRESPONSETONRCREQUESTOF05/09/78FORADDLGENERIC5PLANTSPECIFICINFOTOCONTINUEREVIEWOFTHEMARKIICONTAINMENTPROGRAMsWILLBESUBMITTEDBYANIAGARAMOHAWKSUBMITTAL(GENERIC>ANDPLANT-SPECIFICINFO-WILLBEADDRESSEDINREV1OFUNI~9kg(L>APl5586SHeumR~-PLANTNAME:NINEMILEPOINT-UNIT2DISTRIBUTIONOFTHISMATERIALFPSAR/FSARAMDTSANDRELATEDCORESPONDENCE(DISTRIBUTIONCODEB001)REVIEWERINITIAL:XJMISTRIBUTORINITIAL:AISASFOLLOWS'++++++<++++w+wwwwe'QRACTION:INTERNAL:EXTERNAL:ASSTDIRVASSALLQ4+LTRONLY(i>PRKANE4<LTRONLY(i)REGFILLTRONLY<1)++LTRONLY(2>OPERATORLICBR44LTRONLY<i)QAB++LTRONLY(1)MIPC++LTRONLY<1)MECHENGBR~+LTRONLY(1>MATERIALENGBR+4LTRONLY<2)REACTORSYSTEMSBR++LTRONLY(iCOREPERFORMANCEBR4~LTRONLY<AUXILIARYSYSBR4+LTRONLY(1>I8(CSYSTEMSBR4+LTRONLY(i)ADFORSITETECH>+LTRONLY(4>ACCIDENTANALYSIS44LTR-ONLY<1)RADASSESSMENTBR4+LTRONLY(1>LPDR'SOSWEGO'Y+4LTRONLY(i)TIC++LTRONLY(1)NSIC44LTRONLY(1)ACRSCATB4+LTRONLY(16>BRCHIEFLWRI4BC+>LTRONLY(i)LICASSTSERVICE++LTRONL'Y<1)NRCPDR44LTRONLY<1)GELD>+LTRONLY(i>EMERGENCYPLANBR++LTRONLY<i).CASE++LTRONLY(1>ADFORENGw4LTRONLY<i)STRUCTURALENGBR~>LTRONLY(i>ADFOR.REACSFTY<<LTRONLY(1)ANALYSISBR+>LTRONLY(i>1ADFORPLANTSYSTEMS+<LTRONLYCONTAINMENTSYSTEMS~+LTRONLY(POWERSYSBR4%LTRONLY<1)ADFORSITEANLYS>>LTRONLY(i>EFFLUENTTREATtSYS<+LTRONLY<iKIRKWOOD>+LTRONLY(1)DISTRIBUTION:LTR56ENCL0SIZE:1PCONTROLNBR:781650034THEEND%%%%%%%%%%%%%%4%%%%%%%%%4t%0%%%%%% | | {{#Wiki_filter:g REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS > |
| SNUCLEARREGULATORYCOMMISSIONC'AILYACCESSIONL'IST"05/IO/78PAGEFILELiOCATIOM968125-0322ETTERPTASKMBR-FICHEMBRNOTARIZED:NOLPDR-YESCLASS-UREG-0219DRAFT02RECPAFFILIATION-TNVALLEYAUTHORGAFFIL'ATIONNRCIMGMUREG-0219mDRAFT2yWHICHOUTLINESTHECURRENTPOSITION'OFTHENRRNIftPLEMENTATIOMOFTHEREQUIREMENTSTOUPGRADETHEQUALIFICATIOMsGyLEQUIPPINGOFSECURITYPERSONNEL~It//0ENCL~KPl7333-0099EHOPTASKMBR-IIFICHENBRNOTARIZEDNOLPDR-NOCLASS=RECPAFFILIATION-NRCORGAFFILIATION:NRCTASKMBR.FICHEMBRMOTARIZED-LPDR.NONOCLASS:IRECP4FFILIATIOM-NRCORGAFFILIATION:NRCORSUBMISSIONTOTHESEABROOKBOARD~K027333-00'99EMOORSUBMISSIONTOTHESEABROOKBOARDe NIAGARAMOHAWKPOWERCORPORATIONNIAGARA~MOHAWK300ERIEBOULEVARD.WESTSYRACUSE.N.Y.13202June8,1978a~C~/ye~oJgMr.EdsonG..Case,ActingDirectorOfficeofNuclearReactorRegulationU.S.NuclearRegulatoryCommissionWashington,D.C.20555
| | DISTRIBUTION FOR INCOMING MATERIAL 50-410 CASE E ORG: RHODE G K DOCDATE:- 06/08/78 SUBJECT.'TR REC: G NRC NIAGARA MOHAWK PWR DATE RCVD: 06/13/78 4 |
| | DQCTYPE: LETTER - NOTARIZED: NO COPIES RECEIVED 1 |
| | ADVISING RESPONSE TO NRC REQUEST OF 05/09/78 FOR ADDL GENERIC 5 PLANT SPECIFIC INFO TO CONTINUE REVIEW OF THE MARK I I CONTAINMENT PROGRAMs WILL BE SUBMITTED BY A NIAGARA MOHAWK SUBMITTAL (GENERIC> AND PLANT- SPECIFIC INFO-WILL BE ADDRESSED IN REV 1 OF UNI~ 9 kg( L>AP l5586SHeum R~- |
| | PLANT NAME: NINE MILE POINT UNIT 2 REVIEWER INITIAL: XJM ISTR IBUTOR INITIAL: |
| | A DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS'++++++<++++w+wwwwe F |
| | PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE B001) 'QR ACTION: ASST DIR VASSALLQ4+LTR ONLY(i> BR CHIEF LWRI4 BC+>LTR ONLY(i) |
| | PR KANE4<LTR ONLY(i) LIC ASST SERVICE++LTR ONL'Y< 1) |
| | INTERNAL: REG F IL LTR ONLY < 1 ) NRC PDR44LTR ONLY< 1) |
| | ++LTR ONLY(2> GELD>+LTR ONLY(i> |
| | OPERATOR LIC BR44LTR ONLY<i) EMERGENCY PLAN BR++LTR ONLY<i) |
| | QAB++LTR ONLY(1) .CASE++LTR ONLY(1> |
| | MIPC++LTR ONLY< 1) AD FOR ENGw4LTR ONLY<i) |
| | MECH ENG BR~+LTR ONLY(1> STRUCTURAL ENG BR~>LTR ONLY(i> |
| | MATERIAL ENG BR+4LTR ONLY<2) AD FOR .REAC SFTY<<LTR ONLY(1) |
| | REACTOR SYSTEMS BR++LTR ONLY(i ANALYSIS BR+>LTR ONLY(i> |
| | CORE PERFORMANCE BR4~LTR ONLY< 1 AD FOR PLANT SYSTEMS+<LTR ONLY AUXILIARY SYS BR4+LTR ONLY(1> CONTAINMENT SYSTEMS~+LTR ONLY( |
| | I 8( C SYSTEMS BR4+LTR ONLY(i) POWER SYS BR4%LTR ONLY< 1) |
| | AD FOR SITE TECH>+LTR ONLY(4> AD FOR SITE ANLYS>>LTR ONLY(i > |
| | ACCIDENT ANALYSIS44LTR -ONLY< 1 ) EFFLUENT TREAT tSYS<+LTR ONLY<i RAD ASSESSMENT BR4+LTR ONLY(1> KIRKWOOD>+LTR ONLY(1) |
| | EXTERNAL: LPDR'S OSWEGO'Y+4LTR ONLY(i) |
| | TIC++LTR ONLY(1) |
| | NSIC44LTR ONLY(1) |
| | ACRS CAT B4+LTR ONLY(16> |
| | DISTRIBUTION: LTR 56 ENCL 0 CONTROL NBR: 781650034 SIZE: 1P THE END %%%%%%%%%%%%%%4%%%%%%%%%4t%0%%%%%% |
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| ==DearMr.Case:== | | S NUCLEAR REGULATORY COMMISSION C 'AILY ACCESSION L'IST" 05/IO/78 PAGE 96 FILE LiOCA TIOM 8125-0322 TASK MBR-ETTER FI CHE M BR P NOTARIZED: NO LPDR- YES CLASS-UREG-0219 DRAFT 02 RECP AFFILIATION- TN VALLEY AUTH ORG AFFIL'ATION NRC IMG MUREG-0219m DRAFT 2y WHICH OUTLINES THE CURRENT POSITION 'OF THE NRR N IftPLEMENTATIOM OF THE REQUIREMENTS TO UPGRADE THE QUALIFICATIOMs Gy L EQUIPPING OF SECURITY PERSONNEL ~ It//0 ENCL ~ |
| Re:NineMilePointUnit2DocketNo.50-410CPPR-112Mr.StevenA.Varga'sletterofMay9,1978requestedadditionalinformationrequiredtocontinuereviewoftheMarkIIContainmentProgram.Therequestedinformation,whichisgeneric,willbesubmittedaspartoftheMarkIIContainmentProgramandwillsubsequentlybereferencedonourdocketbyaNiagaraMohawksubmittal.Therequestedinformation,whichisplantspecific,willbeaddressedinRevision1oftheNineMilePointUnit2LoadAssessmentReport.Verytrulyyours,NIAGARAMOHAWKPOWERCORPORATIONra.de,VicePresidentSyternPojectManagementPEF/szd78165003'eIIgy 0T1L~p 6p,RRSCy'Ip0Cy/p+~*~4DocketNo.50-410NUCLEARREGULATORYCOMMISSIONREGIONI631PARKAVENUEKINGOFPRUSSIA.PENNSYLVANIA19406Mg3f519NiagaraMohawkPowerCorporationATTN:Mr.G.K.RhodeVicePresidentSystemProjectManagement300ErieBoulevard,WestSyracuse,NewYork13202Gentlemen: | | K Pl 7333-0099 TASK MBR- II EHO FICHE NBR P NOTARIZED NO LPDR- NO CLASS= |
| | RECP AFFILIATION- NRC ORG AFFILIATION: NRC OR SUBMISSION TO THE SEABROOK BOARD ~ |
| | K 02 7333-00'99 TASK MBR. |
| | EMO FI CHE MBR MOTARIZED- NO LPDR. NO CLASS: |
| | I RECP 4 FF ILIA TI OM - NRC ORG AFFILIATION: NRC OR SUBMISSION TO THE SEABROOK BOA RDe |
| | |
| | NIAGARA MOHAWK POWER CORPORATION NIAGARA |
| | ~ MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y. 13202 a |
| | ~C~/ye ~o Jg June 8, 1978 Mr. Edson G.. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
| | |
| | ==Dear Mr. Case:== |
| | |
| | Re: Nine Mile Point Unit 2 Docket No. 50-410 CPPR-112 Mr. Steven A. Varga's letter of May 9, 1978 requested additional information required to continue review of the Mark II Containment Program. The requested information, which is generic, will be submitted as part of the Mark II Containment Program and will subsequently be referenced on our docket by a Niagara Mohawk submittal. The requested information, which is plant specific, will be addressed in Revision 1 of the Nine Mile Point Unit 2 Load Assessment Report. |
| | Very truly yours, NIAGARA MOHAWK POWER CORPORATION ra . de, Vice President Sy tern P oject Management I |
| | PEF/szd 78165003'eIgy |
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| | Cy NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA. PENNSYLVANIA 19406 |
| | /p |
| | +~*~4 Mg 3f519 Docket No. 50-410 Niagara Mohawk Power Corporation ATTN: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| RockStressEvaluation(YourletterofApril28,1978)Thankyouforyourletter,referencedabove,whichforwardedafinalreportpursuantto10CFR50.55(e)regardingthesubjectmatter.Thismatterwillbereviewedduringasubsequentinspection.However,thedesigninformationreferredtoinyourletterisnotrequiredtobefurnishedtotheOfficeofInspectionandEnforcement,RegionI.Yourcooperationwithusisappreciated.Sincerely,cc:EugeneB.Thomas,Jr.,EsquireobertT.Carlson,ChiefReactorConstructionandEngineeringSupportBranch yLv)~~PI DocketNo:50-4100'stribution:ocketFileNRCPDRLocalPDRLWR84FileD.VassalloF.WilliamsS.VargaW.KaneMAY331978ELDIE(3)bcc:J.Buchanan,NSICT~Abernathy,TIC.ACRS(16)M.ServiceNiagarattohawkPowerCorporationATTN:Nr.GeraldK.Rhode,VicePresidentSystemProjectNanagement300ErieBoulevard,HestSyracuse,NewYork13202Gentlemen:
| | Rock Stress Evaluation (Your letter of April 28, 1978) |
| | Thank you for your letter, referenced above, which forwarded a final report pursuant to 10 CFR 50.55(e) regarding the subject matter. |
| | This matter will be reviewed during a subsequent inspection. However, the design information referr ed to in your letter is not required to be furnished to the Office of Inspection and Enforcement, Region I. |
| | Your cooperation with us is appreciated. |
| | Sincerely, obert T. Carlson, Chief Reactor Construction and Engineering Support Branch cc: |
| | Eugene B. Thomas, Jr., Esquire |
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| | MAY 33 1978 0 'stribution: |
| | ocket File ELD NRC PDR IE (3) |
| | Local PDR LWR 84 File bcc: |
| | D. Vassallo J. Buchanan, NSIC Docket No: 50-410 F. Williams T Abernathy, TIC |
| | ~ |
| | S. Varga .ACRS (16) |
| | W. Kane M. Service Niagara ttohawk Power Corporation ATTN: Nr. Gerald K. Rhode, Vice President System Project Nanagement 300 Erie Boulevard, Hest Syracuse, New York 13202 Gentlemen: |
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| ==SUBJECT:== | | ==SUBJECT:== |
| (PALITYASSURANCEPROGRAMFORNINEtlILEPOINT.NUCLEARSTATION-UNIT2IntheNiagaraMohawkPlacerCorporationletter,G.RhodetoE.Case,datedApril26,1978youtransmittedrevisionstotheStone8WebsterEngineeringCorporation's"gualityAssuranceProgramttanual,NineNilePointNuclearStation-Unit2."Theserevisionshabebeenrevieiedbythestaffandweconcludetheyareacceptable.Ifyouhaveanyquestionsregardingthismatterpleasecontactthe.staff'sassigned'licensingprojectmanager.,Sincerely,--8Msi808g'bing4aAo,Vary'tevenA.Varga,ChiefLightHaterReactossBranchNo.4DivisionofProjectt1anagementcc:SeePage2CIPPICS~SURNAME&.DP.A...4.....ga....CATS'5J22/.78NRCFORbf318(9.76)NRCM02406UISOOVSRNMSNTPRINTINOOPPICSIISTSSSS,SSS iaIgh$)IhI~LIII-III-~'F'II'"h~IIII~tFpt,IqhIItr~FIIIIII4,+*-I~FII~hIIII=-IIFI'llIII4<<%II'lIIIg$0~(~pgQ(.'"4<<I~IIpIII*IId(W'<<hV@i,FVII'f]/'gtAI Niagara'ohawkPowerCorporation-'-cc.s:ArvinE.Upton,Esq."LeBoeuf,Lamb,Leiby8HacRae1757NStreet,N.Washington,D.C.20036AnthonyZ;Roisman,Esq.NaturalResources0fenseCouncil91715thStreet,N."W.Washington,D.C.20005llr.RichardGoldsmithSyracuseUni'versityCollegeofLawE.I.WhiteHall.CampusSyracuse,NewYo~k13210T.,K.DeBoer,Director1'echnologicalDevelopmentProgramsNewYorkStateEnergyOffice'wanStreetBuildingCore1-2ndFloor'mpire,StatePlazaAlbany,NewYork12223}} | | (PALITY ASSURANCE PROGRAM FOR NINE tlILE POINT. NUCLEAR STATION - UNIT 2 In the Niagara Mohawk Placer Corporation letter, G. Rhode to E. Case, dated April 26, 1978 you transmitted revisions to the Stone 8 Webster Engineering Corporation's "guality Assurance Program ttanual, Nine Nile Point Nuclear Station - Unit 2." These revisions habe been revieied by the staff and we conclude they are acceptable. |
| | If you have any questions regarding this matter please contact the |
| | .staff's assigned 'licensing project manager., |
| | Sincerely, |
| | -- 8 M si808g'bing 4a Ao, A. Varga, Chief Vary'teven Light Hater Reactoss Branch No. 4 Division of Project t1anagement cc: See Page 2 CIPPICS~ .DP . A...4..... |
| | SURNAME& ga.... |
| | CATS'5J22/.78 NRC FORbf 318 (9.76) NRCM 0240 6 UI S OOVSRNMSNT PRINTINO OPPICSI ISTS SSS,SSS |
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| | Niagara'ohawk Power Corpora ti on -'- |
| | c c.s: |
| | Arvin E. Upton, Esq. " |
| | LeBoeuf, Lamb, Leiby 8 HacRae 1757 N Street, N. |
| | Washington, D. C. 20036 Anthony Z; Roisman, Esq. |
| | Natural Resources 0 fense Council 917 15th Street, N." W. |
| | Washington, D. C. 20005 llr. Richard Goldsmith Syracuse Uni'versi ty College of Law E. I. White Hall. Campus Syracuse, New Yo~ k 13210 T., K. DeBoer, Director 1'echnological Development Programs New York State Energy Office'wan Street Building Core 1 - 2nd Floor State Plaza 'mpire, Albany, New York 12223}} |
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Category:Letter
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Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-30030 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3516, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-29029 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021 Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2 NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2 NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021 Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020 Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2 NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016 Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....2016-01-25025 January 2016 Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A.... NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016 Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... 2023-08-04
[Table view] |
Text
g REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >
DISTRIBUTION FOR INCOMING MATERIAL 50-410 CASE E ORG: RHODE G K DOCDATE:- 06/08/78 SUBJECT.'TR REC: G NRC NIAGARA MOHAWK PWR DATE RCVD: 06/13/78 4
DQCTYPE: LETTER - NOTARIZED: NO COPIES RECEIVED 1
ADVISING RESPONSE TO NRC REQUEST OF 05/09/78 FOR ADDL GENERIC 5 PLANT SPECIFIC INFO TO CONTINUE REVIEW OF THE MARK I I CONTAINMENT PROGRAMs WILL BE SUBMITTED BY A NIAGARA MOHAWK SUBMITTAL (GENERIC> AND PLANT- SPECIFIC INFO-WILL BE ADDRESSED IN REV 1 OF UNI~ 9 kg( L>AP l5586SHeum R~-
PLANT NAME: NINE MILE POINT UNIT 2 REVIEWER INITIAL: XJM ISTR IBUTOR INITIAL:
A DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS'++++++<++++w+wwwwe F
PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE B001) 'QR ACTION: ASST DIR VASSALLQ4+LTR ONLY(i> BR CHIEF LWRI4 BC+>LTR ONLY(i)
PR KANE4<LTR ONLY(i) LIC ASST SERVICE++LTR ONL'Y< 1)
INTERNAL: REG F IL LTR ONLY < 1 ) NRC PDR44LTR ONLY< 1)
++LTR ONLY(2> GELD>+LTR ONLY(i>
OPERATOR LIC BR44LTR ONLY<i) EMERGENCY PLAN BR++LTR ONLY<i)
QAB++LTR ONLY(1) .CASE++LTR ONLY(1>
MIPC++LTR ONLY< 1) AD FOR ENGw4LTR ONLY<i)
MECH ENG BR~+LTR ONLY(1> STRUCTURAL ENG BR~>LTR ONLY(i>
MATERIAL ENG BR+4LTR ONLY<2) AD FOR .REAC SFTY<<LTR ONLY(1)
REACTOR SYSTEMS BR++LTR ONLY(i ANALYSIS BR+>LTR ONLY(i>
CORE PERFORMANCE BR4~LTR ONLY< 1 AD FOR PLANT SYSTEMS+<LTR ONLY AUXILIARY SYS BR4+LTR ONLY(1> CONTAINMENT SYSTEMS~+LTR ONLY(
I 8( C SYSTEMS BR4+LTR ONLY(i) POWER SYS BR4%LTR ONLY< 1)
AD FOR SITE TECH>+LTR ONLY(4> AD FOR SITE ANLYS>>LTR ONLY(i >
ACCIDENT ANALYSIS44LTR -ONLY< 1 ) EFFLUENT TREAT tSYS<+LTR ONLY KIRKWOOD>+LTR ONLY(1)
EXTERNAL: LPDR'S OSWEGO'Y+4LTR ONLY(i)
TIC++LTR ONLY(1)
NSIC44LTR ONLY(1)
ACRS CAT B4+LTR ONLY(16>
DISTRIBUTION: LTR 56 ENCL 0 CONTROL NBR: 781650034 SIZE: 1P THE END %%%%%%%%%%%%%%4%%%%%%%%%4t%0%%%%%%
S NUCLEAR REGULATORY COMMISSION C 'AILY ACCESSION L'IST" 05/IO/78 PAGE 96 FILE LiOCA TIOM 8125-0322 TASK MBR-ETTER FI CHE M BR P NOTARIZED: NO LPDR- YES CLASS-UREG-0219 DRAFT 02 RECP AFFILIATION- TN VALLEY AUTH ORG AFFIL'ATION NRC IMG MUREG-0219m DRAFT 2y WHICH OUTLINES THE CURRENT POSITION 'OF THE NRR N IftPLEMENTATIOM OF THE REQUIREMENTS TO UPGRADE THE QUALIFICATIOMs Gy L EQUIPPING OF SECURITY PERSONNEL ~ It//0 ENCL ~
K Pl 7333-0099 TASK MBR- II EHO FICHE NBR P NOTARIZED NO LPDR- NO CLASS=
RECP AFFILIATION- NRC ORG AFFILIATION: NRC OR SUBMISSION TO THE SEABROOK BOARD ~
K 02 7333-00'99 TASK MBR.
EMO FI CHE MBR MOTARIZED- NO LPDR. NO CLASS:
I RECP 4 FF ILIA TI OM - NRC ORG AFFILIATION: NRC OR SUBMISSION TO THE SEABROOK BOA RDe
NIAGARA MOHAWK POWER CORPORATION NIAGARA
~ MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y. 13202 a
~C~/ye ~o Jg June 8, 1978 Mr. Edson G.. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Case:
Re: Nine Mile Point Unit 2 Docket No. 50-410 CPPR-112 Mr. Steven A. Varga's letter of May 9, 1978 requested additional information required to continue review of the Mark II Containment Program. The requested information, which is generic, will be submitted as part of the Mark II Containment Program and will subsequently be referenced on our docket by a Niagara Mohawk submittal. The requested information, which is plant specific, will be addressed in Revision 1 of the Nine Mile Point Unit 2 Load Assessment Report.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION ra . de, Vice President Sy tern P oject Management I
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+~*~4 Mg 3f519 Docket No. 50-410 Niagara Mohawk Power Corporation ATTN: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Gentlemen:
Subject:
Rock Stress Evaluation (Your letter of April 28, 1978)
Thank you for your letter, referenced above, which forwarded a final report pursuant to 10 CFR 50.55(e) regarding the subject matter.
This matter will be reviewed during a subsequent inspection. However, the design information referr ed to in your letter is not required to be furnished to the Office of Inspection and Enforcement, Region I.
Your cooperation with us is appreciated.
Sincerely, obert T. Carlson, Chief Reactor Construction and Engineering Support Branch cc:
Eugene B. Thomas, Jr., Esquire
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MAY 33 1978 0 'stribution:
ocket File ELD NRC PDR IE (3)
Local PDR LWR 84 File bcc:
D. Vassallo J. Buchanan, NSIC Docket No: 50-410 F. Williams T Abernathy, TIC
~
S. Varga .ACRS (16)
W. Kane M. Service Niagara ttohawk Power Corporation ATTN: Nr. Gerald K. Rhode, Vice President System Project Nanagement 300 Erie Boulevard, Hest Syracuse, New York 13202 Gentlemen:
SUBJECT:
(PALITY ASSURANCE PROGRAM FOR NINE tlILE POINT. NUCLEAR STATION - UNIT 2 In the Niagara Mohawk Placer Corporation letter, G. Rhode to E. Case, dated April 26, 1978 you transmitted revisions to the Stone 8 Webster Engineering Corporation's "guality Assurance Program ttanual, Nine Nile Point Nuclear Station - Unit 2." These revisions habe been revieied by the staff and we conclude they are acceptable.
If you have any questions regarding this matter please contact the
.staff's assigned 'licensing project manager.,
Sincerely,
-- 8 M si808g'bing 4a Ao, A. Varga, Chief Vary'teven Light Hater Reactoss Branch No. 4 Division of Project t1anagement cc: See Page 2 CIPPICS~ .DP . A...4.....
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Arvin E. Upton, Esq. "
LeBoeuf, Lamb, Leiby 8 HacRae 1757 N Street, N.
Washington, D. C. 20036 Anthony Z; Roisman, Esq.
Natural Resources 0 fense Council 917 15th Street, N." W.
Washington, D. C. 20005 llr. Richard Goldsmith Syracuse Uni'versi ty College of Law E. I. White Hall. Campus Syracuse, New Yo~ k 13210 T., K. DeBoer, Director 1'echnological Development Programs New York State Energy Office'wan Street Building Core 1 - 2nd Floor State Plaza 'mpire, Albany, New York 12223