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| {{#Wiki_filter:g REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>DISTRIBUTION FOR INCOMING MATERIAL 50-410 REC: CASE E G ORG: RHODE G K DOCDATE:-06/08/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 06/13/78 4 DQCTYPE: LETTER-NOTARIZED: | | {{#Wiki_filter:g REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS > |
| NO COPIES RECEIVED SUBJECT.'TR 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 DISTRIBUTION OF THIS MATERIAL F PSAR/FSAR AMDTSAND RELATED CORESPONDENCE (DISTRIBUTION CODE B001)REVIEWER INITIAL: XJM ISTR IBUTOR INITIAL: A IS AS FOLLOWS'++++++<++++w+wwwwe | | 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 |
| 'QR ACTION: INTERNAL: EXTERNAL: ASST DIR VASSALLQ4+LTR ONLY(i>PR KANE4<LTR ONLY(i)REG F IL LTR ONLY<1)++LTR ONLY(2>OPERATOR LIC BR44LTR ONLY<i)QAB++LTR ONLY(1)MIPC++LTR ONLY<1)MECH ENG BR~+LTR ONLY(1>MATERIAL ENG BR+4LTR ONLY<2)REACTOR SYSTEMS BR++LTR ONLY(i CORE PERFORMANCE BR4~LTR ONLY<AUXILIARY SYS BR4+LTR ONLY(1>I 8(C SYSTEMS BR4+LTR ONLY(i)AD FOR SITE TECH>+LTR ONLY(4>ACCIDENT ANALYSIS44LTR-ONLY<1)RAD ASSESSMENT BR4+LTR ONLY(1>LPDR'S OSWEGO'Y+4LTR ONLY(i)TIC++LTR ONLY(1)NSIC44LTR ONLY(1)ACRS CAT B4+LTR ONLY(16>BR CHIEF LWRI4 BC+>LTR ONLY(i)LIC ASST SERVICE++LTR ONL'Y<1)NRC PDR44LTR ONLY<1)GELD>+LTR ONLY(i>EMERGENCY PLAN BR++LTR ONLY<i).CASE++LTR ONLY(1>AD FOR ENGw4LTR ONLY<i)STRUCTURAL ENG BR~>LTR ONLY(i>AD FOR.REAC SFTY<<LTR ONLY(1)ANALYSIS BR+>LTR ONLY(i>1 AD FOR PLANT SYSTEMS+<LTR ONLY CONTAINMENT SYSTEMS~+LTR ONLY(POWER SYS BR4%LTR ONLY<1)AD FOR SITE ANLYS>>LTR ONLY(i>EFFLUENT TREAT tSYS<+LTR ONLY<i KIRKWOOD>+LTR ONLY(1)DISTRIBUTION: | | DQCTYPE: LETTER - NOTARIZED: NO COPIES RECEIVED 1 |
| LTR 56 ENCL 0 SIZE: 1P CONTROL NBR: 781650034 THE END%%%%%%%%%%%%%%4%%%%%%%%%4t%0%%%%%% | | 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~- |
| S NUCLEAR REGULATORY COMMISSION C'AILY ACCESSION L'IST" 05/IO/78 PAGE FILE LiOCA TIOM 96 8125-0322 ETTER P TASK MBR-FI CHE M BR NOTARIZED:
| | PLANT NAME: NINE MILE POINT UNIT 2 REVIEWER INITIAL: XJM ISTR IBUTOR INITIAL: |
| 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 EHO P TASK MBR-II FICHE NBR NOTARIZED NO LPDR-NO CLASS=RECP AFFILIATION-NRC ORG AFFILIATION:
| | A DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS'++++++<++++w+wwwwe F |
| NRC TASK MBR.FI CHE MBR MOTARI ZED-LPDR.NO NO CLASS: I RECP 4 FF IL IA TI OM-NRC ORG AFFILIATION:
| | PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE B001) 'QR ACTION: ASST DIR VASSALLQ4+LTR ONLY(i> BR CHIEF LWRI4 BC+>LTR ONLY(i) |
| NRC OR SUBMISSION TO THE SEABROOK BOARD~K 02 7333-00'99 EMO OR SUBMISSION TO THE SEABROOK BOA RDe NIAGARA MOHAWK POWER CORPORATION NIAGARA~MOHAWK 300 ERIE BOULEVARD.
| | PR KANE4<LTR ONLY(i) LIC ASST SERVICE++LTR ONL'Y< 1) |
| WEST SYRACUSE.N.Y.13202 June 8, 1978 a~C~/ye~o Jg Mr.Edson G..Case, Acting Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | 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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| ==Dear Mr.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: 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. | | K Pl 7333-0099 TASK MBR- II EHO FICHE NBR P NOTARIZED NO LPDR- NO CLASS= |
| 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 PEF/szd 78165003'e I Igy 0 T 1 L~p 6p,R RSCy'Ip 0 Cy/p+~*~4 Docket No.50-410 NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA.PENNSYLVANIA 19406 Mg 3f519 Niagara Mohawk Power Corporation ATTN: Mr.G.K.Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Gentlemen: | | 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 |
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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: |
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| ==Subject:== | | ==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. | | Rock Stress Evaluation (Your letter of April 28, 1978) |
| 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. | | Thank you for your letter, referenced above, which forwarded a final report pursuant to 10 CFR 50.55(e) regarding the subject matter. |
| Sincerely, cc: Eugene B.Thomas, Jr., Esquire obert T.Carlson, Chief Reactor Construction and Engineering Support Branch yL v)~~P I Docket No: 50-410 0'stribution: | | 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. |
| ocket File NRC PDR Local PDR LWR 84 File D.Vassallo F.Williams S.Varga W.Kane MAY 33 1978ELD IE (3)bcc: J.Buchanan, NSIC T~Abernathy, TIC.ACRS (16)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: | | 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:== |
| (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. | | (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, Vary'teven A.Varga, Chief Light Hater Reactoss Branch No.4 Division of Project t1anagement cc: See Page 2 CIPPICS~SURNAME&.DP.A...4..... | | If you have any questions regarding this matter please contact the |
| ga....CATS'5J22/.78 NRC FORbf 318 (9.76)NRCM 0240 6 UI S OOVSRNMSNT PRINTINO OPPICSI ISTS SSS,SSS ia I gh$)I h I~LI I I-I I I-~'F'I I'" h~I I II~tF pt , Iq h I It r~F I II I II 4 ,+*-I~F I I~h I I I I=-I I F I'll II I 4<<%I I'l I II g$0~(~p gQ(.'" 4<<I~I I p II I*I Id(W'<<hV@i, F V I I'f]/'g tA I 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'mpire, State Plaza Albany, New York 12223}} | | .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.... |
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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}} |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request 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 . 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 2024-09-12
[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