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Category:Letter
MONTHYEARNMP1L3570, 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, 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 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
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Docket NRC PDR Local PDR ORB¹3 Rdg KRGoller Docket Ho. 50<<2?0 TJCarter
'Lear CParrish JJiagar a mohawk Power Cor poration JGuibert ATTW: )lr. Gerald K. Fhode . OELD Vice President - Engineering 'I8IE (7) 300 Brie Boulevard 3feat DE I senhut Syracuse, dew York 13202 TBAbernathy JRBuchanan Gent,ler.en: ACRS (16)
BE: l/ino Nile Point., Unit 1 As a rosuit of a recent additional asscasnent of the structuraj, integrity of the lfark I contairment syste~ used in your reactor facilit,y, @embers of our respective technical staffs net in Bethesda on February 26, 1976.
"<<his letter will confim t,he results of these discussions and tho conclusions reached by the HBH staff subsequont,, to the nieeting.
On January,28, 1976, the tfark X owners group specified that the torus support downward load strength,ratios were based on an clastic analysis. Hatios around 1.0 vere not of great concern to you because you believed that a redistribution of loads would occur and that these factor " would be reduced when an ela tic-plastic analysis waa later per forr>ed. On those facilities wit,h strength ratios greater than 0.9, the NHC staff requested furt,her infort..ation which we are currently evaluat.ing.
On << ebruary 19 and ZO, 1976, a nore detailed discussion of the above t,echnical points occurred. After studying details of the st,ress distribution fro: Pcchtel s computer outp>>t, it's our judgment, and your con ultant,s agree that. redistribution of loads r:,ay not.
be significant, for thc wclds at tho top of thc torus columns.
'<<herefore, the r.;argin 'of safety at, these velda are lower than those for other'"lark X components.
Because of this reduced var"xn, the r.cct.in,", in Petheada r 5 called t,o discuss your plans to promptly r ostore a<equate nar;;inc of safct,y for thc'atruct,ure. You <<-.'cscribed and discussed with our staff various oper'atinp r odifications which would reduce the loads, such as usc of an increased dryveii pre.".sur,e and decreased torus
>uter level. Aft,er discussing your planned actions and t,he length of ti:.:e required to provide enhanced safety'Tar~ins usin,", thc, operational actions, you and other r.cnbers of thc t.'ark E o.ner" OPPICC~
8VRNAMCW DATC~
FOrPI ABC 518 (RCT. 9-S3) hECM 0240 0 III 8I OOVCRNMCNT PRIIITINO OPFICCI I874 888 I88
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Niagara Vlolw~lc Power Covporation - 2 <<
J group indicated that you ~jould prompt,ly enhanco safety narpinb by pvessuvinG the containnont to establish a difforontial pressure of at loaat 1 psi bot~rcen tho drytrell atmosphere and torus. You proposed to assur o that. such differential was established by Vonday, Birch l, 1976.
Our tochnical staff hao assessed this pvopoaal and aIrvce srith your tcchnioal repreocntativoo that the eotabliatment of a differential preosuro of at leaot l pai >ril'1 provide a rcduotion in potential loads during a postulated loss of coolant aocidont and an associated restoration of the margins of oafoty so that, the margin of safety is about a facto of'rio.
1'n pleased. with the prompt response by the Uyvk X owners'roup, to our concern that safety nargino be rest.orcd in a pronpt fashion, This, therefore confirao our discussions of yesterday that you will establish by Vonday, lLarch 1, 1976, a differontial pressure of a minir1un of one psi between tho drywell atmosphere and thc torus'apor space and that this differential pveaoure ~rill be naintainod >>hencvor tho rcactov io in oporat;ion, until furt,her author ization by the NBC. 7hia,1rill reopond to our directive of yesterday 'that safety margins for tho 'ot;vucturc bo enhanced progptly.-
Gone of t,he oyotcno may be modified thereafter by a p1r1pback syates to- nininize t,he nit.rogcn requircrlento. Ouv staff will revietr ouch proposal promptly vhon your plans become moro definite. 'ny
-. 'oroovev, Mc also ~rill continuo to work (~1th your staff on prcnpt
'; inp3.er1ontation of your plants for ot,ructur al dodlficationo of the contairL~ent aystcr1o in accordance ~.ith tho oatabliahcd program
, of t.hc Hark I ouner." group.
Sincerely, Bcn C. Buachc, Director Offioc of t;uclcar ficI1otov Ilopulatfon cc; Sce nc.":t. pago OSSICC~ .,DOB,.;,QBB.-...2 ....,.. GELD........,....;....... NRR.:DIR..
SVANAMCW DLZiemann:es JScinto es neman BCRusche oATS ~,P/AIt,. f76,. 2/......,l..7,6..............W.......l..76......................2....i.7..6. ...2/.......l.7.6...
POINI hBC-318 (RST. 9-55) hECM 0240 0 III SI OOVSIINMNNl'tIIINTINOOIXIOP IOTA 444 144
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Niagara Mohawk Power Corporation - 3 CC:
Arvin E. Upton, Esquire LeBoeuf, Lamb, Leiby g MacRae 1757 N Street, N. W.
Washington, D. C. 20036 Anthony Z. Roisman, Esquire Roisman, Kessler and Cashdan 1712 N Street, N. 14.
1(ashington, D. C. 20036 Dr. Nilliam Seymour, Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 99 Washington Street Albany, New York 12207 Oswego City Library 120 E. Second Street Oswego,. New York 13126 Mr. Robert P, Jones, Supervisor Town of Scriba R. D. 84 Oswego, New York 13126
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