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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
[Table view] Category:Annual Operating Report
MONTHYEARNMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report NMP1L3499, CFR 50.46 Annual Report2023-01-27027 January 2023 CFR 50.46 Annual Report NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report NMP1L3444, CFR 50.46 Annual Report2022-01-27027 January 2022 CFR 50.46 Annual Report NMP2L2765, Submittal of 2020 Annual Environmental Operating Report2021-04-23023 April 2021 Submittal of 2020 Annual Environmental Operating Report NMP1L3374, 10 CFR 50.46 Annual Report2021-01-27027 January 2021 10 CFR 50.46 Annual Report NMP1L3336, Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 2019 Radioactive Effluent Release Report2020-04-30030 April 2020 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 2019 Radioactive Effluent Release Report NMP1L3325, 10 CFR 50.46 Annual Report2020-01-27027 January 2020 10 CFR 50.46 Annual Report NMP2L2697, Submittal of 1O CFR 50.59 Evaluation Summary2019-02-12012 February 2019 Submittal of 1O CFR 50.59 Evaluation Summary NMP1L3259, 10 CFR 50.46 Annual Report2019-01-25025 January 2019 10 CFR 50.46 Annual Report NMP1L3212, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-10010 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report NMP1L3197, Submittal of 1O CFR 50.46 Annual Reporting Information2018-01-26026 January 2018 Submittal of 1O CFR 50.46 Annual Reporting Information ML18018B0562018-01-18018 January 2018 Annual Radiological Environmental Operating Report ML18011A6252017-12-11011 December 2017 the 2017 Annual Report of the Ceng Independent Nuclear Advisory Committee to the Ceng Board of Directors NMP2L2617, Transmittal of 2015 Annual Environmental Operating Report2016-04-15015 April 2016 Transmittal of 2015 Annual Environmental Operating Report ML16011A0032016-01-0707 January 2016 Submittal of Annual Report of the Nuclear Advisory Committee NMP2L2579, 2014 Annual Environmental Operating Report2015-04-10010 April 2015 2014 Annual Environmental Operating Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report ML14139A0832014-05-0808 May 2014 Annual Radiological Environmental Operating Report ML14118A0402014-04-11011 April 2014 2013 Annual Environmental Operating Report ML13037A3032013-01-31031 January 2013 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2012 ML13037A3802012-12-17017 December 2012 Attachment 1b, 2012 Annual Report of the Ceng Independent Nuclear Advisory Committee ML12144A4132012-05-15015 May 2012 Transmittal of 2011 Annual Radiological Environmental Operating Report ML12131A5202012-05-0101 May 2012 Radioactive Effluent Release Report, January - December 2011 ML12108A0032012-04-0606 April 2012 2011 Annual Environmental Operating Report ML12039A0942012-01-31031 January 2012 CFR 50.46 ECCS Evaluation Model Annual Reports for 2011 ML11145A0692011-05-13013 May 2011 Submittal of 2010 Annual Radiological Environmental Operating Report ML11123A0172011-04-22022 April 2011 2010 Annual Environmental Operating Report ML1104001942011-01-31031 January 2011 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2010 ML1013806562010-05-0707 May 2010 Submittal of 2009 Annual Radiological Environmental Operating Report ML1013006842010-05-0101 May 2010 Radioactive Effluent Release Report, January - December 2009 ML1013006832010-05-0101 May 2010 Radioactive Effluent Release Report, January - December 2009 ML1011701222010-04-20020 April 2010 2009 Annual Environmental Operating Report ML1003405892010-01-28028 January 2010 CFR 50.46 ECCS Evaluation Model Annual Reports for 2009 ML0913908252009-05-15015 May 2009 2008 Annual Radiological Environmental Operating Report ML0912804332009-05-0101 May 2009 Radioactive Effluent Release Report, January - December 2008 ML0803201512008-01-31031 January 2008 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 ML0712704232007-04-24024 April 2007 Constellation Slides - Nine Mile Point Meeting Annual Assessment Summary 2006-07 ML0710904622007-04-0909 April 2007 Annual Environmental Operating Report ML0514002702005-05-12012 May 2005 Points, Units 1 and 2, 2004 Annual Radiological Environmental Operating Report ML0416800592004-06-0404 June 2004 Units. 1 and 2 - 2003 Annual Financial Reports of Constellation Energy and Long Island Power Authority ML0414504102004-05-13013 May 2004 Annual Radiological Environmental Operating License ML0309905132003-03-31031 March 2003 Transmittal of 2002 Annual Environmental Operating Report ML0212901432002-04-30030 April 2002 Transmittal of 2001 Annual Radiological Environmental Operating Report for Nine Mile Point, Units 1 & 2 ML0213504572002-04-26026 April 2002 Transmittal of 2001 Annual Environmental Operating Report from Nine Mile Point Unit 2 ML18018B0501978-02-27027 February 1978 Annual Environmental Operating Report January 1, 1977 - December 31, 1977 ML17037B6071977-06-30030 June 1977 Letter Regarding Annual Report for 01/01/1976 Through 12/31/1976 and Enclosed Copies of the 6.9.1b(3) Report Which Reflect Programming Modifications ML18018B0491977-02-25025 February 1977 Letter Enclosing the Annual Environmental Operating Report January 1, 1976 - December 31, 1976 ML17037C4701975-06-18018 June 1975 Letter Regarding Guidance for Proposed License Amendments Relating to Refuelings and an Enclosed List of Information Needed to Forecast Requirements for Reviews of Proposed License Amendments Relating to Refueling 2024-01-26
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P.O. Box 63 Lycoming, New York 13093 CENG..
a joint venture of 0Constellation eDF NINE MILE POINT NUCLEAR STATION January 31, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Document Control Desk
Subject:
Nine Mile Point Nuclear Station, LLC Unit Nos. 1 and 2; Docket Nos. 50-220 and 50-410 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2012 Pursuant to the reporting requirements of 10 CFR 50.46(a)(3)(ii), Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting the Emergency Core Cooling System (ECCS) evaluation model annual reports for Nine Mile Point Unit I (NMP1) and Nine Mile Point Unit 2 (NMP2).
These annual reports, provided in Attachments I and 2, summarize the nature of and estimated effect of any changes or errors in the ECCS models for NMP1 and NMP2 for the period January 1, 2012 through December 31, 2012.
Should you have any questions regarding this submittal, please contact John J. Dosa, Licensing Director, at (315) 349-5219.
Very truly yours, Paul M. Swift Manager, Engineering Services PMS/MHS k-OOL NOi-
Document Control Desk January 31, 2013 Page 2 Attachments: 1. Nine Mile Point Unit 1 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2012
- 2. Nine Mile Point Unit 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2012 cc: NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager
ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 Nine Mile Point Nuclear Station, LLC January 31, 2013
ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual report summarizes the nature of and estimated effect of any changes or errors in the Emergency Core Cooling System (ECCS) model for the period January 1, 2012 through December 31, 2012 for Nine Mile Point Unit I (NMPI).
DISCUSSION No changes or errors to the ECCS evaluation model were identified in 2012 for NMPI.
IMPACT Not applicable.
CONCLUSION As documented in Table 1, the NMPI Loss of Coolant Accident analysis Peak Clad Temperature (PCT) remains in compliance with 10 CFR 50.46(b)(1), which requires that the PCT shall not exceed 2200 0 F.
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ATTACHMENT 1 NINE MILE POINT UNIT 1 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 Table 1 LOCA Margin Summary Sheet Nine Mile Point Nuclear Station, LLC Nine Mile Point Unit 1 Evaluation Model: General Electric SAFER / CORCL / GESTR methodology Net PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 °F 0 OF Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 0 OF 0 OF This Year Absolute Sum of 10 CFR 50.46 Changes APCT = 0 OF The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200'F.
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ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 Nine Mile Point Nuclear Station, LLC January 31, 2013
ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 BACKGROUND In accordance with 10 CFR 50.46(a)(3)(ii), this annual report summarizes the nature of and estimated effect of any changes or errors in the Emergency Core Cooling System (ECCS) model for the period January 1, 2012 through December 31, 2012 for Nine Mile Point Unit 2 (NMP2).
DISCUSSION On November 29, 2012, Nine Mile Point Nuclear Station, LLC (NMPNS) was informed by its fuel vendor (GE Hitachi (GEH)) of an error in its Emergency Core Cooling System (ECCS) evaluation model peak clad temperature (PCT) calculation that could affect NMP2. Based on the information provided by GEH, NMPNS determined that correction of the identified errors resulted in a less than 50° increase in calculated PCT. Therefore, the errors did not meet the 30-day reporting requirements delineated in 10 CFR 50.46(a)(3)(ii). A description of the notification regarding the ECCS evaluation model, as detailed by the vendor, is as follows:
GEH Notification Letter 2012-01, PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, Replacing GESTR Fuel Properties:
GESTR-LOCA was considered to be an integral part of the approved GEH ECCS Evaluation Model, with SAFER, for compliance to 10 CFR 50.46. NRC Information Notice (IN) 2011-21 addressed inaccuracies in fuel pellet thermal conductivity as a function of exposure. PRIME fuel rod thermal-mechanical (T-M) performance addresses these concerns. This 10 CFR 50.46 notification estimates the magnitude of the change in PCT due to the change in fuel properties from GESTR to PRIME. Applying this estimated change in Licensing Basis PCT constitutes interim implementation of the PRIME fuel properties as it pertains to the analysis basis Evaluation Model for the plant, pending a plant ECCS-LOCA re-analysis explicitly using PRIME.
IMPACT There is no impact to PCT as a result of the 2012-01 error notification. As such, no Maximum Average Planar Linear Heat Generation Rate adjustments were required to maintain the desired PCT margin with the error in the accepted evaluation model.
CONCLUSION As documented in Table 1, the NMP2 Loss of Coolant Accident analysis PCT remains in compliance with 10 CFR 50.46(b)(1), which requires that the PCT shall not exceed 2200'F.
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ATTACHMENT 2 NINE MILE POINT UNIT 2 10 CFR 50.46 ECCS EVALUATION MODEL ANNUAL REPORT FOR 2012 Table 1 LOCA Margin Summary Sheet Nine Mile Point Nuclear Station Nine Mile Point Unit 2 Evaluation Model: General Electric SAFER / GESTR - LOCA methodology Net PCT Effect Absolute PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections -
Previous Years
- 1. Notification 2011-02 (GE14) APCT = 30 OF 30 OF
- 2. Notification 2011-03 (GE 14) APCT = -5 OF 5 OF B. Prior 10 CFR 50.46 Changes or Error Corrections -
This Year
- 1. Notification 2012-01 (GE14) APCT= 0 OF 0 OF Absolute Sum of 10 CFR 50.46 Changes APCT = 35 OF The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 2200'F.
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