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| {{#Wiki_filter:CENG..a joint venture of 0Constellation eDF P.O. Box 63 Lycoming, New York 13093 NINE MILE POINT NUCLEAR STATION January 31, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: | | {{#Wiki_filter: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 |
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| Document Control Desk 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:
| | 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). |
| : 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.
| | 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. |
| 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.1 of 2 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 | | Should you have any questions regarding this submittal, please contact John J. Dosa, Licensing Director, at (315) 349-5219. |
| -Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections | | Very truly yours, Paul M. Swift Manager, Engineering Services PMS/MHS k-OOL NOi- |
| -This Year Absolute Sum of 10 CFR 50.46 Changes APCT = 0 °F APCT = 0 OF APCT =0 OF 0 OF 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.2 of 2 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: | | 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 |
| 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. | | : 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 |
| 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. | | 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 |
| 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.1 of 2 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)2. Notification 2011-03 (GE 14)APCT = 30 OF APCT = -5 OF 30 OF 5 OF B. Prior 10 CFR 50.46 Changes or Error Corrections
| | 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). |
| -This Year 1. Notification 2012-01 (GE14)Absolute Sum of 10 CFR 50.46 Changes APCT= 0 OF APCT =0 OF 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.2 of 2}}
| | 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. |
| | 1 of 2 |
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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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Category:Letter
MONTHYEARNMP1L3608, 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 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 ML24213A1412024-07-31031 July 2024 Requalification Program Inspection 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 NMP2L2880, 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) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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 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 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) 2024-09-04
[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
[Table view] |
Text
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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