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| SUPPLEMENT NO.1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U.S.ATOMIC ENERGY CO~QHSSION IN THE MATTER OF NIAGARA MOMtK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE NINE MILE POINT UNIT 1 DOCKET NO.50-220 NOVEMBER 15''1974 | | SUPPLEMENT NO.1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U.S.ATOMIC ENERGY CO~QHSSION IN THE MATTER OF NIAGARA MOMtK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE NINE MILE POINT UNIT 1 DOCKET NO.50-220 NOVEMBER 15''1974 |
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| TABLE OF CONTENTS l.0 INTRODUCTION 2.0 REPORT OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)2.,1 Main Steam Line Isolation Valve Leakage 2.2 Reactor Pressure Vessel In-Service Inspection 2.3 Possible Additional Backfit Improvements 3.0 QUALITY ASSURANCE PROGRAM 4cO CONCLUSIONS APPENDICES'PPENDIX A Report of ACRS | | TABLE OF CONTENTS l.0 INTRODUCTION |
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| | ===2.0 REPORT=== |
| | OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)2.,1 Main Steam Line Isolation Valve Leakage 2.2 Reactor Pressure Vessel In-Service Inspection |
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| | ===2.3 Possible=== |
| | Additional Backfit Improvements |
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| | ===3.0 QUALITY=== |
| | ASSURANCE PROGRAM 4cO CONCLUSIONS APPENDICES'PPENDIX A Report of ACRS |
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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
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Category:ACRS Summary Report
MONTHYEARML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C2071974-09-25025 September 1974 Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform. ML17037C4801974-09-13013 September 1974 Letter Transmitting ACRS Report Dated September 10, 1974, on the Application for Conversion of the Provisional Operating License to a Full-Term Operating License for the Nine Mile Point Nuclear Station Unit ML17037C4901974-02-20020 February 1974 Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use ML17037C3691971-03-12012 March 1971 Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level ML17037C3501970-06-19019 June 1970 Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970 1974-09-25
[Table view] 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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23151A3472023-08-21021 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 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 NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-30030 September 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position NMP2L2762, License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2021-05-26026 May 2021 License Amendment Request Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3369, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-12-18018 December 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process NMP2L2716, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-12-26026 December 2019 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors NMP2L2706, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.2019-10-31031 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability NMP1L3278, License Amendment Request - Administrative Changes to the Technical Specifications2019-06-26026 June 2019 License Amendment Request - Administrative Changes to the Technical Specifications RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate2019-05-31031 May 2019 License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. NMP2L2694, Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances2018-12-0606 December 2018 Emergency License Amendment Request: One Time Extension to the High Pressure Core Spray Completion Time and Associated Surveillances NMP1L3192, License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration2018-06-26026 June 2018 License Amendment Request - Revise Technical Specification 3.3.1 for Primary Containment Oxygen Concentration RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) NMP1L3188, License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks2018-02-0909 February 2018 License Amendment Request - Proposed Change to Remove Boraflex Credit from Spent Fuel Racks NMP1L3142, License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-15015 December 2017 License Amendment Request - Revise Technical Specifications to Apply TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NMP2L2660, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change2017-11-0303 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change NMP2L2652, License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note2017-08-22022 August 2017 License Amendment Request - Revise Surveillance Requirement 3.5.1.2 to Remove Note NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 12017-05-31031 May 2017 Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1 NMP2L2641, License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 02017-05-31031 May 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Revision 0 ML17164A1532017-05-31031 May 2017 Enclosure 4B - EAL Red-Line Basis Document for Nine Mile Point Nuclear Station, Unit 1 ML17164A1552017-05-31031 May 2017 Enclosure 4D - EAL Front Matter for Nine Mile Point Nuclear Station, Unit 1 ML17164A1542017-05-31031 May 2017 Enclosure 4C - EAL Basis Document for Nine Mile Point Nuclear Station, Unit 1 JAFP-17-0050, Exigent License Amendment Request to Revise Emergency Action Level HU1.52017-05-19019 May 2017 Exigent License Amendment Request to Revise Emergency Action Level HU1.5 ML17037C4192017-05-11011 May 2017 Amendment to Operating License/Change to Appendix a of Technical Specification Concerning Certain Repairs at Facility and Concomitantly to Allow a Continuation of a Slightly Lower Water Level in the Reactor... NMP2L2643, License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes2017-04-0505 April 2017 License Amendment Request-Adoption of TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process NMP2L2640, License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-02-28028 February 2017 License Amendment Request - Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2639, Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-032017-02-17017 February 2017 Supplement to License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy- Nuclear 10 CFR Part 21 Safety Communication SC05-03 NMP1L3122, License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup2017-01-0303 January 2017 License Amendment Request - Proposed Changes Regarding Partial Length Fuel Rod (PLR) Burnup NMP2L2584, License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-032016-12-13013 December 2016 License Amendment Request - Proposed Revision to Technical Specification in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03 NMP2L2634, Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications2016-11-26026 November 2016 Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications 2023-08-21
[Table view] Category:Safety Evaluation Report
MONTHYEARML0628901292006-09-30030 September 2006 NUREG-1900, Vol 1 Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station Units 1 & 2 ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application ML17037B5881978-05-26026 May 1978 Letter Regarding a Request for Evaluation of the Effect on Unit 1 Containment of Multiple Subsequent Actuations of Safety/Relief Valves Following a Postulated Isolation Event ML17037B9231977-08-22022 August 1977 Letter Regarding a Report Describing the Unit 2 Reactor Building Polar Crane and a Review of the Information Provided in a July 20, 1977 Letter ML17037B6251977-06-0202 June 1977 Letter Regarding a Review of Licensee Responses to Previous Generic Request for Information Relative to the Electrical Power Distribution Systems and an Enclosed Safety Evaluation and Statement of Staff Positions ML17037B9601976-03-0505 March 1976 Letter Regarding a Review of the Design and Analysis Methods for the Revetment-Ditch System and Requesting a First Review and Approval of Section 4, Physical Model Study. ML17037C4771974-11-15015 November 1974 Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License ML17037C0291973-06-15015 June 1973 Letter Regarding the Safety Evaluation of Niagara Mohawk Power Corporation Application for a Permit to Construct the Nine Mile Point Nuclear Station Unit 2 2006-09-30
[Table view] |
Text
Docket No.50-220 Gentlemen:
full-tenn operating license for Unit 1 of your Nine Mile Point priginal Signed November 15, 1974 DISTRIBUTION:
AEC PDR DMuller Local PDR KRGoller Docket TJCarter ORBi/3 Rdg OIS (5 copies)HJMcAlduff RBrodsky.Niagara Mohawk Power Corporation SHanauer CStephens (2 copies)ATTN: Mr., Philip D.Raymond AGiambusso CJDeBevec Vice President-Engineering FSchroeder SATeets 300 Erie Boulevard Hest RBoyd (4 copies)NDube Syracuse, New York 13202 DKnuth (2 copies)'Jones (2 cps)RMaccary (2 copies)CLong RTedesco (2 copies)RVollmer HDenton (2 copies)RSchemel The Directorate of Licensing has issued the enclosed Supplement VBenaroya BGrimes No.1 to the Safety Evaluation Report on your application for a GLainas SPawlicki TIppolito JKastner Nuclear Station.SVarga JOsloond Sincerely, RO (8)TEnglehardt George Lear, Chief Operating Reactors Branch 83 Directorate of Licensing
Enclosure:
Supplement No.1 to Safety Evaluation Report cc: See next page@p~-EEE ATTACHED FOR OGC CONCURRENCE OF-11//74 ORB./(3..EATR.k4.....1/./+/Z4,....
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4 V, S, OOVNRHMNNT PlllNTINO OPPICNI 1S74 SRS lSS I L f 1 cdl4)<<41'I f ,f Niagara:fohawk Power Corporation November 15, 1974 cc: w/enclosure Hr.Arvin E.Upton, Esquire Le3oeuf, Lamb, Leiby 6 tfacRae 1757 N Street, N.U.Washington, D.C.20036 Hr.Robert P.Jones, Supervisor Town of Scriba R.D.04 Oswego, New York 13126 Hiss Juanita I ersey, Librarian Oswego City Library 120 E.Second Street Ommgo, New York 13126 Dr.Vill%am E.Seymour Staff Coordinator New York State Atomic Energy Council New York State Department of Commerce 99 Tfashington Street Albany, New York 12210 OPRICE5H'VRHAMC~
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SUPPLEMENT NO.1 TO THE SAFETY EVALUATION REPORT BY THE DIRECTORATE OF LICENSING U.S.ATOMIC ENERGY CO~QHSSION IN THE MATTER OF NIAGARA MOMtK POWER CORPORATION CONVERSION FROM PROVISIONAL OPERATING LICENSE TO FULL-TERM OPERATING LICENSE NINE MILE POINT UNIT 1 DOCKET NO.50-220 NOVEMBER 151974
TABLE OF CONTENTS l.0 INTRODUCTION
2.0 REPORT
OF ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)2.,1 Main Steam Line Isolation Valve Leakage 2.2 Reactor Pressure Vessel In-Service Inspection
2.3 Possible
Additional Backfit Improvements
3.0 QUALITY
ASSURANCE PROGRAM 4cO CONCLUSIONS APPENDICES'PPENDIX A Report of ACRS
1.0 INTRODUCTION
The AEC Regulatory staff's Safety Evaluation Report (SER), in the matter of the Niagara Mohawk Power Corporation (herein'I referred to as NMPC or the licensee)application for conversion of Provisional Operating License No.DPR-17 to a full-term I operating license for Nine Mile Point Unit 1 (NMP-1)was issued on July 3, 1974.Copies of this report were made available to the Advisory Committee on Reactor Safeguards (ACRS or Committee) to assist it in its review of this application.
The Committee 2.0 completed its review of the licensee's application in September 1974 and reported its findings to the Commission by letter dated.September 10, 1974.REPORT OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS A copy of the ACRS report to.the Commission is included's Appendix A.Me have considered the comments and recommendations made by the ACRS in this report and the actions which we have taken or will'take relative to these comments and recommendations are described in the following paragraphs.
The Committee identified three matters for further surveillance:
these matters consist of maintaining leak tightness of main steam line isolation valves;'possible improvements in accessibility for in-service inspection of the reactor pressure vessel to assure continued vessel integrity; and consideration to the possible advisability of additional backfitting where significant and practical safety improvements can be trade.The Committee concluded that there
F exists reasonable assurance that the Nine Mile Point Nuclear Station Unit 1 can continue to be operated at power level's.up to 1850 1%it without undue risk to the health and safety of the 2.1 public.Moreover, the Committee concurred in conversion, of the present provisional operating license to a full-term operating license.Main Steam Line Isolation Valve Leaka e The Committee indicated its awareness of the difficulty that has been experienced at EP-1 in maintaining the required leak tightness of the main steam line isolation valves (MSLIV)and stated that the Regulatory staff should continue to follow this matter closely.The licensee stated its belief that leakage through these valves will be maintained at acceptable rates below the Technical Specification limits as a result of changes in maintenance procedures involving the valve seats and plugs, initiated during the 1974 refueling shutdown.The next leakage rate test of the ll'SLIVs'will be performed during the 1975 refueling shutdown.The Regulatory staff will follow this mat'ter to confirm'that the problem, is corrected.
l 2.2 Reactor Pressure Vessel In-Service Ins ection The Committee expressed its belief that additional means for assuring continued vessel integrity, including possible improvement in accessibility for inspection, should continue to be actively studied and implemented to the degree practical.
The licensee has stated its'interest to continue to seek possible improvements in the matter of vessel acchssibility and to implement such
improvements to the degree practical.
Our on-going review oi the operating facility will monitor progress in this area..2.3 Possibl6 Additional Backfit Im rovements'The Committee recommended that the Regulatory staff and the licensee'ive further consideration to additional backfitting where significant and practical safety improvements can be made.The licensee has indicated that it has a continuing program'of review to determine the conCormance of RP-1 with new Regulat:ory Guides as these are issu'ed.'he Regulatory staff will continue its on-going review of~~RP-l, including consideration of backfitting where significant
,.3.0 and,practical safety improvements can be made.UALITY ASSURANCE (A)PROGKQf As stated in our SER, we have reviewed the licensee's QA Program and concluded that it is acceptable.
The licensee's QA Program was described in four different submittals.
This information.was superseded by the licensee's submittal of August 28,'974, entitled,"Tenth Supplement to the Final Safety Analysis Report" which ,consolidates and unifies the earlier submittals.
We have reviewed and determined that the Tenth Supplement to the FSAR is 4:0 the same as the QA Program which we had previously reviewed and found acceptable.
C CONCLUSIONS Our conclusions as stated in the Safety Evaluation Report remain unchanged..
C APPENDIX A n n f7'>fl P3 D1 September 10, 1974~Honorable Dixy Lee Ray Chairman U.S.Atomic Energy Commission Mashington, D.C.20545 ADYlSORY COMMlTTEE ON REACTOR SAFEGUARDS UNlTED STATES ATOMlC ENERGY COMMlSSlON VifASHlMkTOH, D.C:.10545 a pJ 0 fj I jul CD
Subject:
REPORT ON NINE MILE.POINT NUCLEAR STATION UN'
Dear Dr.Ray:
At its 173rd meeting, September 5-7, 1.974, the Advisory Committee'on Reactor Safeguazds complete a rev ew o d i f the application by the Niagara Mohawk Power Corporation for conversion o s f its Nine Mile Point Nuclear Station Vnit 1~1~provisiona opera 1ng c 1 tin license to a full-tean ooerating l.icense.The app 1-cation also was considered at a Subcommittee meeting in as ng on, July 29, 1974.During ltd review, the Committee had the benefit of discus-sions with representat ves o i f the Niagara Mohawk Power Corporation, General d the Electric Company, an t e d he AEC Regulatory Staff.The Committee also ha t e benefit oE the documents l.isted.The Committee previous y iscusse project in an operating license report of p*f A ri 1 17 1969 and in subsequent xeports dated June 16, 1970 and Februazy 6, 1971.In its zev1ewp t e omm h C ittee evaluated the operation and performance of h't ith'rticular emphasis on the response of the app 1can o past recommendations for improvements in safety relate sys ems.Un t s anon-e U i 1 i on-jet pump boiling water.reactor of 1850~M(t)rated power leve.ommexc1a 1 C 1 power operation of-the plant was begun 1n However The operating is ory o h'of the unit has been generally satisfactory.
ountezed o o eratin roblems or design deficiencies have been encoun a number of operat ng pro during the approximately five year pexiod o=power opera ion.rackin of a coxe spray nozzle safe end;development o crac s these are: crac 1ng o a c lu ishness.'failure of: th steam dryer assembly;contxol.rod scram s ugg1s i.xn e s ntzol rods to remain fully inserted aEter scram, increased control.some con zo r to assure rotection for a pos-xod'operating restrictions found necessary to assure p 1 d d dro accident.feedwatex contxol deficiency, with resultant b xelief valve steam floodin of steam lines;torus baffle dislocation y xe oo 1ngo s failure of a relief valve to reclose, All discharge into the torus;and, fai ure o ril corrected.
Reactor of these deficiencies appear to have been satisfactorily coxrecte.a availability has averaged approximately 667..
~e Honorable Dixy Lee Ray.C r'0 September 10, 1974 Difficulty also has been experienced in respect to repeated occurrences of excessive'leakage rates of the main steam isolation valves under'test con-ditions.The applicant now proposes to remachine the valve seats and plugs to an improved configuration and believes that this, together with the probable low levels of residual stressesnow existing in these valves, wi'll enable maintenance of acceptable leakage rates"in the future'.-This matter should be followed closely by the Regulatory Staff.a A number of design improvements have been accomplished or comnitted to since operation began.Among the most significant of these from the point of view of safety are the following.
The feedwoter" system has been modified also to serve as an additional emergency core cooling system for small breaks;emergency power for this system is supplied by an offsite source of hydro-electric power.'fuel cask drop protection system has been designed and approved, and installation will be completed before shipment of spent fuel is undertaken.
A containment atmosphere dilution (CAD)system for combustible gas control will be installed and available for operation in 1976.An ad-ditional primary pressure boundary leak detection system has been added, and position'indication in the control room for the contaitunent vacuum breaker valves has been provided.Approximately one-fifth of the reactor 7x7 fuel bundles have been replaced with 8x8 fuel;through additional reloads, the core eventually is to consist entirely of,8x8 fuel.Because of the relatively limited accessibility for in-service inspection of the reactor pressure vessel, the Committee wishes to emphasize again its belief that additional means for assuring continued vessel integrity, in-cluding possible improvement in accessibility, should continue,to be actively studied'and implemented to the degree practical.
The Committee recotrrnends that the Regulatory Staff and the applicant give turther consideration to the possible advisability of additional backfitting of Unit 1 where s'ignificant and practical safety improvements can bc made.The Committee believes that, in view of the generally satisfactory operating experience to date and the'improvements'made in the plant'as noted herein, and subject to the above comments and-those in previous ACRS reports on this plant, there exists reasonable assurance that the Nine Mile Point"'-Nuclear Station Unit 1, can continue to be operated at power levels up to 1850 MM('t)without undue risk to the health and safety of'he public.The Committee concurs in conversion of the present provisional operating license to a full-term operating license.Sincerely yours, M.R.Stratton Choirman
References:
Sec Page 3
~+)'~~Honorable Dixy Lee Ray e&3%0 September 10.'974 References!
1.Niagara Mohawk Power Company Technical Supplement to Petition for Conversion from Provisional Operating, License to Full-Term Operating License dated July 1972.2.Applicant'nvironmental Report, Operating License Stage, Conversion to Full-Term Operating License, June 1972.3.Amendments 1 through 3 to Application for Full-Term Operating License.4.Directorate'f Licensing Safety Evaluation Report dated July.3, 1974.5~Directorate of'icensing letter dated July 3, 1974 concerning list of outstanding items in connection with their review of application for Full-Term Operating License.6.Niagara Mohawk Power Corporation letter dated November 20, 1972 con-cerning Fuel Densification and its Effect on Reactor Operation Including Transients and Postulated Loss-of-Coolant Accident.
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