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Category:Exemption from NRC Requirements
MONTHYEARML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule ML23208A2422023-09-0101 September 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - FRN ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A2322023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026)- Exemption ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant ML20345A0002020-12-15015 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0210 (COVID-19)) ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20282A3322020-10-15015 October 2020 Extension of Exemption from Specific Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0159 (COVID-19)) NRC 2020-0033, Exemption to 10 CFR Part 26 - Work Hour Controls2020-10-0606 October 2020 Exemption to 10 CFR Part 26 - Work Hour Controls ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 ML20231A5192020-08-27027 August 2020 Exemption from Select Requirements of 10 CFR Part 55, Operators' Licenses (EPID L-2020-LLE-0127 (COVID-19)) ML20219A7512020-08-17017 August 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0129 (COVID-19)) ML20218A7022020-08-0505 August 2020 Request for Exemption from the Not to Exceed Two Years Requirement for the Requalification Program in 10 CFR 55.59(c)(1); ML20202A5312020-07-24024 July 2020 Approval of Exemption from Certain Requirements of 10 CFR Part 26, Fitness for Duty Programs (EPID L-2020-LLE-0080 (COVID-19)) ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20153A0112020-06-15015 June 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L-2020-LLE-0081 to L-2020-LLE-0088 (COVID-19)) NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic ML14126A5942014-06-30030 June 2014 Exemption from the Requirements of 10 CFR 50.61 and Appendix G to 10 CFR Part 50 ML14058B0592014-05-0909 May 2014 Transmittal Letter Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo Clad Fuel Rods ML0611100322006-05-22022 May 2006 Exemption to 10 CFR 50.71(e)(4) ML0505500772005-06-0202 June 2005 Exemption from Certain Requirements of 10 CFR Part 50, Section 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 NRC 2004-0079, Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 2362004-08-0303 August 2004 Request for Withdrawal of Request for Exemptions to 10CFR50.61, Appendices G and H to 10CFR50, Approval of PTS Application for Point Beach, Unit 2 and Withdrawal of Associated License Amendment Request 236 NRC 2004-0026, Request for Exemption to 10 CFR 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979.2004-03-0505 March 2004 Request for Exemption to 10 CFR 50, Appendix R, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979. NRC 2003-0058, License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report2003-06-27027 June 2003 License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report 2024-01-24
[Table view] Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] Category:Technical Specifications
MONTHYEARML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML17159A7782017-07-27027 July 2017 Issuance of Amendment to Approve H*: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region ML17039A3002017-02-22022 February 2017 Issuance of Amendments -Removal of Completed License Conditions and Changes to the Ventilation Filter Testing Program NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-02-12012 February 2016 License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program NRC 2015-0075, License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation2016-01-15015 January 2016 License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation ML15232A2082015-08-25025 August 2015 Correction Letter for Amendment Nos. 253 and 257 ML15195A2012015-07-28028 July 2015 Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control ML15155A5392015-07-14014 July 2015 Issuance of Amendments Concerning Extension of Cyber Security Plan Milestone 8 NRC 2015-0027, Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee..2015-05-28028 May 2015 Response to Request for Additional Information for Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee.. ML15014A2492015-01-27027 January 2015 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation (Tac Nos. MF4353 and MF4354) ML14213A0032014-08-14014 August 2014 Correction to Technical Specification Page 5.6-5 Associated with Amendment Nos. 250 and 254 NRC 2014-0003, License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2014-07-0303 July 2014 License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0202 July 2014 License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14126A3782014-06-30030 June 2014 Issuance of License Amendment Nos. 250 and 254 Regarding Change to Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML14058B0292014-05-0909 May 2014 Issuance of Amendment Nos. 249 and 253 Regarding Use of Optimized Zirlo Fuel Cladding Material NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding2013-06-0404 June 2013 License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013 Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML12362A0092013-01-29029 January 2013 Issuance of License Amendment Nos. 248 and 252 Operations Manager Qualification Requirements NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013 License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012 License Amendment Request 270, Operations Manager Qualification Requirements NRC 2012-0033, License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 22012-04-30030 April 2012 License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 2 NRC 2011-0040, License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements2011-05-0303 May 2011 License Amendment Request 264, Supplement 1, Diesel Fuel Oil Storage Requirements NRC 2010-0181, Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS)2010-11-16016 November 2010 Supplement to License Amendment Request 241 Alternative Source Term Modified License Condition and Technical Specification for Control Room Emergency Filtration System (CREFS) NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power Uprate2010-08-24024 August 2010 License Amendment Request 261, Supplement 7, Extended Power Uprate NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010 License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate NRC 2010-0040, License Amendment Request 261, Supplement 4 Extended Power Uprate2010-04-15015 April 2010 License Amendment Request 261, Supplement 4 Extended Power Uprate NRC 2009-0080, License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information2009-08-20020 August 2009 License Amendment Request 241, Alternative Source Term, Response to Request for Additional Information NRC 2009-0045, Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)2009-04-17017 April 2009 Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab) NRC 2009-0030, License Amendment Request 261, Extended Power Uprate2009-04-0707 April 2009 License Amendment Request 261, Extended Power Uprate NRC-2008-0086, License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum2008-11-25025 November 2008 License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair2008-05-28028 May 2008 License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair NRC 2008-0018, License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification2008-03-31031 March 2008 License Amendment Request 259, Application for Tech Spec Improvement to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activity Technical Specification NRC 2008-0014, Pressure and Temperature Limits Report2008-02-27027 February 2008 Pressure and Temperature Limits Report ML0804303372008-02-26026 February 2008 Technical Specification ML0804303942008-02-19019 February 2008 Tech Spec Page for Amendments 231 and 236 Deletion of Containment Purge Valve Surveillance Requirement ML0731803152007-11-16016 November 2007 Tech Spec Page for Amendments 230 and 235 TSTF- 491, Revision 2, Removal of Main Steam and Feedwater Valve Isolation Times Technical Specification 3.7.2 ML0721802192007-10-18018 October 2007 Technical Specifications, Revises TS 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) to Add the Ferret Code as an Approved Methodology for Determining RCS Pressure and Temperature Limits NRC 2007-0051, License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item..2007-06-29029 June 2007 License Amendment Request 255, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item.. ML0709502652007-04-0404 April 2007 Technical Specification Pages Steam Generator Tube Repair in the Tubesheet Amendment ML0705103122007-02-15015 February 2007 Tech Spec Pages for Amendments 224 and 230 Regarding Core Alterations NRC-2007-0003, Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program2007-01-19019 January 2007 Supplement 1 to License Amendment Request 248: Technical Specification 5.5.8, Steam Generator Program NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations2006-10-23023 October 2006 License Amendment Request 246 - Deletion of Core Alterations ML0626804152006-09-18018 September 2006 Tech Spec Pages to Correction to Amendment 223 Regarding Steam Generator Tube Integrity ML0623501982006-08-22022 August 2006 Technical Specifications, Steam Generator Tube Integrity, MD0194 & MD0195 L-HU-06-029, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-07-13013 July 2006 Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program2006-07-11011 July 2006 LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program ML0616001172006-06-0808 June 2006 Technical Specifications - Issuance of Amendments Inservice Testing Program L-HU-06-023, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-11011 May 2006 Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity NRC-2006-0032, License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals2006-03-0606 March 2006 License Amendment Request 242, Supplement 2 Technical Specification 5.5, Programs and Manuals L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-02-16016 February 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity 2024-01-23
[Table view] |
Text
. b.
Committed to Nuclear Exellence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC NRC 2003-0058 10 CFR 50.12 10 CFR 50.90 June 27, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKETS 50-266 AND 50-301 LICENSE AMENDMENT REQUEST 235 TECHNICAL SPECIFICATION LCO 5.6.5, REACTOR COOLANT SYSTEM (RCS)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
References:
- 1. Letter from NMC to NRC dated March 3, 2003.
- 2. Letter from NRC to NMC dated July 23, 2001.
In Reference 1, Nuclear Management Company, LLC (NMC) submitted requests for exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, and approval of Pressurized Thermal Shock (PTS) application for Point Beach Nuclear Plant (PBNP) Unit 2 and proposed heatup and cooldown limit curves for PBNP Units 1 and 2, in accordance with the provisions of 10 CFR 50.12.
In association with the request for exemptions, PBNP identified that prior to crediting use of the new P/T curves and the associated methodology, a revised reference in PBNP Technical Specifications (TS) 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)", would be needed.
In accordance with 10 CFR 50.90, NMC is therefore submitting this request for an amendment to the TS for PBNP, Units I and 2. The proposed amendment would modify TS 5.6.5, to replace the reference to the NRC letter accepting the current PTLR methodology (Reference 2) with a reference to the issuance date of the NRC safety evaluation accepting the new methodology.
This amendment request is consistent with changes made to NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Technical Specification Task Force TSTF- 419, Revision 0, "Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR".
Attachment I to this letter provides a description, justification, and a significant hazards determination for the proposed change. Attachment II provides the existing Technical Specifications pages marked up to show the proposed change. Attachment IlIl provides revised (clean) Technical Specifications pages.
6590 Nuclear Road ' Two Rivers, Wisconsin 54241 A 0 Telephone: 920.755.2321
NRC 2003-0058 Page 2 NMC requests approval of the proposed license amendment by October 2003, concurrent with the approval of the exemption request submitted March 3, 2003, with the amendment being implemented within 60 days.
This letter contains no new commitments and no revision to existing commitments.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Wisconsin Official.
I declare under penalty of perjury that the foregoing is true and accurate. Executed on June 27, 2003.
A.l y4iaa Site ent LASSOS Attachments:
I. Description and Assessment I. Proposed Technical Specification Change Ill. Revised Technical Specification Pages cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, NRR, USNRC NRC Resident Inspector - Point Beach Nuclear Plant PSCW
NRC 2003-0058 Attachment I Page 1 of 5 DESCRIPTION AND ASSESSMENT OF CHANGE LICENSE AMENDMENT REQUEST 235 TECHNICAL SPECIFICATION LCO 5.6.5, "REACTOR COOLANT SYSTEM (RCS)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)"
POINT BEACH NUCLEAR PLANT, UNITS I AND 2
NRC 2003-0058 Attachment I Page 2 of 5
1.0 DESCRIPTION
This proposed License Amendment Request (LAR) is made pursuant to 10 CFR 50.90 to modify Technical Specifications (TS) 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)".
2.0 BACKGROUND
NMC is requesting that the PBNP TS be modified consistent with the changes described in the staff approved IndustrylTSTF Standard TS Change, TSTF-419 Revision 0 (TSTF-419), "Revise PTLR Definition and References in ITS 5.6.6, RCS PTLR".
TSTF-419 was approved by the NRC on March 21, 2002.
NRC Generic Letter 96-03, "Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits", dated January 31, 1996, allows licensees to relocate the pressure temperature (PIT) limit curves from their plant TS to a PTLR or a similar document. The methodology used to determine the P/T and LTOP system limit parameters must comply with the specific requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR),
be documented in an NRC approved topical report or an NRC approved plant-specific submittal, and be incorporated by reference into the TS. Subsequent changes in the methodology must be approved by a license amendment.
3.0 DESCRIPTION
OF CHANGE Summary of Proposed Technical Specifications Change:
NMC proposes to modify TS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)", to delete the reference to the NRC letter accepting the current methodology used to determine the RCS pressure and temperature limits, and replace it with a reference to the NRC safety evaluation accepting the new methodology.
4.0 ASSESSMENT This amendment request is consistent with TSTF-419, meeting the requirements in TS 5.6.5, to identify either the Topical Report(s) by number and title or the NRC Safety Evaluation for a plant specific methodology by NRC letter and date. The NRC letter currently referenced in TS 5.6.5 is the NRC safety evaluation dated July 23, 2001. This proposed amendment would replace the reference to the July 23, 2001 letter with a reference to the NRC letter that will be issued accepting the revised methodology.
The details of the proposed change and the justification for the finding of no significant hazards are provided in this attachment. Attachments II and IlIl provide the revisions to the affected TS pages.
NRC 2003-0058 Attachment I Page 3 of 5
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Determination In accordance with the requirements of 10 CFR 50.90, Nuclear Management Company, LLC (NMC) (licensee) hereby requests amendments to facility operating licenses DPR-24 and DPR-27, for Point Beach Nuclear Plant (PBNP), Units 1 and 2, respectively.
The purpose of the proposed amendments is to revise TS 5.6.5, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)", to delete the reference to the NRC letter accepting the current methodology used to determine the RCS pressure and temperature limits, and replace it with a reference to the NRC safety evaluation accepting the new methodology.
NMC has evaluated the proposed amendment in accordance with 10 CFR 50.91 against the standards in 10 CFR 50.92 and has determined that the operation of PBNP in accordance with the proposed amendments presents no significant hazards. Our evaluation against each of the criteria in 10 CFR 50.92 follows.
- 1. Operation of PBNP in accordance with the proposed amendments does not result In a significant Increase In the probability or consequences of any accident previously evaluated.
The proposed change references the NRC safety evaluation accepting the new methodology used to determine the P/T limits or LTOP setpoints that have been reviewed and approved by the NRC. Implementation of revisions to Topical Reports would still be reviewed in accordance with 10 CFR 50.59 and, where required, receive NRC review and approval. The proposed change does not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configuration of the facility or the manner in which the plant is operated and maintained. The proposed change does not alter or prevent the ability of structures, systems, and components (SSCs) from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed change does not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the proposed change does not increase the types or amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures. The proposed change is consistent with safety analysis assumptions and resultant consequences. Therefore, it is concluded that this change does not increase the probability of occurrence of an accident previously evaluated.
NRC 2003-0058 Attachment I Page 4 of 5
- 2. Operation of PBNP in accordance with the proposed amendments does not result in a new or different kind of accident from any accident previously evaluated.
The proposed change references the NRC safety evaluation accepting the new methodology used to determine the P/T limits or LTOP setpoints that have been reviewed and approved by the NRC. Implementation of revisions to Topical Reports would still be reviewed in accordance with 10 CFR 50.59 and, where required, receive NRC review and approval. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the changes do not impose any new or different requirements or eliminate any existing requirements.
The changes do not alter assumptions made in the safety analysis. The proposed changes are consistent with the safety analysis assumptions and current plant operating practice. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Operation of PBNP in accordance with the proposed amendments does not result in a significant reduction in a margin of safety.
The proposed change references the NRC safety evaluation accepting the new methodology used to determine the P/T limits or LTOP setpoints that have been reviewed and approved by the NRC. Implementation of revisions to Topical Reports would still be reviewed in accordance with 10 CFR 50.59 and, where required, receive NRC review and approval. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The setpoints at which protective actions are initiated are not altered by the proposed changes. Sufficient equipment remains available to actuate upon demand for the purpose of mitigating an analyzed event.
Conclusion Operation of PBNP in accordance with the proposed amendment will not result in a significant increase in the probability or consequences of any accident previously analyzed; will not result in a new or different kind of accident from any accident previously analyzed; and, does not result in a significant reduction in any margin of safety. Therefore, operation of PBNP in accordance with the proposed amendment does not result in a significant hazards determination.
5.2 Applicable Regulatory Requirements Administrative Controls, per 10 CFR 50.36(c)(5), are "...the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." The technical analysis performed by NMC concludes that the proposed changes to TS 5.6.5 will continue to assure operation of the facility in a safe manner.
NMC concludes that the proposed changes are in accordance with 10 CFR 50.36(c)(5) with regards to use of approved analytical methods and providing the necessary reporting requirements. The proposed changes thus continue to be compliant with the above regulatory requirements.
NRC 2003-0058 Attachment I Page 5 of 5 5.3 Commitments There are no actions committed to by NMC in this document. Any statements in this submittal are provided for information purposes and are not considered to be commitments.
6.0 ENVIRONMENTAL EVALUATION NMC has determined that the information for the proposed amendment does not involve a significant hazards consideration, authorize a significant change in the types or total amounts of effluent release, or result in any significant increase in individual or cumulative occupational radiation exposure.
Accordingly, this proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with this proposed amendment.
NRC 2003-0058 1 Page 1 of 2 PROPOSED TECHNICAL SPECIFICATION CHANGES LICENSE AMENDMENT REQUEST 235 TECHNICAL SPECIFICATION LCO 5.6.5, "REACTOR COOLANT SYSTEM (RCS)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)"
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 MARKUP TS PAGE:
TS 5.6-5
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(1) LCO 3.4.3, -RCS Pressure and Temperature (P/T) Limits" (2) LCO 3.4.6, -RCS Loops-MODE 4" (3) LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10, 'Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)"
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000 and July 23, 201 [ , 20031.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.6 PAM Report When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.
Point Beach 5.6-5 Unit 1 - Amendment No. 2-O7 Unit 2 - Amendment No. 24 NRC 2003-0058 Attachment III Page 1 of 2 PROPOSED TECHNICAL SPECIFICATION CHANGES LICENSE AMENDMENT REQUEST 235 TECHNICAL SPECIFICATION LCO 5.6.5, "REACTOR COOLANT SYSTEM (RCS)
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)"
POINT BEACH NUCLEAR PLANT, UNITS I AND 2 REVISED TS PAGE:
TS 5.6-5
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(1) LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits" (2) LCO 3.4.6, -RCS Loops-MODE 4" (3) LCO 3.4.7, -RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10, 'Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)"
- b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000 and , 2003.
- c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
5.6.6 PAM Report When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.
Point Beach 5.6-5 Unit 1 - Amendment No.
Unit 2 - Amendment No.