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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2022-177, Subsequent License Renewal Application - Second Annual Update2022-11-28028 November 2022 Subsequent License Renewal Application - Second Annual Update L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 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 ML22193A1142022-09-12012 September 2022 Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1 L-2021-147, Subsequent License Renewal Application - Aging Management Supplement 3 Revision 12021-07-26026 July 2021 Subsequent License Renewal Application - Aging Management Supplement 3 Revision 1 L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021 Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses L-2021-113, Subsequent License Renewal Application - Aging Management Supplement 32021-05-27027 May 2021 Subsequent License Renewal Application - Aging Management Supplement 3 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 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses ML20329A2142020-11-16016 November 2020 Enclosure 1, Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application Enclosures Summary ML20329A2642020-11-16016 November 2020 Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version) ML20329A2192020-11-16016 November 2020 Enclosure 2, Affidavits Supporting Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 ML20329A2482020-11-16016 November 2020 Enclosure 3, Attachment 2, Appendix E Applicant'S Environmental Report Subsequent Operating License Renewal Point Beach Nuclear Plant Units 1 and 2 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 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2018-0028, NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2018-07-30030 July 2018 NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements NRC 2018-0001, Transmittal of Construction Truss License Amendment Request Document2018-04-12012 April 2018 Transmittal of Construction Truss License Amendment Request Document NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency2018-03-30030 March 2018 License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency NRC 2017-0043, License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants2017-08-31031 August 2017 License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants NRC 2017-0028, License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2017-06-23023 June 2017 License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances2017-03-31031 March 2017 License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2016-07-29029 July 2016 License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC-2016-0009, License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves2016-03-10010 March 2016 License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves 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 NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-27027 March 2015 LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process NRC 2014-0075, Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog2014-12-0808 December 2014 Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog 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 NRC 2013-0092, License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 8052013-09-16016 September 2013 License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805 NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 22013-06-26026 June 2013 Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3 ML13182A3502013-06-26026 June 2013 License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3 NRC 2013-0028, License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 32013-06-26026 June 2013 License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 3 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) 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 2012-0073, License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change2012-09-17017 September 2012 License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012 License Amendment Request 270, Operations Manager Qualification Requirements NRC 2012-0040, License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change2012-06-18018 June 2012 License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change NRC 2011-0066, License Amendment Request 254, Removal of the Table of Contents from Technical Specifications2011-06-23023 June 2011 License Amendment Request 254, Removal of the Table of Contents from Technical Specifications NRC 2010-0189, License Amendment Request 261, Extended Power Uprate Response to Request for Clarification2010-12-21021 December 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Clarification NRC 2010-0154, License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information2010-09-28028 September 2010 License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information NRC 2010-0146, License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-09-28028 September 2010 License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate NRC 2010-0145, License Amendment Request 261, Supplement 9 Extended Power Uprate2010-09-21021 September 2010 License Amendment Request 261, Supplement 9 Extended Power Uprate NRC 2010-0132, License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information2010-09-0101 September 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information NRC 2010-0133, License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change2010-08-12012 August 2010 License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change 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 2010-0084, License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan2010-07-0808 July 2010 License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan 2023-09-19
[Table view] Category:Technical Specification
MONTHYEARL-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML22140A1342022-05-20020 May 2022 Attachment 2 - Proposed Technical Specification Changes (Mark-Up) ML22140A1372022-05-20020 May 2022 Attachment 3 - Proposed Technical Specification Bases Changes (Mark-Up) 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-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 2018-0028, NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2018-07-30030 July 2018 NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements NRC 2018-0025, Technical Specification Bases Change Summary2018-05-0202 May 2018 Technical Specification Bases Change Summary ML16349A0802017-01-30030 January 2017 Issuance of Amendments for Elimination of Technical Specifications 3.7.14, Primary Auxiliary Building Ventilation NRC 2016-0038, Technical Specifications Bases Change Summary for 20152016-08-23023 August 2016 Technical Specifications Bases Change Summary for 2015 NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2016-07-29029 July 2016 License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC 2015-0044, Submits Technical Specification Bases Change Summary2015-08-11011 August 2015 Submits Technical Specification Bases Change Summary NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-27027 March 2015 LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process NRC-2014-0060, Submittal of Technical Requirements Manual Change Summary2014-08-21021 August 2014 Submittal of Technical Requirements Manual Change Summary NRC-2014-0059, Technical Specification Bases Change Summary2014-08-21021 August 2014 Technical Specification Bases Change Summary NRC 2013-0082, Technical Specification Bases Change Summary2013-08-28028 August 2013 Technical Specification Bases Change Summary NRC 2012-0045, Technical Specification Bases Change Summary2012-06-12012 June 2012 Technical Specification Bases Change Summary 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 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-02-25025 February 2010 License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate 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 2009-0042, Supplement to License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LBLOCA) Analyses Using Astrum2009-04-0808 April 2009 Supplement to License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LBLOCA) Analyses Using Astrum NRC 2008-0044, Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control2008-07-24024 July 2008 Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control NRC 2008-0044, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control2008-07-24024 July 2008 License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control NRC 2008-0048, Technical Specification Bases Change Summary from January 1, 2007 Through June 30, 20082008-06-27027 June 2008 Technical Specification Bases Change Summary from January 1, 2007 Through June 30, 2008 NRC 2007-0034, License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves2007-07-12012 July 2007 License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves NRC 2007-0052, Technical Specification Bases Change Summary2007-06-29029 June 2007 Technical Specification Bases Change Summary NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report2006-12-14014 December 2006 License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report ML0514003852004-10-0808 October 2004 Enclosure IV Attachments 1 & 2 Point Beach Revised EAL Submittal. Attachment 1: Red Line of the Technical Basis Document. Attachment 2: Clean Copy of the Technical Basis Document NRC 2004-0062, Technical Specifications Bases Revisions2004-06-10010 June 2004 Technical Specifications Bases Revisions NRC 2004-0034, License Amendment Request 239 Technical Specification Surveillance Requirements SR 3.8.4.6 and SR 3.8.4.7, DC Sources - Operating2004-04-0808 April 2004 License Amendment Request 239 Technical Specification Surveillance Requirements SR 3.8.4.6 and SR 3.8.4.7, DC Sources - Operating ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process NRC 2003-0033, Technical Specification Bases Revisions2003-04-0909 April 2003 Technical Specification Bases Revisions ML0233704602002-11-29029 November 2002 Technical Specifications for Amendment Nos. 207 and 212, Increase the Licensed Reactor Core Power Level NRC 2002-0108, Technical Specification Bases Revisions2002-11-10010 November 2002 Technical Specification Bases Revisions NRC 2002-0081, License Amendment Request 229 Technical Specifications LCO 3.5.2, ECCS - Operating, & LCO 3.5.3, ECCS - Shutdown2002-09-12012 September 2002 License Amendment Request 229 Technical Specifications LCO 3.5.2, ECCS - Operating, & LCO 3.5.3, ECCS - Shutdown NRC 2002-0040, Technical Specification Bases Revisions2002-05-13013 May 2002 Technical Specification Bases Revisions ML0209105352002-03-29029 March 2002 Technical Specification Pages, Point. Beach, Units 1 and 2 - Amendment 203 and 208 NRC 2002-0010, Technical Specification Bases B3.3.1 Revision for Point Beach Nuclear Plant, Units 1 and 22002-01-17017 January 2002 Technical Specification Bases B3.3.1 Revision for Point Beach Nuclear Plant, Units 1 and 2 2023-09-19
[Table view] Category:Amendment
MONTHYEARL-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML22140A1342022-05-20020 May 2022 Attachment 2 - Proposed Technical Specification Changes (Mark-Up) 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 2018-0028, NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2018-07-30030 July 2018 NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML16349A0802017-01-30030 January 2017 Issuance of Amendments for Elimination of Technical Specifications 3.7.14, Primary Auxiliary Building Ventilation NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2016-07-29029 July 2016 License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-27027 March 2015 LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process NRC 2009-0042, Supplement to License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LBLOCA) Analyses Using Astrum2009-04-0808 April 2009 Supplement to License Amendment Request 258, Incorporate Best Estimate Large Break Loss of Coolant Accident (LBLOCA) Analyses Using Astrum NRC 2008-0044, Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control2008-07-24024 July 2008 Point Beach, Units 1 & 2, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control NRC 2008-0044, License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control2008-07-24024 July 2008 License Amendment Request No. 247, Transmittal of Changes to Technical Specifications Spent Fuel Pool Storage Criticality Control NRC 2007-0034, License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves2007-07-12012 July 2007 License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report2006-12-14014 December 2006 License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report NRC 2004-0034, License Amendment Request 239 Technical Specification Surveillance Requirements SR 3.8.4.6 and SR 3.8.4.7, DC Sources - Operating2004-04-0808 April 2004 License Amendment Request 239 Technical Specification Surveillance Requirements SR 3.8.4.6 and SR 3.8.4.7, DC Sources - Operating ML0404204242004-01-30030 January 2004 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0233704602002-11-29029 November 2002 Technical Specifications for Amendment Nos. 207 and 212, Increase the Licensed Reactor Core Power Level NRC 2002-0081, License Amendment Request 229 Technical Specifications LCO 3.5.2, ECCS - Operating, & LCO 3.5.3, ECCS - Shutdown2002-09-12012 September 2002 License Amendment Request 229 Technical Specifications LCO 3.5.2, ECCS - Operating, & LCO 3.5.3, ECCS - Shutdown ML0209105352002-03-29029 March 2002 Technical Specification Pages, Point. Beach, Units 1 and 2 - Amendment 203 and 208 2023-09-19
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Nuclear Management Company, LLC NMC *Point Beach Nuclear Plant Commiotted to NuclearEcellence 6610 Nuclear Road Two Rivers, WI 54241 NRC 2002-0081 10 CFR 50.90 September 12, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Dockets 50-266 and 50-301 Point Beach Nuclear Plant, Units 1 and 2 License Amendment Request 229 Technical Specification LCO 3 5.2, ECCS - Operating, and LCO 3.5.3, ECCS - Shutdown In accordance with the provisions of 10 CFR 50.90, Nuclear Management Company, LLC (NMC) is submitting a request for an amendment to the Technical Specifications (TS) for Point Beach Nuclear Plant, Units 1 and 2.
The proposed amendment would revise TS 3.5.2, ECCS - Operating, and TS 3.5.3, ECCS Shutdown, to add a surveillance to verify the emergency core cooling system (ECCS) piping is full of water every 31 days. This proposed amendment is consistent with NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 2.
NMC requests approval of the proposed license amendment by March 31, 2003, with the amendment being implemented within 45 days. The approval date was administratively selected to allow for NRC review but the plant does not require this amendment to allow continued safe full power operation.
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 correct.
Executed on September 12, 2002.
iD"ekm dent RDS/kmd
NRC 2002-0081 Page 3 bcc: R. A. Anderson A. J. Cayia T. J. Carter (ENG)
B. Day K. M. Duescher (3) J. Freels R. R. Grigg (P460) M. E. Reddemann L. Schofield (JOSRC)
D. Schoon T. H. Taylor D. A. Weaver (P129)
T. J. Webb E. J. Weinkam III File
ATTACHMENT I DESCRIPTION OF CHANGES LICENSE AMENDMENT REQUEST 229 TECHNICAL SPECIFICATION LCO 3.5.2, ECCS - OPERATING, AND LCO 3.5.3, ECCS - SHUTDOWN POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
NRC 2002-0081 Page 2 of 5
1.0 INTRODUCTION
This License Amendment Request (LAR) is made pursuant to 10 CFR 50.90 to modify Technical Specification (TS) 3.5.2, ECCS - Operating and TS 3.5.3, ECCS - Shutdown, to add a surveillance to require verification that the Emergency Core Cooling System (ECCS) piping is full of water every 31 days.
2.0 BACKGROUND
The function of the ECCS is to provide core cooling and negative reactivity to ensure that the reactor core is protected after any of the following accidents:
- a. Loss of coolant accident (LOCA), coolant leakage greater than the capability of the normal charging system;
- b. Rod ejection accident;
- c. Loss of secondary coolant accident, including uncontrolled steam release; and
- d. Steam generator tube rupture (SGTR).
The addition of negative reactivity is designed primarily for the loss of secondary coolant accident where primary cooldown could add enough positive reactivity to achieve criticality and return to significant power.
System License Basis In Modes 1, 2, and 3, two independent (and redundant) ECCS trains are required to ensure that sufficient ECCS flow is available, assuming a single failure affecting either train. Additionally, individual components within the ECCS trains may be called upon to mitigate the consequences of other transients and accidents.
An ECCS train consists of, a safety injection (SI) subsystem, and a residual heat removal (RHR) subsystem. Each train includes the piping, instruments, and controls to ensure an operable flow path taking suction from the refueling water storage tank (RWST) upon an SI signal and capable of manually transferring suction to the containment sump.
During an event requiring ECCS actuation, a flow path is required to provide an abundant supply of water from the RWST to the reactor coolant system (RCS) via the ECCS pumps and their respective supply headers to the RCS. In the long term, this flow path may be switched to take its supply from the containment sump.
The flow path for each train must maintain its designed independence to ensure that no single failure can disable both ECCS trains.
In Mode 4, one of the two independent (and redundant) ECCS trains is required to be operable to ensure that sufficient ECCS flow is available to the core following a design basis accident (DBA).
NRC 2002-0081 Page 3 of 5
3.0 PROPOSED CHANGE
The proposed amendment adds surveillance requirement (SR) 3.5.2.2 to TS 3.5.2, to require verification that the ECCS piping is full of water. Within TS 3.5.2, surveillance requirements subsequent to SR 3.5.2.2 are renumbered to reflect the insertion of the new SR. Additionally, SR 3.5.3.1 is revised to reflect the addition of SR 3.5.2.2 to TS 3.5.2 and the applicability of SR 3.5.2.2 for all equipment required to be operable per TS 3.5.3.
Technical Specification Bases changes are also being made to reflect the proposed Technical Specifications changes.
The proposed change is consistent with NUREG-1 431, Standard Technical Specifications, Westinghouse Plants, Revision 2.
4.0 ANALYSIS Each ECCS subsystem is taken credit for in a large break LOCA event at full power. This event establishes the requirement for runout flow for the ECCS pumps. The SI pumps are also credited in a small break LOCA event. This event establishes the flow and discharge head at the design point for the SI pumps, as well as the maximum response time for their actuation.
The SGTR and main steam line break (MSLB) events also credit the SI pumps. The small break LOCA and MSLB events establish the maximum response time for the SI pumps. The operability requirements for the ECCS are based on the following LOCA analysis assumptions:
- a. A large break LOCA event, with offsite power available and a single failure disabling one RHR pump (offsite power is assumed for modeling full containment heat removal and reactor coolant pump operation); and
- b. A small break LOCA event, with a loss of offsite power and a single failure disabling one ECCS train.
During the blowdown stage of a LOCA, the RCS depressurizes as primary coolant is ejected through the break into the containment. The nuclear reaction is terminated either by moderator voiding during large breaks or control rod insertion for small breaks. Following depressurization, emergency cooling water injected into the reactor vessel upper plenum and RCS cold legs, flows into the downcomer, fills the lower plenum, and refloods the core.
The effects on containment mass and energy releases are accounted for in the Final Safety Analysis Report (FSAR), Chapter 14, Accident Analysis. TS 3.5.2 ensures that an ECCS train will deliver sufficient water to match boiloff rates soon enough to minimize the consequences of the core being uncovered following a large LOCA. TS 3.5.2 also ensures that the SI pumps will deliver sufficient water and boron during a small LOCA to maintain core subcriticality.
The ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases. The presence of voids and pockets of entrained gases in ECCS piping could lead to water hammer, pump cavitation, and pumping of noncondensible gas into the reactor vessel following an SI signal or during shutdown cooling. Venting the ECCS piping will remove any voids and pockets of entrained gases, however during the venting process that ECCS train is considered inoperable. Although performance of this surveillance will affect the availability of the associated ECCS train, the
NRC 2002-0081 Attachment I Page 4 of 5 surveillance requirement is consistent with the requirements of NUREG-1431, Standard Technical Specifications for Westinghouse Plants, Revision 2. Additionally, maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand.
5.0 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 amendment is to revise Technical Specification (TS) 3.5.2, ECCS - Operating, and TS 3.5.3, ECCS -Shutdown, to add a surveillance requirement to require verification that the ECCS piping is full of water every 31 days.
NMC has evaluated the proposed amendments in accordance with 10 CFR 50.91 against the standards in 10 CFR 50.92 and has determined that the operation of the Point Beach Nuclear Plant 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 the Point Beach Nuclear Plant in accordance with the proposed amendments does not result in a significant increase in the probability or consequences of any accident previously evaluated.
Operation of this facility under the proposed Technical Specifications will not create a significant increase in the probability or consequences of an accident previously evaluated.
This license amendment request proposes to add a surveillance requirement to verify the ECCS is full of water every 31 days while operating in Modes 1, 2, 3 and 4.
This proposed change does not cause an increase in the probabilities of any accidents previously evaluated, because the change will not cause an increase in the probability of any initiating events for accidents previously evaluated. In particular, the change affects the ECCS, which serves to mitigate rather than initiate accidents.
The consequences of the accidents previously evaluated in the PBNP Final Safety Analysis Report (FSAR) are determined by the results of analyses that are based on initial conditions of the plant, the type of accident, transient response of the plant, and the operation and failure of equipment and systems. The change proposed in this license amendment request provides an appropriate surveillance requirement for the ECCS, and thus does not increase the probability of failure of this equipment or its ability to operate as required for the accidents previously evaluated in the PBNP FSAR.
Therefore, the consequences of an accident previously evaluated in the PBNP FSAR will not be significantly increased as a result of the proposed change, because the factors that are used to determine the consequences of accidents are not being changed.
NRC 2002-0081 Page 5 of 5
- 2. Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments does not result in a new or different kind of accident from any accident previously evaluated.
Equipment important to safety will continue to operate as designed. The proposed change does not result in any event previously deemed incredible being made credible.
The change does not result in more adverse conditions or result in any increase in the challenges to safety systems. Therefore, operation of the Point Beach Nuclear Plant in accordance with the proposed amendment will not create the possibility of a new or different type of accident from any accident previously evaluated.
- 3. Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments does not result in a significant reduction in a margin of safety.
There are no new or significant changes to the initial conditions contributing to accident severity or consequences. The proposed amendment will not otherwise affect the plant protective boundaries and will not cause a release of fission products to the public.
Venting the piping associated with a train of ECCS will render that ECCS train inoperable while it is being vented. Performance of this surveillance will therefore affect the availability of the associated ECCS train, but performance of the surveillance requirement at the specified frequency is consistent with the requirements of NUREG 1431, Standard Technical Specifications for Westinghouse Plants, Revision 2.
Additionally, verifying the ECCS piping is full of water ensures that the system will perform properly, injecting its full capacity into the RCS, upon demand. Therefore, adopting a surveillance requirement to verify the ECCS piping is full of water, will not result in more than a minimal reduction in the margin of safety.
Conclusion Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments 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 more than a minimal reduction in any margin of safety.
Therefore, operation of the Point Beach Nuclear Plant in accordance with the proposed amendments does not result in a significant hazards determination.
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. Therefore, we conclude that the proposed amendment meets the categorical exclusion requirements of 10 CFR 51.22(c)(9) and that an environmental impact appraisal need not be prepared.
ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES LICENSE AMENDMENT REQUEST 229 TECHNICAL SPECIFICATION LCO 3.5.2, ECCS - OPERATING, AND LCO 3.5.3, ECCS - SHUTDOWN POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.
NOTE -----------------------
In MODE 3, both safety injection (SI) pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform pressure isolation valve testing per SR 3.4.14.1.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ECCS train A.1 Restore train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SSR 3.5.2.2 Verify ECCS pipingq is full of water. 31 days (continued)
Point Beach 3.5.2-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.2-3 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the required developed head. Inservice Testing Program Verify each ECCS automatic valve in the flow 18 months I SR 3.5.2.34 path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.2.45 Verify each ECCS pump starts automatically on 18 months an actual or simulated actuation signal.
I SR 3.5.2.56 Verify, by visual inspection, each ECCS train 18 months containment sump suction inlet is not restricted by debris and the suction inlet debris screens show no evidence of structural distress or abnormal corrosion.
Point Beach 3.5.2-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all In accordance equipment required to be OPERABLE: with applicable SRs SR 3.5.2.1 SR 3.5.2.4 SR 3.5.2.2 SR 3.5.2.5 SR 3.5.2.3 SR 3.5.2.6 Point Beach 3.5.3-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES LICENSE AMENDMENT REQUEST 229 TECHNICAL SPECIFICATION LCO 3.5.2, ECCS - OPERATING, AND LCO 3.5.3, ECCS - SHUTDOWN POINT BEACH NUCLEAR PLANT, UNITS I AND 2
ECCS - Operating B 3.5.2 BASES ACTIONS (continued) An event accompanied by a loss of offsite power and the failure of an EDG can disable one ECCS train until power is restored. A reliability analysis (Ref. 5) has shown that the impact of having one full ECCS train inoperable is sufficiently small to justify continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
With more than one component inoperable such that both ECCS trains are not available, the facility is in a condition outside design and licensing basis. Therefore, LCO 3.0.3 must be immediately entered.
B.1 and B.2 If the inoperable trains cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.5.2.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an actuation signal is allowed to be in a non-accident position provided the valve will automatically reposition within the proper stroke time. This Surveillance does not require any testing or valve manipulation. Rather, it involves verification that those valves capable of being mispositioned are in the correct position. The 31 day Frequency is appropriate because the valves are operated under administrative control, and an improper valve position would only affect a single train. This Frequency has been shown to be acceptable through operating experience.
SR 3.5.2.2 The ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, iniecting its full capacity into the RCS upon demand This will also prevent water hammer, pump cavitation, and pumping noncondensible 10/20/01 Beach Point Beach BB 3.5.2-6 3.5.2-6 10/20101
ECCS - Operating B 3.5.2 BASES SURVEILLANCE .gas (e.gq., air, nitrogen, or hydrogen) into the reactor vessel following an REQUIREMENTS SI sigqnal or during shutdown cooling. The 31 day Frequency takes into (continued) consideration the gradual nature of gas accumulation in the ECCS piping and the procedural controls governing system operation.
SR 3.5.2.32 Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by Section X1 of the ASME Code. This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve. This verifies both that the measured performance is within an acceptable tolerance of the original pump baseline performance and that the performance at the test flow is greater than or equal to the performance assumed in the plant safety analysis. SRs are specified in the Inservice Testing Program, which encompasses Section Xl of the ASME Code.
Section XI of the ASME Code provides the activities and Frequencies necessary to satisfy the requirements.
SR 3.5.2.43 and SR 3.5.2.54 These Surveillances demonstrate that each automatic ECCS valve actuates to the required position on an actual or simulated SI signal and that each ECCS pump starts on receipt of an actual or simulated SI signal. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The 18 month Frequency is based on the need to perform these Surveillances under the conditions that apply during a plant outage and the potential for unplanned plant transients if the Surveillances were performed with the reactor at power. The 18 month Frequency is also acceptable based on consideration of the design reliability (and confirming operating experience) of the equipment. The actuation logic is tested as part of ESF Actuation System testing, and equipment performance is monitored as part of the Inservice Testing Program.
SR 3.5.2.65 Periodic inspections of the containment sump suction inlet ensure that it is unrestricted and stays in proper operating condition. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage, and on the need to have access to the location. This Frequency has been found to be sufficient to detect abnormal degradation and is confirmed by operating experience.
Point Beach B 3.5.2-7 10/20/01
ECCS - Operating B 3.5.2 BASES REFERENCES 1. FSAR, Section 6.1.1.
- 2. 10 CFR 50.46.
- 3. FSAR, Section 6.2.1.
- 4. FSAR, Chapter 14, "Accident Analysis."
- 5. NRC Memorandum to V. Stello, Jr., from R.L. Baer, "Recommended Interim Revisions to LCOs for ECCS Components,"
December 1, 1975.
Point Beach B 3.5.2-8 10/20/01
ATTACHMENT 4 REVISED TECHNICAL SPECIFICATION PAGES LICENSE AMENDMENT REQUEST 229 TECHNICAL SPECIFICATION LCO 3.5.2, ECCS - OPERATING, AND LCO 3.5.3, ECCS - SHUTDOWN POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.
NOT E .........
-------- TE................
In MODE 3, both safety injection (SI) pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform pressure isolation valve testing per SR 3.4.14.1.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ECCS train A.1 Restore train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable. OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.2 Verify ECCS piping is full of water. 31 days (continued)
Point Beach 3.5.2-1 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify each ECCS pump's developed head at the In accordance test flow point is greater than or equal to the with the required developed head. Inservice Testing Program I SR 3.5.2.4 Verify each ECCS automatic valve in the flow 18 months path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.2.5 Verify each ECCS pump starts automatically on 18 months an actual or simulated actuation signal.
SR 3.5.2.6 Verify, by visual inspection, each ECCS train 18 months containment sump suction inlet is not restricted by debris and the suction inlet debris screens show no evidence of structural distress or abnormal corrosion.
Point Beach 3.5.2-2 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ECCS - Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all In accordance equipment required to be OPERABLE: with applicable SRs SR 3.5.2.1 SR 3.5.2.4 SR 3.5.2.2 SR 3.5.2.5 SR 3.5.2.3 SR 3.5.2.6 Point Beach 3.5.3-2 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ECCS - Operating B 3.5.2 BASES ACTIONS (continued) An event accompanied by a loss of offsite power and the failure of an EDG can disable one ECCS train until power is restored. A reliability analysis (Ref. 5) has shown that the impact of having one full ECCS train inoperable is sufficiently small to justify continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
With more than one component inoperable such that both ECCS trains are not available, the facility is in a condition outside design and licensing basis. Therefore, LCO 3.0.3 must be immediately entered.
B.1 and B.2 Ifthe inoperable trains cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.5.2.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an actuation signal is allowed to be in a non-accident position provided the valve will automatically reposition within the proper stroke time. This Surveillance does not require any testing or valve manipulation. Rather, it involves verification that those valves capable of being mispositioned are in the correct position. The 31 day Frequency is appropriate because the valves are operated under administrative control, and an improper valve position would only affect a single train. This Frequency has been shown to be acceptable through operating experience.
SR 3.5.2.2 The ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent water hammer, pump cavitation, and pumping noncondensible Point Beach B 3.5.2-6 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ECCS - Operating B 3.5.2 BASES SURVEILLANCE gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an REQUIREMENTS SI signal or during shutdown cooling. The 31 day Frequency takes into (continued) consideration the gradual nature of gas accumulation in the ECCS piping and the procedural controls governing system operation.
SR 3.5.2.3 Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by Section XI of the ASME Code. This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve. This verifies both that the measured performance is within an acceptable tolerance of the original pump baseline performance and that the performance at the test flow is greater than or equal to the performance assumed in the plant safety analysis. SRs are specified in the Inservice Testing Program, which encompasses Section Xl of the ASME Code.
Section Xl of the ASME Code provides the activities and Frequencies necessary to satisfy the requirements.
SR 3.5.2.4 and SR 3.5.2.5 These Surveillances demonstrate that each automatic ECCS valve actuates to the required position on an actual or simulated SI signal and that each ECCS pump starts on receipt of an actual or simulated SI signal. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The 18 month Frequency is based on the need to perform these Surveillances under the conditions that apply during a plant outage and the potential for unplanned plant transients if the Surveillances were performed with the reactor at power. The 18 month Frequency is also acceptable based on consideration of the design reliability (and confirming operating experience) of the equipment. The actuation logic is tested as part of ESF Actuation System testing, and equipment performance is monitored as part of the Inservice Testing Program.
SR 3.5.2.6 Periodic inspections of the containment sump suction inlet ensure that it is unrestricted and stays in proper operating condition. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage, and on the need to have access to the location. This Frequency has been found to be sufficient to detect abnormal degradation and is confirmed by operating experience.
Point Beach B 3.5.2-7 Unit 1 - Amendment No.
Unit 2 - Amendment No.
ECCS - Operating B 3.5.2 BASES REFERENCES 1. FSAR, Section 6.1.1.
- 2. 10 CFR 50.46.
- 3. FSAR, Section 6.2.1.
- 4. FSAR, Chapter 14, "Accident Analysis."
- 6. NRC Memorandum to V. Stello, Jr., from R.L. Baer, "Recommended Interim Revisions to LCOs for ECCS Components,"
December 1, 1975.
Point Beach B 3.5.2-8 Unit 1 - Amendment No.
Unit 2 - Amendment No.