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TAC:MD8423, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
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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 (Amend/Renewal/New) for DKT 30
[Table view] Category:40
MONTHYEARL-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2021-081, Subsequent License Renewal Application - Aging Management Supplement 12021-04-21021 April 2021 Subsequent License Renewal Application - Aging Management Supplement 1 L-2021-015, and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Fimiocial Assurance Update2021-03-30030 March 2021 and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Fimiocial Assurance Update L-2015-064, Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2015-03-27027 March 2015 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2013-103, Decommissioning Funding Status Reports2013-03-25025 March 2013 Decommissioning Funding Status Reports L-2012-442, Units 1 & 2 - ISFSI Decommissioning Funding Plans2012-12-17017 December 2012 Units 1 & 2 - ISFSI Decommissioning Funding Plans L-2011-209, Duane Arnold Energy Center, & Point Beach, Units 1 and 2, Response to Request for Additional Information Related to Decommissioning Funding Status Report2011-06-0808 June 2011 Duane Arnold Energy Center, & Point Beach, Units 1 and 2, Response to Request for Additional Information Related to Decommissioning Funding Status Report L-2009-207, Units 1 & 2, Update to Decommissioning Funding Status and Financial Assurance Plan2009-09-11011 September 2009 Units 1 & 2, Update to Decommissioning Funding Status and Financial Assurance Plan L-2009-172, and Point Beach Nuclear Plant, Units 1 and 2 - Decommissioning Funding Status and Financial Assurance Plan2009-07-27027 July 2009 and Point Beach Nuclear Plant, Units 1 and 2 - Decommissioning Funding Status and Financial Assurance Plan L-2009-055, Units 1 and 2, Decommissioning Funding Status Reports2009-03-27027 March 2009 Units 1 and 2, Decommissioning Funding Status Reports 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 L-HU-07-011, Plants, Decommissioning Funding Status Reports2007-03-30030 March 2007 Plants, Decommissioning Funding Status Reports L-HU-05-008, Decommissioning Funding Status Reports2005-03-31031 March 2005 Decommissioning Funding Status Reports ML0329009652003-10-16016 October 2003 Decommissioning Funding Status Reports - Supplemental Response for Duane Arnold, Kewaunee, Monticello, Palisades, Point Beach, Units 1 and 2, and Prairie Island, Units 1 and 2 ML0309300582003-03-31031 March 2003 Decommissioning Funding Status Reports ML0134500042002-01-28028 January 2002 Amendment, TS Change Missed Surveillance Using the Consolidated Line Item Improvement Process 2023-03-28
[Table view] Category:70
MONTHYEARL-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2021-081, Subsequent License Renewal Application - Aging Management Supplement 12021-04-21021 April 2021 Subsequent License Renewal Application - Aging Management Supplement 1 L-2021-015, and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Fimiocial Assurance Update2021-03-30030 March 2021 and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Fimiocial Assurance Update L-2015-064, Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2015-03-27027 March 2015 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2013-103, Decommissioning Funding Status Reports2013-03-25025 March 2013 Decommissioning Funding Status Reports L-2012-442, Units 1 & 2 - ISFSI Decommissioning Funding Plans2012-12-17017 December 2012 Units 1 & 2 - ISFSI Decommissioning Funding Plans L-2011-209, Duane Arnold Energy Center, & Point Beach, Units 1 and 2, Response to Request for Additional Information Related to Decommissioning Funding Status Report2011-06-0808 June 2011 Duane Arnold Energy Center, & Point Beach, Units 1 and 2, Response to Request for Additional Information Related to Decommissioning Funding Status Report L-2009-207, Units 1 & 2, Update to Decommissioning Funding Status and Financial Assurance Plan2009-09-11011 September 2009 Units 1 & 2, Update to Decommissioning Funding Status and Financial Assurance Plan L-2009-172, and Point Beach Nuclear Plant, Units 1 and 2 - Decommissioning Funding Status and Financial Assurance Plan2009-07-27027 July 2009 and Point Beach Nuclear Plant, Units 1 and 2 - Decommissioning Funding Status and Financial Assurance Plan L-2009-055, Units 1 and 2, Decommissioning Funding Status Reports2009-03-27027 March 2009 Units 1 and 2, Decommissioning Funding Status Reports 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 L-HU-07-011, Plants, Decommissioning Funding Status Reports2007-03-30030 March 2007 Plants, Decommissioning Funding Status Reports L-HU-05-008, Decommissioning Funding Status Reports2005-03-31031 March 2005 Decommissioning Funding Status Reports ML0329009652003-10-16016 October 2003 Decommissioning Funding Status Reports - Supplemental Response for Duane Arnold, Kewaunee, Monticello, Palisades, Point Beach, Units 1 and 2, and Prairie Island, Units 1 and 2 ML0309300582003-03-31031 March 2003 Decommissioning Funding Status Reports ML0134500042002-01-28028 January 2002 Amendment, TS Change Missed Surveillance Using the Consolidated Line Item Improvement Process 2023-03-28
[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
FPL Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 FPL Energy Point Beach Nucilear Plant March 31,2008 NRC 2008-0018 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 259 Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System (RCS) Specific Activitv Technical Specification
References:
(1) Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) approving TSTF-490, Revision 0, (ML070250176)
(2) Federal Resister Notice for Comment published on November 20, 2006, 71 FR 67170, (ML062780062)
(3) Federal Renister Notice of Availability dated March 15, 2007, 72 FR 12217 (ML070250176)
In accordance with the provisions of 10 CFR 50.90, "Application for amendment of license or construction permit," FPL Energy Point Beach, LLC is submitting a request for an amendment to the Point Beach Nuclear Plant (PBNP) Technical Specifications (TS) for Facility Operating Licenses DPR-24 and DPR-27, Units 1 and 2, respectively.
The proposed amendments would replace the current TS 3.4.16 limit on reactor coolant system (RCS) gross specific activity with a new limit on RCS noble gas specific activity. The noble gas specific activity limit would be based on a new DOSE EQUIVALENT Xe-133 (DEX) definition that would replace the current E Bar AVERAGE DISINTEGRATION ENERGY definition. In addition, the current DOSE EQUIVALENT 1-131 (DEI) definition would be revised to clarify the use of additional thyroid dose conversion factors (DCFs).
The proposed changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification." The availability of this TS improvement was announced in the Federal Resister on March 15, 2007, 72 FR 12217, as part of the consolidated line item improvement process (CLIIP).
An FPL Group company
Document Control Desk Page 2 Enclosure 1 provides a description and assessment of the proposed changes, as well as confirmation of applicability. Enclosure 2 provides the existing TS pages marked-up to show the proposed changes. Enclosure 3 provides the existing TS Bases pages marked-up to show the proposed changes.
FPL Energy Point Beach requests approval of the proposed license amendment by September 30, 2008. Once approved, the amendment will be implemented within 30 days.
This submittal has been reviewed by the Plant Operations Review Committee. This application contains no new commitments or revisions to existing commitments.
In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated Wisconsin Official.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 31,2008.
Very truly yours, FPL ENERGY POINT BEACH, LLC r - d f 7
/ Site Vice President !
Enclosures cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
ENCLOSURE I FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS IAND 2 LICENSE AMENDMENT REQUEST 259 DELETION OF E BAR DEFINITION AND REVISION TO T HE REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION IN ACCORDANCE WITH TSTF-490, REVISION 0,
SUMMARY
DESCRIPTION PROPOSEDCHANGES BACKGROUND TECHNICAL ANALYSIS REGULATORY ANALYSIS NO SIGNIFICANT HAZARDS CONSIDERATION ENVIRONMENTAL CONSIDERATION REFERENCES 3 pages follow
1.0
SUMMARY
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," FPL Energy Point Beach proposes changes to Renewed Licenses Nos. DPR-24 and DPR-27 and Technical Specifications for Point Beach Nuclear Plant, Units 1 and 2, respectively.
The proposed changes would replace the current limits on primary coolant gross specific activity with limits on primary coolant noble gas activity. The noble gas activity would be based on DOSE EQUIVALENT Xe-133 and would take into account only the noble gas activity in the primary coolant. The changes were approved by the NRC staff Safety Evaluation (SE)
(ML070250176) (Reference 1). Technical Specification Task Force (TSTF) change traveler TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification," was announced for availability in the Federal Reaister on March 15, 2007 (ML070250176) (Reference 3), as part of the consolidated line item improvement process (CLIIP).
2.0 PROPOSED CHANGE
S Consistent with NRC-approved TSTF-490, Revision 0, the proposed TS changes:
A. Revise the definition of DOSE EQUIVALENT 1-131 B. Delete the definition of "E Bar, AVERAGE DISINTEGRATION ENERGY."
C. Add a new TS definition for DOSE EQUIVALENT Xe-133.
D. Revise LC0 3.4.16, "RCS Specific Activity" to delete references to gross specific activity; add limits for DOSE EQUIVALENT 1-1 31 and DOSE EQUIVALENT Xe-133; and delete Figure 3.4.16-1, "Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit versus Percent of RATED THERMAL POWER."
E. Revise LC0 3.4.16 "APPLICABILITY to specify the LC0 is applicable in MODES 1, 2, 3, and 4.
Page 1 of 3
F. Modify ACTIONS Table as follows:
- 1. CONDITION A is modified to delete the reference to Figure 3.4.16-1, and define an upper limit that is applicable at all power levels.
- 2. CONDITION B is modified to provide a CONDITION and REQUIRED ACTION for DOSE EQUIVALENT Xe-133 instead of gross specific activity. The Completion Time is changed from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. A Note allowing the APPLICABILITY of LC0 3.0.4.c is added, consistent with the Note to REQUIRED ACTION A.1.
- 3. CONDITION C is modified based on the changes to CONDITIONS A and B and to reflect the change in the LC0 APPLICABILITY.
G. Modify SURVEILLANCE REQUIREMENTS (SR) Table as follows:
- 1. Revise SR 3.4.16.1 to verify the limit for DOSE EQUIVALENT Xe-133. A Note is added, consistent with SR 3.4.16.2 to allow entry into MODES 2, 3, and 4 prior to performance of the SR.
- 2. Delete SR 3.4.16.3.
3.0 BACKGROUND
The background for this application is as stated in the model Safety Evaluation (SE) in NRC's Notice of Availability dated March 15, 2007, 72 FR 12217, the NRC Notice for Comment published on November 20, 2006,71 FR 67170, and TSTF-490, Revision 0.
4.0 TECHNICAL ANALYSIS
FPL Energy Point Beach has reviewed References 1,2 and 3, and the model SE, 71 FR 67170, as part of the CLllP Notice for Comment. FPL Energy Point Beach has applied the methodology in Reference 1 to develop the proposed TS changes. FPL Energy Point Beach has also concluded that the justifications presented in TSTF-490, Revision 0 and the model SE prepared by the NRC staff are applicable to PBNP, Units 1 and 2, and justify this amendment for the incorporation of the changes to the PBNP TS.
5.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability dated March 15, 2007, 72 FR 12217, the NRC Notice for Comment published in 71 FR 67170, and TSTF-490, Revision 0.
PBNP was licensed to operate prior to Appendix A being incorporated into 10 CFR 50 in 1971.
Therefore, the applicable PBNP GDC for the control room at the time of initial plant licensing was GDC 11, not GDC 19, as stated in the regulatory analysis of this CLIIP. PBNP conforms to Appendix A GDC 19, however, via full compliance with NUREG-0737, ltem Ill D.3.4.
6.0 NO SIGNIFICANT HAZARDS CONSIDERATION FPL Energy Point Beach has reviewed the proposed no significant hazards consideration determination published in the Federal Register on March 15, 2007, 72 FR 12217 as part of the CLIIP. FPL Energy Point Beach has concluded that the proposed determination presented in the notice is applicable to PBNP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
7.0 ENVIRONMENTAL EVALUATION FPL Energy Point Beach has reviewed the environmental consideration included in the model SE published in the Federal Register on March 15, 2007, 72 FR 12217 as part of the CLIIP.
FPL Energy Point Beach has concluded that the staff's findings presented therein are applicable to PBNP and the determination is hereby incorporated by reference for this application.
8.0 REFERENCES
I. NRC Safety Evaluation approving TSTF-490, Revision 0 (ML070250176)
- 2. Federal Resister Notice for Comment published on November 20, 2006, 71 FR 67170, "Notice of Opportunity To Comment on Model Safety Evaluation and Model License Amendment Request on Technical Specification lmprovement Regarding Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification; Babcock and Wilcox Pressurized Water Reactors, Westinghouse Pressurized Water Reactors, Combustion Engineering Pressurized Water Reactors Using the Consolidated Line ltem lmprovement Process."
- 3. Federal Register Notice of Availability dated March 15, 2007, 72 FR 12217, Model Safety Evaluation, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Technical Specification Task Force TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification."
ENCLOSURE 2 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 259 PROPOSED TECHNICAL SPECIFICATION CHANGES 6 pages follow
Definitions
- 1. I 1.IDefinitions CHANNEL OPERATIONAL A COT shall be the injection of a simulated or TEST (COT) actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.
CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.4. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. II,1988, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"
Point Beach 1. I - 2 Unit 1 - Amendment No. Z24 Unit 2 - Amendment No.
Definitions
- 1. I 1.IDefinitions DOSE EQUIVALENT DOSE EQUIVALENT Xe-133 shall be that concentration of Xe-I 33 Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body D e e ~ Dose Eauivalent as the combined activities of noble gas nuclides Kr-85m, Kr-85. Kr-87, Kr-88, Xe-131 m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actuallv present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activitv.
The determination of DOSE EQUIVALENT Xe-133 shall be performed usins effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average aamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations," or similar source.
Point Beach 1.I-2a Unit 1 - Amendment No. &&I Unit 2 - Amendment No. XQ
RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT Xe-133 specific activitv shall be within limits:
APPLICABILITY: MODES &ac-&& 1, 2, 3, and 4.
I-, nrc -.A a
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT ------------------ Note-----------------
1-131 not within limit. L C 0 3.0.4.c is applicable.
A. 1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131
-!iw+@f9 A fi
. . .4c S O uCi/qm.
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.
B.
w&&h&kk DOSE EQUIVALENT ~ e - 1 3 3 ------------------ Note-----------------
not within limit. L C 0 3.0.4.c is applicable.
B. I Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT Xe-133 to within limit.
(continued)
Point Beach 3.4.16-1 Unit 1 - Amendment No.
Unit 2 - Amendment No.
RCS Specific Activity 3.4.16 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C. 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 of Condition A AND not met.
C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> DOSE EQUIVALENT 1-131 i&k
>50 uCi1am.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 7 days Onlv required to be performed in MODE 1.
Verifv reactor coolant DOSE EQUIVALENT Xe-133 specific activitv 1520 uCi/am.
SR 3.4.16.2 ........................... NOTE--------------------------
Only required to be performed in MODE 1. 14 days AND Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity 10.8 pCiIgm. Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 2 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Point Beach 3.4.16-2 Unit 1 - Amendment No. 2W Unit 2 - Amendment No.
RCS Specific Activity 3.4.16 Point Beach Unit 1 -Amendment No. XM=
Unit 2 - Amendment No. 2%
RCS Specific Activity 3.4.16 Point Beach 3.4.16-4 Unit 1 - Amendment No.
Unit 2 - Amendment No. 2%
ENCLOSURE 3 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 259 TECHNICAL SPECIFICATION BASES CHANGES 11 pages follow
RCS Specific Activity B 3.4.16 B 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.16 RCS Specific Activity BASES BACKGROUND The maximum dose that an individual at the exclusion area boundary can receive for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following an accident, or at the low population zone outer boundary for the radiological release duration, is specified in 10 CFR 100.11 (Ref. 1). Doses to control room operators must be limited per GDC 19. The limits on specific activity ensure that the offsite and control room doses are appropriately limited during analyzed transients and accidents.
The RCS specific activity LC0 limits the allowable concentration level of radionuclides in the reactor coolant. The LC0 limits are established to minimize the dose consequences in the event of a steam line break
{SLB) or steam generator tube rupture (SGTR) accident.
The LC0 contains specific activity limits for both DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT Xe-133. The allowable levels are intended to ensure that offsite and control room doses meet the appropriate acceptance criteria in the Standard Review Plan (Ref. 2).
Point Beach B 3.4.16-1 9+Qiwxa Unit 1 - Amendment No.
Unit 2 - Amendment No.
RCS Specific Activity B 3.4.16 BASES APPLICABLE SAFETYANALYSES The LC0 limits on the specific activity of the reactor coolant ensure that the resultinq offsite and control room doses meet the appropriate SRP acceptance criteria following a SLB or SGTR accident. The safety analyses (Refs. 3 and 4) assume the specific activitv of the reactor coolant is at the LC0 limits, and an existing reactor coolant steam generator (SG) tube leakage rate of 500 gallons per dav per steam generator exists. The safety analvses assume the specific activitv of the secondary coolant is at its limit of 1.0 uCilqm DOSE EQUIVALENT 1-131 from LC0 3.7.13. "Secondary Specific Activity."
The analvses for the SLB and SGTR accidents establish the acceptance limits for RCS specific activitv. Reference to these analvses is used to assess chanqes to the unit that could affect RCS specific activity, as they relate to the acceptance limits.
Point Beach Unit 1 -Amendment No.
Unit 2 - Amendment No.
RCS Specific Activity B 3.4.16 BASES APPLICABLE SAFETY ANALYSES (continued)
Point Beach Unit 1 -Amendment No. L W Unit 2 - Amendment No.
RCS Specific Activity B 3.4.16 BASES APPLICABLE The safetv analvses consider two cases of reactor coolant iodine SAFETY ANALYSES specific activitv. One case assumes specific activity at 0.8 uCilqm (continued) DOSE EQUIVALENT 1-131 with a concurrent large iodine spike that increases, bv a factor of 500, the rate of release of iodine from the fuel rods containing claddinq defects to the primaw coolant immediatelv after a SLB or SGTR, respectivelv. The second case assumes the initial reactor coolant iodine activitv at 50 uCilgm DOSE EQUIVALENT 1-131 due to an iodine spike caused bv a reactor or RCS transient prior to the accident. In both cases, the noble gas specific activitv is assumed to be 520 uCilgm DOSE EQUIVALENT Xe-133.
The analvsis also assumes a loss of offsite power at the same time as the SGTR event. The SGTR causes a reduction in reactor coolant inventow. The reduction initiates a reactor trip from a low pressurizer pressure signal or an RCS overtemperature AT siqnal.
The coincident loss of offsite power causes the steam dump valves to close to protect the condenser. The rise in pressure in the ru~turedSG discharqes radioactivelv contaminated steam to the atmosphere through the atmos~hericsteam dump valves and the main steam safetv valves. The unaffected SGs remove core decav heat bv venting steam to the atmosphere until the cooldown ends.
The SLB radiological analvsis assumes that offsite power is lost at the same time as the pipe break occurs outside containment. The affected SG blows down completelv and steam is vented directlv to the atmosphere. The unaffected SG removes core decav heat bv ventinq steam to the atmosphere until the cooldown ends and the RHR svstem is placed in service.
O~erationwith iodine specific activitv levels greater than the LC0 limit is permissible, if the activity levels do not exceed 50 uCilgm for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The limits on RCS specific activitv are also used for establishinq standardization in radiation shielding and plant personnel radiation protection practices.
RCS specific activitv satisfies Criterion 2 of 10 CFR 50.36 (c)(Z)(ii).
Point Beach Unit 1 -Amendment No.
Unit 2 - Amendment No.
RCS Specific Activity B 3.4.16 BASES The iodine specific activitv in the reactor coolant is limited to 0.8 uCilam DOSE EQUIVALENT 1-131, and the noble gas specific activitv in the reactor coolant is limited to 520 uCilam DOSE EQUIVALENT Xe-133.
The limits on specific activitv ensure that offsite and control room doses will meet the appropriate SRP acceptance criteria (Ref. 2).
The SLB and SGTR accident analvses (Refs. 3 and 4) show that the calculated doses are within acceptable limits. Violation of the LC0 may result in reactor coolant radioactivitv levels that could, in the event of a SLB or SGTR, lead to doses that exceed the SRP acceptance criteria (Ref. 2).
APPLICABILITY
?4akJs In MODES 1, 2, 3, and 4, operation within the LC0 limits for DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT Xe-133 is necessary to limit the potential consequences of a SLB or SGTR to within the SRP acceptance criteria (Ref. 2).
Point Beach B 3.4.16-3 Unit 1 - Amendment No. 245 Unit 2 -Amendment No.
RCS Specific Activity B 3.4.16 BASES APPLICABILITY In MODES 5 and 6, the steam generators are not being used for decav (continued) heat removal, the RCS and steam generators are depressurized, and primarv to secondary leakage is minimal. Therefore, the monitoring of RCS specific activitv is not required.
ACTIONS A.l and A.2 With the DOSE EQUIVALENT 1-131 greater than the LC0 limit, samples at intervals of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be taken to demonstrate that the specific activitv is 6 0 uCilgm. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is required to obtain and analvze a sample. Sampling is continued everv 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to provide a trend.
The DOSE EQUIVALENT 1-131 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were an iodine spike, the normal coolant iodine concentration would be restored within this time period. Also, there is a low probabilitv of a SLB or SGTR occurring during this time period.
A Note permits the use of the provisions of LC0 3.0.4.c. This allowance permits entrv into the applicable MODE(s), relvinq on Required Action A.l and A.2 while DOSE EQUIVALENT 1-131 LC0 limit is not met. This allowance is acceptable due to the significant Point Beach Unit 1 - Amendment No.
Unit 2 -Amendment No.
RCS Specific Activity B 3.4.16 BASES ACTIONS (continued) conservatism incorporated into the specific activitv limit, the low probabilitv of an event which is limiting due to exceeding this limit, and the abilitv to restore transient-specific activitv excursions while the plant remains at, or proceeds to, power operation.
With the DOSE EQUIVALENT Xe-133 greater than the LC0 limit, DOSE EQUIVALENT Xe-133 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The allowed Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were a noble aas spike, the normal coolant noble gas concentration would be restored within this time period. Also, there is a low probabilitv of a SLB or SGTR occurrinq during this time period.
A note permits the use of the provisions of LC0 3.0.4.c. This allowance permits entrv into the applicable MODE(s), relvina on Required Action B.l while the DOSE EQUIVALENT Xe-133 LC0 limit is not met. This Point Beach Unit 1 -Amendment No. 244 Unit 2 -Amendment No. 2243
RCS Specific Activity B 3.4.16 BASES ACTIONS (continued) allowance is acceptable due to the siqnificant conservatism incorporated into the specific activitv limit, the low probabilitv of an event which is limitinq due to exceeding this limit, and the ability to restore transient-specific activitv excursions while the plant remains at, or proceeds to, power operation.
C.l and C.2 If the Required Action and associated Completion Time of Condition A or B is not met, or if the DOSE EQUIVALENT 1-131 is > 50 uCilgm, the reactor 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 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 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 SURVEILLANCE REQUIREMENTS SR 3.4.16.1 reauires performinq a qamma isotopic analvsis as a measure of the noble gas specific activitv of the reactor coolant at least once every 7 days. This measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken. This Surveillance provides an indication of anv increase in the noble gas specific activitv.
Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LC0 limit under normal o~eratinq conditions. The 7 dav Frequencv considers the low probabilitv of a gross fuel failure during the time.
Point Beach Unit 1 - Amendment No. a Unit 2 - Amendment No. ?XI
RCS Specific Activity B 3.4.16 BASES SURVEILLANCE Due to the inherent difficulty in detecting Kr-85 in a reactor coolant REQUIREMENTS sample due to maskinq from radioisotopes with similar decay energies, (continued) such as F-18 and 1-134, it is acceptable to include the minimum detectable activity for Kr-85 in the SR 3.4.16.1 calculation. If a s~ecific noble gas nuclide listed in the definition of DOSE EQUIVALENT Xe-133 is not detected, it should be assumed to be present at the minimum detectable activity.
A Note modifies this SR to allow entry into and o~erationin MODE 4, MODE 3, and MODE 2 prior to performing the SR. This allows the Surveillance to be performed in those MODES, prior to enterinq MODE 1.
Point Beach Unit 1 - Amendment No. A4 Unit 2 -Amendment No. 22Q
RCS Specific Activity B 3.4.16 BASES SURVEILLANCE REQUIREMENTS (continued)
This surveillance is performed to ensure iodine specific activity rerr-within the LC0 limit during normal operation and followins fast P O M ~
changes when iodine spiking is more apt to occur. The 14 day Frequency is adequate to trend changes in the iodine activity level,.
considering noble gas activity is monitored everv 7 days. The Frequency, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power chanse 25% RTF) within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peal-(
during this time following iodine spike initiation: samples at other ti^^
would provide inaccurate results.
The Note modifies this SR to allow entrv into and operation in MODE 4, MODE 3, and MODE 2 prior to performins the SR. This allows the, Surveillance to be preformed in those MODES, prior to enterinq MODE 1.
Point Beach Unit 1 -Amendment No. %4 Unit 2 - Amendment No. 24%
RCS Specific Activity B 3.4.16 BASES REFERENCES 1. 1 0 C F R 1 0 0 . 1 1 ~
2.
Standard Review Plan (SRP). Section 15.1.5 Appendix A (SLB) and Section 15.6.3 (SGTR).
- 3. FSAR, Section 14.2.4.
Point Beach Unit 1 - Amendment No.
Unit 2 - Amendment No. 2QfS