Letter Sequence Other |
---|
|
|
MONTHYEARML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Other NLS2012040, Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012 Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28 Project stage: Other ML1219300742012-07-10010 July 2012 Acceptance Review Email, License Amendment Request, Revise Technical Specification 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Acceptance Review ML12235A2522012-09-0505 September 2012 Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: RAI ML12285A3562012-10-0303 October 2012 Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Request NLS2012099, Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio2012-10-31031 October 2012 Response to Nuclear Regulatory Commission Request for Additional Information License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio Project stage: Request ML12299A0922012-11-0909 November 2012 Issuance of Amendment No. 243, Revise Technical Specification 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Approval ML12291A8132012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 5/11/2007 Affidavit Executed by Thomas Smed, Studsvik Scandpower Gardel BWR-Cooper Nuclear Station Power Distribution Uncertainties Project stage: Withholding Request Acceptance ML12289A0712012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 9/13/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC VSP-NPP-HP1-12-087 - Response to RAIs Project stage: Withholding Request Acceptance ML12285A1412012-11-15015 November 2012 Request for Withholding Information from Public Disclosure - 4/25/12 Affidavit Executed by L. Trosman, Global Nuclear Fuel - Americas LLC GNF-A Report No. S-0000-0140-2518-R0-P Project stage: Withholding Request Acceptance ML12341A1112012-12-31031 December 2012 Correction to Safety Evaluation Pages Issued with Amendment No. 243 Dated 11/9/2012, Revise TS 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation Project stage: Approval 2012-11-09
[Table View] |
|
---|
Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A1122023-11-0909 November 2023 Project Manager Assignment ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information IR 05000298/20224022022-09-29029 September 2022 NRC Security Inspection Report 05000298/2022402 (Full Report) IR 05000298/20220052022-08-18018 August 2022 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005) IR 05000298/20223012022-08-10010 August 2022 NRC Examination Report 05000298/2022301 IR 05000298/20220022022-07-28028 July 2022 Integrated Inspection Report 05000298/2022002 ML22200A2772022-07-21021 July 2022 Correction to Proposed Inservice Testing Alternative RS-01, Revision of Error in Safety Evaluation ML22152A1232022-07-18018 July 2022 Issuance of Amendment No. 271 Request for Exception from Certain Primary Containment Leak Rate Testing Requirements IR 05000298/20224012022-06-29029 June 2022 Security Baseline Inspection Report 05000298/2022401 IR 05000298/20224032022-06-28028 June 2022 Security Baseline Inspection Report 05000298/2022403 IR 05000298/20220102022-06-16016 June 2022 Triennial Fire Protection Inspection Report 05000298/2022010 ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22147A1122022-06-0101 June 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022301 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 IR 05000298/20220012022-04-28028 April 2022 Integrated Inspection Report 05000298/2022001 IR 05000298/20224042022-04-13013 April 2022 Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public) ML22084A6032022-04-0404 April 2022 Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information ML22090A2892022-04-0101 April 2022 John Larson'S Invitation to Participate in the 8th Nuclear Regulatory Commission'S Workshop on Vendor Oversight ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 IR 05000298/20210062022-03-0202 March 2022 Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006) IR 05000298/20210042022-01-24024 January 2022 Integrated Inspection Report 05000298/2021004 ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements 2024-01-03
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-05-11011 May 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NLS2021015, (CNS) - Technical Specification Bases Changes2021-04-16016 April 2021 (CNS) - Technical Specification Bases Changes NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process NLS2020004, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)2019-05-23023 May 2019 Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1) NLS2019020, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr.2019-05-23023 May 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr. NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2019-02-28028 February 2019 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. NLS2018010, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-06-11011 June 2018 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing.2016-08-26026 August 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing. NLS2016038, Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications2016-06-13013 June 2016 Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications ML16120A3702016-04-21021 April 2016 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2016-03-11011 March 2016 Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NLS2015103, License Amendment Request to Replace Figure with Text in Technical Specifications2015-09-0808 September 2015 License Amendment Request to Replace Figure with Text in Technical Specifications NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function NLS2014030, License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water2014-08-26026 August 2014 License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water NLS2014028, License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications2014-07-17017 July 2014 License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process NLS2014022, License Amendment Request - Revision of Cyber Security Plan Implementation Schedule2014-03-14014 March 2014 License Amendment Request - Revision of Cyber Security Plan Implementation Schedule NLS2013014, License Amendment Request to Revise License Renewal License Condition 2.E2013-02-12012 February 2013 License Amendment Request to Revise License Renewal License Condition 2.E NLS2012042, Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan2012-06-14014 June 2012 Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2011-03-26026 March 2011 License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2010043, License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements2010-10-29029 October 2010 License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements NLS2010006, License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.92010-02-25025 February 2010 License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.9 ML1001900422010-02-0303 February 2010 Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station ML0934309332009-12-0707 December 2009 SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application Cooper Nuclear Station, Docket No. 50-298, DPR-46 NLS2009084, License Amendment Request for Approval of the Cyber Security Plan2009-11-19019 November 2009 License Amendment Request for Approval of the Cyber Security Plan NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process NLS2009010, License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements2009-03-11011 March 2009 License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements ML0829107682008-10-13013 October 2008 Cooper Nuclear Station - License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML0830302502008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.1-1 - Figure 2.3.3 ML0830302462008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix E, Environmental Report ML0830302512008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.4-1 - Figure 2.12-2 ML0830302442008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix D, Technical Specification Changes ML0830302362008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Cover Page ML0830302412008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix a, Updated Safety Analysis Report Supplement ML0830302422008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix B, Aging Management Programs and Activities ML0830302432008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix C, Response to BWRVIP Applicant Action Items 2023-09-06
[Table view] Category:Technical Specifications
MONTHYEARML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021 Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program ML20314A2352020-12-0202 December 2020 Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process ML19238A0072019-10-30030 October 2019 Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML16021A3222016-01-12012 January 2016 Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML15216A2592015-08-27027 August 2015 Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water ML15168A1712015-07-14014 July 2015 Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications ML15135A0052015-05-29029 May 2015 Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS) NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML14055A0232014-04-29029 April 2014 Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML13191A1052013-09-12012 September 2013 Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report ML13085A0962013-03-29029 March 2013 Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML1136302582012-01-31031 January 2012 Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011 Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML0906207232009-02-26026 February 2009 Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment ML0815402852008-06-30030 June 2008 Technical Specifications, Measurement Uncertainty Recapture Power Uprate ML0812202892008-05-12012 May 2008 Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448 NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008 Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007 Corrected Technical Specification Pages NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007 License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML0630405382006-10-31031 October 2006 Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J ML0629602942006-10-23023 October 2006 Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities ML0627700902006-10-0303 October 2006 Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0625003012006-09-0606 September 2006 Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335 ML0624900372006-09-0505 September 2006 Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566 NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation ML0612403772006-05-0303 May 2006 Correction to Amendment No. 218, Technical Specification Page 3.1-12 ML0612304692006-05-0202 May 2006 Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves ML0611802442006-04-27027 April 2006 Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation ML0611001622006-04-18018 April 2006 Corrected Technical Specification Page 3.9-1 Re Refueling Operations NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006 Corrected Technical Specification Page from Amendment No. 218 ML0609004412006-03-30030 March 2006 Technical Specification Pages, Change Request for Various Sections ML0628404572006-03-10010 March 2006 Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006 License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006 License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006 Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0602002922006-01-16016 January 2006 Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences NLS2005102, License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification2005-12-30030 December 2005 License Amendment Request to Establish a Combined Main Steam Line Leakage Rate Technical Specification ML0601104792005-12-16016 December 2005 Corrected Technical Specification Pages Re Secondary Containment Isolation Instrumentation ML0535000852005-12-15015 December 2005 1 TS Page - Cooper Nuclear Station. Issuance of Amd. 214 Unit Staff Qualifications (Tac. MC7346) NLS2005051, Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation2005-08-0101 August 2005 Response to Request for Additional Information License Amendment Request to Revise the Required Channels Per Trip System for Primary & Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation 2023-09-06
[Table view] |
Text
H Nebraska Public Power District Always there when you need us 50.90 NLS2012040 May 30, 2012 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555-0001
Subject:
License Amendment Request to Revise Technical Specifications
-Safety Limit Minimum Critical Power Ratio Cooper Nuclear Station, Docket 50-298, DPR-46
Dear Sir or Madam:
Pursuant to 10 CFR 50.90 and 50.4, Nebraska Public Power District (NPPD) requests an amendment to Renewed Facility Operating License DPR-46 to revise the Cooper Nuclear Station (CNS) Technical Specifications (TS). This proposed change to TS Section 2.0, Safety Limits, will revise two recirculation loop and single recirculation loop Safety Limit Minimum Critical Power Ratio (SLMCPR) values to reflect results of a cycle specific calculation.
NPPD has concluded that the proposed changes do not involve a significant hazards consideration and that they satisfy the categorical exclusion criteria of 10 CFR 51.22(c).NPPD requests Nuclear Regulatory Commission (NRC) approval of the proposed TS change and issuance of the requested license amendment by October 10, 2012. This change is needed to ensure unrestricted full power operation for the up-coming operating cycle (Cycle 28) which is scheduled to start November 9, 2012 following Refuel Outage RE27. Further, the core for the next operating cycle is being designed based on these requested values of SLMCPR. Once approved, the amendment will be implemented prior to startup from RE27.Attachment I provides a description of the TS change, the basis for the amendment, the no significant hazards consideration evaluation pursuant to 10 CFR 50.91 (a)(1), and the environmental impact evaluation pursuant to 10 CFR 51.22. Attachment 2 provides the proposed changes to the current CNS TS in marked up format. Attachment 3 provides the final typed TS pages to be issued with the amendment.
No Bases pages are affected by this amendment request. No formal regulatory commitments are being made by this submittal.
This proposed change is supported by a report prepared by Global Nuclear Fuel -Americas (GNF-A). This report contains information considered by GNF-A to be proprietary as described in 10 CFR 2.390(a)(4).
Specific proprietary text is enclosed within double brackets.
It is requested that this information be withheld from public disclosure.
The proprietary and non-proprietary versions of the GNF-A report are included as Enclosures 1 and 2, respectively.
An COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone:
(402) 825-3811 / Fax: (402) 825-5211 www.nppd.com NLS2012040 Page 2 of 3 affidavit executed by an official of GNF-A requesting withholding from public disclosure in accordance with 10 CFR 2.390(b)(1) is provided as Enclosure 3.This proposed change is also supported by a report prepared by Studsvik Scandpower, Inc (SSP).This report contains information considered by SSP to be proprietary as described in 10 CFR 2.390(a)(4).
Specific proprietary text is enclosed within double brackets.
It is requested that this information be withheld from public disclosure.
The proprietary and non-proprietary versions of the SSP report are included as Enclosures 4 and 5, respectively.
An affidavit executed by an official of SSP requesting withholding from public disclosure in accordance with 10 CFR 2.390(b)(1) is provided as Enclosure 6.This proposed TS change has been reviewed by the necessary safety review committees (Station Operations Review Committee and Safety Review and Audit Board). Amendments to the CNS Facility Operating License through Amendment 241, issued February 16, 2012, have been incorporated into this request. This request is submitted under affirmation pursuant to 10 CFR 50.30(b).By copy of this letter and its attachments and enclosures, the appropriate State of Nebraska official is notified in accordance with 10 CFR 50.91(b)(1).
Copies to the NRC Region IV office and the CNS Resident Inspector are also being provided in accordance with 10 CFR 50.4(b)(1).
Should you have any questions concerning this matter, please contact Mr. David Van Der Kamp, Licensing Manager, at (402) 825-2904.I declare under penalty of perjury that the foregoing is true and correct.Executed On: iMOy 2e b n -Date Sinc rely, Brian J. O'Grad)y Vice President Nuclear and Chief Nuclear Officer/em Attachments:
- 1. License Amendment Request to Revise Technical Specifications Safety Limit Minimum Critical Power Ratio 2. Proposed Technical Specifications Revisions
-Markup Format 3. Proposed Technical Specifications Revisions
-Final Typed Format NLS2012040 Page 3 of 3
Enclosures:
I. GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR -Cooper Cycle 28 (GNF-A Report No. S-0000-0 140-2518-RO-P)
Proprietary Version 2. GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR -Cooper Cycle 28 (GNF-A Report No. S-0000-0140-2518-RO-NP)
Non-Proprietary Version 3. 10 CFR 2.390 Affidavit from Global Nuclear Fuels -Americas 4. Studsvik Scandpower Report, GARDEL BWR -Cooper Nuclear Station Power Distribution Uncertainties (Report No. SSP-07/405-C, Rev. 0) Proprietary Version 5. Studsvik Scandpower Report, GARDEL BWR -Cooper Nuclear Station Power Distribution Uncertainties (Report No. SSP-07/405-C, Rev. 1) Non-Proprietary Version 6. 10 CFR 2.390 Affidavit from Studsvik Scandpower, Incorporated cc: Regional Administrator w/ attachments and enclosures USNRC -Region IV Cooper Project Manager w/ attachments and enclosures USNRC -NRR Project Directorate IV-1 Senior Resident Inspector w/ attachments and enclosures USNRC -CNS Nebraska Health and Human Services w/ attachments and enclosures Department of Regulation and Licensure NPG Distribution w/o attachments or enclosures CNS Records w/ attachments and enclosures NLS2012040 Attachment 1 Page 1 of 9 ATTACHMENT 1 License Amendment Request to Revise Technical Specifications Safety Limit Minimum Critical Power Ratio Cooper Nuclear Station, NRC Docket 50-298, License DPR-46 Revised Technical Specification Page 2.0-1 1.0 Summary Description
2.0 Detailed
Description
2.1 Proposed
Change 2.2 Need for Change 2.3 Bases Changes 3.0 Technical Evaluation
3.1 System Description
3.2 Updated
Safety Analysis Report (USAR) Safety Design Basis 3.3 Current TS Bases 3.4 Analytical Methods, Standards, Data & Results 3.5 Technical Justification of Proposed Changes 3.6 Precedent Applicability
3.7 Conclusion
4.0 Regulatory Safety Analysis 4.1 Applicable Regulatory Requirements/Criteria
4.2 Precedent
4.3 No Significant Hazards Consideration
4.4 Conclusions
5.0 Environmental Consideration
6.0 References
NLS2012040 Attachment I Page 2 of 9 1.0
SUMMARY
DESCRIPTION This letter is a request for amendment of Renewed Operating License DPR-46 for Cooper Nuclear Station (CNS). The proposed change is to revise the value of the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loop operation (TLO) and for single recirculation loop operation (SLO) in Technical Specification (TS) 2.1.1.2 based on analysis performed for CNS operation in Cycle 28.CNS requests approval of this license amendment request (LAR) by October 10, 2012.Once approved, the amendment will be implemented prior to plant startup from refuel outage RE27.2.0 DETAILED DESCRIPTION The following revisions are proposed to TS Section 2.1.1.2.2.1 Proposed Change This LAR proposes to revise the Safety Limit (SL) in TS 2.1.1.2 by changing the value of Minimum Critical Power Ratio (MCPR) for TLO from > 1.10 to > 1.11 and the value of MCPR for SLO from > 1.12 to > 1.13.2.2 Need for Change This change is being proposed in order to ensure unrestricted full power operation of CNS during the up-coming Operating Cycle 28. The reactor core for Operating Cycle 28 is being designed based on these requested values of SLMCPR. As a result, these values will be bounding for Cycle 28, scheduled to begin November 9, 2012.2.3 Bases Changes No changes to the associated Bases are needed.3.0 TECHNICAL EVALUATION
3.1 System Description
CNS is a boiling water reactor (BWR) of General Electric BWR4 design, with a Mark 1 containment.
The design of the BWR core and fuel is based on a proper combination of design variables, such as moderator-to-fuel volume ratio, core power density, thermal-hydraulic characteristics, fuel exposure level, nuclear characteristics of the core and fuel, heat transfer, flow distribution, void content, bundle power, and operating pressure.
The CNS Cycle 28 core has 180 GNF2 and 368 GE14 fuel assemblies, and will be licensed by approval of the Cycle 28 Core Operating Limits Report (COLR). Cycle 28 is scheduled to end the middle of November 2014.
NLS2012040 Attachment 1 Page 3 of 9 3.2 Updated Safety Analysis Report (USAR) Safety Design Basis The safety design basis provided in USAR Section 111-7 is that the thermal hydraulic design of the core shall establish a thermal hydraulic safety limit for use in evaluating the safety margin relating the consequences of fuel barrier failure to public safety. To ensure that adequate margin is maintained, a design requirement based on a statistical analysis was selected as follows. Moderate frequency transients caused by a single operator error or equipment malfunction shall be limited such that, considering uncertainties in manufacturing and monitoring the core operating state, at least 99.9%of the fuel rods would be expected to avoid boiling transition.
The lowest allowable transient MCPR limit which meets the design requirement is termed the fuel cladding integrity SLMCPR.A plant unique operating limit MCPR (OLMCPR) is established to provide adequate assurance that the fuel cladding integrity SLMCPR is not exceeded for any anticipated operational transients.
The OLMCPR is obtained by adding the maximum delta critical power ratio (ACPR) value for the most limiting transient postulated to occur at the plant to the fuel cladding integrity SLMCPR. Cycle specific ACPR values are determined as part of the reload analysis and are reported in the Supplemental Reload Licensing Report.3.3 Current TS Bases The fuel cladding integrity SL is set such that no significant fuel damage is calculated to occur if the limit is not violated.
Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling have been used to mark the beginning of the region in which fuel damage could occur. Although it is recognized that the onset of transition boiling would not result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit. However, the uncertainties in monitoring the core operating state and in the procedures used to calculate the critical power result in an uncertainty in the value of the critical power. Therefore, the fuel cladding integrity SL is defined as the critical power ratio in the limiting fuel assembly for which more than 99.9% of the fuel rods in the core are expected to avoid boiling transition, considering the power distribution within the core and all uncertainties.
The MCPR SL is determined using a statistical model that combines all the uncertainties in operating parameters and the procedures used to calculate critical power. The probability of the occurrence of boiling transition is determined using the approved General Electric Critical Power correlations.
Details of the fuel cladding integrity SL calculation are given in Reference I [NEDE-2401 1-P-A, General Electric Standard Application for Reactor Fuel, (Revision specified in the COLR)].Reference I also includes a tabulation of the uncertainties used in the determination of the MCPR SL and of the nominal values of the parameters used in the MCPR SL statistical analysis.
NLS2012040 Attachment 1 Page 4 of 9 3.4 Analytical Methods, Standards, Data & Results Analyses have been performed which show that at least 99.9% of the fuel rods in the core are expected to avoid boiling transition (and, therefore, cladding damage due to overheating) if the MCPR is equal to or greater than the fuel cladding integrity SLMCPR.The proposed changes to the SLMCPR values are based on an analysis by Global Nuclear Fuels -Americas (GNF-A) for CNS Cycle 28 operations.
The GNF-A report, S-0000-0140-2518-RO-P, "GNF Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR," dated April 25, 2012, supports changing the TLO value of SLMCPR from 1.10 to 1.11, and the SLO value of SLMCPR from 1.12 to 1.13. These values are based on Nuclear Regulatory Commission (NRC) approved methods and procedures.
Proprietary and non-proprietary versions of the GNF-A report are included as Enclosures 1 and 2, respectively.
The GNF-A analyses include an uncertainty to account for an increase in channel bow due to control blade shadow corrosion-induced channel bow. CNS has not experienced channel bow. The current practice at CNS is to place a new fuel channel on each fresh fuel assembly when it is initially loaded into the core. In accordance with this practice, a new fuel channel is placed on each fresh fuel assembly that will be loaded into the core for Cycle 28. Current procedures require installation of new fuel channels on new fuel assemblies.
These procedures will ensure that a new fuel channel is installed on the new fuel assemblies that will be loaded into the core for Cycle 28, and for subsequent cycles.The uncertainties in the adaptive relative power distribution were evaluated by Studsvik Scandpower (SSP). The methodology used for this evaluation and the results are described in the report SSP-07/405-C, "GARDEL BWR -Cooper Nuclear Station Power Distribution Uncertainties," Revision 0, dated February 5, 2007.Proprietary and non-proprietary versions of the SSP report are included as Enclosures 4 and 5, respectively.
3.5 Technical
Justification of Proposed Changes The required information to justify this requested change to the SLMCPR values is provided in the GNF-A and SSP reports.3.6 Precedent Applicability The precedent discussed in Section 4.2 below is directly applicable to CNS, because it is the previous CNS SLMCPR LAR submittal.
NLS2012040 Attachment I Page 5 of 9 3.7 Conclusion In summary, the proposed change is technically sound and continues to maintain the same level of safety as the current licensing basis.4.0 REGULATORY SAFETY ANALYSIS 4.1 Applicable Regulatory Requirements/Criteria
4.1.1 Appendix
A to 10 CFR 50, General Design Criteria for Nuclear Power Plants.General Design Criterion (GDC) 10, Reactor Design, from Section II, Protection by Multiple Fission Product Barriers, states: "The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
The fuel cladding must not sustain damage as a result of normal operation and abnormal operational transients.
The reactor core safety limits are established to preclude violation of the fuel design criterion such that at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling.As part of a reload core design, cycle specific transient analyses are performed to determine the required SLMCPR and the change in Critical Power Ratio (CPR) [ACPR] for specific transients.
To ensure that adequate margin is maintained, a design requirement based on a statistical analysis was selected, in that moderate frequency transients caused by a single operator error or equipment malfunction shall be limited such that, considering uncertainties in manufacturing and monitoring the core operating state, at least 99.9% of the fuel rods would be expected to avoid boiling transition.
The lowest allowable transient MCPR limit which meets the design requirement is termed the fuel cladding integrity SLMCPR.NUREG-0800, Standard Review Plan, Section 4.4, "Thermal and Hydraulic Design," Acceptance Criterion No. 1..B, states, in part, that the limiting (minimum) value of CPR is to be established such that at least 99.9% of the fuel rods in the core would not be expected to experience departure from nucleate boiling during normal operation or anticipated operational occurrences.
A plant unique operating limit MCPR (OLMCPR) is established to provide adequate assurance that the fuel cladding integrity SLMCPR is not exceeded for NLS2012040 Attachment 1 Page 6 of 9 any anticipated operational transients.
The OLMCPR is obtained by adding the maximum value of ACPR for the most limiting transient postulated to occur at the plant to the fuel cladding integrity SLMCPR.4.1.2 CNS USAR Appendix F CNS was designed and constructed to meet the intent of the 70 General Design Criteria (GDC) issued by the Atomic Energy Commission (AEC), as originally proposed in July 1967. These GDCs constitute the licensing basis for CNS, except where specific commitments have been made to the 1971 GDCs. The AEC conducted their technical review of the CNS design against the 1971 GDC, and concluded that the CNS design conforms to the intent of the 1971 GDCs.The 1967 Proposed GDC and CNS conformance with the criteria are discussed in Appendix F of the CNS USAR. Group II of the 1967 Proposed GDC is titled Protection by Multiple Fission Product Barriers.
Criterion 6, of Group II, is titled Reactor Core Design. This criterion states: "The reactor core shall be designed to function throughout its design lifetime, without exceeding acceptable fuel damage limits which have been stipulated and justified.
The core design, together with reliable process and decay heat removal systems shall provide for this capability under all expected conditions of normal operation with appropriate margins for uncertainties and for transient situations which can be anticipated, including the effects of the loss of power to recirculation pumps, tripping out of a turbine generator set, isolation of the reactor from its primary heat sink, and loss ofall offsite power. " The equivalent criterion from the 1971 GDC, 10 CFR 50 Appendix A, is Criterion 10, Reactor Design. Using the sum of the maximum ACPR and cycle specific SLMCPR to determine the OLMCPR preserves compliance with Criterion 6 of the CNS USAR Appendix F, and the equivalent GDC 10. CNS continues to meet Criterion 6 from the CNS USAR Appendix F.4.2 Precedent CNS submitted a LAR to revise TS SLMCPR in letter NLS2007032 dated August 10, 2007. This request was approved and the TS was changed in Amendment 229 to the CNS license dated February 14, 2008.
NLS2012040 Attachment 1 Page 7 of 9 4.3 No Significant Hazards Consideration 10 CFR 50.91 (a)(1) requires that licensee requests for operating license amendments be accompanied by an evaluation of significant hazard posed by issuance of an amendment.
Nebraska Public Power District (NPPD) has evaluated this proposed amendment with respect to the criteria given in 10 CFR 50.92(c).The proposed change would revise the Cooper Nuclear Station (CNS) Operating License by increasing the values of the Safety Limit Minimum Critical Power Ratio (SLMCPR) for two recirculation loop operation (TLO) and for single recirculation loop operation (SLO) in Technical Specification 2.1.1.2. The TLO value of SLMCPR is increased from 1.10 to 1.11 and the SLO value of SLMCPR is increased from 1.12 to 1.13. The revised values of SLMCPR are based on analyses performed by Global Nuclear Fuels -Americas (GNF-A) to determine the SLMCPR for the current operating cycle, as supported by analyses performed by Studsvik Scandpower (SSP).1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.Four accidents have been evaluated previously as reflected in the CNS Updated Safety Analysis Report (USAR). These four accidents are (1) loss-of-coolant, (2) control rod drop, (3) main steam line break, and (4) fuel handling.
The probability of an evaluated accident is derived from the probabilities of the individual precursors to that accident.
Changing the SLMCPR values does not increase the probability of an evaluated accident.
The change does not require any physical modifications to the plant or any components, nor does it require a change in plant operation.
Therefore, no individual precursors of an accident are affected.The consequences of an evaluated accident are determined by the operability of plant systems designed to mitigate those consequences.
This proposed change makes no modification to the design or operation of the systems that are used in mitigation of accidents.
Limits have been established, consistent with Nuclear Regulatory Commission (NRC) approved methods, to ensure that fuel performance during normal, transient, and accident conditions is acceptable.
The proposed change to the values of the SLMCPR continues to conservatively establish this safety limit such that the fuel is protected during normal operation and during any plant transients or anticipated operational occurrences.
Based on the above, NPPD concludes that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
NLS2012040 Attachment 1 Page 8 of 9 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.Creation of the possibility of a new or different kind of accident from an accident previously evaluated would require creation of precursors of that accident.
New accident precursors may be created by modification of the plant configuration or changes in how the plant is operated.
The proposed change does not involve a modification of the plant configuration or in how the plant is operated.
The proposed change to the SLMCPR values assures that safety criteria are maintained.
Based on the above, NPPD concludes that the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?Response:
No.The values of the proposed SLMCPR provides a margin of safety by ensuring that no more than 0.1% of fuel rods are expected to be in boiling transition if the Minimum Critical Power Ratio limit is not violated.
The proposed change will ensure the appropriate level of fuel protection is maintained.
Additionally, operational limits are established based on the proposed SLMCPR to ensure that the SLMCPR is not violated during all modes of operation.
This will ensure that the fuel design safety criteria are met (i.e., that at least 99.9% of the fuel rods do not experience transition boiling during normal operation as well as anticipated operational occurrences).
Based on the above, NPPD concludes that the proposed changes do not involve a significant reduction in a margin of safety.From the discussions above, NPPD concludes that the proposed amendment involves no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.4 Conclusions
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
NLS2012040 Attachment I Page 9 of 9 5.0 ENVIRONMENTAL CONSIDERATION 10 CFR 51.22(c) provides categories of actions which are categorical exclusions from performing an environmental assessment.
An action which is a categorical exclusion does not require an environmental assessment or an environmental impact statement.
10 CFR 51.22(c)(9) allows as a categorical exclusion issuance of an amendment to a license for a reactor pursuant to 10 CFR Part 50 provided that (1) the amendment involves no significant hazards consideration, (2) there is no significant change in the types or significant increase in the amounts of any effluents that may be released off-site, and (3) there is no significant increase in individual or cumulative occupational radiation exposure.NPPD has reviewed the proposed license amendment and concludes that it meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(c), no environmental impact statement or environmental assessment needs to be prepared in connection with issuance of the proposed license changes. The basis for this determination is as follows: 1. The proposed license amendment does not involve significant hazards as described previously in the No Significant Hazards Consideration Evaluation.
- 2. The proposed license amendment does not introduce any new equipment, nor does it require any existing equipment or systems to perform a different type of function than they are presently designed to perform. NPPD has concluded that this proposed change does not result in a significant change in the types or significant increase in the amounts of any effluents that may be released off-site.3. The proposed changes do not adversely affect plant systems or operation and therefore, do not significantly increase individual or cumulative occupational radiation exposure beyond that already associated with normal operation.
6.0 REFERENCES
6.1 NEDE-2401 1-P-A, General Electric Standard Application for Reactor Fuel (Revision specified in COLR).6.2 NEDC-32601 P-A, Methodology and Uncertainties for Safety Limit MCPR Evaluations (August 1999).6.3 NEDC-32694P-A, Power Distribution Uncertainties for Safety Limit MCPR Evaluations (August 1999).6.4 NEDO-10958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation, and Design Application (January 1977).
NLS2012040 Attachment 2 Page 1 of 2 ATTACHMENT 2 Proposed Technical Specifications Revisions
-Markup Format Cooper Nuclear Station NRC Docket 50-298, License DPR-46 Revised Technical Specification Page 2.0-1 SLs 2.0 2.0 SAFETY LIMITS (SLs)2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10%rated core flow: THERMAL POWER shall be < 25% RTP.2.1.1.2 With the reactor steam dome pressure > 785 psig and core flow> 10% rated core flow: k MCPR shall be > 440 for two recirculation loop operation or> 1-42 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.2.1.2 Reactor Coolant System Pressure SL-ý13 Reactor steam dome pressure shall be < 1337 psig.2.2 SL Violations With any SL violation, the following actions shall be compleled within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.Cooper 2.0-1 Amendment No. 229 NLS2012040 Attachment 3 Page 1 of 2 ATTACHMENT 3 Proposed Technical Specifications Revisions
-Final Typed Format Cooper Nuclear Station NRC Docket 50-298, License DPR-46 Revised Technical Specification Page 2.0-1 SLs 2.0 2.0 SAFETY LIMITS (SLs)2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10%rated core flow: THERMAL POWER shall be < 25% RTP.2.1.1.2 With the reactor steam dome pressure > 785 psig and core flow> 10% rated core flow: MCPR shall be > 1.11 for two recirculation loop operation or > 1.13 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be < 1337 psig.2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.Cooper 2.0-1 Amendment No.