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MONTHYEARML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves Project stage: Request ML1104202012011-02-11011 February 2011 Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: Acceptance Review ML1114307042011-06-0303 June 2011 Request for Additional Information, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: RAI ML1118100852011-06-30030 June 2011 Notice of Meeting with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection Project stage: Meeting ML1121401792011-07-11011 July 2011 Licensee Slides from Conference Call with Nebraska Public Power District Project stage: Other ML1121700812011-08-18018 August 2011 7/12/11 - Summary of Teleconference with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs) at Cooper Nuclear Station Project stage: Meeting 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 Project stage: Supplement NLS2011088, Response to Nuclear Regulatory Commission Request for Additional Information for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-18018 October 2011 Response to Nuclear Regulatory Commission Request for Additional Information for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves Project stage: Request ML1104808522011-11-0101 November 2011 Request for Withholding Information from Public Disclosure, 2/18/11 Affidavit Executed by J. Harrison, GE Hitachi Nuclear Energy, NEDC-33543P, Revision 0 Project stage: Withholding Request Acceptance 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 Project stage: Approval 2011-02-11
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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-Operating (New/Renewal/Amendments) DKT 50
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 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 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 ML21040A3002021-03-29029 March 2021 Issuance of Amendment No. 269 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors 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 ML20282A1762020-10-22022 October 2020 Issuance of Amendment No. 267 Regarding Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML20212J1762020-08-24024 August 2020 Temporary Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020-LLE-0110 (Covid 19)) ML19352G1942020-01-28028 January 2020 Issuance of Amendment No. 264 Elimination of Technical Specification Requirements for Hydrogen/Oxygen Monitors 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 ML18348B1032019-02-21021 February 2019 Issuance of Amendment No. 262 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18186A5492018-08-0101 August 2018 Issuance of Amendment No.260 Revision to Technical Specifications to Adopt (TSTF) Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MG0138; EPID L-2017-LLA-0290) ML17144A0822017-06-20020 June 2017 Issuance of Amendment No. 259 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17061A0502017-03-31031 March 2017 Issuance of Amendment No. 258 Adoption of TSTF-425, Revision 3, ML16272A1372016-10-17017 October 2016 Issuance of Amendment No. 257 Revision of Technical Specifications - Safety Limit Minimum Critical Power Ratio ML16146A7492016-07-25025 July 2016 Issuance of Amendment No. 255 Replacement of Technical Specification Figure 4.1-1 with Text ML16119A4332016-07-25025 July 2016 Issuance of Amendment No. 254 Adoption of Technical Specification Task Force Change Traveler TSFT-535, Revision 0 ML16158A0222016-07-25025 July 2016 Issuance of Amendment No. 256 to Relocate the Pressure-Temperature Curves to a Pressure-Temperature Limits Report ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to 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) ML14323A6442014-12-12012 December 2014 Issuance of Amendment No. 249, Request to Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date 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 ML13148A2252013-06-26026 June 2013 Issuance of Amendment No. 246, Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML13032A5262013-02-22022 February 2013 Issuance of Amendment No. 245, Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements 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 ML12318A1602012-12-13013 December 2012 Issuance of Amendment No. 244, Revise Physical Protection License Condition Related to Cyber Security Plan Implementation Schedule Milestone 6 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 ML12251A0982012-09-28028 September 2012 Issuance of Amendment No. 242, Revise Technical Specifications to Implement a 24-Month Fuel Cycle and Adopt Technical Specification Task Force (TSTF)-493, Revision 4, Option a ML1201302052012-02-16016 February 2012 Issuance of Amendment No. 241, Editorial Changes to Several Technical Specifications (Tss) and Revise TS 5.5.6 to Remove Expired One-Time Exception to 5-Year Test Frequency for a Safety Valve 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 ML1128502652011-10-28028 October 2011 Issuance of Amendment No. 239, Correction of Non-Conservative Values in Battery Terminal Voltage and Specific Gravity Values in Technical Specification Surveillance Requirements ML1118010812011-07-27027 July 2011 License Amendment, Issuance of Amendment No. 238, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1103401602011-02-28028 February 2011 License Amendment, Issuance of Amendment 237, Revising Technical Specification Surveillance Requirement 3.8.1.9, Diesel Generator Load Test, in TS Section 3.8.1 to Correct Non-Conservative Power Factor Value ML0815402802008-06-30030 June 2008 Issuance of Amendment Measurement Uncertainty Recapture Power Uprate ML0814200582008-06-10010 June 2008 Correction to Amendment No. 230 Control Room Envelope Habitability License Pages 4 & 5 and SE Pages 3, 4, 8, and 9 ML0812202812008-05-12012 May 2008 Issuance of Amendment No. 230 Control Room Habitability, TSTF-448 ML0730600362007-12-0404 December 2007 Issuance of Amendment No. 228, Revise TS 5.5.6, Inservice Testing Program, to Allow a One-Time Extension of the 5-yr Frequency Requirement for Setpoint Testing of Safety Valve MS-RV-70ARV ML0721300232007-09-0606 September 2007 License Amendment, Issuance of Amendment No. 227 Onsite Spent Fuel Storage Expansion ML0721800082007-08-0909 August 2007 Revised Pages of Facility Operating License No. DPR-46 ML0625400892006-10-31031 October 2006 Issuance of Amendment 226 MSIV Leakage Exemption from 10 CFR 50, Appendix J ML0625400242006-10-0303 October 2006 Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0614400492006-09-0606 September 2006 License Amendment, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335 ML0622602392006-09-0505 September 2006 License Amendment, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566 ML0612300512006-05-0303 May 2006 Correction to Amendment No. 218 ML0606700422006-05-0202 May 2006 Issuance of License Amendment Inoperability of Snubbers ML0606901692006-05-0202 May 2006 License Amendment, Changes to TS Leakage Limit for the Main Stream Isolation Valves ML0608103392006-04-27027 April 2006 License Amendment, Revised Pressure Vessel Fluence and Pressure Temperature Curve Applicability to 30 Effective Full-Power Years of Operation 2024-01-03
[Table view] Category:Safety Evaluation
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 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 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 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 ML22140A1612022-06-0808 June 2022 Proposed Inservice Inspection Alternative RR5-01 Revision 1 ML22111A1382022-05-13013 May 2022 Proposed Inservice Testing Alternative RS-01, Revision 0 ML22045A0012022-03-31031 March 2022 Proposed Inservice Inspection Alternative RI5- 02 Revision 3 ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements ML21040A3002021-03-29029 March 2021 Issuance of Amendment No. 269 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors 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 ML20282A1762020-10-22022 October 2020 Issuance of Amendment No. 267 Regarding Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML20255A2172020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML20077L3392020-03-19019 March 2020 Proposed Inservice Inspection Alternatives RP5-02 and RI5-02 ML19352G1942020-01-28028 January 2020 Issuance of Amendment No. 264 Elimination of Technical Specification Requirements for Hydrogen/Oxygen Monitors 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 ML19079A0702019-05-0707 May 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4384; EPID No. L-2014-JLD-0046) ML19092A1402019-04-29029 April 2019 Proposed Inservice Inspection Alternative PR5-02 ML18348B1032019-02-21021 February 2019 Issuance of Amendment No. 262 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18186A5492018-08-0101 August 2018 Issuance of Amendment No.260 Revision to Technical Specifications to Adopt (TSTF) Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MG0138; EPID L-2017-LLA-0290) ML18183A3252018-07-31031 July 2018 Requests for Relief Associated with - the Fifth 10-year Inservice Inspection Interval Program (CAC Nos. MG0175 Through MG0179; Epids L-2017-LLR-0062 Through L-2017-LLR-0066) ML18064A1022018-03-22022 March 2018 Request No. RI-21, Revision 1 - Request for Relief Concerning Examinations for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9623; EPID L-2017-LLR-0026) ML17226A0322017-09-20020 September 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17144A0822017-06-20020 June 2017 Issuance of Amendment No. 259 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17061A0502017-03-31031 March 2017 Issuance of Amendment No. 258 Adoption of TSTF-425, Revision 3, ML16272A1372016-10-17017 October 2016 Issuance of Amendment No. 257 Revision of Technical Specifications - Safety Limit Minimum Critical Power Ratio ML16158A0222016-07-25025 July 2016 Issuance of Amendment No. 256 to Relocate the Pressure-Temperature Curves to a Pressure-Temperature Limits Report ML16146A7492016-07-25025 July 2016 Issuance of Amendment No. 255 Replacement of Technical Specification Figure 4.1-1 with Text ML16119A4332016-07-25025 July 2016 Issuance of Amendment No. 254 Adoption of Technical Specification Task Force Change Traveler TSFT-535, Revision 0 ML16048A3402016-02-24024 February 2016 Request for Inservice Inspection Program Alternative RP5-01 for Implementation of Code Case N-795 ML16042A3262016-02-24024 February 2016 Request for Relief RR5-01, Alternative Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap in Lieu of Specific ASME Boiler and Pressure Vessel Code Requirements ML16034A4792016-02-17017 February 2016 Request for Relief RI5-02, Alternative to Use Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements ML16034A3032016-02-12012 February 2016 Request for Relief RC3-01 for Alignment of Inservice Inspection and Containment Inservice Inspection (CAC No. MF6333 ML16014A1742016-02-12012 February 2016 Request for Relief RP-01 Through RP-09, RV-01 Through RV-05, and RG-01 Alternative to ASME OM Code Requirements for Inservice Testing for the Fifth Ten-Year Program Interval (CAC Nos. MF5911, MF5913, MF5914, MF5915, MF5916, Etc.) ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to 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) ML15134A2422015-05-20020 May 2015 Relief Request RI-08, Revision 0, Relief from Reactor Vessel Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections, for the Fourth 10-Year Inservice Inspection Interval ML14365A0932015-01-13013 January 2015 Correction to Safety Evaluation Dated December 12, 2014, Regarding Amendment No. 249, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML14323A6442014-12-12012 December 2014 Issuance of Amendment No. 249, Request to Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML14190A0042014-07-25025 July 2014 Redacted, Review of License Renewal Commitment Review Related to Core Plate Hold Down Bolt Inspection Plan and Analysis (TAC Nos. ME9550 and MF3557) 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 ML13263A1532013-10-0707 October 2013 Correction to Amendment No. 247 Issued 9/12/13, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report 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 ML13148A2252013-06-26026 June 2013 Issuance of Amendment No. 246, Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation ML13143A3452013-06-0606 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13032A5262013-02-22022 February 2013 Issuance of Amendment No. 245, Revise Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML12313A1112013-01-22022 January 2013 Relief Request RI-07 from ASME Code Requirements for Residual Heat Removal Shell Circumferential and Nozzle to Head Welds, Fourth 4th 10-Year Inservice Inspection Interval 2024-01-03
[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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 January 31, 2012 Mr. Brian Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 COOPER NUCLEAR STATION -ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION 3.4.3 TO REDUCE THE NUMBER OF SAFETY RELIEF VALVES REQUIRED TO BE OPERABLE FOR OVERPRESSURE PROTECTION (TAC NO. ME5287)
Dear Mr. O'Grady:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 240 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 5, 2011, as supplemented by letters dated October 6 and 18, 2011. The amendment revises TS 3.4.3, "Safety/Relief Valves (SRVs) and Safety Valves (SVs)." The original proposed TS changes would have revised the required number of safety relief valves (SRVs) required to be operable for overpressure protection and Anticipated Transient without Scram from eight to five. By letter dated October 6, 2011, the licensee revised its submittal to propose revising the required number of SRVs to be operable from eight to seven. A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
1. Amendment No. 240 to DPR-46 2. Safety Evaluation cc w/encls: Distribution vIa Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 NEBRASKA PUBLIC POWER DOCKET NO. COOPER NUCLEAR AMENDMENT TO RENEWED FACILITY OPERATING Amendment No. 240 License No. DPR-46 The U.S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Nebraska Public Power District (the licensee), dated January 5,2010, as supplemented by letters dated October 6 and 18, 2011 , complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission: There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Enclosure 1
-Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-46 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 240, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. DPR-46 and Technical Specifications Date of Issuance: January 31, 2012 ATTACHMENT TO LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Renewed Facility Operating License No. DPR-46 and Appendix A Technical Specifications with the enclosed revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Renewed Facility Operating License REMOVE INSERT -3-Technical Specifications REMOVE INSERT 3.4-6 3.4-6
-(5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2419 megawatts (thermal). (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 240, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. (3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Cooper Nuclear Station Safeguards Plan," submitted by letter dated May 17, 2006. NPPD shall fully implement and maintain in effect all provisions of the approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NPPD CSP was approved by License Amendment No. 238. (4) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Cooper Nuclear Station (CNS) Updated Safety Analysis Report and as approved in the Safety Evaluations dated November 29, 1977; May 23, 1979; November 21. 1980; April 29, 1983; April 16, 1984; June 1, 1984; January 3, 1985; August 21! 1985; April 10, 1986; September 9, 1986; November 7, 1988; February 3, 1989; August 15, 1995; and July 31, 1998, subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Amendment No. 240 SRVs and SVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (SRVs) and Safety Valves LCO 3.4.3 The safety function of 7 of 8 SRVs and 3 SVs shall be APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required SRVs or SVs inoperable. A.1 Be in MODE 3. AND A.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Cooper 3.4*6 Amendment No. 240 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 240 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 1.0 INTRODUCTION By application dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 110100291), as supplemented by letters dated October 6 and 18, 2011 (ADAMS Accession Nos. ML 11287 A 138 and ML 11297 A033, respectively), Nebraska Public Power District (the licensee), submitted a license amendment request (LAR) in which it requested changes to the Technical Specifications (TSs) for Cooper Nuclear Station (CNS). The amendment would revise TS 3.4.3, "Safety/Relief Valves (SRVs and Safety Valves (SVs)." Specifically, the amendment would reduce the required number of safety relief valves (SRVs) required to be operable for overpressure protection (OPP) and Anticipated Transient without Scram (ATWS) from eight to seven. The original proposed TS changes would have revised the required number of SRV required to be operable for OPP and A TWS from eight to five. By letter dated October 6, 2011, the licensee supplemented the LAR to propose revising the required number of SRVs to be operable from eight to seven. The supplemental letters dated October 6 and 11, 2011, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on November 1,2011 (76 FR 67488). Enclosure 2
-2 2.0 REGULATORY EVALUATION 2.1 System Description (as stated by the licensee) In its letter dated January 5, 2011, the licensee states: CNS is a boiling-water reactor (BWR) of General Electric BWR/4 design, with a Mark I containment. The pressure relief system at CNS includes three Dresser safety valves (SVs) and eight Target Rock SRVs, all of which are located on the main steam lines, within the drywell, between the reactor vessel and the first main steam isolation valve (MSIV). The SVs discharge directly to the interior space of the drywell and the SRVs discharge to the suppression pool. The safety function (Le., spring-lift function) of each Target Rock SRV is actuated by a pilot valve assembly. In the event that reactor pressure vessel pressure (RPV) rises to the nominal setpoint (NSP) of the SRV (1080 to 1100 psig [pounds per square inch gauge]), the pilot valve will open, admitting steam and allowing the reactor pressure itself to open the SRV and relieve pressure. The Dresser SVs are held closed by a large mechanical spring. Once the Dresser SV NSP is reached (1240 psig), vessel pressure will act against the spring (directly on the valve disc) to open the SV. Together, the SVs and the spring-lift function of the SRVs provide overpressure protection for the reactor vessel as required by the ASME [American Society of Mechanical Engineers Boiler and Pressure Vessel] Code. The pilot-actuated, SRV spring-lift function of the Target Rock SRVs is completely independent of the pressure relief function of these valves. In the Automatic Depressurization System (ADS) and Low Low Set (LLS) modes, the SRVs are pneumatically actuated by direct current powered ADS solenoids, which will admit nitrogen from the ADS accumulators to open the SRVs for pressure control. The ADS serves as backup to the High Pressure Coolant Injection system and is actuated by completely different logic/trip signals. The first lift of any SRV coincident with a pressure scram signal will arm the LLS function. On second and subsequent lifts, the LLS valves will take over, controlling reactor pressure and minimizing SRV cycling. In its letter dated January 5, 2001, the licensee also states: The safety objective of the pressure relief system is to prevent overpressurization of the nuclear system; this protects the RCPB [reactor coolant pressure boundary] from failure which could result in the uncontrolled release of fission products. In addition, the automatic depressurization feature of the pressure relief system acts in conjunction with the emergency core coolant system for reflooding the core. This protects the reactor fuel cladding from failure due to overheating. 2.2 General Requirements Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRC's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications,"
-which requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operations (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls. The regulations in 10 CFR 50.36(c)(2){i), "Limiting conditions for operation," state, in part, that Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. The regulations in 10 CFR 50.36{c)(3), "Surveillance requirements," state that Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. CNS construction predated the issuance of 10 CFR 50, Appendix A 1, "General Design Criteria for Nuclear Power Plants." CNS is designed to conform to the proposed general design criteria (GOC) published in the July 11, 1967, Federal Register, except where commitments were made to specific 1971 GOC. The Atomic Energy Commission accepted CNS conformance with the proposed GOC. By letter dated January 5, 2011, the licensee appropriately identified the following draft GOC as specified in Appendix F to the CNS Updated Safety Analysis Report (USAR):
- USAR Appendix F, Criterion 9, Reactor Coolant Pressure Boundary The reactor coolant pressure boundary shall be designed and constructed so as to have an exceedingly low probability of gross rupture or significant leakage throughout its design lifetime.
- USAR Appendix F, Criterion 14, Core Protection Systems Core protection systems, together with associated equipment, shall be designed to act automatically to prevent or to suppress conditions that could result in exceeding acceptable fuel damage limits.
- USAR Appendix F, Criterion 37, Engineered Safety Features Basis for Design Engineered safety features shall be provided in the facility to back up the safety provided by the core design, the reactor coolant pressure boundary, and their protection systems. As a minimum, such engineered The 1967 Proposed GDC as described in the CNS updated safety analysis report, Appendix F, are the licensing basis for CNS; however, the NRC staff concluded in its 1973 Safety Evaluation Report for CNS that the intent of the 1971 Final Rule for 10 CFR Part 50, Appendix A. had also been met.
-4 safety features shall be designed to cope with any size reactor coolant pressure boundary break up to and including the circumferential rupture of any pipe in that boundary assuming unobstructed discharge from both ends. 3.0 TECHNICAL EVALUATION 3.1 Proposed Changes The current CNS TS 3.4.3 LCO states, The safety function of 8 SRVs and 3 SVs shall be OPERABLE. Revised TS 3.4.3 LCO would state, The safety function of 7 of 8 SRVs and 3 SVs shall be OPERABLE. In addition, the current TS 3.4.3 LCO Condition A. states, One or more SRVs or SVs inoperable. Revised TS 3.4.3 LCO Condition A. would state, One or more required SRVs or SVs inoperable. The licensee also proposed to make conforming changes to the TS Bases. 3.2 Licensee Evaluation As part of the analysis of the proposed reduction of number of SRVs required, GE Hitachi submitted analysis of ASME OPP and ATWS. These evaluations were performed with three SRVs out of service (OOS). After the supplement to propose one SRV OOS, the results of three SRVs OOS are still bounding. The limiting event for the ASME OPP is the MSIV Closure on High Flux. The analysis conservatively assumed core power as well as core flow. End of Cycle conditions were also assumed and are most limiting due to power shapes typically being peaked towards the top of the core and the worth of the early part of the scram is minimized. SRV setpoints were varied and conservatively assumed to be 3 percent above the setpoint. The results of the ASME OPP analysis showed that with three SRVs OOS, the remaining SRVs would be able to mitigate the OPP event with margin to both the dome pressure safety limit of 1337 psig and the peak vessel pressure of 1375. These results conservatively bound the supplemental LAR of one OOS SRV. GE Hitachi used the bounding A TWS evaluation to determine the maximum number of SRVs that could be OOS and still mitigate the event. The evaluation showed that three SRVs could be out of service and the A TWS could still be mitigated. The original LAR requested three SRVs OOS stemming from this evaluation of the maximum number of SRVs OOS in the most limiting event.
-Peak reactor power was assumed and both Beginning of Cycle and End of Cycle conditions were evaluated. The SRVs were assumed to open at the +3 percent range of their setpoint as well. Two ATWS events were analyzed; ATWS with Main Steam Isolation Valve Closure and with Pressure Regulator Failure -Open. These two events were evaluated since they were found to be substantially more limiting than ATWS with Loss of Auxiliary Power or with Inadvertent Opening of Relief Valve. The results showed that CNS would stay under the allowed limits for the ATWS events. The peak vessel pressure was shown to stay below 1500 psig. The peak cladding temperature stayed below 2200 degrees Fahrenheit. The peak vessel pressure came out to be 1489 psig and the peak cladding temperature came out to be 1442 degrees Fahrenheit. These results were under the limits and also came from cases with three SRVs OOS. 3.3. NRC Staff Evaluation By letter dated January 5, 2011, NPPD requested that three SRVs be allowed to be OOS. In evaluating the proposed change, the NRC staff determined that additional information was needed to complete its review (ADAMS Accession No. ML 111430704). Among other issues, the NRC questioned whether the proposed change would involve a significant increase in the probability or consequences of an accident previously evaluated and involve a significant reduction in a margin of safety as described in the Updated Safety AnalYSis Report. During a publicly noticed telephone call on July 12, 2011 (ADAMS Accession No. ML 112170081), NPPD stated that it would submit a revision to the LAR revising the No Significant Hazards Consideration (NSHC) clarifying why the change in probability or consequences and margin is not significant. Subsequent to the public telephone call, by letter dated October 6, 2011, NPPD decided to supplement the LAR to request seven of eight SRVs be required rather than five of eight SRVs and submitted a revised NSHC. The NPPD request would allow one SRV to be OOS. The NRC staff concludes that the licensee has shown that there is reasonable assurance of safety with one SRV OOS and that sufficient margin is maintained throughout the OPP and A TWS events, as evaluated. 3.4 NRC Staff Conclusion The NRC staff has reviewed the proposed changes to TS 3.4.3 regarding the reduction of the safety function of SRVs required to be operable from eight to seven. The staff concludes that the licensee provided sufficient analYSis and calculations to show that CNS would be reasonably assured to operate safely and that margin is maintained in OPP and ATWS scenarios. Furthermore, the NRC staff concludes that the proposed TS changes are in accordance with 10 CFR 50.36 and the applicable draft GDC as described in the CNS USAR. Therefore, the NRC staff concludes that the proposed TS change is acceptable. The NRC staff has no objection to the licensee's proposed changes to the TS Bases. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official had no comments.
-6 5.0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 1,2011 (76 FR 67488). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b}, no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. 6.0 CONCLUSION The Commission has concluded, based on the considerations discussed above, that: (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. Principal Contributor: J. Miller Date: January 31, 2012 January 31, 2012 Mr. Brian Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 COOPER NUCLEAR STATION -ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION 3.4.3 TO REDUCE THE NUMBER OF SAFETY RELIEF VALVES REQUIRED TO BE OPERABLE FOR OVERPRESSURE PROTECTION (TAC NO. ME5287)
Dear Mr. O'Grady:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 240 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 5, 2011, as supplemented by letters dated October 6 and 18,2011. The amendment revises TS 3.4.3, "Safety/ReliefValves (SRVs) and Safety Valves (SVs)." The original proposed TS changes would have revised the required number of safety relief valves (SRVs) required to be operable for overpressure protection and Anticipated Transient without Scram from eight to five. By letter dated October 6, 2011, the licensee revised its submittal to propose revising the required number of SRVs to be operable from eight to seven. A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,IRA! Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosures:
1. Amendment No. 22. Safety Evaluation 40 to DPR-46 cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPLIV rlf RidsAcrsAcnw_MailCTR RidsNrrDeEicb Resource RidsNrrDorlDpr Resource Resource RidsNrrDorlLpl4 Resource RidsNrrDssSrxb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsOgcRp Resource RidsRgn4MailCenter Resource JMiller. NRRlDSS/SRXB MHamm. NRRlDSS/STSB SMazumdar, NRRlDE/EICB ADAMS Accession No. ML113630258 *memodated NRRILPL4/PM NRR/LPL4/LA NRR/DSS/STSB/BC NRRIDSS/SRXB/BC LWilkins JBurkhardt RElliott AUlses* 1/10/12 1/10/12 1110112 12127/11 OFFICE NRR/DE/EICB/BC OGC NLO L4/BC NRR/LPL4iPM NAME GWilson LSubin LWilkins DATE 1/12/12 1/20/12 1/31112