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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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Mr. Oscar Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 August 27, 2015
SUBJECT: COOPER NUCLEAR STATION -ISSUANCE OF AMENDMENT REQUEST TO DELETE CONDENSATE STORAGE TANK AS AN ALTERNATE SOURCE OF MAKEUP WATER {TAC NO. MF4716)
Dear Mr. Limpias:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 252 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment deletes condensate storage tank (CST) as an alternate source of makeup water in response to your application dated August 26, 2014, as supplemented by letters dated February 25 and July 13, 2015. The amendment would revise the CNS Technical Specifications {TSs) by deleting Option b from TS Surveillance Requirement 3.5.2.1. Option b allows use of CST A as an alternative source of makeup water to the reactor pressure vessel during MODE 4 and MODE 5, but CST A is not qualified to Seismic Category I. 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. Docket No. 50-298
Enclosures:
1. Amendment No. 252 to DPR-46 2. Safety Evaluation cc w/encls: Distribution via Listserv
Sincerely,Siva P. Lingam, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 License No. DPR-46 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Nebraska Public Power District (the licensee), dated August 26, 2014, as supplemented by letters dated February 25 and July 13, 2015, 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; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. 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; D. 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 E. 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
-2 -2. 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: (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 252, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
Changes to the Renewed Facility Operating License No. DPR-46 and Technical Specifications FOR THE NUCLEAR REGULA TORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: August 2 7, 2o1 5 ATTACHMENT TO LICENSE AMENDMENT NO. 252 RENEWED FACILITY OPERA TING LICENSE NO. DPR-46 DOCKET NO. 50-298 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--3-Technical Specifications REMOVE INSERT 3.5-9 3.5-9
-3 -(5) Pursuant to the Act and 1 O 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. C. 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. 252, 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 (51 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 as supplemented by changes approved by License Amendments 244 and 249. ( 4) Fire Protection NPPD shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated April 24, 2012 (and supplements dated July 12, 2012, January 14, 2013, February 12, 2013, March 13, 2013, June 13, 2013, December 12, 2013, January 17, 2014, February 18, 2014, and April 11, 2014), and as approved in the safety evaluation dated April 29, 2014. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if Amendment No. 252 ECCS -Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SR 3.5.2.3 Cooper SURVEILLANCE FREQUENCY Verify, for each required ECCS injection/spray 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> subsystem, the suppression pool water level is 12 ft 7 inches. Verify, for each required ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve. ----------------------NOTE------------------------------One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. Verify each required ECCS injection/spray subsystem 31 days manuaf, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. (continued) 3.5-9 Amendment No. 252 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 252 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 August 26, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14246A203), as supplemented by letters dated February 25 and July 13, 2015 (ADAMS Accession Nos. ML15062A037 and ML15202A127, respectively), Nebraska Public Power District (the licensee), requested changes to the Technical Specifications (TSs) for Cooper Nuclear Station (CNS). The license amendment request (LAR) would delete condensate storage tank (CST) as an alternate source of makeup water. The proposed changes would revise the CNS TSs by deleting Option b from TS Surveillance Requirement (SR) 3.5.2.1. Option b allows use of CST A as an alternative source of makeup water to the reactor pressure vessel during MODE 4 and MODE 5, but CST A is not qualified to Seismic Category I, which could cause the safety systems to which it is connected to become technically "Inoperable." CNS revised procedures for core spray (CS) and residual heat removal (RHR) low-pressure coolant injection (LPCI) systems will note that aligning the CS or RHR pumps to take suction from CST A in MODES 4 and 5 could result in the pumps to be technically inoperable for TS purposes due to the CST being Seismic Class II and the pumps being Seismic Class I. The supplemental letters dated February 25 and July 13, 2015, 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) staff's original proposed no significant hazards consideration determination as published in the Federal Register on December 23, 2014 (79 FR 77047). 1 .1 System Description The emergency core cooling system (ECCS) is designed to limit the release of radioactive materials to the environment following a loss-of-coolant accident using flooding and spraying to cool the core. The ECCS systems at CNS consist of the high-pressure coolant injection (HPCI) system, the CS system, the LPCI mode of RHR system, and the automatic depressurization system. The low-pressure ECCS injection/spray subsystems consist of two CS subsystems and Enclosure 2
-2 -two LPCI subsystems. Each CS subsystem consists of one motor-driven pump, piping, and valves to transfer water from the suppression pool or CST to the reactor pressure vessel. Each LPCI subsystem consists of one motor-driven pump, piping, and valves to transfer water from the suppression pool or CST to the reactor pressure vessel. The suppression pool provides the required source of water for the ECCS. The emergency CSTs are capable of providing a source of water for the HPCI system. CST A is capable of providing a source of water for the CS system and LPCI subsystems. SR 3.5.2.1 requires a minimum water level of 12 feet 7 inches for the suppression pool to ensure that CS and LPCI system pumps have adequate net positive suction head. Currently, with the suppression pool water level less than the required limit, all ECCS injection and spray subsystems could be considered inoperable unless aligned to CST A. The condensate storage system provides station system makeup, receives system reject flow, and provides condensate for any continuous service needs and intermittent batch type services. The total stored design quantity is based on the demand requirements during refueling for filling the dryer separator pool, the reactor well, and for coping with a station blackout event. One 450,000-gallon (CST A) and one 700,000-gallon (CST B) capacity CST supply the various station requirements. They can receive demineralized makeup water from the water treatment plant of reprocessed water from the radwaste system. The tanks are constructed of coated carbon steel with electric heaters for anti-freeze protection. 1.2 Background As reported in the LAA, TS changes related to using CST A as a suction path for CS and LPCI when draining the suppression chamber date back to Amendment No. 11 issued December 30, 1975 (ADAMS Accession No. ML021340436), and Amendment 12 issued October 6, 1975 (ADAMS Accession No. ML021340469). The licensee submitted these amendment requests to satisfy a request from the NRC to revise TSs to allow for the draining of the suppression pool and inspection of safety relief valve supports. Modifications were made to the amendments to add the use of the CST as a suction path for ECCS pumps. In its submittal dated August 26, 2014, the licensee states that NRC inspectors questioned if the NRC had been properly apprised that CST A is a Seismic Class II, non-safety-related system, which ties into the Seismic Class I safety-related systems of the CS and LPCI systems. The inspectors questioned whether provisions in TSs, which allow alignment of ECCS to the CST, would render the ECCS pumps inoperable for TS purposes because the CST could not be relied on to survive a safe shutdown earthquake. 2.0 REGULATORY EVALUATION The regulatory requirements and guidance which the NRC staff considered in its review of this LAA are:
- The regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, Technical specifications," contain the requirements for the
-3 -content of TSs. Pursuant to 1 O CFR 50.36(c), TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
- Paragraph 1 O CFR 50.36(c)(3) identifies SRs as one of the categories to be included in TSs and states that SRs 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."
- NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety," dated December 29, 1998 (ADAMS Accession No. ML031110108), discusses the NRC's staff expectations regarding the correction of facility TSs when they are found to contain non-conservative values or specify incorrect actions. This letter also recommends that short-term corrective actions, in the form of administrative controls at the affected facility, will be followed with a formal amendment to the TS to address the non-conservative values or incorrect actions.
- Appendix A to 10 CFR Part 50, "General Design Criteria of Nuclear Power Plants," Criterion 19--Control room, provides requirements for the Control Room from which actions can be taken to operate the plant safely under normal and accident conditions.
- Section 50.120, "Training and qualification of nuclear power plant personnel," of 1 O CFR Part 50, provides requirements to establish, implement, and maintain a training program.
- NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," contains acceptance criteria based on meeting the relevant requirements of the Commission regulations, specifically: Chapter 13.2.1, Revision 3, "Reactor Operator Requalification Program; Reactor Operator Training" (ADAMS Accession No. ML070100636); Chapter 13.5.2.1, Revision 2, "Operating and Emergency Operating Procedures" (ADAMS Accession No. ML070100635); and Chapter 18, Revision 2, "Human Factors Engineering" (ADAMS Accession No. ML070670253).
-4 -* NUREG-0700, Revision 2, "Human-System Interface Design Review Guidelines," May 2002 (ADAMS Accession Nos. ML021700373).
- NUREG-0711, Revision 3, "Human Factors Engineering Program Review Model," November 2012 (ADAMS Accession No. ML 12324A013). 3.0 TECHNICAL EVALUATION 3.1 Proposed TS Changes In the LAA dated August 26, 2014, the licensee proposed the following change in TS 3.5.2, "ECCS -Shutdown": Current SR 3.5.2.1 states: Verify, for each required ECCS injection/spray subsystem, the: a. Suppression pool water level is 12 ft 7 inches; or b. --------------------------------------------------N()TE---------------------------------------()nly one required ECCS injection/spray subsystem may take credit for this option during OPDRVs.111 Condensate storage tank (CST A) water level is 14 ft. Revised SR 3.5.2.1 would state: Verify, for each required ECCS injection/spray subsystem, the suppression pool water level is 12 ft 7 inches. 3.2 NRC Staff Evaluation In its LAA, the licensee has proposed to delete Option b from TS SR 3.5.2.1. TS SR Option b allows the use of CST A as an alternate source of makeup water to the reactor pressure vessel during MODE 4 and MODE 5. Deleting Option b would eliminate the requirement to verify ECCS CST A subsystem requirements and the associated Note. This would reconcile the potential for ECCS pumps becoming inoperable due to a seismic event that can cause the CST to fail. Using a long-term cooling analysis, the licensee has determined that following a design basis loss-of-coolant accident only one low-pressure ECCS injection/spray system is required to provide sufficient heat removal and maintain adequate reactor vessel water level. In MODES 4 and 5, there is low pressure and low-temperature conditions, which require only one pressure ECCS injection/spray system to maintain adequate reactor vessel water level in the 1 Operations with a potential for draining the reactor vessel.
-5 -event of an inadvertent vessel drain down. CNS requires a minimum of two low-pressure ECCS injection or spray subsystems to be OPERABLE in MODES 4 and 5 for redundancy. When suppression pool level is less than 12 feet, 7 inches, the CS system and LPCI subsystems are considered OPERABLE only if they can take suction from CST A. The NRC staff reviewed the proposed deletion of the option to use CST A as an alternate method to provide makeup water to the reactor pressure vessel, along with information contained in the Updated Final Safety Analysis Report (UFSAR), the current TSs. ECCS performance is evaluated for the entire spectrum of possible break sizes including loss-of-coolant accident (LOCA) and drain-down events. NRC request for additional information (RAI) dated January 29, 2015 (ADAMS Accession No. ML 15029A050) asked the licensee to describe how makeup water will be provided to the reactor pressure vessel in a drain-down event, if the ECCS is inoperable, as a result of suppression pool water level less than the required TS limit, if CST A is deleted as an alternate source of water. In its February 25, 2015 RAI response, the licensee stated that, with the suppression pool water level below 12 feet 7 inches, ECCS remains available for makeup water to the reactor pressure vessel. The licensee further described that, in the event of inadvertent drain down below 12 feet 7 inches, LCO 3.5.2 Condition C will be entered and all operations with a potential for draining the reactor vessel must be suspended immediately along with restoration of ECCS operability within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ECCS is restored using Emergency Operating Procedure 5.8.14, "Suppression Pool Make up Systems." The licensee included methods of supplying water to the suppression pool, to restore level, using the main condensate system or reactor building auxiliary condensate booster pump. This is accomplished by aligning to the HPCI minimum flow line, the reactor core isolation cooling minimum flow line, the AHR suppression pool cooling line or the CS test line. Water sources used for level restoration are the CST A and CST B, demineralized water tank, main condenser A and B. The NRC staff reviewed the systems used to supply water to the suppression pool to determine their safety classification. Section Xll-2.1.2.3, "Class I Equipment," of the CNS UFSAR lists the Class I systems required for safe shutdown and isolation of the reactor. All piping and components in the HPCI, reactor core isolation cooling, AHR, and CS systems are included as Class I equipment. This ensures that while in MODES 4 and 5, one low-pressure ECCS injection/spray subsystem will not be impacted by a seismic event and can maintain adequate reactor vessel water level in the event of an inadvertent vessel drain down. With Option b removed from TS SR 3.5.2.1, the suppression pool can be restored above the TS level of 12 feet 7 inches using the systems listed above, which will satisfy LCO 3.5.2 Condition C and restore ECCS to OPERABLE status. Based on the information provided by the licensee in the LAA and RAI responses, the NRC staff concludes that the change does not affect the ability of the ECCS to maintain adequate reactor vessel water level. Therefore, the NRC staff concludes that the proposed change to TS SR 3.5.2.1 is acceptable.
-6 -3.3 Description of Operator Action(s) and Assessed Safety Significance The LAR proposed by the licensee will prohibit alignment of RHR and CS suctions to CST A during MODE 4 and MODE 5. In accordance with the generic risk categories established in Appendix A to NUREG-1764, these task sequences are considered "of low risk-importance" due to the fact that they are prohibited for reactor cooldown during shutdown. Because of the low potential risk, the NRC staff performed a "Level Three" review (i.e., the least stringent of the graded reviews possible under the guidance of NUREG-1764). 3.4 Human-System Interface Design The NRC staff concludes that Human-System Interface design, including the design of the Safety Parameter Display System, will not be affected by the proposed LAR because no changes are being made to the design of the Control Room. 3.5 Procedure Design Removal of Option b from TSs will affect two procedures, Procedure 2.2.9, "CS System, Revision 75, and 2.2.69.1, "RHR LPCI Mode, Revision 26. The licensee stated that this option was used infrequently and only while the plant was shut down. The licensee plans to clarify these two procedures concerning RHR and CS alignment to the CST. The NRC staff concludes that this approach to controlling operator actions is consistent with NUREG-0711 and is, therefore, acceptable. 3.6 Training Program and Simulator Design The licensee stated that, as part of the license amendment implementation, the training lesson plans for CS and RHR systems and the lesson plan for TS 3.5, "Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) System," will be revised to remove reference to operability when the system is aligned to take suction from the CST. Changes to the simulator are not necessary. The NRC staff concludes that this approach to training is consistent with NUREG-0711 and 1 O CFR 50.120, and is acceptable to support this proposed LAR. 3.7 Human Factors Verification and Validation Because no operator actions were added or changed, verification and validation are not necessary. This is consistent with the guidance of NUREG-0711 and, therefore, the NRC staff finds this acceptable. 3.8 Summary The NRC staff has reviewed the proposed LAR and concludes that the proposed changes are consistent with the requirements of 10 CFR 50.36 and NRC guidance for the content of the
-7 -ECCS TS. Therefore, the NRC staff concludes that the proposed amendment to delete the CST as an alternate source of makeup water, from SR 3.5.2.1 Option b, is acceptable. The NRC staff concludes that the proposed LAR is acceptable from the stand point of procedural controls and human performance. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment on August 4, 2015. The State official had no comments. 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, and changes SR. 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 December 23, 2014 (79 FR 77047). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 1 O CFR 51.22{c){9}. Pursuant to 1 O 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) there is reasonable assurance that 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 Contributors: T. Sweat, NRR G. Lapinsky, NRR Date: August 27, 2015 August 27, 2015 Mr. Oscar Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321 SUBJECT: COOPER NUCLEAR STATION -ISSUANCE OF AMENDMENT REQUEST TO DELETE CONDENSATE STORAGE TANK AS AN ALTERNATE SOURCE OF MAKEUP WATER (TAC NO. MF4716)
Dear Mr. Limpias:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 252 to Renewed Facility Operating License No. DPR-46 for the Cooper Nuclear Station (CNS). The amendment deletes condensate storage tank (CST) as an alternate source of makeup water in response to your application dated August 26, 2014, as supplemented by letters dated February 25 and July 13, 2015. The amendment would revise the CNS Technical Specifications (TSs) by deleting Option b from TS Surveillance Requirement 3.5.2.1. Option b allows use of CST A as an alternative source of makeup water to the reactor pressure vessel during MODE 4 and MODE 5, but CST A is not qualified to Seismic Category I. 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. Docket No. 50-298
Enclosures:
Sincerely,IRA/ Siva P. Lingam, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1. Amendment No. 252 to DPR-46 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDor1Lp14-1 Resource RidsNrrDraAphb Resource RidsNrrDssSbpb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCooper Resource RidsRgn4MailCenter Resource KWest, NRR/DSS/STSB GLapinsky, NRR/DRA/APHB TSweat, NRR/DSS/SBPB ADAMS Accession No. ML 15216A259 *via memo OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SBPB/BC NRR/DRA/APHB/BC NAME SLingam JBurkhardt GCasto* SWeerakkody* DATE 8/5/15 8/4/15 8/3/15 7/23/15 OFFICE NRR/DSS/STSB/BC OGC (NLO) NRR/DORL/LPL4-1 /BC N RR/DORL/LPL4-1 /PM NAME RElliott (MChernoff for) MYoung MMarkley Sling am DATE 8/11/15 8/19/15 OFFICIAL RECORD COPY