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Category:Emergency Preparedness-Emergency Plan
MONTHYEARNLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station ML21307A3102021-11-0303 November 2021 Emergency Plan, Revision 79 NLS2021064, Submittal of Revision 79 to Emergency Plan2021-11-0303 November 2021 Submittal of Revision 79 to Emergency Plan NLS2021053, Emergency Plan Implementing Procedure2021-08-30030 August 2021 Emergency Plan Implementing Procedure NLS2021040, Submittal of Emergency Plan, Revision 77 and Summary of 50.54( Q) Analysis2021-06-14014 June 2021 Submittal of Emergency Plan, Revision 77 and Summary of 50.54( Q) Analysis ML21130A6002021-05-10010 May 2021 On-Shift Staffing Analysis, Revision 3 NLS2021001, Emergency Plan, Revision 76, On-Shift Staffing Analysis, Revision 2, and Emergency Plan Implementing Procedures2021-01-0606 January 2021 Emergency Plan, Revision 76, On-Shift Staffing Analysis, Revision 2, and Emergency Plan Implementing Procedures NLS2020051, Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change2020-08-25025 August 2020 Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change NLS2020022, Submittal of Emergency Plan Implementing Procedures2020-04-28028 April 2020 Submittal of Emergency Plan Implementing Procedures ML20115E3592020-04-0909 April 2020 Emergency Plan, Revision 75 NLS2020014, Nebraska Public Power District - Report of Changes to Emergency Plan Implementing Procedure Cooper Nuclear Station, Docket No. 50-298, DPR-462020-03-0303 March 2020 Nebraska Public Power District - Report of Changes to Emergency Plan Implementing Procedure Cooper Nuclear Station, Docket No. 50-298, DPR-46 NLS2019010, Emergency Plan, Revision 722019-02-22022 February 2019 Emergency Plan, Revision 72 NLS2018036, Summary of 50.54(q) Analyses of Emergency Plan, Revision 712018-06-14014 June 2018 Summary of 50.54(q) Analyses of Emergency Plan, Revision 71 ML18044A1092018-02-0606 February 2018 Summary of 50.54(q) Analyses, Emergency Plan, Revision 70 NLS2018005, Submittal of Emergency Plan, Revision 702018-02-0606 February 2018 Submittal of Emergency Plan, Revision 70 NLS2017026, Emergency Plan, Revision 692017-03-14014 March 2017 Emergency Plan, Revision 69 ML17079A0092017-03-14014 March 2017 Submittal of Emergency Plan, Revision 69 NLS2013066, Emergency Plan, Revision 642013-06-24024 June 2013 Emergency Plan, Revision 64 ML0619404222006-07-0707 July 2006 Information on Protective Action Areas and Evacuation Routes NLS2005006, Change to Emergency Plan Implementing Procedure2005-01-28028 January 2005 Change to Emergency Plan Implementing Procedure NLS2004066, Emergency Plan, Revision 462004-05-10010 May 2004 Emergency Plan, Revision 46 2023-01-04
[Table view] Category:Letter type:NLS
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays 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 NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station NLS2022031, Licensee Guarantees of Payment of Deferred Premiums2022-07-19019 July 2022 Licensee Guarantees of Payment of Deferred Premiums NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-06-16016 June 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements NLS2022025, Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring2022-06-0606 June 2022 Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring NLS2022016, Annual Radiological Environmental Report2022-05-10010 May 2022 Annual Radiological Environmental Report NLS2022020, Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report2022-05-0202 May 2022 Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report NLS2022014, Annual Radioactive Effluent Release Report2022-04-27027 April 2022 Annual Radioactive Effluent Release Report NLS2022010, Annual Report of Individual Exposure Monitoring2022-04-0505 April 2022 Annual Report of Individual Exposure Monitoring NLS2022009, Property Insurance Coverage2022-03-23023 March 2022 Property Insurance Coverage NLS2022011, Preparation and Scheduling of Operator Licensing Examinations2022-03-18018 March 2022 Preparation and Scheduling of Operator Licensing Examinations NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 NLS2021067, ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan2021-12-16016 December 2021 ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan NLS2021069, Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-12-15015 December 2021 Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 2024-01-25
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021058, Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-10-12012 October 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2020051, Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change2020-08-25025 August 2020 Response to Nuclear Regulatory Commission'S Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change ML18311A1862018-11-0505 November 2018 Email (11-5-18) RR RFI Responses for Review NLS2018029, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-032018-05-16016 May 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RR5-03 NLS2018017, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station Independent Spent Fuel Storage Installation2018-04-11011 April 2018 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Nebraska Public Power District'S Decommissioning Funding Plan Update for Cooper Nuclear Station Independent Spent Fuel Storage Installation ML18241A3822018-03-23023 March 2018 CNS Email to Beaulieu, George, Kumana: Response to CNS Fan Coil Unit Questions NLS2018012, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-032018-03-14014 March 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI5-03 NLS2018011, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Requests RR5-02 and RR5-032018-03-0808 March 2018 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Requests RR5-02 and RR5-03 NLS2017095, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI-21, Revision 12017-11-30030 November 2017 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request RI-21, Revision 1 NLS2017072, Nebraska Public Power District'S Seismic High Frequency Confirmation - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from2017-08-24024 August 2017 Nebraska Public Power District'S Seismic High Frequency Confirmation - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from t ML17244A2812017-05-0808 May 2017 16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation. NLS2017012, Response to NRC Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report2017-02-0808 February 2017 Response to NRC Request for Information Regarding Near Term Task Force Recommendation 2.1 (Seismic) - Spent Fuel Pool Evaluation Report NLS2016067, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 32016-12-0707 December 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3 NLS2016075, Response to Nuclear Regulatory Commission RAI Regarding License Amendment Request to Adopt TSTF-425, Rev 32016-12-0707 December 2016 Response to Nuclear Regulatory Commission RAI Regarding License Amendment Request to Adopt TSTF-425, Rev 3 ML16258A3732016-11-16016 November 2016 Cooper Nuclear Station - Response Regarding Phase 2 Staffing Submittals Associated with Near-Term Task Force Recommendation 9.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (CAC No. MF7776) NLS2016053, Nebraska Public Power District'S Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information2016-09-14014 September 2016 Nebraska Public Power District'S Spent Fuel Pool Evaluation Report - Response to Nuclear Regulatory Commission Request for Information ML16252A2232016-08-29029 August 2016 Response to NRC Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016045, Nebraska, Final Six-Month Status Report and Response to Request for Additional Information in Response to Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-08-22022 August 2016 Nebraska, Final Six-Month Status Report and Response to Request for Additional Information in Response to Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) NLS2016029, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 9.3, Emergency Preparedness - Staffing, Requested Information Items 1,2, and 6 - Phase 2 Staffing Assessment2016-05-18018 May 2016 Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 9.3, Emergency Preparedness - Staffing, Requested Information Items 1,2, and 6 - Phase 2 Staffing Assessment ML16084A1822016-03-17017 March 2016 Response to Nuclear Regulatory Commission Request for Additional Information (RAI) Regarding Proposed Changes to the Technical Specifications for Implementation of a New Pressure-Temperature Limits Report NLS2015133, Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-022015-12-21021 December 2015 Response to Nuclear Regulatory Commission Request for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-02 NLS2015123, Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, RP5-012015-11-0909 November 2015 Response to Nuclear Regulatory Commission Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, RP5-01 NLS2015112, Response to NRC Requests for Additional Information for Relief Request No. RR5-01, Alternate Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap2015-10-29029 October 2015 Response to NRC Requests for Additional Information for Relief Request No. RR5-01, Alternate Weld Overlay Repair for a Dissimilar Metal Weld Joining Nozzle to Control Rod Drive End Cap NLS2015113, Response to NRC Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-022015-10-21021 October 2015 Response to NRC Requests for Additional Information for Relief Request for Fifth Ten-Year Inservice Inspection Interval, R15-02 NLS2015086, Response to Nuclear Regulatory Commission Additional Requests for Additional Information for License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water2015-07-13013 July 2015 Response to Nuclear Regulatory Commission Additional Requests for Additional Information for License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water NLS2015080, Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program2015-06-30030 June 2015 Response to Request for Additional Information for Relief Requests RP-08, Comprehensive Pump Test Upper Limit, and RP-09, Variance Around the Reference Values, for Fifth Ten-Year Interval Pump and Valve Inservice Testing Program NLS2015068, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2. 1, Seismic Hazard and Screening Report2015-06-22022 June 2015 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2. 1, Seismic Hazard and Screening Report 2024-01-25
[Table view] |
Text
H Nebraska Public Power District
.Always there when you need us" NLS2020051 August 25, 2020 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Response to Nuclear Regulatory Commission's Supplemental Request for Additional Information for License Amendment Request for Approval of Emergency Action Level Scheme Change Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. Email from Thomas Wengert, U.S. Nuclear Regulatory Commission, to Linda Dewhirst, Nebraska Public Power District, dated August 14, 2020, "Cooper - Supplemental Final RAI RE: License Amendment Request for Approval of EAL Scheme Change (EPID L-LLA-2020-0028)"
- 2. Letter from Khalil Dia, Nebraska Public Power District, to the U.S.
Nuclear Regulatory Commission, August 6, 2020, "Response to Nuclear Regulatory Commission's Request for Additional Information for License Amendment Request Emergency Action Level Scheme Change"
Dear Sir or Madrun:
The purpose ofthis letter is for the Nebraska Public Power District to respond to the Nuclear Regulatory Commission's supplemental request for additional information (RAI) (Reference 1) related to the Cooper Nuclear Station response to an RAI in Reference 2.
The response to the supplemental RAl question is provided in Attachment 1 to this letter. contains the revised Emergency Action Level (EAL) Technical Basis document pages. Attachment 3 contains the revised EAL Wallchart.
This letter does not contain any new regulatory commitments.
If you have any questions concerning this matter, please contact Linda Dewhirst, Regulatory Affairs and Compliance Manager, at (402) 825-5416.
COOPER NUCLEAR STATION 72676 648A Ave/ P.O. Box 98 / Brownville, NE 68321 http://www.nppd.com
NLS2020051 Page 2 of2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on: I 8' a~ CrJl)
I (Date Jo Dent, Jr.
Vice President and Chief Nuclear Officer
/dv Attachments: 1. Response to Nuclear Regulatory Commission's Supplemental Request for Additional Information (RAI) for License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6
- 2. Revised Cooper Nuclear Station EAL Technical Basis
- 3. Revised EAL Wallchart cc: Regional Administrator w/ attachments USNRC - Region IV Cooper Project Manager w/ attachments USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments CNS Records w/ attachments
NLS2020051 Page 1 of2 Attachment 1 Response to Nuclear Regulatory Commission's Supplemental Request for Additional Information (RAI) for License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 Cooper Nuclear Station, Docket No. 50-298, DPR-46 The Nuclear Regulatory Commission (NRC) supplemental request for additional information regarding the request to adopt an emergency action level (EAL) scheme pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, is shown in italics. The Nebraska Public Power District (NPPD) response to the request is shown in normal font.
Supplemental RAI-3 Fuel Clad Potential Loss-2 (FC-2) and Reactor Coolant System Loss-I (RC-1) use the condition "Reactor Pressure Vessel (RPV) level cannot be determined" as a threshold value. Considering that CNS emergency operating procedures (EOPs) use the condition "RPV water level cannot be determined" in RC-4 [Reactor Coolant] of RPV Control, the CNP EOPs align well with the guidance provided by NEI 99-01, Revision 6for FC-2 and RCS-I. Based on the NRC staff's initial review of the provided technical bases, the EAL comparison matrix, and CNP EOPs, the addition of the parenthetical "RPV Flooding required" could result in unintended delays in the declaration ofa Site Area Emergency classification. As such, RAI-3 stated:
Please explain how the addition of "RPV Flooding required" to the threshold values for FC-2 and RCS-I will not delay or otherwise impact EAL assessment for conditions where RPV level cannot be determined.
In response to RAI-3, NPPD provided a reiteration of information provided in the technical basis discussion, a discussion on valid instrument readings, and the discussion provided in RAI-3 as justification. As such, the NRC staffremains concerned that the addition of "RPV Flooding required" could result in unintended delays in the declaration of a Site Area Emergency classification.
Please explain how the addition of "RPV Flooding required" to the threshold values for FC-2 and RCS-I will not delay or otherwise impact EAL assessment for conditions where RPV level cannot be determined.
This explanation should provide a justification for adding an extra condition to FC-2 and RCS-I, as well as providing a clear definition ofwhat is specifically meant by "RPV Flooding required. "
NLS2020051 Page2 of2 NPPD Response:
The phrase, "RPV Flooding Required," was not intended to be an extra condition nor expected/intended to delay or otherwise impact EAL assessment conditions where RPV water level cannot be determined. Upon further review and to avoid any potential for confusion, NPPD has elected to remove the phrase thereby negating the need to explain how it will not result in an unintended delay in declaration of a Site Area Emergency and the need to provide a clear definition of what is specifically meant by "RPV Flooding Required." Revised pages of the EAL Technical Basis Document are included in Attachment 2 and the revised Hot Condition Wallchart is included in Attachment 3.
NLS2020051 Attachment 2 Revised Cooper Nuclear Station EAL Technical Basis Cooper Nuclear Station, Docket No. 50-298, DPR-46 (Attachment 2 contains two pages)
COOPER EAL Technical Bases Document NUCLEAR Revision XX STATION Attachment 1 - Emergency Action Level Technical Bases Barrier: Fuel Clad Category: A. RPV Water Level Degradation Threat: Potential Loss Threshold:
FC2 RPV water level cannot be restored and maintained> -158 in. {TAF) or cannot be determined (RPV Flooding required)
Definition(s):
None Basis:
This water level (-158 in.) corresponds to the top of the active fuel and is used in the EOPs to indicate a challenge to core cooling (ref. 1). When RPV level is at or above the TAF, the core is completely submerged. Core submergence is the most desirable means of core cooling. When RPV level is below TAF, the uncovered portion of the core must be cooled by less reliable means (i.e., steam cooling or spray cooling). If core uncovery is threatened, the EOPs specify alternate, more extreme, RPV water level control measures in order to restore and maintain adequate core cooling. Since core uncovery begins if RPV level drops to TAF, the level is indicative of a challenge to core cooling and the Fuel Clad barrier.
When RPV water level cannot be determined, EOPs require entry to RPV Flooding procedures. RPV water level indication provides the primary means of knowing if adequate core cooling is being maintained. When all means of determining RPV water level are unavailable, the Fuel Clad barrier is threatened and reliance on alternate means of assuring adequate core cooling must be attempted. The instructions in the RPV Flooding procedures specify these means, which include emergency depressurization of the RPV and injection into the RPV at a rate needed to flood to the elevation of the main steam lines (ref. 2, 4). If RPV water level cannot be determined with respect to the top of active fuel, a potential loss of the Fuel Clad barrier exists.
In high-power ATWS/failure to scram events, EOPs may direct the operator to deliberately lower RPV water level to the top of active fuel in order to reduce reactor power. RPV water level is then controlled between the top of active fuel and the Minimum Steam Cooling RPV Water Level (MSCRWL). Although such action is a challenge to core cooling and the Fuel Clad barrier, the immediate need to reduce reactor power is the higher priority. For such events, EALs SA6.1 or SS6.1 will dictate the need for emergency classification (ref. 3).
Page 122 of 258
COOPER EAL Technical Bases Document NUCLEAR Revision XX STATION Attachment 1 - Emergency Action Level Technical Bases Barrier: Reactor Coolant System Category: A. RPV Water Level Degradation Threat: Loss Threshold:
RCS1 RPV water level cannot be restored and maintained> -158 in. (TAF) or cannot be determined (RPV Flooding required)
Definition(s):
None.
Basis:
In high-power ATWS/failure to scram events, EOPs may direct the operator to deliberately lower RPV water level to the top of active fuel in order to reduce reactor power. RPV water level is then controlled between the top of active fuel and the Minimum Steam Cooling RPV Water Level (MSCRWL). Although such action is a challenge to core cooling and the Fuel Clad barrier, the immediate need to reduce reactor power is the higher priority. For such events, EALs SA6.1 or SS6.1 will dictate the need for emergency classification (ref. 3).
This water level (-158 in.) corresponds to the top of active fuel and is used in the EOPs to indicate a challenge to core cooling (ref. 1). When RPV level is at or above the TAF, the core is completely submerged. Core submergence is the most desirable means of core cooling. When RPV level is below TAF, the uncovered portion of the core must be cooled by less reliable means (i.e., steam cooling or spray cooling). If core uncovery is threatened, the EOPs specify alternate, more extreme, RPV water level control measures in order to restore and maintain adequate core cooling. Since core uncovery begins if RPV level drops to TAF, the level is indicative of a challenge to core cooling and the Fuel Clad barrier.
When RPV water level cannot be determined, EOPs require entry to RPV Flooding procedures. RPV water level indication provides the primary means of knowing if adequate core cooling is being maintained. When all means of determining RPV water level are unavailable, the Fuel Clad barrier is threatened and reliance on alternate means of assuring adequate core cooling must be attempted. The instructions in the RPV Flooding procedures specify these means, which include emergency depressurization of the RPV and injection into the RPV at a rate needed to flood to the elevation of the main steam lines (ref. 2, 4). If RPV water level cannot be determined with respect to the top of active fuel, a potential loss of the Fuel Clad barrier exists.
Page 135 of 258
NLS2020051 Attachment 3 Revised EAL Wallchart Cooper Nuclear Station, Docket No. 50-298, DPR-46 (Attachment 3 contains one page)
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