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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
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Nebraska Public Power District Alwa:ys there when :you need us NLS2017072 August 24, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Nebraska Public Power District's Seismic High Frequency Confirmation -
Response to Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review oflnsights from the Fukushima Dai-ichi Accident Cooper Nuclear Station, Docket No. 50~298, DPR-46
References:
- 1. NRC letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012
- 2. NRC letter, "Final Deterrpination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated October 27, 2015
- 3. NEI letter, "Request for NRC Endorsement of High Frequency Program:
Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396)," dated July 30, 2015
- 4. EPRI 3002004396, "High Frequency Program Application Guidance for Functional Confirmation and Fragility Evaluation," dated July 2015
- 5. NRC letter, "Endorsement of Electric Power Research Institute Final Draft Report 3002004396, 'High Frequency Program: Application Guidance for Functional Confirmation and Fragility,'" dated September 17, 2015
- 6. EPRI 1025287, "Seismic Evaluation Guidance - Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," February 2013 COOPER NUCLEAR STATION
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P.O. Box 98 /Brownville, NE 68321-0098 Telephone: (402) 825-3811 /Fax: (402) 825-5211 www.nppd.com
NLS2017072 Page 2 of3
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 (Recommendation 2.1: Seismic), Requested Information Item 4, of Reference 1, requested addressees to provide information related to the functionality of high-frequency sensitive structures, systems, and components under certain circumstances. By letter dated October 27, 2015 (Reference 2), the NRC transmitted final seismic hazard evaluation screening determination results and the associated schedules for submittal of the remaining seismic hazard evaluation activities. This letter identified that Nebraska Public Power District is to submit a limited scope, high frequency evaluation for Cooper Nuclear Station (CNS) by August 31, 2017.
By Reference 3, Nuclear Energy Institute submitted an Electric Power Research Institute (EPRI) report entitled, High Frequency Program Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396) (Reference 4) for NRC review and endorsement. EPRI 3002004396 provides methods and criteria for evaluating the high frequency sensitive equipment to the reevaluated ground motion response spectrum (GMRS) hazard levels. This report supplements the guidance in the Seismic Evaluation Guidance - Screening, Prioritization and Implementation Details (Reference 6), for plants where the GMRS exceeds the safe shutdown earthquake spectrum in the frequency range greater than 10 Hz. NRC endorsement of Reference 4 was provided in Reference 5.
The enclosure to this letter provides the requested information in response to Reference 1 for CNS, based on the guidance in Reference 4.
There are no new regulatory commitments and no revisions to existing regulatory commitments contained in this letter. Should you have any questions or if additional information is required, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
I declare under penalty of perjury that the foregoing is true and correct.
Executed On ~:J.<{li80lf-Date)
John Dent, Jr.
Vice President - Nuclear and Chief Nuclear Officer
/bk
Enclosure:
Cooper Nuclear Station - Seismic High Frequency Confirmation
NLS2017072 Page 3 of3 cc: Regional Administrator, w/ enclosure USNRC - Region IV Director, w/ enclosure USNRC - Office of Nuclear Reactor Regulation Cooper Project Manager, w/ enclosure USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector, w/ enclosure USNRC-CNS CNS Records, w/ enclosure NPG Distribution, w/o enclosure
NLS2017072 Enclosure ENCLOSURE Cooper Nuclear Station - Seismic High Frequency Confirmation
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED INFORMATIONAL USE 3-EN-DC-147 I
PAGE 1 of5 REV. 5C1 Engineering Reports ATTACHMENT9.1 ENGINEERING REPORT COVER SHEET & INSTRUCTIONS Sheet 1of2 Engineering Report No.
- -2017-006
Rev 0 Page 1 of _5_---1 Engineering Report Cover Sheet Engineering Report
Title:
Review ofS&A Report 16C4384-RPT-005, 50.54(+/-) NTTF 2.1 Seismic High Frequency Confirmation Engineering Report Type: (3)
New 12] Revision D Cancelled D Superseded D Superseded by:
(6)
ECR No. NIA EC No.17-003 (4) Report Origin: D CNS ~ Vendor Vendor Document No.: 16C4384-RPT-005 (5) Quality-Related: D Yes 12] No Prepared by: Stevenson and Associates Date: Sl~/17 Responsible Engineer (Print Name/Sign)
Desiga Verified: NIA Date: -
Date: -
Date: 5/i I I 1/J7 ER 2017-006 Rev 0
~Entergy NUCLEAR MANAGEMENT MANUAL QUALITY RELATED INFORMATIONAL USE Engineering Reports 3-EN-DC-147 PAGE 2 of5 I REV. 5C1 Table of Contents ATTACHMENT 9.1, COVER SHEET 1 SCOPE AND OBJECTIVE ..............................................................................................................3 2 DESIGN INPUTS ............................................................................................................................3 3 ASSUMPTIONS ..............................................................................................................................3 4 DETAILED DISCUSSION ...............................................................................................................3 5 OPERATING EXPERIENCE ...........................................................................................................5 6
SUMMARY
OF RESULTS ..............................................................................................................5 7 CONCLUSIONS AND RECOMMENDATIONS ............................................................................... 5 8 REFERENCES ...............................................................................................................................5 9 ATTACHMENTS .............................................................................................................................5 ER 2017-006 Rev 0
ENGINEERING REPORT ER2017-006 Rev 0 HNPPD COOPER NUCLEAR Page 3 of 5 STATION 1 SCOPE AND OBJECTIVE This report provides a review of vendor (Stevenson & Associates) prepared report 16C4384-RPT-005, referred to as the "Report" within this ER. The Report's purpose is to provide summary information describing the High Frequency Confirmation evaluations and results in support of formal response to the NRC's Near-Term Task Force (NTTF), 50:54(f) letter request associated with, Enclosure 1, Item (4) referred to as the "Letter" within this ER.
Enclosure 1 to the 50.54(f) letter requests that addressees perform a reevaluation of the seismic hazards at their sites using present-day NRC requirements and guidance to develop a ground motion response spectrum (GMRS). In addition, the required response section of Enclosure 1, Item (4) requests that each addressee provide a comparison of the GMRS and SSE to confirm, if necessary, that SSCs which may be affected by high-frequency evaluation ground motion will maintain their functions important to safety.
2 DESIGN INPUTS Section 6.0 of the Report provides a reference list of design inputs used in performing the evaluation. The inputs have been reviewed and have been found to be.acceptable.
3 ASSUMPTIONS None 4 DETAILED DISCUSSION EPRI guidance document 3002004396 was used for Cooper Nuclear Station engineering evaluations described in the Report. Section 4.1 of the guidance document provided
- general steps to follow for the high frequency confirmation component evaluation.
Accordingly, the following topics are addressed within the Report:
- a. Cooper Nuclear Station's SSE and GMRS Information
- b. Selection of components and a list of specific components for high-frequency confirmation
- c. Estimation of seismic demand for subject components
- d. Estimation of seismic capacity for subject components
- e. Summary of subject components' high-frequency evaluations
- f. Summary of Results ER 2017-006 Rev O
ENGINEERING REPORT ER2017-006 Rev 0 HNPPD COOPER NUCLEAR Page 4of 5 STATION SSE and GMRS Information Copper Nuclear Station submitted reevaluated seismic hazard information including GMRS and seismic hazard information to the NRC on March 31, 2014 and amended this information on February 11, 2015. In a letter dated September 8, 2015, the NRC staff concluded that the submitted GMRS adequately characterizes the reevaluated seismic hazard for the Cooper Nuclear Station site. The NRC final screening determination letter concluded that the Cooper Nuclear Station GMRS to SSE comparison resulted in a need to perform a High Frequency Confirmation in accordance with the screening criteria in the SPID (Screening, Prioritization and Implementation Details) EPRI guidance document 1025287.
Selection of Components The fundamental objective of the high frequency confirmation review is to determine whether the occurrence of a seismic event could cause credited equipment to fail to perform as necessary. This objective was achieved by confirming that key plant safety functions critical to immediate plant safety are preserved (reactor trip, reactor vessel inventory and pressure control, and core cooling) and that the plant operators have the necessary power available to achieve and maintain this state immediately following the seismic event (AC/DC power support systems).
Within the applicable functions, the components that required a high frequency confirmation were contact control devices subject to intermittent states in seal-in or lockout (SILO) circuits. Accordingly, the objective of the review as stated in the Report was to determine if seismic induced high frequency relay chatter would prevent the completion of the subject key plant safety functions.
Estimation of Seismic Demand The basis for calculating high-frequency seismic demand on the subject components in the horizontal direction is the Cooper Nuclear Station horizontal ground motion response spectrum (GMRS), which was generated as part of the Cooper Nuclear Station Seismic Hazard and Screening Report submitted to the NRC on March 31, 2014, amended on February 11, 2015 and accepted by the NRC on September 8, 2015.
The horizontal GMRS and site soil conditions were used to calculate the vertical GMRS (VGMRS), which was the basis for calculating high-frequency seismic demand on the subject components in the vertical direction.
Estimation of Seismic Capacity Seismic capacities are defined as the highest seismic test level reached by the contact device without chatter or other malfunction. The capacity was determined by the following:
(1) If a contact device was tested as part of the EPRI High Frequency Testing program, then the component seismic capacity from this program is used.
ER 2017-006 Rev 0
ENGINEERING REPORT ER2017-006 Rev 0 HNPPD COOPER NUCLEAR Page 5 of5 STATION *
(2) If a contact device was not tested as part of (1 ), then one or more of the following means to determine the component capacity were used:
(a) Device-specific seismic test reports (either from the station or from the SQURTS testing program).
(b) Generic Equipment Ruggedness Spectra (GERS).
(c) Assembly (e.g. electrical cabinet) tests where the component functional performance was monitored.
The high-frequency capacity of each device was evaluated with the component mounting point demand from Section 3 using the criteria in Section 4.5 of EPRI Report 3002004396.
The high-frequency evaluations as described above were performed in NEDC 17-002 (Stevenson & Associates Calculation 16C4384-CAL-001, High Frequency Functional Confirmation and Fragility Evaluation of Relays).
5 OPERATING EXPERIENCE CNS or industry Operating Experience does not apply to the criteria set forth by the scope of this 50.54(f) letter response summary document.
6
SUMMARY
OF RESULTS Cooper Nuclear Station has performed a High Frequency Confirmation evaluation in response to the NRC's 50.54(f) letter using the methods in EPRI report 3002004396. The evaluation identified a total of 136 components that required evaluation. As summarized in Table B-1, Appendix B of the "Report, 89 of the devices have adequate seismic capacity, two (2) have existing plant procedures to cope with the effect of contact chatter, and 45 components required resolution following the criteria in Section 4.6 of EPRI report 3002004396.
7 CONCLUSIONS AND RECOMMENDATIONS As a result of this evaluation, and the effort to continue to improve plant safety, Cooper Nuclear Station intends to address equipment sensitive to high frequency ground motion for the reevaluated seismic hazard information through mitigation strategies in lieu of a separate resolution of the 45 components identified under the Letter which do not impact the credited path for mitigation strategies.
8 REFERENCES Section 6.0 of the evaluation provides a list of references that have been reviewed for suitability to support this report. The review agrees that references are suitable and correct.
9 ATTACHMENTS
- 1. Stevenson and Associates Document No: 16C4384-RPT-005, "50.54(f) NTTF 2.1 Seismic High Frequency Confirmation" ER 2017-006 Rev 0
ENGINEERING REPORT ER2017-006 Rev 0 HNPPD COOPER NUCLEAR STATION ATTACHMENT 1 Stevenson and Associates Document No: 16C4384-RPT-005, "50.54(f) NTTF 2.1 ER 2017-006 Rev 0