Letter Sequence Response to RAI |
---|
|
|
|
|
---|
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] |
Text
N Nebraska Public Power District "Always there when you need us" 50.90 NLS2008078 September 19, 2008 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Response to Nuclear Regulatory Commission Request for Additional Information Re: Reactor Equipment Cooling System (TAC No. MD8374)
Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. Letter from Carl F. Lyon, U. S. Nuclear Regulatory Commission, to Stewart B. Minahan, Nebraska Public Power District, dated August 1, 2008, "Cooper Nuclear Station - Request for Additional Information Re:
Reactor Equipment Cooling System (TAC No. MD8374)"
- 2. Letter from Stewart B. Minahan, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated March 24, 2008, "License Amendment Request to Revise Technical Specification 3.7.3, Reactor Equipment Cooling System"
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District to submit a response to a request for additional information (RAI) from the Nuclear Regulatory Commission (NRC)
(Reference 1). The RAI requested information in support of the NRC review of a license amendment request (LAR) to revise the Technical Specifications (TS) for Cooper Nuclear Station (CNS) (Reference 2). The LAR proposed revisions to TS 3.7.3, Reactor Equipment Cooling System.
The response to the specific questions in the RAI is provided in Attachment 1. No regulatory commitments are made in this submittal.
The information submitted by this response to the RAI does not change the conclusions or the basis of the no significant hazards consideration evaluation provided with Reference 2.
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com
NLS2008078 Page 2 of 2 If you have any questions concerning this matter, please contact David W. Van Der Kamp, Licensing Manager, at (402) 825-2904.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on /* 'fl'7 r (date)
Sincerely, Stewart B. Minahan Vice President - Nuclear and Chief Nuclear Officer
/rr Attachment cc: Regional Administrator w/ attachment USNRC - Region IV Cooper Project Manager w/ attachment USNRC - NRR Project Directorate IV- 1 Senior Resident Inspector w/ attachment USNRC - CNS Nebraska Health and Human Services w/ attachment Department of Regulation and Licensure NPG Distribution w/o attachment CNS Records w/ attachment
NLS2008078 Page 1 of 2 Attachment 1 Response to Nuclear Regulatory Commission Request for Additional Information Re: Reactor Equipment Cooling System (TAC No. MD8374)
Cooper Nuclear Station, Docket No. 50-298, DPR-46 NRC Question #1 The LAR stated that operator action to align the Service Water (SW) system to the REC critical loops following a loss of the REC system during a loss of coolant accident (LOCA) can be performed within an hour. [a] How much time does the operatoractually have available to realign the SW system to provide cooling to the Emergency Core Cooling System pump rooms if the REC system is not available or determined to be inoperable during a LOCA? [b] How was the one hour time frame determined? [c] Does the assumed available time of one hour bound the recent (June 30, 2008) Measurement Uncertainty Recapturepower uprate approved by the NRC?
Response
[a] As explained in the response to part [b] below, the period of one hour to align the SW System to the Reactor Equipment Cooling (REC) System was an assumption in the calculations. The operators are able to make the alignment within one hour. Based on the acceptable results of the one hour, some additional time may be available. However, this has not been quantified. Since the operators are able to make this alignment within one hour, additional time is not needed.
The license amendment request (LAR) dated March 24, 2008, discussed the performance of scenarios on the Cooper Nuclear Station (CNS) simulator to demonstrate the ability of the control room staff to make this alignment within one hour. As noted in the LAR, these scenarios successfully demonstrated that ability.
[b] The one-hour period was determined based on it being identified as sufficient time for the control room staff to recognize the need to align the SW System to the REC critical loops and to make the alignment, in conjunction with taking the other actions required to mitigate the accident. Based on one hour being sufficient time to make this system alignment, the one hour was used as an assumption in CNS calculation NEDC 00-095E, Revision 2, "CNS Reactor Building Post-LOCA Heating Analysis," performed to determine the impact of the revised SW-to-REC alignment process on temperatures in the Reactor Building. Because the system alignment is performed from the Main Control Room and the Cable Spreading Room, areas which are readily accessible in any plant condition, making the system alignment within the time assumed in the analysis is not a challenge. The one-hour time period is not a derived value.
[c] The one-hour period does bound the MUR power uprate. This is based on the CNS post-LOCA design basis containment thermal response analysis-of-record having been performed assuming an initial reactor power of 102% of licensed power level. The Emergency Core Cooling System evaluation model includes a 2% margin to allow for uncertainties in core thermal power measurement in accordance with Appendix K of 10 CFR Part 50. NEDC 00-095E, Revision 2,
NLS2008078 Page 2 of 2 performed with the assumption of one hour to align SW to REC critical loops, is based on the post-LOCA design input at 102% power. As a result, this calculation remains bounding for the MUR power uprate with respect to the Reactor Building thermal environment.
NRC Question #2 Discuss whether the operatingcrews will have an opportunity during operator trainingto perform a variety of scenarios involving the recognition of the loss of the REC system and realignment of the SW system to the REC system (in addition to long-term recoveryfrom a LOCA).
Response
Licensed personnel at CNS currently have had, and will continue to have, opportunities to perform a variety of scenarios involving recognition of the loss of the REC System and taking the actions to align the SW System to the critical loops of the REC System. (Use of the SW System as a backup source of cooling water to the REC System seven days after the occurrence of a LOCA was credited and made a part of the CNS licensing basis by Amendment 185, dated March 13, 2001, to the CNS operating license.)
The task of aligning the SW System to the REC critical loops is included in both the Initial License Operator Training (ILT) and the License Operator Requalification (LOR) Programs. Simulator scenarios are included as part of this training. Through the LOR Program the operators are provided simulator training on this task every two years.
Simulator training is provided in the ILT Program through two lesson plans. The two plans are titled (1) "Reactor Equipment Cooling System" [required], and (2) "Loss of All REC" [optional].
Simulator training is provided in the LOR Program through one lesson plan, titled "Turbine Equipment Cooling Heat Exchanger Tube Leak, Loss of All REC."
CNS uses the Systematic Approach to Training (SAT) identified in 10 CFR 55.59 for reactor operators and senior reactor operators to identify requalification training requirements. This process is approved by the NRC using the Institute of Nuclear Power Operation training program accreditation process.
ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS@
OCATTACHMENT 3 LIST OF REGULATORY COMMITMEENTS Correspondence Number: NLS2008078 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None
_ _ _ _ ___ _ _I _
+
+
I PROCEDURE 0.42 REVISION 22 PAGE 18 OF 25 1