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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
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Nebraska Public Power District Always there when you need us NLS2004011 February 16, 2004 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Clarification of Generic Letter 96-06 Safety Evaluation Cooper Nuclear Station NRC Docket 50-298, DPR-46
References:
- 1. U.S. Nuclear Regulatory Commission letter to Nebraska Public Power District dated November 3, 2003, "Cooper Nuclear Station (CNS) - Final Closeout of Responses to Generic Letter 96-06 (TAC NO. M96799)"
- 2. Nebraska Public Power District letter to the U.S. Nuclear Regulatory Commission dated June 9, 2003, "Response to NRC Generic Letter 96-06" The purpose of this letter is to clarify statements made in a safety evaluation (SE) issued by the U.S. Nuclear Regulatory Commission (NRC) in Reference 1 for the Cooper Nuclear Station (CNS). The SE documented closure of Generic Letter 96-06 for CNS, as submitted by Reference 2. The clarification is attached.
If you have any questions regarding this issue please call me at (402) 825-2774.
Licensing and Regulatory Affairs Manager
/rer Attachments
-7 2, COOPER NUCLEAR STATION P.O. Box 98/ Brownville, NE 68321-0098 Telephone: (402) 825-8811 / Fax.: (402) 825-5211 www.nppd.com
NLS200401 1 Page 2 of 2 cc: Regional Administrator w/ attachments USNRC - Region IV Senior Project Manager Nv/ attachments USNRC - NRR Project Directorate IV-l Senior Resident Inspector w/ attachments USNRC Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments Records w/ attachments
NLS200401 1 Page 1 of 1 Attachment Clarification of Generic Letter 96-06 Safety Evaluation Cooper Nuclear Station Nebraska Public Power District
- 1. Section 3.1, second paragraph, first sentence, in the Generic Letter (GL) 96-06 Safety Evaluation (SE) for Cooper Nuclear Station (CNS) states:
"Following a LOOP, the REC pumps will stop and the isolation valves between the REC pumps and the drywell FCUs will close on reduced system pressure."
The isolation valves are electrically powered. The valves will not close following a Loss-of-Offsite Power until the bus is re-energized, either by start of a diesel generator or restoration of offsite power.
- 2. Section 3.1, second paragraph, fourth sentence, in the GL 96-06 SE states:
"A small MSLB might not cause drywell spray to actuate, resulting in elevated containment temperatures and subsequent voiding in the containment FCUs."
This sentence could be interpreted as stating that drywell spray actuates automatically.
Drywell spray at CNS does not actuate automatically. Rather, it is actuated manually by operators when appropriate conditions exist, as directed by the Emergency Operating Procedures.
- 3. Section 3.1, second paragraph, next to last sentence, in the GL 96-06 SE states:
"In actuality, the isolation valve downstream of the REC pumps has a long opening stroke of 32 seconds."
In the submittal Nebraska Public Power District referred to the opening stroke time of valve REC-MOV-702 as "approximately" 32 seconds. Stating the valve opening time in the SE as a specific 32 seconds rather than "approximately" 32 seconds could cause a reader to think that the opening time must be exactly 32 seconds. The principal consideration here is that a slow valve opening stroke will allow any steam voids that might be present to be swept away without causing a waterhammer.
I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© I Correspondence Number: NLS2004011 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 & Regulatory Affairs Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None I PROCEDURE 0.42 l REVISION 14 l PAGE 15 OF 17 l
Text
Nebraska Public Power District Always there when you need us NLS2004011 February 16, 2004 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Clarification of Generic Letter 96-06 Safety Evaluation Cooper Nuclear Station NRC Docket 50-298, DPR-46
References:
- 1. U.S. Nuclear Regulatory Commission letter to Nebraska Public Power District dated November 3, 2003, "Cooper Nuclear Station (CNS) - Final Closeout of Responses to Generic Letter 96-06 (TAC NO. M96799)"
- 2. Nebraska Public Power District letter to the U.S. Nuclear Regulatory Commission dated June 9, 2003, "Response to NRC Generic Letter 96-06" The purpose of this letter is to clarify statements made in a safety evaluation (SE) issued by the U.S. Nuclear Regulatory Commission (NRC) in Reference 1 for the Cooper Nuclear Station (CNS). The SE documented closure of Generic Letter 96-06 for CNS, as submitted by Reference 2. The clarification is attached.
If you have any questions regarding this issue please call me at (402) 825-2774.
Licensing and Regulatory Affairs Manager
/rer Attachments
-7 2, COOPER NUCLEAR STATION P.O. Box 98/ Brownville, NE 68321-0098 Telephone: (402) 825-8811 / Fax.: (402) 825-5211 www.nppd.com
NLS200401 1 Page 2 of 2 cc: Regional Administrator w/ attachments USNRC - Region IV Senior Project Manager Nv/ attachments USNRC - NRR Project Directorate IV-l Senior Resident Inspector w/ attachments USNRC Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments Records w/ attachments
NLS200401 1 Page 1 of 1 Attachment Clarification of Generic Letter 96-06 Safety Evaluation Cooper Nuclear Station Nebraska Public Power District
- 1. Section 3.1, second paragraph, first sentence, in the Generic Letter (GL) 96-06 Safety Evaluation (SE) for Cooper Nuclear Station (CNS) states:
"Following a LOOP, the REC pumps will stop and the isolation valves between the REC pumps and the drywell FCUs will close on reduced system pressure."
The isolation valves are electrically powered. The valves will not close following a Loss-of-Offsite Power until the bus is re-energized, either by start of a diesel generator or restoration of offsite power.
- 2. Section 3.1, second paragraph, fourth sentence, in the GL 96-06 SE states:
"A small MSLB might not cause drywell spray to actuate, resulting in elevated containment temperatures and subsequent voiding in the containment FCUs."
This sentence could be interpreted as stating that drywell spray actuates automatically.
Drywell spray at CNS does not actuate automatically. Rather, it is actuated manually by operators when appropriate conditions exist, as directed by the Emergency Operating Procedures.
- 3. Section 3.1, second paragraph, next to last sentence, in the GL 96-06 SE states:
"In actuality, the isolation valve downstream of the REC pumps has a long opening stroke of 32 seconds."
In the submittal Nebraska Public Power District referred to the opening stroke time of valve REC-MOV-702 as "approximately" 32 seconds. Stating the valve opening time in the SE as a specific 32 seconds rather than "approximately" 32 seconds could cause a reader to think that the opening time must be exactly 32 seconds. The principal consideration here is that a slow valve opening stroke will allow any steam voids that might be present to be swept away without causing a waterhammer.
I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS© I Correspondence Number: NLS2004011 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 & Regulatory Affairs Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None I PROCEDURE 0.42 l REVISION 14 l PAGE 15 OF 17 l