Letter Sequence Other |
|---|
|
|
MONTHYEARL-PI-08-072, Update to Three-Month Response and Request for Extension to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-09-15015 September 2008
Update to Three-Month Response and Request for Extension to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
Project stage: Request
ML0823208242008-10-0808 October 2008
an 2 - Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Proposed Alternative Course of Action (TAC Nos MD7866 & MD7867)
Project stage: Other
L-PI-08-088, Nine-Month Response to NRC GL 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems2008-10-14014 October 2008
Nine-Month Response to NRC GL 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
Project stage: Request
L-PI-09-012, Ninety-Day 2R25 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2009-01-30030 January 2009
Ninety-Day 2R25 Post-Outage Report Pursuant to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
Project stage: Request
L-PI-09-102, Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Commitment Changes2009-09-28028 September 2009
Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Commitment Changes
Project stage: Request
ML0926501342009-09-28028 September 2009
Request for Additional Information Related to Response to Generic Letter (GL) 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
Project stage: RAI
L-PI-09-122, Supplement to Responses to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems2009-11-24024 November 2009
Supplement to Responses to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
Project stage: Supplement
ML1001400732010-01-27027 January 2010
Closeout of Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal and Containment Spray Systems.
Project stage: Other
2009-01-30
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024
Integrated Inspection Report 05000282/2023004 and 05000306/2023004
ML23356A1232024-01-29029 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)
ML24024A0722024-01-24024 January 2024
Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML24017A0182024-01-19019 January 2024
Confirmation of Initial License Examination
ML23356A0032024-01-17017 January 2024
Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
IR 07200010/20234012023-12-20020 December 2023
Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401
ML23349A0572023-12-15015 December 2023
and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota
ML23215A1672023-12-15015 December 2023
Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3
IR 05000282/20234012023-12-13013 December 2023
Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401
L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023
Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3
ML23304A1632023-11-15015 November 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3
ML23319A3182023-11-15015 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000282/20230032023-11-0808 November 2023
Integrated Inspection Report 05000282/2023003 and 05000306/2023003
ML23311A3572023-11-0707 November 2023
Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0
ML23285A3062023-10-12012 October 2023
Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant
ML23270B9022023-09-29029 September 2023
Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report
L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023
License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3
ML23265A2532023-09-26026 September 2023
Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report
ML23262B0372023-09-19019 September 2023
Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports
ML23256A1682023-09-13013 September 2023
Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection
L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023
Baffle Former Bolts Alternate Aging Management Strategy
IR 05000282/20230052023-08-30030 August 2023
Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005
IR 05000282/20230102023-08-17017 August 2023
NRC Inspection Report 05000282/2023010 and 05000306/2023010
ML23222A0122023-08-10010 August 2023
Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence
IR 05000282/20230022023-08-0303 August 2023
Integrated Inspection Report 05000282/2023002 and 05000306/2023002
ML23214A2032023-08-0202 August 2023
Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010
ML23206A2342023-07-25025 July 2023
Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence
ML23202A0032023-07-21021 July 2023
Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1)
ML23199A0922023-07-18018 July 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004
ML23195A1732023-07-14014 July 2023
Revision of Standard Practice Procedures Plan
L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023
License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT
ML23181A0192023-06-30030 June 2023
Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023
License Amendment Request to Revise Technical Specification 3.7.8 Required Actions
L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023
2022 10 CFR 50.46 LOCA Annual Report
IR 05000282/20234202023-06-0101 June 2023
Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420
ML23150A1722023-05-30030 May 2023
Preparation and Scheduling of Operator Licensing Examinations
2024-02-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 January 27, 2010 Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, Minnesota 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL AND CONTAINMENT SPRAY SYSTEMS" (TAC NOS. MD7866 AND IVlD7867)
Dear Mr. Schimmel:
On January 11,2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072910759). The stated purpose of GL 2008-01 was (a) to request addressees to submit information to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance; and (b) to collect the requested information to determine if additional regulatory action is required.
GL 2008-01 requested that licensees provide the following information within 9 months of the date of the GL:
(a) A description of the results of evaluations that were performed pursuant to requested actions specified in the GL. This description should provide sufficient information to demonstrate that you are or will be in compliance with the quality assurance criteria in Sections III, V, XI, XVI, and XVII of Appendix B to 10 CFR Part 50, and the licensing basis and operating license as those requirements apply to the subject systems; (b) A description of all corrective actions, including plant, programmatic, procedure, and licensing basis modifications that you determined were necessary to assure compliance with these regulations; and (c) A statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.
In your letters dated April 10, September 15, and October 14, 2008, January 30, September 28, and November 24,2009 (ADAMS Accession Nos. ML081020368, ML082600139, ML082880483, ML090300705, ML092730109, and ML093280925, respectively), you provided information in response to the GL. The NRC staff has reviewed the submitted information and has concluded that for Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2 (PINGP), your
M. Schimmel -2 response to the GL is acceptable. Consequently, your GL response is considered closed and no further information or action is requested of you.
Notwithstanding, the NRC's Region III staff may decide to perform (and would contact you to schedule) an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ADAMS Accession No. ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically- controlled actions described in the licensee's response to GL 2008-01, and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
The NRC staff recognizes that, in your letter dated September 15, 2008, the PINGP licensee committed to "submit results of the evaluations of the walkdowns of Unit 1 containment and RHR pits 90 days following the completion of 'I R26," and that you have not yet provided this submittal. The NRC staff considers the walkdowns to be confirmatory in nature.
If you have any questions regarding this letter, please feel free to contact me at (301) 415-4037.
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Distribution via Listserv
ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically- controlled actions described in the licensee's response to GL 2008-01, and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
The NRC staff recognizes that, in your letter dated September 15, 2008, the PINGP licensee committed to "submit results of the evaluations of the walkdowns of Unit 1 containment and RHR pits 90 days following the completion of 1R26," and that you have not yet provided this submittal. The NRC staff considers the walkdowns to be confirmatory in nature.
If you have any questions regarding this letter, please feel free to contact me at (301) 415-4037.
Sincerely,
/RAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsOgcRp Resource RidsNrrDorlLpl3-1 Resource RidsDssSrxb Resource RidsNrrLATHarris Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource GCranston, NRR RidsNrrPMPrairielsland Resource WLyon, NRR RidsAcrsAcnw_MailCTR Resource DWoodyatt, NRR ADAMS Accession Number' ML100140073 *via memo dated 12/23/09 OFFICE NRR/DORULPL3-1/PM NRR/DORLlLPL3-1/LA NRR/DSS/SRXB/BC NRR/DORULPL3-1/BC NAME TWengert THarris GCranston* RPascarelli DATE 01/26/10 01/26/10 12/23/09 01/27/10
