Letter Sequence Request |
---|
|
|
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
@ Xcel Energye SEP 2 8 2009 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Generic Letter 2008-01, "Manaaina Gas Accumulation in Emeraencv Core Coolina, Decav Heat Removal, and Containment Sprav Svstems", Commitment Changes
References:
- 1. Nuclear Regulatory Commission (NRC) Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems", dated January 11, 2008, Accession Number ML072910759.
- 2. Northern States Power Company, a Minnesota corporation (NSPM) letter to NRC RE: 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", dated January 30,2009, Accession Number ML090300705.
- 3. Northern States Power Company, a Minnesota corporation (NSPM) letter to NRC RE: Nine-Month Response to NRC Generic Letter 2008- 01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems", dated October 14, 2008, Accession Number ML082880483.
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," requesting information on this subject (Reference 1).
In response to this NRC request, Northern States Power Company, a Minnesota Corporation (NSPM) submitted information for Prairie Island Nuclear Generating Plant (PINGP) in several letters including a ninety day 2R25 post-outage report on January 30,2009 (Reference 2) and a nine-month response on October 14, 2008 (Reference 3).
As part of the nine-month response (Reference 3), NSPM made the following commitment:
NSPM will state in the procedure purpose for procedures that perform [Residual Heat Removal] RHR and [Safety Injection]
SI check valve testing (e.g., [Surveillance Procedure] SP 1092A) that they also dynamically vent the RHR and 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone:
651.388.1121 Document Control Desk Page 2 SI systems. These procedures will explicitly recognize their dynamic vent capability. NSPM will ensure that these outage procedures will be scheduled appropriately as a post-maintenance verification for activities in an outage that may introduce voids into the system. In the process of implementing this commitment, opportunities for enhancement were found. The original commitment required that dynamic venting be performed as a portion of other tasks (check valve testing). The commitment has been revised to allow dynamic venting to be done by an independent procedure or work instruction.
As part of the ninety-day 2R25 post-outage report (Reference 2), NSPM made the following commitment:
By the end of third quarter 2009 for Unit 2 and end of second quarter 2010 for Unit 1, NSPM will develop and implement interim surveillance measures in owner-controlled documents (until implementation of Reference 3, Enclosure Section B, Commitment 2 activities is complete) to periodically verify the piping is sufficiently full such that its functional requirements are maintained.
This commitment references a commitment from the nine-month response (Reference
- 3) to evaluate the resolution of Technical Specification (TS) issues with respect to the changes contained in the Technical Specification Task Force traveler to determine applicability and further assess any changes to the TS and TS Bases. Currently, surveillance measures for known void locations are being tracked through the corrective action process. The commitment has been revised to indicate that the interim surveillance measures will be implemented in owner-controlled documents for Unit 2 by the end of fourth quarter 2009.
Please contact Kathryn Mews (651 -388-1 121, ext. 7384) if you have any questions related to this submittal. Summary of Commitments This letter revises Commitment 6 in Reference 3, Enclosure Section B to:
Procedures or work instructions will be written to dynamically vent portions of the RHR and SI systems that are currently vented in association with check valve testing. NSPM will state in the purpose that such venting is being performed. NSPM will ensure that these procedures and work instructions will be scheduled appropriately as a post-maintenance verification for activities in an outage that may introduce voids into the systems.
Document Control Desk Page 3 This letter revises Commitment 1 in Reference 2, Enclosure Section B.2 to: By the end of fourth quarter 2009 for Unit 2 and end of second quarter 2010 for Unit 1, NSPM will develop and implement interim surveillance measures in owner- controlled documents (until implementation of Reference 3, Enclosure Section B, Commitment 2 activities is complete) to periodically verify the piping is sufficiently full such that its functional requirements are maintained.
Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC