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Category:Letter type:L
MONTHYEARL-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 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-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data 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 L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 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 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 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 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 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 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 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 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring 2024-01-26
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Committed to Nuclear Excellence
/' Nuclear Management Company, LLC March 14,2006 L-HU-06-012 10 CFR 50.48 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Palisades Nuclear Plant Docked 50-263 Dockets 50-255 and 72-7 License No. DPR-22 License No. DPR-20 Point Beach Nuclear Plant, Units 1 and 2 Prairie Island Nuclear Generating Plant, Dockets 50-266, 50-301 and 72-5 Units 1 and 2 License Nos. DPR-24 and DPR-27 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42 and DPR-60 Revision of and Supplement to Letter of Intent to Transition to 10 CFR 50.48(c) - National Fire Protection Association Standard NFPA 805, "Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition.
Reference:
Letter from NMC to NRC, "Letter of Intent to Transition to 10 CFR 50.48(c) -
National Fire Protection Association Standard NFPA 805. "Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition", dated November 30, 2005 By the referenced letter, NMC committed to a transition to 10 CFR 50.48(c) and provided a schedule for the implementation of the transition. This letter revises the schedule and supplements the scope and methodology of the transition plan as described in the referenced letter and confirms the previously documented request for enforcement discretion, in accordance with the NRC's Interim Enforcement Policy with an extension beyond the two years provided within the policy. This letter also deletes Duane Arnold Energy Center (DAEC) from the above transition plan, as NMC is no longer the licensed operator of DAEC.
On November 30, 2005, NMC transmitted its letter of intent to transition to 10 CFR 50.48(c) for the following plants:
Point Beach Nuclear Plant, Units 1 and 2 Monticello Nuclear Generating Plant Palisades Nuclear Plant Prairie Island Nuclear Generating Plant, Units 1 and 2 Duane Arnold Energy Center 700 First Street Hudson, Wisconsin 54016 Telephone: 715.377.3300
Document Control Desk Page 2 A teleconference was held on December 19, 2005, to discuss the planned duration of the project and the associated enforcement discretion. As part of this teleconference, NMC agreed to review the project schedule for its plants. A second teleconference was held on February 8, 2006, at which time NMC presented a revised schedule for the transition to 10CFR50.48(c) for Point Beach Nuclear Plant, Units 1 and 2, Monticello Nuclear Generating Plant, Palisades Nuclear Plant, and Prairie Island Nuclear Generating Plant, Units Iand 2.
This letter documents the proposed schedule as presented during the above teleconference.
The transition to the performance-based standard as defined by 10 CFR 50.48(c) has been accelerated from the previously submitted schedule (Ref. I ) , and the transition schedule has been revised accordingly. The transition includes the development of a full fire PRA for Point Beach Nuclear Plant, Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 and Palisades Nuclear Plant; this work has been started at Point Beach, however the methodology will be common to the other sites. Due to the high degree of train separation, Monticello is expected to transition with a combination of deterministic methods and probabilistic methods using a limited scope fire PRA. Though the dates for the associated License Amendment Requests (LAR) are staggered, tasks will be perFormed in parallel as resources allow.
Point Beach Nuclear Plant (Units 1 and 2) LAR submitted by November 2008 Prairie Island Nuclear Generating Plant, Units 1 and 2, LAR submitted by June 2009 Palisades Nuclear Plant LAR submitted by November 2009 Monticello Nuclear Generating Plant LAR submitted by November 2009 Due to the high degree of train separation, Monticello is expected to transition primarily through deterministic methods with little fire PRA support necessary. Therefore, the transition of the Monticello Nuclear Generating Plant is scheduled to begin January 2010 with the LAR complete December 201 1.
In accordance with the NRC Enforcement Policy section titled, "Interim Enforcement Policy Regarding Enforcement Discretion for Certain Fire Protection Issues (10 CFR 50.48)," NMC requests enforcement discretion for NRC identified non-compliances and unresolved items and for NMC identified non-compliances related to the fire protection program. To ensure low risk during the transition process while under enforcement discretion, NMC will review identified non-compliances in accordance with the enforcement manual for application of enforcement discretion during the enforcement discretion period.
An evaluation of risk significance will be performed and corrective actions andlor compensatory measures taken commensurate with the significance.
A review of the item will consider extent of condition.
The unresolved items will be placed into the corrective action program to ensure resolution prior to or part of the transition to 10 CFR 50.48(c).
Document Control Desk Page 3 NMC requests an extension of the enforcement discretion window to 36 months for Point Beach Nuclear Plant, Units 1 and 2; 42 months for Prairie lsland Nuclear Generating Plant, Units 1 and 2; and 48 months for the Palisades Nuclear Plant and Monticello Nuclear Generating Plant. The reasons for this request are as follows:
Preliminary activities must be performed to provide for an efficient and quality transition. These include the updating of the cable and raceway databases and the development of a state-of-the-art fire PRA.
The industry has provided a wide range of estimates for resources necessary to perform the transition including the development of a high quality fire PRA. Two NMC plants (Point Beach Nuclear Plant and Prairie lsland Nuclear Generating Plant) are expected to be at the high end of the estimates, primarily due to the vintage of the plants.
The schedule has been developed such that NMC can apply lessons learned from the pilot plants in the industry that are currently in the process of transitioning.
NMC will need to rely on outside resources to support the transition. Resources with the narrow bands of expertise in PRA, Safe Shutdown, and Circuit Analysis are limited.
This letter contains no new commitments and no revisions to existing commitments.
Daniel J. alone Vice President, Nuclear Operations Support Nuclear Management Company, LLC Cc: ~dministrator,USNRC, Region Ill USNRC NRR Project Manager, Point Beach Nuclear Plant, Prairie lsland Nuclear Generating Plant, Monticello Nuclear Generating Plant, Palisades Nuclear Plant USNRC NRC Resident Inspector, Point Beach Nuclear Plant, Prairie lsland Nuclear Generating Plant, Monticello Nuclear Generating Plant, Palisades Nuclear Plant, USNRC