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MONTHYEARML0430106032004-11-0101 November 2004 Westinghouse Electric Co, Withholding from Public Disclosure, WCAP-16219-P, Development and Qualifications of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants, Revision 0, April 2004 Project stage: Other ML0509605602005-03-17017 March 2005 3/17/05, RAI - E-Mail - Development and Qual. of a Gothic Containment Eval. Model for the PINGP - WCAP-16219-P (April 2004) TAC Nos. MC4245/MC4246 Project stage: RAI ML0514002802005-05-17017 May 2005 Supplement to License Amendment Request (LAR) Dated September 1, 2004. Request for Use of Gothic 7 in Containment Response Analyses Project stage: Supplement ML0520000052005-07-20020 July 2005 Westinghouse Electric Company Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0520000462005-08-12012 August 2005 License Amendments, Approve the Use of Generation of Thermal-Hydraulic Information for Containment Version 7.1 Patch 1 (Gothic 7), for Licensing Analyses Project stage: Other L-PI-05-086, Clarification of Safety Evaluation for License Amendment Request Dated September 1, 2004, Request for Use of Gothic 7 in Containment Response Analyses2005-09-16016 September 2005 Clarification of Safety Evaluation for License Amendment Request Dated September 1, 2004, Request for Use of Gothic 7 in Containment Response Analyses Project stage: Request ML0733105722007-10-30030 October 2007 Email from Dale M. Vincent to Mahesh Chawla Gothic SE Clarification Project stage: Request ML0732402442007-12-0303 December 2007 Clarification Letter for Gothic (TAC MC4245 and MC4246) Project stage: Other 2005-07-20
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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
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December 3, 2007 Mr. Michael D.
Wadley Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 RE: CLARIFICATION LETTER FOR USE OF GOTHIC (TAC NOS. MC4245 AND MC4246)
Dear Mr. Wadley:
On September 1, 2004, the Nuclear Management Company (NMC, the licensee) submitted a license amendment request (LAR) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042570289) requesting approval to use the GOTHIC methodology for Prairie Island Nuclear Generating Plant (PINGP) analyses. The Nuclear Regulatory Commission (NRC) approved the LAR by a safety evaluation (SE) dated August 12, 2005 (ADAMS Accession No. ML052000046), which had the following statement in the conclusion:
The mass and energy releases and the initial and boundary conditions used in future PINGP license applications using GOTHIC 7 will be reviewed by the staff to assure that the analyses are performed consistent with the guidance in the SRPs and the description presented in WCAP-16219-P.
However, your staff has expressed concern with the above statement in the SE. In an e-mail dated October 30, 2007 (ADAMS Accession No. ML073310572), NMC stated that according to its interpretation, each use (application) of GOTHIC would require the submittal of an LAR. It further stated that requiring an LAR for each use would not be consistent with the industry use of approved topical reports, such as WCAP-16219-P, and would preclude the use of Section 50.59 of Part 50 to Title 10 of the Code of Federal Regulations (10 CFR 50.59) for determining whether prior NRC approval is required. Thus, NMC requested that the NRC withdraw this SE statement or provide clarification.
The NRC staff does not agree with NMCs interpretation of the SE statement. The following interpretation is provided by the staff.
The NRC staff notes that 10 CFR 50.59 is the controlling regulation in determining whether GOTHIC analyses must receive prior NRC review and approval. The intent of the staffs statement is that when an LAR is submitted, the staff will review the mass and energy release calculations, not that every GOTHIC analysis must be submitted.
M. Wadley I hope this provides the necessary clarification requested by NMC. If you have any further questions, please contact me at 301-415-8371.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: See next page
ML073240244 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/DSS/SCVB/BC NRR/LPL3-1/(A)BC NAME MChawla THarris RDennig RL for CMunson PDM for DATE 11/21/07 11/29/07 11/30/07 12/3/07 Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Tribal Council Vice President, Counsel & Secretary Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.
Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 Michael B. Sellman Manager - Environmental Protection Division President and Chief Executive Officer Minnesota Attorney General=s Office Nuclear Management Company, LLC 445 Minnesota St., Suite 900 700 First Street St. Paul, MN 55101-2127 Hudson, MI 54016 U.S. Nuclear Regulatory Commission Dennis L. Koehl Resident Inspector's Office Chief Nuclear Officer 1719 Wakonade Drive East Nuclear Management Company, LLC Welch, MN 55089-9642 700 First Street Hudson, WI 54016 Administrator Goodhue County Courthouse Joel P. Sorenson Box 408 Director, Site Operations Red Wing, MN 55066-0408 Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC Commissioner 1717 Wakonade Drive East Minnesota Department of Commerce Welch, MN 55089 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 July 2006