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Category:Letter
MONTHYEARML24025A9362024-01-31031 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000263/20230042024-01-31031 January 2024
Integrated Inspection Report 05000263/2023004
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
IR 05000263/20244012024-01-22022 January 2024
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401
L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024
Subsequent License Renewal Application Supplement 8
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-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
ML23349A0572023-12-15015 December 2023
and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota
IR 05000263/20234022023-12-13013 December 2023
Security Baseline Inspection Report 05000263/2023402
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-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023
Subsequent License Renewal Application Supplement 7
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
ML23319A3182023-11-15015 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000263/20230032023-11-13013 November 2023
Integrated Inspection Report 05000263/2023003 and 07200058/2023001
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-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
ML23291A1102023-10-23023 October 2023
Environmental Audit Summary and RCIs and RAIs
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
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-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
ML23262B0372023-09-19019 September 2023
Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports
ML23248A2092023-09-18018 September 2023
Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve
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
IR 05000263/20230102023-09-0707 September 2023
Commercial Grade Dedication Inspection Report 05000263/2023010
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
ML23214A2412023-08-31031 August 2023
Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application
IR 05000263/20230052023-08-30030 August 2023
Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005)
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
ML23241A9732023-08-21021 August 2023
Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263)
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
ML23222A0122023-08-10010 August 2023
Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence
ML23215A1312023-08-0909 August 2023
License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application
IR 05000263/20230022023-08-0707 August 2023
Plantintegrated Inspection Report 05000263/2023002
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-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
ML23198A0412023-07-28028 July 2023
LRA Availability Letter
ML23206A2342023-07-25025 July 2023
Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence
ML23201A0352023-07-24024 July 2023
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
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)
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
ML23195A1732023-07-14014 July 2023
Revision of Standard Practice Procedures Plan
IR 05000263/20235012023-07-13013 July 2023
Emergency Preparedness Inspection Report 05000263/2023501
2024-01-31
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Text
December 31, 2003 Mr. Thomas J. Palmisano Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT ISSUANCE OF CORRECTED PAGE FOR FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST NO. 7 (TAC NO. MB6897)
Dear Mr. Palmisano:
Our letter of October 3, 2003 (ADAMS Accession No. ML032040157), authorized an alternative pursuant to Title 10 of the Code of Federal Regulations, Section 50.55a(a)(3)(ii),
allowing the Nuclear Management Company, LLC, to use the 2001 edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for repair/replacement activities and procedures. Your Monticello licensing staff noted a minor editorial error in our safety evaluation. Section 3.4 (page 5, line 4) of the safety evaluation should have referred to paragraph IWA-4540(c) of the 1998 edition of the ASME Code instead of paragraph IWA-4540. This letter forwards a corrected page 5.
Sincerely,
/RA/
L. Mark Padovan, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Corrected Safety Evaluation page 5 cc w/encl: See next page
ML032040157), authorized an alternative pursuant to Title 10 of the Code of Federal Regulations, Section 50.55a(a)(3)(ii),
allowing the Nuclear Management Company, LLC, to use the 2001 edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, for repair/replacement activities and procedures. Your Monticello licensing staff noted a minor editorial error in our safety evaluation. Section 3.4 (page 5, line 4) of the safety evaluation should have referred to paragraph IWA-4540(c) of the 1998 edition of the ASME Code instead of paragraph IWA-4540. This letter forwards a corrected page 5.
Sincerely,
/RA/
L. Mark Padovan, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Corrected Safety Evaluation page 5 cc w/encl: See next page DISTRIBUTION:
PUBLIC OGC GHill(2)
PDIII-1 Reading ACRS RBouling LRaghavan EReichelt BBurgess, RGN-III LPadovan TChan ADAMS Accession No. ML040050075 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME LPadovan RBouling LRaghavan DATE 12/31/03 12/31/03 12/31/03 Monticello Nuclear Generating Plant cc:
Jonathan Rogoff, Esquire Commissioner Vice President, Counsel & Secretary Minnesota Department of Commerce Nuclear Management Company, LLC 121 Seventh Place East 700 First Street Suite 200 Hudson, WI 54016 St. Paul, MN 55101-2145 U.S. Nuclear Regulatory Commission Manager - Environmental Protection Division Resident Inspectors Office Minnesota Attorney Generals Office 2807 W. County Road 75 445 Minnesota St., Suite 900 Monticello, MN 55362 St. Paul, MN 55101-2127 Manager, Regulatory Affairs John Paul Cowan Monticello Nuclear Generating Plant Executive Vice President & Chief Nuclear Nuclear Management Company, LLC Officer 2807 West County Road 75 Nuclear Management Company, LLC Monticello, MN 55362-9637 700 First Street Hudson, WI 54016 Robert Nelson, President Minnesota Environmental Control Nuclear Asset Manager Citizens Association (MECCA) Xcel Energy, Inc.
1051 South McKnight Road 414 Nicollet Mall, R.S. 8 St. Paul, MN 55119 Minneapolis, MN 55401 Commissioner Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 October 2003
testing requirements on a plant-specific basis. This potentially allows different utility organizations to implement inadequate or inconsistent pressure-testing practices and requirements for the same types of repair and replacement activities. Therefore, the NRC staff requires implementation of paragraph IWA-4540(c) of the 1998 edition in lieu of that of the 2001 l edition when implementing the 2001 edition of ASME Code,Section XI, Article IWX-4000 for repair and replacement activities. The NRC staff recognizes that the 1999 addenda through the 2000 addenda of the ASME Code has been incorporated by reference in 10 CFR 50.55a without referencing a limitation paragraph IWA-4540(c). The NRC staff will address this in an upcoming rulemaking regarding the incorporation by reference of the 2001 edition through the 2002 addenda of the ASME Code into 10 CFR 50.55a.
NMC has committed to implement the limitations and modifications to the 1998 edition through 2000 addenda of the ASME Code,Section XI, as stated in 10 CFR 50.55a(b)(2) when implementing the 2001 edition. NMC has further committed to implement any limitations and modifications to the 2001 edition of the ASME Code for its repair and replacement program when the NRC incorporates, by reference, this edition into the regulations. As a result, updating the two separate repair/replacement programs to meet the 2001 edition of the ASME Code,Section XI, including all the related requirements, as NMC proposed, and including paragraph IWA-4540(c) of the 1998 edition of the ASME Code as discussed above, provides an acceptable alternative. When the 2001 edition of the ASME Code is incorporated by reference in 10 CFR 50.55a, NMC must comply with all limitations and modifications stated in the regulations, if any, regarding the implementation of the 2001 edition of the ASME Code, as applied to Relief Request No. 7.
4.0 CONCLUSION
Based on the above, the NRC staff concludes that updating two separate repair/replacement programs at Monticello to meet the 2001 edition of the ASME Code Section XI, including all related requirements, as NMC proposes and as modified by the staff, provides an acceptable alternative pursuant to 10 CFR 50.55a(a)(3)(ii). Maintaining two separate repair/replacement programs will result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, the NRC staff authorizes NMCs proposed alternative, and as modified by the NRC staff, pursuant to 10 CFR 50.55a(a)(3)(ii) for the fourth 10-year ISI interval at Monticello. When the 2001 edition of the ASME Code is incorporated by reference in 10 CFR 50.55a, NMC must comply with all limitations and modifications, if any, regarding the implementation of the 2001 edition of the ASME Code, as applied to RR-7. All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: E. Reichelt Date: October 3, 2003 Corrected by NRC letter dated December 31, 2003 l
