Letter Sequence Other |
|---|
|
|
MONTHYEARML18121A0312018-04-30030 April 2018
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Implementation of the Provisions of 10 CFR 50.69
Project stage: Acceptance Review
L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-03-13013 March 2019
Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors
Project stage: Response to RAI
L-MT-19-030, Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.2019-05-15015 May 2019
Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.
Project stage: Supplement
ML19176A4212019-08-29029 August 2019
Issuance of Amendment No. 203 Adoption of 10 CFR 50.69
Project stage: Approval
ML19305A8012019-11-12012 November 2019
Correction Letter for Amendment No. 203 to Renewed Operating License No. DPR-22
Project stage: Other
2019-03-13
[Table View] |
|
|---|
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
[Table view] |
Text
UNITED STATES WASHINGTON, D.C. 20555-0001 November 12, 2019 Mr. Christopher Church Senior Vice President and Chief Nuclear Officer Northern States Power Company - Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - CORRECTION LETTER FOR AMENDMENT NO. 203 TO RENEWED OPERATING LICENSE NO. DPR-22 (EPID L-2018-LLA-0076)
Dear Mr. Church:
On August 29, 2019 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML19176A421 ), the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 203 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant (MNGP). The amendment adds a condition to the MNGP renewed facility operating license to allow the implementation of Title 10 of the Code of Federal Regulations, Section 50.69, "Risk informed categorization and treatment of structures, systems and components for nuclear power reactors."
This letter corrects the issuance of Amendment No. 203 for MNGP to correct an administrative error to RFOL No. DPR-22, Page 10. The amendment revised the numeration for conditions that were not related to the amendment request and were not intended to be renumbered.
Specifically, the amendment changed the numbering of conditions 15(e), 15(f), 15(g), and 15(h) to 15(a), 15(b), 15(c), and 15 (d). The enclosed RFOL No. DPR-22, Page 10, reverts the numbering to the convention prior to Amendment 203.
Robert F. Kuntz, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Renewed Facility Operating License DPR-22, Page 10 cc: Listserv
Enclosure:
Renewed Facility Operating License DPR-22, Page 1O
- 2. Level 1 performance criteria; and
- 3. The methodology for establishing the limit curves used for the Level 1 and Level 2 performance.
(e) The results of the power ascension testing to verify the continued structural integrity of the steam dryer shall be submitted to the NRC staff in a report that includes a final load definition and stress report of the steam dryer, including the results of a complete re-analysis using the ACE 2.0 and ACE2.0-SPM specific bias and uncertainties. The report will be provided within 90 days of the completion of EPU power ascension testing.
(f) During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer in accordance with the inspection guidelines provided to the NRC.
(g) The results of the visual inspections of the steam dryer shall be reported to the NRC staff within 90 days following startup from the respective refueling outage.
(h) At the end of the second refueling outage, following the implementation of the EPU, the licensee shall submit a long-term steam dryer inspection plan based on industry operating experience along with the baseline inspection results for NRC review and approval.
The license conditions described above shall expire ( 1) upon satisfaction of the requirements in Paragraphs 15(f) and 15(g), provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw(s) or unacceptable flaw growth that is due to fatigue, and (2) upon satisfaction of the requirements specified in Paragraph 15(h).
- 16. Adoption of 10 CFR 50.69 1 "Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants" NSPM is approved to implement 10 CFR 50.69 using the approaches for categorization of Risk Informed Safety Class (RISC}-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using:
Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding and internal fire, with the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (AN0-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e.,
seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards (e.g., external flooding and high winds) updated using the external hazard screening significance criteria identified in Renewed License No. DPR-22 Amendment No. 203
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT-CORRECTION LETTER FOR AMENDMENT NO. 203 TO RENEWED OPERATING LICENSE NO. DPR-22 (EPID L-2018-LLA-0076) DATED NOVEMBER 12, 2019 DISTRIBUTION:
PUBLIC RidsACRS_MailCTR Resource RidsNrrDorlLpl3 Resource RidsNrrLASRohrer Resource RidsNrrPMMonticello Resource RidsRgn3MailCenter Resource 3/LA NRR/D0RULPL3/BC NRR/D0RULPL3/PM NSalgado (SWall for) RKuntz 19 11/07/19 11/12/19 OFFICIAL RECORD COPY
