Letter Sequence Other |
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MONTHYEARML0205803792002-01-30030 January 2002
Response to NRC RAI Regarding License Amendment Request for Revised Reference for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvements to the Bases
Project stage: Response to RAI
ML0207902892002-03-0101 March 2002
Additional Information Provided in Support of Previously Submitted License Amendment for Revised Reference for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvements to the Bases
Project stage: Other
ML0216902622002-06-11011 June 2002
Technical Specification Pages for Amendment No. 128 for Monticello
Project stage: Other
ML0133906772002-06-11011 June 2002
Issuance of Amendment, Relating to Technical Specification Revisions to Reference Point for Reactor Vessel Level Setpoints, to Safety Limits & to Bases
Project stage: Approval
2002-03-01
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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
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Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence
ML23215A1312023-08-0909 August 2023
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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
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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
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LRA Availability Letter
ML23206A2342023-07-25025 July 2023
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ML23201A0352023-07-24024 July 2023
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ML23202A0032023-07-21021 July 2023
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L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023
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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
NMC Committed to Nuclear Exllence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC March 1, 2002 10 CFR Part 50, Section 50.90 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Additional Information Provided in Support of Previously Submitted License Amendment for Revised Reference for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvements to the Bases (TAC NO. MB2246)
Reference 1: Nuclear Management Company, LLC letter to Nuclear Regulatory Commission, "Revised Reference Point for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvements to the Bases," dated June 18, 2001.
Reference 2: Nuclear Management Company, LLC letter to Nuclear Regulatory Commission, "Response to NRC Request for Additional Information Regarding License Amendment Request for Revised Reference Point for Reactor Vessel Level Setpoints, Simplification of Safety Limits, and Improvements to the Bases (TAC NO. MB2246)," dated January 30, 2002.
By Reference 1 letter, as supplemented by Reference 2, Nuclear Management Company, LLC (NMC) requested a change to the Technical Specifications (TS),
Appendix A of Operating License DPR-22, for the Monticello Nuclear Generating Plant.
This letter clarifies the previous submittal made by Reference 1, as supplemented by Reference 2, and provides NMCs additional justification for part of the previously submitted TS change. This additional justification is being provided for the previously proposed revision to the Safety Limit Section of the Monticello TS; no additional revised pages are required.
The Current Technical Specifications (CTS) for Monticello state that if a Safety Limit is exceeded, the reactor shall be shut down immediately. The Proposed Technical Specifications (PTS) state that with any Safety Limit violation, the following actions shall 2807 West County Road 75 ? Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 ? Fax: 763.295.1454 A- o
ULSNRC Nuclear Management Company, LLC Page 2 be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: A. Restore compliance with all Safety Limits; and B.
Insert all insertable control rods. As stated in Reference 1 Bases for PTS 2.2, exceeding a Safety Limit may cause fuel damage and create a potential for radioactive releases in excess of 10 CFR 100, "Reactor Site Criteria," guidelines. Therefore, it is required to insert all insertable control rods and restore compliance with the Safety Limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time ensures that the operators take prompt remedial action and also ensures that the probability of an accident occurring during this period is minimal. This information should have also been provided as justification for the revision to CTS as provided in the PTS submittal. Additionally, the less restrictive 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time is also justified because it allows appropriate actions to be evaluated by the operator and completed in a timely manner. This will prevent the operator from feeling time pressured by a TS requirement which requires an immediate response and allows time to evaluate the situation before responding. This could possibly prevent a plant transient and a worse situation than was originally entered into, therefore, the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completion time to restore compliance with all Safety Limits is reasonable.
The above referenced additional justification has no technical impact on pages or justifications previously submitted. This justification is consistent with the previously proposed changes. Therefore, the Determination of No Significant Hazards Consideration and Environmental Assessment submitted by Reference 1 are also applicable to this supplemental submittal.
If you have any questions regarding this letter or the previous License Amendment Requests please contact Doug Neve, Licensing Project Manager, at (763) 295-1353.
Jeffrey S. Forbes Vice President Monticello Nuclear Generating Plant cc: Regional Administrator-Ill, NRC NRR Project Manager, NRC Sr. Resident Inspector, NRC Minnesota Department of Commerce J Silberg, Esq.
