ML25101A216
Text
ENCLOSURE 5 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 5THIS DOCUMENT IS DECONTROLLED Xcel Energy April 10, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50:,-263 Subsequent Renewed Facility Operating License No. DPR-22 Submittal of Revision 42 to the Updated Safety Analysis Report 2807 West County Road 75 Monticello, MN 55362 L-MT-25-004 10 CFR 50.71 10 CFR 50.59 10 CFR 72.48 Pursuant to 10 CFR 50.71 (e), Revision 42 to the Monticello Nuclear Generating Plant (MNGP) Updated Safety Analysis Report (USAR) is provided. This revision completes an update of the information in the USAR for the period from December 21, 2023, to December 28, 2024.
The changes in this revision reflect the incorporation of modifications, license amendments, and editorial corrections and clarifications. These changes are made in accordance with the guidance provided in Nuclear Energy Institute (NEI) Report NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports", Revision 1, dated June 1999 and Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in accordance with 10 CFR 50.71(e)", dated September 1999., "Report of Changes, Tests and Experiments", states that there were no 10 CFR 50.59 evaluations performed. This report is provided as required by 10 CFR 50.59(d)(2)., "Report of Changes to Licensee Docketed Commitments", indicates that in accordance with the guidance provided in NEI 99-04, "Guidelines for Managing NRC Commitment Changes", dated July 1999, for this period, there were no commitment retirements and one ( 1) change to a commitment., "Summary of Information Removed from the USAR", provides the information removed from the USAR for this revision cycle. This information is provided in accordance with Revision 1 of NEI 98-03 and Regulatory Guide 1.181.
ENCLOSURE 5 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 5 THIS DOCUMENT IS DECONTROLLED L-MT-25-004 Page 2 of 2 (Non-Proprietary) provides a copy of the USAR that has been redacted for public use. (Proprietary) provides a copy of the USAR that contains sensitive information to be withheld from public disclosure per 10 CFR 2.390(d)(1)., "Report of Changes to the Monticello Fire Protection Program", provides a summary of changes to the program. Changes to the Fire Protection Program are provided in accordance with the guidance contained in Generic Letter 86-10, "Implementation of Fire Protection Requirements", dated April 24, 1986., This summary report is in lieu of adding a level of detail to the Monticello Nuclear Generating Plant (MNGP) Updated Safety Analysis Report (USAR) that is greater in the remainder of the USAR, including the License Renewal Supplement in Appendix K. The contents of this report are consistent with the requirements of 10 CFR 54.37(b) and the guidance of Regulatory Issue Summary (RIS) 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses" (ADAMS Accession Number ML100250279)., In accordance with 10 CFR 72.48(d), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM") is submitting a report for any changes related to the facility or independent spent fuel storage installation (ISFSI) cask design, and for any tests, experiments or procedure changes related to 10 CFR 72.48(c)(1), at MNGP.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
In accordance with 10 CFR 50. 71 (e)(2), I certify that the information presented herein, accurately presents changes made since the previous submittal prepared pursuant to Commission requirement and identifies changes made under the provisions if 10 CFR 50.59 not previously submitted to the Commission.
G~?~~
Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (8) cc:
Administrator, Region Ill, USNRC Resident Inspector, Monticello, USNRC (without enclosure 4, enclosure 5)
State of Minnesota, Department of Commerce (letter with enclosure 1)
Page 1 of 1 ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT REPORT OF CHANGES, TESTS AND EXPERIMENTS The following includes a brief description and summary of the 10 CFR 50.59 for those changes, tests and experiments that were carried out without prior U.S. Nuclear Regulatory Commission (NRC) approval, pursuant to the requirements of 10 CFR 50.59(d)(2).
- For the period December 21, 2023 to December 28, 2024 there were no 50.59 evaluations performed.
ENCLOSURE 2 Page 1 of 2 MONTICELLO NUCLEAR GENERATING PLANT REPORT OF CHANGES TO LICENSEE DOCKETED COMMITMENTS Commitments are identified and reported to the Commission in accordance with guidance provided in NEI Technical Report 99-04 Revision 0, "Guidelines for Managing NRC Commitment Changes."
This enclosure provides a brief description and a summary of changes to commitments established with the NRC by the Monticello Nuclear Generating Plant (MNGP) per NEI 99-04 guidelines.
For Revision 42:
One (1) commitment is being changed.
- 1. Commitment Tracking Number:
M79101A (Commitment Change)
Commitment source document:
RFM00546, secondary documents SWB00002 and SLV00145.
Issue: SER 3.1.6.(1), Breathing Equipment 8/29/1979 The purpose for the original commitment was to provide NRC on position to support, comply with Branch Technical Position Requirement APCSB 9.5-1 IV.B.4(h) which became NRC Commitment M79007A Original Commitment Wording:
Upgrade the capability of air breathing apparatus to meet the needs of ten (10) people for a period of six (6) hours at a usage rate of three (3) air bottles per hour per person.
Revised Commitment Wording:
Upgrade the capability of air breathing apparatus to meet the needs of ten (10) people for a period of six (6) hours at a usage rate of two (2) 45-minute air bottles per hour per person.
Justification:
The new cascade system will contain 8,177 scf of breathing air (481 scf/cylinder X (4+13 cylinders)). Assuming perfect depletion of the cylinders and refilling completely exhausted SCBAs, this equates to approximately 123 SCBA refills, or approximately 2 refills of the 45-min bottles per hour per person (123 SCBAs/(10 people x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)).
The original (per SER August 29,1979) cascade system contained 5,580 scf of breathing air (310 scf/cylinder x (5+13 cylinders)). Assuming perfect depletion of the cylinders and refilling completely exhausted SCBAs, this equates to approximately 124 SCBA refills, or approximately 2 refills of the 30-min bottles per hour per person (124 SCBAs/(10 people x 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)). It should also be noted that per R.05.07 the site does have sufficient reserve supply for the 3 bottles per hour.
The above information from Engineering Change 601000003575 justifies the change to Page 2 Page 2 of 2 Breathing Air System as described in the SER 8/29/1979. In addition, this information provides the details to prove compliance with the Appendix R to part 50 III.H continues to be maintained.
M79101A requires 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of breathing are at a usage rate of 3 bottles an hour. The commitment language is using 30-minute bottles as an input. The 30-minute bottles time to depletion was reduced by a third. The one third reduction is continuing to be applied to the new 45-minute bottles, however, only 2 bottle refills would be required per hour.
This change is acceptable as the site continues to apply the same reduction factor the NRC applied to the 30-minute bottles.
The above information is included in Fire Protection Engineering Change, FPEE-23-004.
FPEE-23-004 concluded that the impacts of the Safety Evaluation Report (SER) 8/29/1979 Section 4.4.3 - Breathing Air and NRC Commitment M79101A do not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
This satisfies the requirements of 2.C.4 (Fire Protection).
ENCLOSURE 3 MONTICELLO NUCLEAR GENERATING PLANT
SUMMARY
OF INFORMATION REMOVED FROM THE USAR Page 1 of 1 Consistent with the guidance in Nuclear Energy Institute (NEI) Report NEI 98-03, Guidelines for Updated Final Safety Analysis Reports, Revision 1 and Regulatory Guide 1.181, Content of the Updated Final Safety Analysis Report in Accordance With 10 CFR 50.71(e), Information removed from the Monticello Nuclear Generating Plant Updated Safety Analysis Report (USAR) for the period December 21, 2023 to December 28, 2024 is summarized below.
- For the Period December 21, 2023 to December 28, 2024, there was no information removed from the Monticello Nuclear Generating Plant Updated Safety Analysis Report (USAR)
ENCLOSURE 6 MONTICELLO NUCLEAR GENERATING PLANT REPORT OF CHANGES TO THE MONTICELLO FIRE PROTECTION PROGRAM Page 1 of 2 This enclosure contains a report of changes to the Monticello Fire Protection Program (FPP) in accordance with the provisions of Generic Letter (GL) 86-10.
In conformance with GL 86-10, the Updated Fire Hazards Analysis (UFHA) and the Safe Shutdown Analysis (SSDA) are incorporated directly into the Updated Safety Analysis Report (USAR) as Appendix J.5 and J.4 respectively. The following summarizes fire protection program document changes since the previous submittal.
- 1.
USAR J.04, SAFE SHUTDOWN ANALYSIS Revision 42P No changes to J.04 in revision 41P
- 2.
USAR J.05, FIRE HAZARDS ANALYSIS Revision 42P Licensing Document Change 604000001095 o Pg 517, Fire Detection System information in section 5.1.5(a) was updated to add the Security Diesel Building (Fire Zone 29) as having 'flame detectors.'
o Pg 538, Table 2 'Fire Zone Summary' was updated to include "Flame" as a Fire Detection method for fire area XX.
o Pg 586, Fire Hazards Analysis Matrix for Fire Zone 3C was updated to include information on a Fire Protection Engineering Evaluation (FPEE) for FZ-0520 o Pg 696, Fire Hazards Analysis Matrix for Fire Zone 21D was updated to include information on a Fire Protection Engineering Evaluation (FPEE) for FZ-0520 o Pg 715, Fire Hazards Analysis Matrix for Fire Zone 29 was updated to add 'flame' as a detection method in section IX (Fire Protection).
o Pg. 769, Attachment D Calculation/Evaluation Index updated to include FPEE 23-002, Evaluation of Fire Penetration FZ-0520.
License Document Change 604000001056 o Pg 550, Fire Hazards Analysis Matrix for Fire Zone 1E was updated to make the Fire Protection ventilation section more consistent with the Fire Zone 1-E, HPCI Room - Reactor Building Elevation 896 Strategy A.3-01-E.
- 3.
FIREPROTECT, FIRE PROTECTION PROGRAM PLAN (was 4 AWI-08.01.00)
Page 2 of 2 Revision 04 PCR 602000033404 o Pg 12, Revise Section 4.4.2.12.5 removing the reference to ICES and replacing with IRIS
- 4.
B.08.05-05, FIRE PROTECTION - SYSTEM OPERATION, TABLES A.2-1, A.2-2, A.2-3, AND A.2-4 Revision 83 PCR 602000026966 o Pg 10, 1AR removed from secton describing ASDS panel instrumentation controls.
o Pg 11-12, Appendix R Emergency Lighting section revised to describe the operation of Streamlight Eflood Litebox HL lights.
o Pg 18, Note added regarding the Lightworks units testing o Pg 26, Cooling Tower deluges were removed from the General Precautions section as these are retired in place after the cooling towers were replaced using non combustible materials.
Report Consistent with 10 CFR 54.37(b)
This summary report is in lieu of adding a level of detail to the Monticello Nuclear Generating Plant (MNGP) Updated Safety Analysis Report (USAR) that is greater in the remainder of the USAR, including the License Renewal Supplement in Appendix K.
The contents of this report are consistent with the requirements of 10 CFR 54.37(b) and the guidance of Regulatory Issue Summary (RIS) 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses" (ADAMS Accession Number ML100250279).
Fatigue Exemption TLAA Summary During development of the Subsequent License Renewal (SLR) project, it was identified that a Time Limited Aging Analyses (TLAA) specifically reflecting Fatigue Waivers exists in NUREG-2191 Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR). NUREG-1801 GALL Rev. 0 (Monticello Nuclear Generating Plant (MNGP)
Initial License Renewal) does not specify fatigue waivers as an example of a TLAA. It was determined that these Fatigue Waiver components will be include in the current license renewal period as a TLAA similar to how they will be aged managed for Subsequent Period of Extended Operation.
The design stress reports for the MNGP Reactor Pressure Vessel (RPV) include fatigue waivers that determined that some RPV components did not require explicit fatigue analyses because the criteria from ASME Section III, Paragraph N-415.1 or NB-3222.4(d) were satisfied (USAR-H).
The newly identified Fatigue Wavier (RPV) components identified with fatigue waiver evaluations are:
- Main Closure Flange
- Head Cooling Spray and Instrumentation Nozzles
- Vent Nozzle
- Instrumentation Nozzles
- Jet Pump Instrumentation Nozzles
- Intermediate Range Monitor/Source Range Monitor Dry Tube
- Power Range Detector Assembly
- In-Core Detector Assembly All components reviewed in this reevaluation were found acceptable regarding fatigue usage for 80 years, including effects of rerate and EPU. The ASME Section III Class 1 fatigue waiver acceptance criterion continues to be satisfied based on 80-year projected transient cycles through the SPEO which will be bounding for current license renewal period of 60 years.
TLAA Disposition:
The ASME Code,Section III, Class 1 component fatigue waivers will be managed by the Fatigue Monitoring AMP in accordance with 10 CFR 54.21(c)(1)(iii). The Fatigue Monitoring AMP will monitor the transient cycles which are the inputs to the fatigue waiver reevaluations and require action prior to exceeding design limits that would invalidate their conclusions.
There are no new material or environments associated with this TLAA description.
1 of 1 Report Consistent with 10 CFR 72.48 Evaluation Summary Report For the period from January 1, 2024, to December 31, 2024, there were no 10 CFR 72.48 evaluations performed.