ML21070A104
| ML21070A104 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/11/2021 |
| From: | Conboy T Xcel Energy, Northern States Power Company, Minnesota |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21070A105 | List:
|
| References | |
| L-MT-21-004 | |
| Download: ML21070A104 (11) | |
Text
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 4 THIS DOCUMENT IS DECONTROLLED
- & Xcel Energy*
February 11, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263
~enewed Facility Operating License No. DPR-22 Submittal of Revision 38 to the Updated Safety Analysis Report 2807 West County Road 75 Monbcello, MN 55089 L-MT-21-004 10 CFR 50.71(e) 10 CFR 50.59(d)(2)
Pursuant to 10 CFR 50.71 (e), Revision 38 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 October 16, 2019, to December 15, 2020.
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 was one change to commitments., "Summary of Information Removed from the USAR", provides the information removed from the USAR far this revision cycle. This information is provided in accordance with Revision 1 of NEI 98-03 and Regulatory Guide 1.181.
- contains Revision 38 of the MNGP USAR. The USAR is being submitted electronically, in its entirety, on CD-ROM according to the instructions in Regulatory Issue A-1>5~
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 1 O CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 4 THIS DOCUMENT IS DECONTROLLED L-MT-21-004 Page 2 of 2 Summary (RIS} RIS 2001-005, "Guidance on Submitting Documents to the NRG by Electronic Information Exchange or on CD-ROM"., "Report of Changes to the Monticello Fire Protection Program 11
, 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 Aplil 24, 1986.
summary of Commitments This letter contains no new 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 of 10 CFR 50.59 not previously submitted to the Commission.
Thomas A Conboy Site Vice President Monticello Nuclear Generati nt Northern States Power Company - Minnesota Enclosures (5) cc:
Administrator, Region Ill, USNRC Resident Inspector, Monticello, USNRC (without enclosure 4)
ENCLOSURE 1 MONTICELLO NUCLEAR GENERA TING PLANT REPORT OF CHANGES, TESTS AND EXPERIMENTS The following includes a brief description and summary of the 10 CFR 50.59 evaluation 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 October 16, 2019 to December 15, 2020 there were no 50.59 evaluations performed.
Page 1 of 1
ENCLOSURE 2 MONTICELLO NUCLEAR GENERA TING 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 the time period from October 16, 2019 through December 15, 2020 one change is being reported.
For Revision 38:
- 1. Commitment Tracking Number:
M89188A Commitment source document:
The original letter was in response to GL 88-14 Instrument Air Supply Problems System Problems Affecting Safety-Related Equipment dated February 17, 1989.
Original Commitment wording:
All major instrument air delivery components receive preventative maintenance annually.
Justification:
The air compressors as referenced in this commitment, M89188A, are subject to the maintenance rule and the preventative maintenance is now governed by 10 CFR 50.65, therefore the commitment is no longer required to be tracked as a regulatory commitment and was retired.
Page 1 of 1
ENCLOSURE 3 MONTICELLO NUCLEAR GENERA TING PLANT
SUMMARY
OF INFORMATION REMOVED FROM THE USAR 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) is summarized below.
USAR Change 604000000451 Affected sections:
Section USAR-12, Plant Structures and Shielding 12.4, Radioactive Materials Safety Deletion of statement in section 12.4 referenced an NRC submittal that described the Station's Radioactive Material Safety Program as it existed in 1974. The content is now obsolete.
12.5, References Deletion of Reference 82 since reference is no longer used in USAR discussion.
USAR Change 604000000470 Affected sections:
Section USAR-J, Appendix J Fire Protection Program J.4.5.3, Circuit Analysis Deletion of non-category 2 spurious operations components.
USAR Change 604000000421 Affected sections:
Section USAR-J, Appendix J Fire Protection Program Attachment E Deletion of Attachment E eliminates duplication of information within USAR-J.05.
Page 1 of 1
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 ENCLOSURE 4 MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 38 SEE ENCLOSED CD-ROM ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390
ENCLOSURE 5 MONTICELLO NUCLEAR GENERATING PLANT REPORT OF CHANGES TO THE MONTICELLO FIRE PROTECTION PROGRAM 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 38 Licensing Document Change 604000000513 o
Section J.4.2 updated amount of exemptions from Four to Five.
o Table J.4.5-3 was updated to remove an out of date reference and update the disposition for MSIVs.
Licensing Document Change 604000000470 o
Page 121, removed non-category 2 spurious operations components.
- 2.
USAR J.05, FIRE HAZARDS ANALYSIS Revision 38 Licensing Document Change 604000000421 o
Page 3, deleted Attachment E of USAR-J.05 from Table of Contents.
o Fire Hazard Analysis Matrix for Fire Zone7B corrected FPEE 002 to FPEE-19-002 o
Fire Hazard Analysis Matrix for Fire Zone 8 and 10 added South/C205 Dampers (V-DF-404, V-DF-413, and V-DF-414) acceptability of the fire damper rating is documented in FPEE 001 to the Comments Section.
o Fire Hazard Analysis Matrix for Fire Zone 12A added West Fire Door, Door-15, acceptability of the fire door rating is documented in FPEE-13-004 to the Comments Section.
o Fire Hazard Analysis Matrix for Fire Zone 12E added East Fire Door, Door-15, acceptability of the fire door rating is documented in FPEE-13-004 to the Comments Section.
o Fire Hazard Analysis Matrix for Fire Zone 13B added additional barrier acceptability discussion regarding CA-02-103 the Comments Section Items 1, 3, and 4.
Page 1 of 3
o Fire Hazard Analysis Matrix for Fire Zone 15B added Fire Zone 15A(Trench) barrier rating acceptability is documented in FPEE-15-001 to the Comments Section.
o Attachment D added MOD 02Q230 to Summary Description for CR 02004912, CR02008132, CR 02008344, CR 02008349, CR 02008354, CR 02008444, CR 02008450, CR 02008625, CR 02008632, CR 02008636.
o Attachment D added FPEE-05-001, FPEE-19-001, and FPEE 002.
o Attachment E Deleted and incorporated into Fire Hazard Analysis Matrices and other Attachments.
- 3.
4 AWl-08.01.00, FIRE PROTECTION PROGRAM PLAN Revision 24 Procedure Change Request 602000015895 o 4.0 revised Operating Experience lanagauge to align with fleet requirements.
o 4.4.3.A.1.a, removed out of date software for eye exam requirements.
- 4.
B.08.05-05, FIRE PROTECTION - SYSTEM OPERATION, TABLES A.2-1, A.2-2, A.2-3 AND A.2-4 Revision 77 PCR 602000012564 o
Table A.2 None o Table A.2 The surveillance frequency for the functional check of the ASDS control circuit was changed from 24 months to 48 months under STRIDE MT-2018-ASD-13.
o Table A.2 None o Table A.2 Included guidance on functionality requirement for Door-125 and fire dampers V-DF-404, V-DF-413, and V-DF-414 and their impact on the functionality of the halon suppression system in the Cable Spreading Room. Also, changed 'System Engineer' to 'Fire Protection Engineer'.
Revision 78 PCR 602000012966 o Table A.2 None o Table A.2 None o Table A.2 None o Table A.2 Revised Section G.8 - Reset Deluge Valves to add placekeeping and update language for performing steps.
Revision 79 PCR 602000014366 Page 2 of 3
o Table A.2-1 -Added LC-104 and 1AR as support systems to Specfication H.1 -Alternate Shutdown System Panel.
o Table A.2 Removed Specification H.2 to align with Table A.2-1 Specification H.
o Table A.2 None o Table A.2 Removed reference to Passport and replaced with "See component data base for valves related to the system".
Revision 80 PCR 602000017643 o Table A.2 Specification 8.3 revised to add "(Reference MOC 608000000592 for Engineering Evaluation FPEE-20-002 (Alternate Compensatory Measure for 2 Fire Pumps Out of Service or Non-Functional) to document acceptable alternate compensatory measures for 2 fire pumps non-functional)"
o Table A.2 None o Table A.2 None o Table A.2 None Page 3 of 3
ENCLOSURE 4 - DISC 1 MONTICELLO NUCLEAR GENERA TING PLANT USAR REVISION 38 File Name Rev. 38 001 - USAR LOEP 002 - USAR TOG 003 - USAR Section 1 004 - USAR Section 2 005 - USAR Section 3 006 - USAR Section 4 007 - USAR Section 5 008 - USAR Section 6 009 - USAR Section 7 010- USAR Section 8 011 - USAR Section 9 012 - USAR Section 10 013 - USAR Section 11 014 - USAR Section 12 015 - USAR Section 13 016 - USAR Section 14 017 - USAR Section 15-1 ENCLOSED CD-ROM 017 - USAR Section 15-2 DRAWING SET - Part 1 of 2 017 - USAR Section 15-3 DRAWING SET-Part 2 of 2 018 - USAR Appendix A 019 - USAR Appendix C 020 - USAR Appendix D 021 - USAR Appendix E 022 - USAR Appendix F 023 - USAR Appendix G 024 - USAR Appendix H 025 - USAR Appendix I 026 - USAR Appendix J 027 - USAR Appendix K File Size (KB) 168 119 716 1,887 1,928 2,032 3,248 1,721 2,334 1,182 350 770 1,225 753 319 5,438 136 12,799 14,444 7,691 61 349 492 10,383 2,582 10,763 594 4,973 551
ENCLOSURE 4 - DISC 2 - Security Related Information MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 38 File Name Rev. 38 006 - USAR Section 04 007 - USAR Section 05 016 - USAR Section 14-1 016 - USAR Section 14-2 016 - USAR Section 14-3 ENCLOSED CD-ROM 017-USAR Section 15 DRAWING SET 018 - USAR Appendix A 025 - USAR Appendix I 026 - USAR Appendix J File Size (KB) 50 47 44 46 47 7,526 1,003 3,995 56