L-MT-19-058, 7 to Updated Safety Analysis Report
| ML20003D172 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/09/2019 |
| From: | Church C Xcel Energy, Northern States Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20003D143 | List:
|
| References | |
| L-MT-19-058 | |
| Download: ML20003D172 (13) | |
Text
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 4 THIS DOCUMENT IS DECONTROLLED fl Xcel Energy*
RESPONSIBLE BY NATURE December 9, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Submittal of Revision 37 to the Updated Safety Analysis Report 2807 West County Road 75 Monticello, MN 55362 L-MT-19-058 10 CFR 50.71 (e) 10 CFR 50.59(d)(2)
Pursuant to 1 O CFR 50.71 (e), Revision 37 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 November 2, 2018, to October 15, 2019.
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 three changes to commitments., "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. contains Revision 37 of the MNGP USAR. The USAR is being submitted
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l) D(p electronically, in its entirety, on CD-ROM according to the instructions in Regulatory lssuA pt; S
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ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 4 THIS DOCUMENT IS DECONTROLLED L-MT-19-058 Page 2 of 2 Summary (RIS) RIS 2001-005, "Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM"., "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.
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.
~t.U Christopher R. Church Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (5) cc:
Administrator, Region 111, USNRC Resident Inspector, Monticello, USNRC (without enclosure 4)
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 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 November 2, 2018 to October 15, 2019 there were no 50.59 evaluations performed.
Page 1 of 1
ENCLOSURE 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 NRG Commitment Changes."
This enclosure provides a brief description and a summary of changes to commitments established with the NRG by the Monticello Nuclear Generating Plant (MNGP) per NEI 99-04 guidelines for time period from November 2, 2018 to October 15, 2019.
Three commitments have been retired from the MNGP commitment tracking program.
- 1. Commitment Tracking Number:
M05016A Commitment source document:
Letter, L-MT-05-014, from Thomas J. Palmisano Nuclear Management Company (NMC) to Document Control Desk (NRC), "Application for Renewed Operating License," dated March 16, 2005 (ADAMS Accession No. ML050880241).
Original Commitment Wording:
The Buried Piping and Tanks Inspection Program will be revised to specify a 10-year buried pipe inspection frequency.
Justification:
This commitment is being retired because it was incorparted into the Updated Safety Analysis Report (USAR) Appendix K in 2007 and thus no longer requires to be tracked as a regulatory commitment.
- 2. Commitment Tracking Number:
M89186A Commitment source document:
Letter from Thomas M. Parker (NSPM) to Document Control Desk (NRG),
"Description and Evaluationof the Modification to the 480 Volt Bus Supplying the LPCI Injection Valves," dated July 14, 1989 (ADAMS Accession No.
8907210199).
Original Commitment Wording:
Page 1 of 2 Upon loss of offs;te power, bus transfer does occur when Division I 480 voltage to Bus 1338/1438 fails to be restored within ten seconds. This test will be accomplished by: 1) interrupting the Division I 480 V source to Bus 1338/1438 ahead of the loss of voltage relay, 2) recording the delay time and 3) verifying that the transfer occurs.
Justification:
This commitment is being retired because it was incorparted into the Updated Safety Analysis Report (USAR) Section 8.3.5.3 in 1989 and thus no longer requires to be tracked as a regulatory commitment.
- 3. Commitment Tracking Number:
M89187A Commitment source document:
Letter from Thomas M. Parker (NSPM) to Document Control Desk (NRC),
"Description and Evaluationof the Modification to the 480 Volt Bus Supplying the LPCI Injection Valves," dated July 14, 1989 (ADAMS Accession No.
8907210199).
Original Commitment Wording:
Upon loss of offsite power, bus transfer does not occur when the Division I diesel is available and restores 480 voltage within ten seconds to Bus 1338/1438. This test will be integrated with the diesel generator starting and restoring power to the Division I source to Bus 1338/1438.
Justification:
This commitment is being retired because it was incorparted into the Updated Safety Analysis Report (USAR) Section 8.3.5.3 in 1989 and thus no longer requires to be tracked as a regulatory commitment.
Page 2 of 2
ENCLOSURE 3 MONTICELLO NUCLEAR GENERATING 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 604000000340 Affected sections:
Section USAR-10, Plant Auxiliary Systems 10.2.4.3, Performance Analysis Deletion of "from the main control room" removed from last sentence of first paragraph. The RHR system is able to be re-aligned from shutdown cooling (SOC) to LPCI. The sentence specified that alignment is from the Main Control Room.
USAR Change 604000000250 Affected sections:
Section USAR-1, Appendix I Evaluation of High Energy Line breaks Outside Containment 1.1.2, Assumptions Deletion of Assumption 1.1.2.10 as electrical coordination related to faulted equipment was not part of the original response to the Atomic Energy Commission Letter dated 12-18-1972.
1.6, References Deletions of Reference 1.6.1 and 1.6.5 since references are no longer used in USAR discussion.
USAR Change 604000000333 Affected sections:
Section USAR-03, Reactor Table 3.1-1 Deletion of bundle types no longer in use.
Section USAR-14, Plant Safety Analysis 14.7.2.11, Summary of AREVA ECCS-LOCA Results Deletion of the 10 CFR 50.46 report referenced as it is no longer current.
Page 1 of 1
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 37
- Licensing Document Change 604000000188 o Reference J.4.7.40 title was changed.
- Licensing Document Change 604000000300 o
Table J.4.1-1 was revised to include '(Exemption)' for Fire Zone 8 Cable Spreading Room.
o Table J.4.1-1 was revised to remove Fire Zone 8 Cable Spreading Room from Fire Area VI and added it to Fire Area VIII.
o Table J.4.1-2 was revised to remove Fire Zone 8 Cable Spreading Room from Fire Area VI and added it to Fire Area VIII.
o Section J.4.2 was revised to change the number of exemptions to five and to provide information regarding the Cable Spreading Room Structural Steel Exemption.
o Tables J.4.5-1 and J.4.6-1 were revised to include changes related to removing Fire Zone 8 from Fire Area VI and adding it to Fire Area VIII.
o Tables J.4.6-1 removed 'and Green' from Fire Area IX Fire Zones other than Fire Zone 23A.
o Section J.4.7 - added references J.4.7.86 thru J.4.7.91 which are all related to the Cable Spreading Room Structural Steel Exemption.
- 2.
USAR J.05, FIRE HAZARDS ANALYSIS Revision 37
- Licensing Document Change 604000000271 o
Fire Hazards Analysis Matrix was changed for Fire Zone 1 F, 2F, and 2C to credit FPEE-17-001 with the correct fire zones.
- Licensing Document Change 604000000300 Page 1 of 4 o
Section 2.0 added High-Hazard Fire Source definition which was used in the Cable Spreading Room Structural Steel Exemption.
o Table 1 was revised to remove Fire Zone 8 Cable Spreading Room from Fire Area VI and added it to Fire Area VIII.
o Table 2 was revised to remove Fire Zone 8 Cable Spreading Room from Fire Area VI and added it to Fire Area VIII.
o Fire Hazards Analysis Matrix was revised to remove Fire Zone 8 Cable Spreading Room from Fire Area VI and added it to Fire Area VIII.
o Fire Hazards Analysis Matrix for Fire Zones 7A, 78, 7C, 8, and 10 was revised to include reference FPEE-19-002 to support the fire barrier rating for the Ceiling 8NIII.
o Fire Hazard Analysis Matrix for Fire Zones 8 and 10 were revised to include Door-124 as a Fire Doors in Required Fire Barriers Section.
o Fire Hazard Analysis Matrix for Fire Zone 8 and 10 were revised to include dampers V-DF-404, V-DF-413, and V-DF-414 as Fire Dampers in Required Fire Barriers Section.
o Fire Hazard Analysis Matrix for Fire Zone 8 was revised to include a statement providing the basis for combining the Cable Spreading Room to Control Room and the removing crediting the Ceiling for Appendix R purposes.
o Fire Hazard Analysis Matrix for Fire Zone 9 was revised to from VDF-600 to V-DF-600.
o Door-124 was added to Attachment B - Fire Doors.
o V-DF-404, V-DF-413, and V-DF-414 were added to Attachment C
- Fire Dampers.
o Attachment C 'VDF' was changed to 'V-DF' as necessary.
- 3.
4 AWl-08.01.00, FIRE PROTECTION PROGRAM PLAN Revision 23
- Procedure Change Request 602000010643 o 4.4.2 added new list of Roles and Responsibilities o 4.4.3.A.2.a, bullet #2 '1' was revised to 'I' o 4.5.5.B.1 revision for changes to fleet Standard Design Process (SOP) o 4.8.2.F and 4.8.3.D revised to include the Cable Spreading Room Structural Steel Exemption.
o Figure 5.1 revision for changes to fleet Standard Design Process (SDP) and deletion of Corporate Directive 5.13 o Figure 5.2 revision due to Elimination of the Director Site Engineering position.
o Figure 5.3 'System Engineer' was revised to 'EFIN or Strategic Engineer'.
o Figure 5.4 revised to include basis for Section 4.4.2 Page 2 of 4
- 4.
8.08.05-05, FIRE PROTECTION - SYSTEM OPERATION, TABLES A.2-1, A.2-2, A.2-3 AND A.2-4 Revision 72
- PCR 602000007885 o Table A.2 None o Table A.2 None o Table A.2 None o Table A.2 Provided clarification to the functionality requirements for Door-124 and its impact on the functionality of the halon suppression system in the Cable Spreading Room.
Also, added an equipment ID and name for a Pressure Indicator for fire pump starting.
Revision 73
- PCR 602000008700 o Table A.2 Removed incomplete criteria that was added as an operator aid from Specification G.1.
o Table A.2 None o Table A.2 None o Table A.2 None Revision 74
- PCR 602000009123 o Table A.2 None o Table A.2 None o Table A.2 None o Table A.2 None Revision 75
- PCR 602000011288 o Table A.2 None o
Table A.2 None o Table A.2 None o Table A.2 None Revision 76
- PCR 602000012618 o Table A.2 None o Table A.2 None o Table A.2 None o Table A.2 None Revision 77
- PCR 602000012564 o Table A.2 None Page 3 of 4 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'.
Page 4 of 4
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 ENCLOSURE 4 MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 37 SEE ENCLOSED CD-ROM ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390
ENCLOSURE 4 - DISC 1 MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 37 File Name Rev. 37 001 - USAR LOEP 002 - USAR TOC 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, Part 1 of 2 017 - USAR Section 15-3, 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) 155 99 993 2,406 1,909 1,966 3,991 1,897 2,636 1,388 331 650 1,203 814 300 4,091 159 14,309 13,410 7,535 52 331 473 9,622 1,587 10,601 580 5,525 485
ENCLOSURE 4 - DISC 2 - Security Related Information MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 37 File Name Rev. 37 006 - USAR Section 4 007 - USAR Section 5 016-USAR Section 14.1 016 - USAR Section 14.2 016-USAR Section 14.3 ENCLOSED CD-ROM 017 - USAR Section 15 Drawings 018 - USAR Appendix A 025 - USAR Appendix I 026 - USAR Appendix J File Size (KB) 626 580 580 595 596 5,599 1,110 3,973 571