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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 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] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23006A1322022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix H, Revision 29, Reactor Pressure Vessel Design Summary Report L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement2022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement ML23006A1532022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix C, Revision 26, Quality Assurance Program ML23006A1492022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML23006A1282022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix I, Revision 38, Evaluation of High Energy Line Breaks Outside Containment ML23006A1512022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design ML23006A1292022-12-19019 December 2022 0 to Updated Safety Analysis Report, Table of Contents ML23006A1472022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15, Table of Contents - USAR Drawings ML23006A1482022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 14, Plant Safety Analysis ML23006A1502022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 8, Plant Electrical System ML23006A1452022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards ML23006A1432022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 13, Plant Operations ML23006A1412022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML23006A1422022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix G, Probable Maximum Flood at Mississippi at Monticello Minnesota May 26, 1969 ML23006A1402022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 11, Plant Power Conversion System ML23006A1302022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 1, Introduction and Summary ML23006A1462022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 12, Plant Structures and Shielding ML23006A1442022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 5, Containment System ML23006A1392022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 2, Site and Environs ML23006A1382022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix J, Revision 40, Fire Protection Program ML23006A1372022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 15-2 Drawing Set ML23006A1362022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix D, Revision 35, Pre-Operational and Startup Tests ML23006A1272022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control System ML23006A1522022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 4, Reactor Coolant System ML23006A1552022-12-19019 December 2022 0 to Updated Safety Analysis Report, Section 3, Reactor ML23006A1352022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix a, Revision 29, Seismic Design Criteria ML23006A1342022-12-19019 December 2022 0 to Updated Safety Analysis Report, List of Effective Pages ML23006A1562022-12-19019 December 2022 0 to Updated Safety Analysis Report, Appendix E, Revision 35, Plant Comparative Evaluation with the Proposed AEC 70 Design Criteria ML23006A1332022-12-19019 December 2022 Submittal of Revision 40 to Updated Safety Analysis Report ML21070A1112021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 3, Reactor ML21070A1202021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix D, Pre-Operational and Startup Tests ML21070A1062021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 12, Plant Structure and Sheilding ML21070A1092021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 8, Plant Electrical Systems ML21070A1332021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML21070A1252021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix J, Fire Protection Program ML21070A1342021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 10, Plant Auxiliary Systems ML21070A1182021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 2, Site and Environs ML21070A1222021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix H, Reactor Pressure Vessel Design Summary Report ML21070A1322021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 13, Plant Operations ML21070A1102021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1242021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 15, Drawings ML21070A1142021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix F, Containment Vessel Design Summary Design ML21070A1162021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix I, Evaluation of High Energy Line Breaks Outside Containment ML21070A1262021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control Systems ML21070A1072021-02-11011 February 2021 8 to Updated Safety Analysis Report, Appendix C, Quality Assurance Program ML21070A1042021-02-11011 February 2021 8 to the Updated Safety Analysis Report ML21070A1292021-02-11011 February 2021 8 to Updated Safety Analysis Report, Drawings ML21070A1312021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 1, Introduction and Summary L-MT-21-004, 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems2021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 11, Plant Conversion Systems ML21070A1212021-02-11011 February 2021 8 to Updated Safety Analysis Report, Section 6, Plant Engineered Safeguards 2022-12-19
[Table view] |
Text
ENCLOSURE 4 CONTAINS SECURITY-RELATED INFORMATION WITHHOLD UNDER 10 CFR 2.390 WHEN SEPARATE FROM ENCLOSURE 4 THIS DOCUMENT IS DECONTROLLED
- & Xcel Energy* 2807 West County Road 75 Monbcello, MN 55089 February 11, 2021 L-MT-21-004 10 CFR 50.71(e) 10 CFR 50.59(d)(2)
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 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 10 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 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 October 16, 2019 to December 15, 2020 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 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 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 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 GENERATING PLANT USAR REVISION 38 ENCLOSED CD-ROM File Name Rev. 38 File Size (KB) 001 - USAR LOEP 168 002 - USAR TOG 119 003 - USAR Section 1 716 004 - USAR Section 2 1,887 005 - USAR Section 3 1,928 006 - USAR Section 4 2,032 007 - USAR Section 5 3,248 008 - USAR Section 6 1,721 009 - USAR Section 7 2,334 010- USAR Section 8 1,182 011 - USAR Section 9 350 012 - USAR Section 10 770 013 - USAR Section 11 1,225 014 - USAR Section 12 753 015 - USAR Section 13 319 016 - USAR Section 14 5,438 017 - USAR Section 15-1 136 017 - USAR Section 15-2 DRAWING SET - Part 1 of 2 12,799 017 - USAR Section 15-3 DRAWING SET- Part 2 of 2 14,444 018 - USAR Appendix A 7,691 019 - USAR Appendix C 61 020 - USAR Appendix D 349 021 - USAR Appendix E 492 022 - USAR Appendix F 10,383 023 - USAR Appendix G 2,582 024 - USAR Appendix H 10,763 025 - USAR Appendix I 594 026 - USAR Appendix J 4,973 027 - USAR Appendix K 551
ENCLOSURE 4 - DISC 2 - Security Related Information MONTICELLO NUCLEAR GENERATING PLANT USAR REVISION 38 ENCLOSED CD-ROM File Name Rev. 38 File Size (KB) 006 - USAR Section 04 50 007 - USAR Section 05 47 016 - USAR Section 14-1 44 016 - USAR Section 14-2 46 016 - USAR Section 14-3 47 017- USAR Section 15 DRAWING SET 7,526 018 - USAR Appendix A 1,003 025 - USAR Appendix I 3,995 026 - USAR Appendix J 56