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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24162A0882024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 ML24141A1502024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2272024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits IR 05000336/20240112024-04-0101 April 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000336/2024011 and 05000423/2024011 ML24092A0752024-03-28028 March 2024 3R22 Refueling Outage Inservice Inspection (ISI) Owners Activity Report Extension ML24088A2352024-03-26026 March 2024 Decommissioning Funding Status Report ML24086A4762024-03-22022 March 2024 Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process ML24086A4802024-03-22022 March 2024 Alternative Request IR-4-14, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examination for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles ML24051A1922024-03-0808 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000336/20230062024-02-28028 February 2024 Annual Assessment Letter for Millstone Power Station, Units 2 and 3, (Reports 05000336/2023006 and 05000423/2023006) ML24053A2632024-02-21021 February 2024 Unit 3, and Independent Spent Fuel Storage Installation, Notification Pursuant to 10 CFR 72.212(b)(1) Prior to First Storage of Spent Fuel Under a General License ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage 2024-09-04
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23193A8692023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML23193A8982023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Drawing Incorporated by Reference ML23193A9072023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML23193A8962023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML23193A8902023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Frontmatter ML23193A8852023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 7, Instruments and Controls ML23193A9002023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML23193A9062023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics ML23193A8732023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML23193A8912023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System ML23193A8832023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML23193A8682023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 3, Reactor ML23193A9012023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML23193A8842023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML23193A8742023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ML23193A8822023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Frontmatter ML23193A8582023-06-28028 June 2023 8 to Defueled Safety Analysis Report, Drawings Incorporated by Reference ML23193A8722023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 2, Site and Environment ML23193A8702023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features Systems ML23193A8942023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23193A8872023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML23193A8652023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML23193A8892023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML23193A8812023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations ML23193A9022023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML23193A8782023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operation ML23193A8882023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML23193A8952023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML23193A8992023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML23193A8592023-06-28028 June 2023 8 to Defueled Safety Analysis Report, Technical Requirements Manual ML23193A8772023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 15, License Renewal ML23193A8752023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Processing and Radiation Protection Systems ML23193A9032023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML23193A8972023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Fire Protection Evaluation Report ML23193A8672023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control ML23193A8862023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML23193A8572023-06-28028 June 2023 8 to Defueled Safety Analysis Report, Redacted ML23193A8762023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML23193A8712023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 5, Structures ML23193A8662023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Drawings Incorporated by Reference - Redacted ML23193A8802023-06-28028 June 2023 1 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis ML23193A9042023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Tables 2.3-15 & Appendices, Monthly and Annual Wind Direction and Speed Distributions for 33-Foot Winds at Millstone ML23193A9052023-06-28028 June 2023 6 to Updated Final Safety Analysis Report, Chapter 19, License Renewal ML22193A1352022-06-23023 June 2022 5 to Updated Final Safety Analysis Report ML22193A0232022-06-23023 June 2022 7 to Defueled Safety Analysis Report ML22193A0762022-06-23023 June 2022 0 to Updated Final Safety Analysis Report, Chapter 15, License Renewal ML22193A1392022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Tables & Appendices ML22193A1362022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22193A1332022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance 2023-06-28
[Table view] |
Text
Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station 314 Rope Ferry Road, Waterford, CT 06385 DominionEnergy.com JUN 2 2. 2020 SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 U.S. Nuclear Regulatory Commission Serial No.20-223 Attention: Document Control Desk MPS Lic/LD RO Washington, DC 20555 Docket Nos. 50-336 50-423 License Nos. DPR-65 NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3 UPDATES TO THE FINAL SAFETY ANALYSIS REPORTS In accordance with 10 CFR 50.71(e), Dominion Energy Nuclear Connecticut,_ Inc. (DENG) hereby submits revisions to the Millstone Power Station Units 2 (MPS2) and Unit 3 (MPS3)
Updated Final Safety Analysis Reports (UFSARs).
Four CD-ROMs are enclosed in this submittal. Enclosure 1 contains a CD-ROM labeled as follows: Millstone Power Station Unit 2 Updated Final Safety Analysis Report Revision 38 Docket No. 050-00336 - Security-Related Information - Withhold Under 10 CFR 2.390. The CD-ROM contains the electronic version of the MPS2 FSAR Revision 38 in the following file:
000 MPS2 UFSAR Frontmatter.pdf 2,744,320 bytes 001 MPS2 UFSAR Chapter 1.pdf 1,771,520 bytes 002 MPS2 UFSAR Chapter 2.pdf 12,822,528 bytes 003 MPS2 UFSAR Chapter 3.pdf 16,717,824 bytes 004 MPS2 UFSAR Chapter 4.pdf 16,879,616 bytes 005 MPS2 UFSAR Chapter 5.pdf 49,295,360 bytes 006 MPS2 UFSAR Chapter 6.pdf 8,679,424 bytes 007 MPS2 UFSAR Chapter 7.pdf 11,030,528 bytes 008 MPS2 UFSAR Chapter 8.pdf 3,176,448 bytes 009 MPS2 UFSAR Chapter 9.pdf 18,315,264 bytes 010 MPS2 UFSAR Chapter 10.pdf 430,080 bytes 011 MPS2 UFSAR Chapter 11.pdf 5,654,528 bytes 012 MPS2 UFSAR Chapter 12.pdf 169,984 bytes 013 MPS2 UFSAR Chapter 13.pdf 1,349,632 bytes 014 MPS2 UFSAR Chapter 14.pdf 37,345,280 bytes 015 MPS2 UFSAR Chapter 15.pdf 539,920 bytes MPS2 UFSAR DWGS 61,841,408 bytes MPS2 UFSAR TRM 7,266,304 bytes This enclosure contains Security-Related Information that DENG requests be withheld from public disclosure in accordance with 10 CFR 2.390.
ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3, THIS LETTER IS DECONTROLLED.
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Serial No.20-223 FSAR Updates Page 2 of 6 Enclosure 2 contains a CD-ROM labeled as follows: Millstone Power Station Unit 2 Updated Final Safety Analysis Report Revision 38 - Redacted Docket No. 050-00336. The CD-ROM contains the electronic version of the MPS2 FSAR Revision 38 in the following files:
000 MPS2 UFSAR Frontmatter.pdf 2,744,320 bytes 001 MPS2 UFSAR Chapter 1.pdf 692,224 bytes 002 MPS2 UFSAR Chapter 2.pdf 11,272,192 bytes 003 MPS2 UFSAR Chapter 3.pdf 16,717,824 bytes 004 MPS2 UFSAR Chapter 4.pdf 16,879,616 bytes 005 MPS2 UFSAR Chapter 5.pdf 45,555,712 bytes 006 MPS2 UFSAR Chapter 6.pdf 8,679,424 bytes 007 MPS2 UFSAR Chapter 7 .pdf 8,951,808 bytes 008 MPS2 UFSAR Chapter 8.pdf 1,112,064 bytes 009 MPS2 UFSAR Chapter 9.pdf 18,315,264 bytes 010 MPS2 UFSAR Chapter 10.pdf 430,080 bytes 011 MPS2 UFSAR Chapter 11.pdf 3,129,344 bytes 012 MPS2 UFSAR Chapter 12.pdf 169,984 bytes 013 MPS2 UFSAR Chapter 13.pdf 1,349,632 bytes 014 MPS2 UFSAR Chapter 14.pdf 37,345,280 bytes 015 MPS2 UFSAR Chapter_ 15.pdf 539,920 bytes MPS2 UFSAR DWGS 46,786,560 bytes MPS2 UFSAR TRM 5,779,465 bytes ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3, THIS LETTER IS DECONTROLLED.
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Serial No.20-223 FSAR Updates Page 3 of 6 Enclosure 3 contains a CD-ROM labeled as follows: Millstone Power Station Unit 3 Updated Final Safety Analysis Report Revision 33 Docket No. 050-00423 - Security-Related Information - Withhold Under 10 CFR 2.390. The CD-ROM contains electronic version of MPS3 FSAR, Revision 33 in the following files:
000 MPS3 UFSAR Frontmatter.pdf 3,428,352 bytes 001 MPS3 UFSAR Chapter 1.pdf 2,547,712 bytes 002 MPS3 UFSAR Chapter 2 (part 1).pdf 11,481,088 bytes 002 MPS3 UFSAR Chapter 2 (part 2).pdf 56,825,856 bytes 002 MPS3 UFSAR Chapter 2 (part 3).pdf 82,511,872 bytes 002 MPS3 UFSAR Chapter 2 (Tables & Appendices) 98,959,360 bytes 003 MPS3 UFSAR Chapter 3.pdf 99,731,456 bytes 004 MPS3 UFSAR Chapter 4.pdf 5,982,208 bytes 005 MPS3 UFSAR Chapter 5.pdf 3,905,536 bytes 006 MPS3 UFSAR Chapter 6.pdf 17,035,264 bytes 007 MPS3 UFSAR Chapter 7.pdf 5,345,280 bytes 008 MPS3 UFSAR Chapter 8.pdf ,_
8,718,336 bytes 009 MPS3 UFSAR Chapter 9.pdf 18,869,696 bytes 010 MPS3 UFSAR Chapter 10.pdf 4,255,744 bytes 011 MPS3 UFSAR Chapter 11.pdf 2,914,304 bytes 012 MPS3 UFSAR Chapter 12.pdf 31,963,136 bytes 013 MPS3 UFSAR Chapter 13.pdf 1,011,712 bytes 014 MPS3 UFSAR Chapter 14.pdf 2,150,400 bytes 015 MPS3 UFSAR Chapter 15.pdf 13,000,704 bytes 016 MPS3 UFSAR Chapter 16.pdf 55,296 bytes 017 MPS3 UFSAR Chapter 17.pdf 59,392 bytes 018 MPS3 UFSAR Chapter 18.pdf 65,536 bytes 019 MPS3 UFSAR Chapter 19.pdf 346,112 bytes MPS3 UFSAR FPER 2,113,536 bytes MPS3 UFSAR DWGS 71,372,800 bytes MPS3TRM 3,196,928 bytes This enclosure contains Security-Related Information that DENG requests be withheld from public disclosure in accordance with 10 CFR 2.390.
ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3, THIS LETTER IS DECONTROLLED.
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Serial No.20-223 FSAR Updates Page 4 of 6 Enclosure 4 contains a CD-ROM labeled as follows: Millstone Power Station Unit 3 Updated Final Safety Analysis Report Revision 33" - Redacted Docket No. 050-00423.
The CD-ROM contains electronic version of MPS3 FSAR, Revision 33 in the following files:
000 MPS3 UFSAR Frontmatter.pdf 3,433,352 bytes 001 MPS3 UFSAR Chapter 1.pdf 1,153,024 bytes 002 MPS3 UFSAR Chapter 2 (part 1).pdf 9,414,656 bytes 002 MPS3 UFSAR Chapter 2 (part 2).pdf 53,209,088 bytes 002 MPS3 UFSAR Chapter 2 (part 3).pdf 43,587,584 bytes 002 MPS3 UFSAR Chapter 2 (Tables & Appendices) 98,959,360 bytes 003 MPS3 UFSAR Chapter 3.pdf 40,835,072 bytes 004 MPS3 UFSAR Chapter 4.pdf 5,982,208 bytes 005 MPS3 UFSAR Chapter 5.pdf 3,905,536 bytes 006 MPS3 UFSAR Chapter 6.pdf 14,106,624 bytes 007 MPS3 UFSAR Chapter 7.pdf 5,345,280 bytes 008 MPS3 UFSAR Chapter 8.pdf 8,161,280 bytes 009 MPS3 UFSAR Chapter 9.pdf 19,869,696 bytes 010 MPS3 UFSAR Chapter 10.pdf 4,255,744 bytes 011 MPS3 UFSAR Chapter 11.pdf 2,914,304 bytes 012 MPS3 UFSAR Chapter 12.pdf 2,605,056 bytes 013 MPS3 UFSAR Chapter 13.pdf 938,040 bytes 014 MPS3 UFSAR Chapter 14.pdf 2,150,400 bytes 015 MPS3 UFSAR Chapter 15.pdf 13,000,704 bytes 016 MPS3 UFSARChapter 16.pdf 55,296 bytes 017 MPS3 UFSAR Chapter 17.pdf 59,392 bytes 018 MPS3 UFSAR Chapter 18.pdf 65,536 bytes 019 MPS3 UFSAR Chapter 19.pdf 346,112 bytes MPS3 UFSAR FPER 1,263,616 bytes MPS3 UFSAR DWGS 65,400,832 bytes MPS3 UFSAR 3,196,928 bytes ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3, THIS LETTER IS DECONTROLLED.
SECURITYwRELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Serial No.20-223 FSAR Updates Page 5 of 6 Should you have any questions or require additional information, please contact Mr. Jeffry A.
Langan, {860) 444-5544.
Sincerely,
/J$g;;;}~
Jo~:. Daugherty Site Vice President - Millstone STATE OF CONNECTICUT COUNTY OF NEW LONDON The foregoing document was acknowledged before me, in and for the County and State aforesaid, today by John R. Daugherty, who is Site Vice President - Millstone of Dominion Energy Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to*
execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
tJ Acknowledged before me this :)..~,.. day of T--iwli , 2020.
TIMOTHY F. OLSOWY NOTARYPUBLIC MY COMMISSION IEXPIIIES APR. 30, 2021 ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3 1 THIS LETTER IS DECONTROLLED.
SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390 Serial No.20-223 FSAR Updates Page 6 of 6
Enclosures:
4 Commitments made in this letter: None.
cc: (w/ enclosures)
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 NRC Senior Resident Inspector Millstone Power Station cc: (w/o enclosures)
T. H. Carter NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F8 11545 Rockville Pike Rockville, MD 20852-2738 L: A. Kauffman .
Health Physicist-DNMS U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman.
NRC Senior Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission Orie White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 ENCLOSURES 1 & 3 TO THIS LETTER CONTAIN SECURITY-RELATED INFORMATION WHICH IS TO BE WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390.
UPON REMOVAL OF ENCLOSURES 1 & 3*, THIS LETTER IS DECONTROLLED.