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Category:Emergency Preparedness-Review of Emergency Plan Changes
MONTHYEARML19070A1192019-03-0404 March 2019 Attachment 1 - Millstone Power Station Emergency Plan, Revision 58 - 10 CFR 50.54(q)(5) Summary ML18255A0712018-09-0505 September 2018 Attachment 1 - Millstone Power Station Emergency Plan, Revision 57 10 CFR 50.54(q)(5) Summary ML16355A2112016-12-14014 December 2016 ISFSI - Summary of Change Analysis for Revision 54 to the Emergency Plan 2019-03-04
[Table view] Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 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) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 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 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications 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 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 2024-09-04
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Dominion Nuclear Connecticut, Inc. **
5000 Dominion Boulevard, Glen Allen, VA 23060 Dom1n1on Web Address: www.dom.com December 14, 2016 U.S. Nuclear Regulatory Commission Serial No.: 16-457 Attention: Document Control Desk NRNTJS: RO Washington, D.C. 20555 Docket Nos.: 50-245/336/423 72-47 License Nos.: DPR-21/65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 1, 2, 3 AND ISFSI REVISION TO MILLSTONE POWER STATION EMERGENCY PLAN REPORT OF CHANGE Pursuant to 10 CFR 50.54(q)(5) and 10 CFR 72.44(f), attached is a summary of the change analysis for Revision 54 to the Millstone Power Station (MPS) Emergency Plan which was effective on November 18, 2016. This revision incorporates a change that did not require prior NRC approval and does not implement actions that reduce the effectiveness of the MPS Emergency Plan. The Emergency Plan continues to meet the standards of 10 CFR 50.47(b).
If you have any questions or require additional information, please contact Mr. Thomas Szymanski at (804) 273-3065.
Sincerely,
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Mark D. Sartain Vice President - Nuclear Engineering Attachment Commitments made by this letter: None
Serial No.16-457
./ Docket Nos. 50-245/336/423, 72-4 7 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission, Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 ATTN: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Mr. R. Guzman (without attachment)
NRC Senior Project Manager (Units 2 and 3)
U.S. Nuclear Regulatory Commission, Mail Stop 08 C-2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. T. H. Carter (without attachment)
NRC Senior Project Manager (Unit 1)
U.S. Nuclear Regulatory Commission, Mail Stop T-8 F5 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Mr. J.M. Goshen (without attachment)
NRC Project Manager (ISFSI)
U. S. Nuclear Regulatory Commission, Mail Stop EBB-E3-D2M One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.16-457 Docket Nos. 50-245/336/423, 72-47 Attachment 1 Millstone Power Station Emergency Plan 10 CFR 50.54(g)(5) Summary Dominion Nuclear Connecticut, Inc. (DNC)
Serial No.16-457 Docket Nos. 50-245/336/423, 72-4 7 Page 1 of 1 10 CFR 50.54(q)(5) Summary of Analysis for Submittal 16-457 Millstone Emergency Plan Revision 54 clarified the Unit 2 Barrier Failure Reference Table, Coolant Leakage, Potential Loss emergency action level (EAL) for the Containment Barrier.
This clarification acknowledges that when addressing a loss of coolant accident coincident with one or more other events, entry into emergency operating procedure (EOP) 2540, Functional Recovery, is identical to entry into EOP 2532, Loss of Coolant Accident. The scope of NRC Safety Evaluation, subject: Millstone Nuclear Power Station Emergency Plan Revision 24 (TAC Nos. MA0838, MA0839 and MA0840), dated June 4, 1998, includes the current EAL scheme. The current EAL scheme is based on the National Environmental Studies Project (NESP) of the Nuclear Management and Resources Council, Inc.
(NUMARC) NESP/NUMARC-007, Revision 2, Methodology for Development of Emergency Action Levels (January 1992). Per Regulatory Issue Summary (RIS) 2003-18, Supplement 2, "Use of Nuclear Energy Institute (NEI) 99-01, "Methodology for Development of Emergency Action Levels," Revision 4, dated January 2003, this clarification maintains the existing classification scheme because it does not alter the intent of the initiating condition or EAL. Thus, the Title 10, Code of Federal Regulations, Part 50, Appendix E,Section IV.B.2 requirement for amending the license for proposed scheme changes does not apply. The regulatory basis for the EALs has not been changed because the new EALs agree with the approved scheme in meaning and intent such that the same emergency classification level results. The emergency planning standard for using a standard emergency classification and action level scheme per 10 CFR 50.47(b)(4) continues to be met because the EAL scheme remains intact and Appendix E,Section IV.B requirements continue to be met.