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Category:Emergency Preparedness-Emergency Plan
MONTHYEARML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes ML23061A0602023-03-0101 March 2023 Associated Independent Spent Fuel Storage Installation - Revision to Emergency Plan - Report of Change ML21076A3962021-03-17017 March 2021 Revision to Emergency Plan - Report of Change ML21035A2812021-02-0404 February 2021 Revision to Emergency Plan - Report of Change ML21067A1502021-01-26026 January 2021 Management Program for Maintaining Emergency Preparedness ML20303A2192020-10-29029 October 2020 Revision to Emergency Plan - Report to Change ML20261H5972020-09-17017 September 2020 Request for Exemption from Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, Sections IV.F.2.b and IV.F.2.c ML19175A0752019-06-17017 June 2019 Emergency Plan, Revision 60: 10 CFR 50.54(q)(5) Summary ML19175A0742019-06-17017 June 2019 Submittal of Revision 60 to Emergency Plan ML18241A0912018-08-0303 August 2018 Emergency Plan ML18103A0332018-04-10010 April 2018 ISFSI - Revision to Emergency Plan, Report of Change ML18103A0342018-04-10010 April 2018 ISFSI - Attachment 1 to 18-126, Emergency Plan, Revision 56 10 CFR 50.54(q)(5) Summary ML17090A4132017-02-24024 February 2017 ISFSI, Revision to Millstone Power Station Emergency Plan Report of Change ML16138A2042016-05-0505 May 2016 Revision 053 to MP-26-EPI-EPMP, Emergency Plan ML16076A1882016-03-0808 March 2016 Emergency Plan, Revision 52 ML16028A3172016-01-20020 January 2016 Revision 51 to the Emergency Plan ML12348A0142012-11-21021 November 2012 Submittal of the Final Action Report, After Action Report/Improvement Plan, Radiological Emergency Preparedness Program. ML0932903122009-11-24024 November 2009 ISFSI (Lbdcrs 09-MP1-001, 09-MP2-020, and 09-MP3-008) - Application for Proposed Change to Emergency Plan ML0736009742007-12-19019 December 2007 Petition for Rulemaking PRM-50-89 Submitted by Ray West Regarding, to Amend CFR 5-.55a-Codes and Standards - Revision 1 ML0436400382004-12-20020 December 2004 Emergency Plan, Revision 31 2024-07-25
[Table view] Category:Letter
MONTHYEARML24317A2562024-11-12012 November 2024 Core Operating Limits Report, Gycle 30 IR 05000245/20240012024-11-12012 November 2024 Safstor Inspection Report 05000245/2024001 IR 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) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 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) 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) 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 ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 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 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 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) ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating 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 2024-09-04
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Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Web Address: www.dom.com February 24, 2017 U.S. Nuclear Regulatory Commission Serial No.: 17-071 Attention: Document Control Desk NRAffJS: 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 55 to the Millstone Power Station (MPS) Emergency Plan which was effective on January 26, 2017. This revision incorporates changes 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 and Fleet Support Attachment Commitments made by this letter: None r
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Serial No.17-071 Docket Nos. 50-245/336/423, 72-47 Page 2of2 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.17-071 Docket Nos. 50-245/336/423, 72-47 Attachment 1 Millstone Power Station Emergency Plan 10 CFR 50.54(9)(5) Summary Dominion Nuclear Connecticut, Inc. (DNC)
Serial No.17-071 Docket Nos. 50-245/336/423, 72-47 Page 1of2 10 CFR 50.54(g)(5) Summary of Analysis for Millstone Emergency Plan Revision 55 Millstone Emergency Plan, Revision 55, incorporated the changes described below. A description of why the change was not a reduction in the effectiveness of the emergency plan and the regulatory basis for each non-editorial change is also provided.
- 1. Section 4, Tables 4-1 to 4-4 (Emergency Class - Licensee Actions): Emergency class definitions were revised to align with Unit 2 and Unit 3 EAL Table Classification definitions listed in Appendix I, Emergency Action Level Scheme (previously determined to satisfy the provisions of 10 CFR 50.47(b)(4)).
- 2. Section 5, Table 5-1, Station Emergency Response Organization: Added the Work Control Senior Reactor Operator (WCSRO) as an option to take the Station Duty Officer (SDO) role initially in lieu of the opposite unit's Shift Technical Advisor (STA) or relieve the Security Shift Operations Supervisor (SSOS) to provide a person knowledgeable in plant operations. The WCSRO can relieve the SSOS as the SDO if that is their only SERO position for the event and they are qualified to fill the SDO position. The emergency planning standards associated with staff response and for maintaining adequate staffing to provide initial facility accident response in key functional areas per 10 CFR 50.47(b)(1) and (2) continue to be met because on-shift personnel assigned emergency plan implementation functions are not assigned responsibilities that would prevent the timely performance of their assigned functions as specified in the emergency plan.
- 3. Section 5, Table 5-1, Station Emergency Response Organization: Aligned the respirator qualification requirements for the Assistant Radiological Protection Supervisor (ARPS) in the Operational Support Center Assembly Area (OSCAA) with other OSCAA positions. Since the OSCAA does not have a filtered ventilation system, personnel are relocated from the OSCAA if radiological conditions warrant.
The emergency planning standard associated with emergency radiological exposure control per 10 CFR 50.47 (b)(11) continues to be met because means are provided for controlling radiological exposure.
- 4. Section 6.1, Notification and Activation of Emergency Organizations, and Section 7.1.2, Alert and Notification: Updated the description of the notification call out process to indicate that the electronic distribution of the Incident Report Form provides off-site officials information* previously obtained by calling and listening to a recording. The emergency planning standard associated with the capability of alerting state and local governmental agencies of the declared emergency within 15 minutes after declaration of an emergency per 10 CFR 50.47(b)(5) continues to be met because technological advancements have expanded the means of delivering emergency messages with functionally equivalent or superior devices.
Serial No.17-071 Docket Nos. 50-245/336/423, 72-47 Page 2 of 2
- 5. Section 8, Maintaining Emergency Preparedness: Updated list of Manager, Emergency Preparedness responsibilities to conform with Topical Report DOM-QA-1, Nuclear Facility Quality Assurance Program Description (Revision 22, effective July 1, 2016), as it relates to facility emergency preparedness. The emergency planning standards for ensuring primary responsibilities for emergency response, training and maintaining the emergency plan per 10 CFR 50.47 (b) (1), (15) and (16) continue to be met because program responsibilities continue to be assigned.
- 6. Appendix D, Supporting Procedures List: The list of procedures supporting the plan is updated to reflect procedure consolidations and process changes. The emergency planning standard for maintaining the emergency plan per 10 CFR 50.47 (b)(16) continues to be met because a list of supporting procedures is provided as an appendix.