|
---|
Category:Emergency Preparedness-Emergency Plan
MONTHYEARML23159A2202023-06-0808 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 2023-06-08
[Table view] Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] |
Text
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 Attention:
Document Control Desk Washington, D.C. 20555 Serial No.: 17-071 NRAff JS: RO 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, . Mark D. Sartain Vice President
-Nuclear Engineering and Fleet Support Attachment Commitments made by this letter: None r 11x1-15
µrv165
.*... , . '.: -,--,, --------------------------------------
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
' -* Attachment 1 Serial No.17-071 Docket Nos. 50-245/336/423, 72-47 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.