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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) ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code 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 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 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) 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) 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 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 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 ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) 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 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 2024-09-04
[Table view] Category:Schedule and Calendars
MONTHYEARML13183A0602013-06-26026 June 2013 Offsite Assessment Capability During an Event Involving Multiple Release Sources ML13032A1322012-08-23023 August 2012 8:30 Am Daily Reactor Oversight Coordination Meeting ML13032A1312012-08-21021 August 2012 8:30 Am Daily Reactor Oversight Coordination Meeting ML13032A1302012-08-20020 August 2012 8:30 Am Daily Reactor Oversight Coordination Meeting ML13032A1292012-08-16016 August 2012 8:30 Am Daily Reactor Oversight Coordination Meeting ML0827309112008-09-29029 September 2008 NRC Regulatory Issue Summary 2008-16, Correction to Submittal for Preparation and Scheduling of Operator Licensing Examinations ML0504806042004-04-0202 April 2004 E-mail from Richard Emch of NRC to Richard Gallagher of DNC, Dated 04/02/2004 Millstone Site Audit Information Needs & Schedule ML18295A5431978-08-0808 August 1978 Combustion Engineering Owners' Group Proposed Plan to Resolve the Asymmetric LOCA Loads Issue 2013-06-26
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Text
Dominion Nuclear Connecticut, Inc.
5Y)00 Dominion Boulevard, Glen Allen, VA 23060 Dominion Web Address: www.dom.com June 26, 2013 U.S. Nuclear Regulatory Commission Serial No. 13-242B Attention: Document Control Desk NLOS/VDC R2 Washington, DC 20555 Docket Nos. 50-336 50-423 License Nos. DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3 OFFSITE DOSE ASSESSMENT CAPABILITY DURING AN EVENT INVOLVING MULTIPLE RELEASE SOURCES In a letter to the Nuclear Energy Institute (NEI) from the NRC dated February 27, 2013 (ML13029A632), the NRC requested additional detailed information regarding licensee's site-specific, current or planned, multi-unit dose assessment capabilities. In response to the Director, Nuclear Security and Incident Response, dated March 14, 2013 (ML13073A522), NEI notified the NRC that licensees would provide letters directly to the NRC describing multi-unit/multi-source dose assessment capability.
In accordance with the NEI letter, Dominion Nuclear Connecticut, Inc. (DNC) provides the following information regarding the capability to perform offsite dose assessment at Millstone Power Station (MPS) during an event involving multiple release sources (e.g.,
the ability to assess concurrent releases from reactor containment and the spent fuel pool).
Currently, MPS uses Meteorological Information Dose Assessment System (MIDAS) software from ABS Consulting, Inc., as its dose calculation model. MIDAS is a personal computer based program for rapidly assessing the radiological impact of accidents at nuclear power plants. It calculates total effective dose equivalent (TEDE) and thyroid doses. Source term information is derived from plant effluent monitors, reactor coolant system (RCS) or containment samples, field monitoring teams, or a default design basis accident scenario. In the event of a set of events involving multiple units/sources, individual dose assessment results can be summed to determine a total offsite dose assessment result.
Furthermore, an upgraded version of MIDAS software with a Multiple Accident Report Combiner (MARC) MIDAS Module has been procured. This MARC MIDAS Module can process up to five individual accidents and present results on a graphically displayed map with results combined for multiple release sources. The software upgrade will be implemented as indicated in the attached schedule.
Serial No. 13-242B Docket Nos. 50-336/423 Page 2 of 3 If you have any questions regarding this information, please contact Wanda Craft at (804) 273-4687.
Sincerely, David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Commitments made in this letter: None
Attachment:
Implementation Schedule for MARC MIDAS Module for Multi-Unit Dose Assessment Capability COMMONWEALTH OF VIRGINIA
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A. Heacock, who is President and Chief Nuclear Officer of Dominion 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 /7-/of his know dge and belief.
Acknowledged before me this, day of 2013.
My Commission Expires: 3 I VICKI L.HULL Notary Public Notary Public I Commonwealth of Virginia 140542 Uu*n~mZ..liA ;vnirn@ Urn, .1 *fl1A P! misel m Ownllliril MiV %1 2014VI I
Serial No. 13-242B Docket Nos. 50-336/423 Page 3 of 3 cc: Director, Office of Nuclear Reactor Regulation One White Flint North Mail Stop 13H16 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd.
Suite 100 King of Prussia, PA 19406-2713 Nadiyah S. Morgan Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 13-242B Docket Nos. 50-336/423 ATTACHMENT IMPLEMENTATION SCHEDULE FOR MARC MIDAS MODULE FOR MULTI-UNIT DOSE ASSESSMENT CAPABILITY MILLSTONE POWER STATION UNITS 2 AND 3 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 13-242B Docket Nos. 50-336/423 Attachment, Page 1 of 1 IMPLEMENTATION SCHEDULE The following table lists the milestones to implement the MARC MIDAS Module for multi-unit dose assessment capability at Millstone Power Station. The milestones are being tracked in the Central Reporting System via LCO01 164.
Item Implementation Estimated No. Task Completion Date Obtain MIDAS software with a Multiple Accident Complete Report Combiner (MARC) MIDAS Module 2 Complete acceptance testing of MARC MIDAS 09/03/2013 Module 3 Develop end-user documents (e.g., implementing 10/31/2013 procedures, guidelines, etc.)
4 Develop and conduct training on MARC MIDAS 09/09/2014 Module 5 Implement multi-unit dose assessment capability 12/31/2014