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Results
Other: ML13063A012, ML13242A011, ML13242A014, ML13357A398, ML14006A159, ML14069A011, ML14069A013, ML14069A014, ML14176A952, NOC-AE-13002959, Overall Integrated Plan Regarding Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
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MONTHYEARML13063A0122013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other NOC-AE-13002959, Overall Integrated Plan Regarding Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-02-28028 February 2013 Overall Integrated Plan Regarding Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ML13126A2062013-04-30030 April 2013 Supplement to Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12-049) Project stage: Supplement ML13175A2422013-06-26026 June 2013 Request for Additional Information Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumental Project stage: RAI ML13213A0152013-07-26026 July 2013 Response to Request for Additional Information to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Response to RAI ML13242A0112013-08-23023 August 2013 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) Project stage: Other ML13242A0142013-08-23023 August 2013 Connecticut, Inc. & Millstone Power Station Units 2 and 3 Six-Month Status Report in Response to Letter Dated March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Project stage: Other ML13291A1152013-10-29029 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation (TAC Nos. MF0838 and MF0839 Project stage: RAI ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 Project stage: Other ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 Project stage: Other ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Acceptance Review ML14069A0132014-02-28028 February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML14069A0112014-02-28028 February 2014 Six-Month Status Report in Response to March 12. 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ML14069A0142014-02-28028 February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML14176A9522014-07-0202 July 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML14275A0172014-11-17017 November 2014 Report for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Acceptance Review 2013-08-23
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Category:Letter
MONTHYEARIR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 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 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 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) 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 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) IR 05000336/20244402024-04-25025 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 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 ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 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 ML24043A0062024-02-15015 February 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Support Implementation of Framatome Gaia Fuel IR 05000336/20230042024-02-14014 February 2024 Integrated Inspection Report 05000336/2023004 and 05000423/2023004 ML24030A7522024-01-30030 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 2024-08-06
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Dominion Nuclear Connecticut, Inc. D 5000 Dominion Boulevard, Glen Allen, VA 23060 Domin iote Web Address: www.dom.com 10 CFR 2.202 April 30, 2013 EA-12-049 Attention: Document Control Desk Serial No.: 12-161C U.S. Nuclear Regulatory Commission NL&OS/MAE: RO Washington, D.C. 20555-0001 Docket Nos.: 50-336/423 License Nos.: DPR-65 DOMINION NUCLEAR CONNECTICUT, INC. NPF-49 MILLSTONE POWER STATION UNITS 2 AND 3 SUPPLEMENT TO OVERALL INTEGRATED PLAN IN RESPONSE TO MARCH 12, 2012 COMMISSION ORDER MODIFYING LICENSES WITH REGARD TO REQUIREMENTS FOR MITIGATION STRATEGIES FOR BEYOND-DESIGN-BASIS EXTERNAL EVENTS (ORDER NUMBER EA-12-049)
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (the Order) to Dominion Nuclear Connecticut, Inc. (DNC). DNC responded to the Order by letters dated March 26, 2012, October 25, 2012, and February 28, 2013 (Serial Nos.12-161, 12-161A and 12-161B, respectively).
The purpose of this letter is to supplement the Overall Integrated Plan that was provided in DNC's February 28, 2013 letter. The additional information is provided for Millstone Units 2 and 3 in the attachment to this letter.
If you have any questions, please contact Ms. Margaret Earle at (804) 273-2768.
Sincerely, Eugene S. Grecheck VICKI L.HULL Vice President Nuclear Engineering and Development Commonwealth of Virginia Dominion Nuclear Connecticut, Inc. F y omision140342 Expires May 31, 2014 COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck who is Vice President Nuclear Engineering and Development 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 the Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 5 0'day
' of prLi 2013.
My Commission Expires:
Notary Public (SEAL)
Serial No. 12-161C Docket Nos. 50-336/423 Order EA-12-049 Page 2 of 2 Attachment Commitments made by this letter: No New Regulatory Commitments cc: Director of Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 13H16M 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission, Region I Regional Administrator 2100 Renaissance Blvd.
Suite 100 King of Prussia, PA 19406-2713 Mr. J. S. Kim NRC Project Manager Millstone Units 2 and 3 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 C 2A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. J. A. Kratchman U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 D2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 12-161C Docket Nos. 50-336/423 Order EA-12-049 Attachment Supplement To Millstone Units 2 and 3 Overall Integrated Plan Requirements for Mitigation Strategies For Beyond-Design-Basis External Events Millstone Power Station Units 2 and 3 Dominion Nuclear Connecticut, Inc. (DNC)
Serial No. 12-161C Docket Nos. 50-336/423 Order EA-12-049 Attachment, Page 1 of 2 Supplement To Millstone Units 2 and 3 Overall Integrated Plan Requirements for Mitigation Strategies For Beyond-Design-Basis External Events By letter dated February 28, 2013, Serial No. 12-161B, DNC provided an Overall Integrated Plan (OIP) to address Beyond-Design-Basis (BDB) events at Millstone Units 2 and 3 as required by Order Number EA-12-049, dated March 12, 2012. It was stated that the OIP was based on conceptual design information and that final design information and revisions would be provided via updates. Various open items were inserted into the OIP to identify information that would be provided or confirmed at a later date. This attachment provides the basis for closure of Open Item No. 2 for Unit 2 and Open Item No. 3 for Unit 3.
Millstone Unit 2:
Open Item No. 2 - Preliminaryanalyses have been performed to determine the time to SG overfill without operator action to reduce AFW flow, time to SG dryout without AFW flow, and time to depletion of the CST. Final durations will be provided when the analyses are completed.
The analysis for secondary side inventories and heat removal has been finalized. Slight changes were observed from the preliminary values reported in the OIP. These changes are as follows:
- 1) The time to steam generator (SG) overfill decreased from 2.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
As stated in the OIP, operators would be assigned within the first 15 minutes of the event to control flow in order to maintain proper SG level. The throttling would be performed locally using the auxiliary feedwater (AFW) regulating valves or their bypass valves at the turbine driven auxiliary feedwater (TDAFW) pump.
Operators could access the area in less than 5 minutes to begin to control AFW flow in order to maintain SG levels. Therefore, the basis for acceptability stated in the OIP remains valid for the reduced SG overfill time of 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 2) The time for SG dryout increased from 50 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This provides additional time, if needed, to perform a manual start of the TDAFW pump as part of the Phase 1 core cooling strategy.
- 3) The time to depletion of the water supply from the condensate storage tank increased from 7.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 8.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This provides additional time to setup and engage Phase 2 BDB equipment as part of the long-term core cooling strategy.
The finalized analysis also confirmed the statement that the site pond was capable of providing core cooling supply for greater than 20 days to each unit.
This response closes Open Item No. 2 for Millstone Unit 2.
Serial No. 12-161C Docket Nos. 50-336/423 Order EA-12-049 Attachment, Page 2 of 2 Millstone Unit 3:
Open Item No. 3 - Preliminaryanalyses have been performed to determine the time to steam generator overfill without operator action to reduce AFW flow, time to steam generator dryout without AFW flow, and time to depletion of the useable volume of the DWST. The final durations will be provided when the analyses are completed.
The analysis for secondary side inventories and heat removal has been finalized. Slight changes were observed from the preliminary values reported in the OIP. These changes are as follows:
- 1) The time to steam generator (SG) overfill decreased from 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
As stated in the OIP, operators would be assigned within the first 15 minutes of the event to control flow in order to maintain proper SG level. AFW flow rate can be controlled by locally throttling the AFW header isolation valves. Operators could access the area in less than 5 minutes to begin to control AFW flow in order to maintain SG levels. Therefore, the basis for acceptability stated in the OIP remains valid for the reduced SG overfill time of 1.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- 2) The time for SG dryout increased from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 1.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This provides additional time, if needed, to perform a manual start of the turbine driven auxiliary feedwater (TDAFW) pump as part of the Phase 1 core cooling strategy.
- 3) The time to depletion of the water supply from the demineralized water storage tank (DWST) increased from 20.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> to 22.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. This provides additional time to setup and engage Phase 2 BDB equipment as part of the long-term core cooling strategy.
The finalized analysis also confirmed the statement that the site pond was capable of providing core cooling supply for greater than 20 days to each unit.
This response closes Open Item No. 3 for Millstone Unit 3.