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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 ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification 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 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) 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) 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 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 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) 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 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:Report
MONTHYEARML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 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 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 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 ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20309A5052020-11-0303 November 2020 Inspector Notes Cover Sheet ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ZS-2015-0156, Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask2015-10-26026 October 2015 Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. 2024-06-10
[Table view] Category:Technical
MONTHYEARML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24093A1022024-04-0101 April 2024 Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification 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 ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML18247A2752018-06-18018 June 2018 Technical Requirements Manual NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) 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 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 ML14087A0992013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13074A7962013-02-28028 February 2013 Small Break LOCA Sensitivity Study Summary Report, ANP-3205NP, Rev 0 ML12172A0602012-06-21021 June 2012 Closeout of Bulletin 2011-01, Mitigating Strategies ML1023904192010-08-31031 August 2010 DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. ML1014600622010-05-25025 May 2010 Second Report Regarding Lead Test Assembly ML0920902162009-06-30030 June 2009 WCAP-16896-NP, Rev 2, Millstone Unit 2 RCS Surge, Spray, Shutdown Cooling, Safety Injection, Charging Inlet, and Letdown/Drain Nozzles Structural Weld Overlay Qualification. ML0911701502009-03-31031 March 2009 Enclosure 1- Part 1 of 2 - Report FAI/09-22, Test Results for the Millstone-3 Gas-Water Transport Tests ML0911701372009-03-13013 March 2009 Enclosure 1 - Part 2 of 2 - Calculation FAI/09-44R, Revision 0, Post-Test Analysis of the Fai Millstone 3 RWST 1/4 Scale Gas Entrainment Test ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0811400832008-04-17017 April 2008 WCAP-16896-NP, Rev. 1, Millstone, Unit 2, RCS Surge, Spray, Shutdown Cooling, Safety Injection, Charging Inlet, and Letdown/Drain Nozzles Structural Weld Overlay Qualification. ML0809802292008-04-0404 April 2008 Stations - Request for Approval of Appendix C of Fleet Report DOM-NAF-2 Qualification of the Westinghouse WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code ML0814900882008-01-31031 January 2008 Enclosure 4 - LTR-CDME-08-11 NP-Attachment, Interim Alternative Repair Criterion for Cracks in the Lower Region of the Tubesheet Expansion Zone ML0727504062007-06-30030 June 2007 Internal Report, IR-2007-277, EPRI Review of Millstone Unit 2 Dissimilar Metal Weld Walkdown Information. ML0731706782007-05-19019 May 2007 SCS-00684, Rev. Draft-2, Design Report, ASME Bp&V Section III, Class 3, SS-45S8-18622-NSR Ball Valve, SS-45XS8-18623-NSR Ball Valve, Enclosure 2 ML0709603562007-03-31031 March 2007 WCAP-16734-NP, Revision 0, Millstone, Unit 3 Pressurizer, Relief, and Surge Nozzles Structural Weld Overlay Qualification. ML0706601292007-01-31031 January 2007 LTR-PAFM-07-12, Technical Basis for Relaxation Request from NRC Order EA-03-009 for Millstone Unit 3. ML0628502212006-10-0202 October 2006 Submittal of Third Reactor Vessel Surveillance Capsule Report, WCAP-16629-NP, Rev 0 ML0518900442005-06-29029 June 2005 10 CFR 50.59 and Commitment Change Report for 2004 2024-06-10
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171 Dominion Nuclear Connecticut, Inc. i .Do mnno Rope Ferry Road, Waterford, CT 06385 DominioU Web Address: www.dom.com OCT 17 2013 U. S. Nuclear Regulatory Commission Serial No.13-552 Attention:
Document Control Desk MPS Lic/GJC RD Washington, DC 20555 Docket No. 50-245 License No. DPR-21 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNITS 1 AND 2 10 CFR 71.95 REPORT 120B CASK CERTIFICATE OF COMPLIANCE NONCOMPLIANCE DUE TO AN INADEQUATE VENDOR LEAK TEST PROCEDURE Dominion Nuclear Connecticut Inc. (DNC) is submitting this report pursuant to 10 CFR 71.95(a)(3) regarding instances in which the conditions of approval in the Certificate of Compliance
- 9168 for the 8-120B cask were not observed when making shipments from Millstone Power Station Unit Nos. 1 and 2 (MPS1 and MPS2). This report is based on a 10 CFR 71.95 report dated August 14, 2013 by the certificate holder, EnergySolutions, to the NRC which is enclosed.The enclosed notification is applicable to use of the 8-120B cask by MPS1 and MPS2. DNC records show that MPS1 and MPS2 made a total of 4 Type B shipments using the 8-120B cask since 2001 which are listed in the attachment.
During 2 of those shipments the vendor leak test procedure required the vent port seal test be performed for 20 minutes rather than 60 minutes as required by the cask's Safety Analysis Report (SAR).EnergySolutions has revised the procedure to include a 60 minute test of the vent port seal.If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.Sincerely, Step nVic Sc ce Millo Site Vice President
-Millstone~~S'sOI Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3)
Report Page 2 of 2
Enclosure:
EnergySolutions 10 CFR 71.95 Report on the 8-120B Cask dated August 14, 2013.
Attachment:
List of MPS1 and MPS2 Type B shipments using the 8-120B cask since 2001.Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 M. D. Lombard Director -Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 NRC Senior Resident Inspector Millstone Power Station Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3)
Report ENCLOSURE EnergySolutions Letter CD13-0232, Dated: August 14, 2013, To: M. D. Lombard Director -Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards, USNRC, From: D. B. Shrum, Senior Vice President, Regulatory Affairs, EnergySolutions, Subiect: 10 CFR 71.95 Report on the 8-120B Cask.MILLSTONE POWER STATION UNIT 1 AND 2 DOMINION NUCLEAR CONNECTICUT, INC.
ENERGYSOLUTIONS August 14, 2013 CD1 3-0232 Mark Lombard, Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 ATTN: Document Control Desk
Subject:
10 CFR 71.95 Report on the 8-120B Cask
Dear Mr. Lombard:
EnergySolutions hereby submits the attached report providing the information required by 10 CFR 71.95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance
- 9168) may not have been observed in making certain shipments.
The circumstances described in this report are applicable to all licensed users of the cask.If you have any questions regarding this submittal, please contact me at 801-649-2109.
Sincerelv Daniel B. Shrum Senior Vice President, Regulatory Affairs EnergySolutions
Attachment:
Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time cc: Michele Sampson, Chief Thermal and Containment Branch Pierre M. Saverot Licensing Branch 423 West 300 South, Suite 200 -Salt Lake City; UT 84101 www.energysolutions.com EN ERGYSOLUTIONS Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time August 14, 2013 1) Abstract This report provides the information required by 10 CFR 71.95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance
- 9168) may not have been observed in making certain shipments.
The circumstances described in this report-are applicable to all licensed users of the cask.EnergySolutions' air pressure drop test procedure TR-TP-002 describes a 20-minute hold time for the pre-shipment leak test of the cask vent port. The 8-12013 Safety Analysis Report (SAR), however, specifies a hold time of 60 minutes for the leak test of the vent port;therefore the conditions of approval in the Certificate of Compliance may not necessarily have been observed in making shipments.
TR-TP-002 is the basis for leak tests on all EnergySolutions shipments, as well as the suggested procedure content for most shipments by our authorized users.t The 8-120B CoC requires the package to be prepared for shipment and operated in accordance with Chapter 7 of the SAR, and tested and maintained in accordance with Chapter 8 of the SAR. TR-TP-002 captures the applicable SAR requirements and provides further detail for the development of a shipper's operating procedure.
Recently, an 8-120B cask user identified the hold time discrepancy between TR-TP-002 and the SAR (i.e., 20 versus 60 minutes).
Based on a review of past revisions of CoCs, SARs, and cask handling procedures, it appears that this discrepancy has existed for approximately 12 years, spanning approximately 88 cask users and approximately 1,400 shipments.
Upon notification and after confirmation of the discrepancy, EnergySolutions revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test. This change to TR-TP-002 was communicated to all EnergySolutions registered cask users on June 13, 2013. The SAR requires pre-shipment leak testing of the vent port only when the port has been opened since the preceding vent port leak test. EnergySolutions issued a notice to registered cask users on July 2, 2013 to clarify this issue. Operation of a package vent port is infrequent.
However some vent ports may have been opened during the past 12 years; and therefore the pre-shipment leak testing would have been required.The licensing basis for the pre-shipment leak tests for all three of the 8-120B lid containment seals is a pressure drop calculation for the largest of the three seals (the primary lid seal).The required hold time is therefore conservative for the two seals with smaller test volumes.Because of the small size of the vent port seal test volume, EnergySolutions has determined that the 20-minute hold time meets the same criterion by which the 60-minute hold time was derived for the larger primary lid seal. In fact, in the case of the vent port leak test, the 20-minute hold time provides substantial margin for detecting any leakage from the vent port. It therefore follows that there is no safety significance associated with the condition.
Since registered users of the 8-120B package are licensees, these licensees would normally prepare and issue an approved procedure to control their pre-shipment activities.
EN ERGYSOLUTIOZVS Furthermore, there is no continuing safety concern as new lids are required to be used after August 31, 2013 with different testing procedures.
Due to the long timeframe over which this condition has existed, the large number of 8-120B cask users, the many shipments that have occurred, the difficulty of determining which if any shipments may have been out of compliance, and the finding of no significant safety impact, EnergySolutions hereby submits this notification to summarize the issue as it applies to all 8-120B users. Because of the imminent rollout of new lids and related test procedures, no further corrective actions by certificate users are necessary to address this leak test procedure.
- 2) Narrative Description of the Event a) Status of Components All 8-120B components are operating normally.b) Dates of Occurrences February 2001 to present.c) Cause of Error Discrepancy between EnergySohltions air pressure drop test procedure TR-TP-002 and Chapter 8 of the 8-120B SAR.d) Failure Mode, Mechanism, and Effects Not applicable; no 8-120B packaging components have failed.e) Systems or Secondary Functions Affected Not applicable.
f) Method of Discovery of the Error The condition was identified by an 8-120B cask user.3) Assessment of Safety Consequences There is nio safety consequence of performing the pre-shipment leak test of the 8-120B cask vent port using a 20-minute hold time versus the 60-minute hold time that is required by the 8-120B CoC. The required hold time varies in proportion to the test volume if the test pressure and acceptance criterion remain unchanged.
Larger test volumes require longer hold times. The test volume includes the free volume of the space to be tested and the volume of the test manifold.
For the original subject 8-120B lids, Section 4.4 of the July 2012 SAR Addendum shows the calculation basis for a 60-minute hold time. Only one calculation was presented for the large primary lid containment seal. Since the other seals have smaller test volumes, a 60-minute hold time was conservatively specified for all seals, including the vent port.
ENERGUCOLUTIONS The SAR test volume for the primary containment seal was 103.2 cc. For the pre-shipment vent port leak test, there is no safety impact from a 20-minute hold time provided that the test volume is less than or equal to the 20/60 times the primary containment seal test chamber volume, or (20/60)* 103.2.= 34.4 cc. The vent port test volume is equal to the combined volume of the test manifold (10 cc) plus a very small residual volume inside the vent port, which is less than 34.4 cc. Therefore, pre-shipment leak tests of the vent port performed using a 20-minute hold time are adequate to demonstrate compliance with maximum leak rate acceptance criteria, and there is no safety consequence from testing vent ports for 20 minutes instead of 60 minutes.4) Planned Corrective Actions As noted above, upon notification and after confirmation of the discrepancy, EnergySolutions revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test and notified registered cask users of the change.Beginning September 1, 2013, the 8-120B fleet will ship with a new lid design, authorized in the latest revision of the CoC.2 Thereafter, the 8-120B cask may no longer be used with the old seals that were authorized in Revision No. 17 of the 8-120B CoC. Shipments with the new lids will be required to use the seals authorized in Revision 19 of the CoC. The EnergySolutions air pressure drop test procedure TR-TP-002 is being revised and reissued based on the requirements of Revision 19 of the 8-120B CoC. These revisions are reviewed and approved by the EnergySolutions Cask Licensing Manager to assure that they are compliant with the requirements of the CoC.EnergySolutions also has initiated a lifecycle procedure for managing Type B casks to assure that CoC requirements flow through the design, fabrication, and operational phases. This is a new procedure that also would identify existing inconsistencies and prevent future inconsistencies between the SAR and operating procedures.
The procedure will be effective August 19, 2013.The error in incorporating the revised 60-minute vent port leak rate criteria into TR-TP-002 raises a question as to whether there are other similar errors involving the flow-down of requirements into operating procedures.
Accordingly, EnergySolutions plans to conduct a review of the 8-120B and other EnergySolutions Type B packagings to verify that CoC and SAR requirements have been accurately translated into the prescribed operating procedures.
If any such discrepancies are found, EnergySolutions will expand the scope of these reviews as necessary.
- 5) Previous Similar Events Involving the 8-120B No previous similar events have been identified.
' No shipments have been made using the new lids to date.
EN ERGISOLUTIONS
- 6) Contact for Additional Information Dan Shrum EnergySolutions Senior Vice President, Regulatory Affairs (801) 649-2109 7) Extent of Exposure of Individuals to Radiation or Radioactive Materials None.
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3)
Report ATTACHMENT LIST of MPS1 and MPS2 TYPE B SHIPMENTS SINCE 2001 USING the 8-120B CASK MILLSTONE POWER STATION UNIT I AND 2 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3)
Report Attachment List of MPSI and MPS2 Type B Shipments Since 2001 Using the 8-120B Cask Shipments Which Did Not Require the Vent Port Test RMRS #03-012-1 03-017-1 Cask Used 8-120B 8-120B Destination Chem-Nuclear, Barnwell, SC Chem-Nuclear, Barnwell, SC Date of Shipment 08/04/2003 10/01/2003 Unit 1 1 Shipments Which Required the Vent Port Test RMRS #05-098-1 06-029 Cask Used 8-120B 8-120B Destination Chem-Nuclear, Barnwell, SC Chem-Nuclear, Barnwell, SC Date of Shipment 06/23/2005 03/23/2006 Unit 1 2