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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 ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24032A1112024-02-0101 February 2024 Owners Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML23214A1942023-09-0505 September 2023 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information - 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 ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML22263A2852022-05-23023 May 2022 Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65 ML22119A1722022-04-13013 April 2022 Post-Accident Monitoring (PAM) Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage 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 ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments 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 ML20246G7062020-08-24024 August 2020 Enclosure 4: Attachment 1 - PWROG-18005-NP, Revision 2, Determination of Unirradiated Rt and Upper-Shelf Values of the North Anna Units 1 and 2 Reactor Vessel Materials 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 ML20149K6712020-05-31031 May 2020 PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis ML20140A2392020-05-18018 May 2020 ASME Section XI Inservicee Inspection Program Proposed Inservice Inspection Alternative N1-15-NDE-002 ML20246G7012020-03-31031 March 2020 Enclosure 4: Attachment 3 - WCAP-18364-NP, Rev. 1, North Anna Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal (SLR) ML20090B3972020-03-26026 March 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20246G7072020-01-31031 January 2020 Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19106A3562019-04-23023 April 2019 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage 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 ML20246G7092018-10-31031 October 2018 Enclosure 4: Attachment 2 - WCAP-18353-NP, Rev. 0, Reactor Internals Fluence Evaluation for a Westinghouse 3-Loop Plant with Two Units - Subsequent License Renewal ML18198A1192018-05-31031 May 2018 Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report ML17186A0842017-06-29029 June 2017 Flooding Focused Evaluation Summary ML16187A3232016-06-24024 June 2016 Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ML15238A8442015-09-25025 September 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15175A1902015-06-17017 June 2015 Owner'S Activity Report ML15057A2492015-04-20020 April 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 Relating to Recommendation 2.1 ML15058A0342015-02-23023 February 2015 Summary of Facility Changes, Tests and Experiments ML14133A0112014-05-0707 May 2014 March 12, 2012 Information Request Phase 2 Staffing Assessment Report ML14080A0022014-03-31031 March 2014 PNNL-22553, Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station. ML14092A4162014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites)For Recommendation 2.1 ML14084A3272014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14084A2122014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14283A0462014-02-28028 February 2014 MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles (EPRI 3002002441), Attachment 1 2024-06-10
[Table view] Category:Miscellaneous
MONTHYEARML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24032A1112024-02-0101 February 2024 Owners Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval 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 ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments 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 ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML17186A0842017-06-29029 June 2017 Flooding Focused Evaluation Summary ML16187A3232016-06-24024 June 2016 Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ML15238A8442015-09-25025 September 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15175A1902015-06-17017 June 2015 Owner'S Activity Report ML15057A2492015-04-20020 April 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 Relating to Recommendation 2.1 ML15058A0342015-02-23023 February 2015 Summary of Facility Changes, Tests and Experiments ML14084A3272014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14084A2122014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14024A6022014-01-10010 January 2014 Post Accident Monitoring (PAM) Report ML14015A3142014-01-0808 January 2014 Submittal of Owner'S Activity Report Refueling Outage N1R23 (Form OAR-1) ML12160A2682012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML12060A3492012-02-16016 February 2012 Owner'S Activity Report for Refueling Outage N2R21 ML12039A1602012-01-25025 January 2012 Steam Generator Tube Inspection Report ML12039A1612012-01-25025 January 2012 Steam Generator Tube Inspection Report ML12005A0112011-12-0909 December 2011 Independent Spent Fuel Storage Installation Response to Earthquake ML1103107402011-01-25025 January 2011 Owner'S Activity Report ML1019304172010-05-0606 May 2010 Tritium Database Report ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913206392009-05-12012 May 2009 Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025 ML0912504812009-05-0404 May 2009 30-Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0901304802009-01-0505 January 2009 Owner'S Activity Report for Refueling Outage ML0812702032008-04-25025 April 2008 Summary of Facility Changes, Tests and Experiments ML0807903432008-03-18018 March 2008 Response to Request for Additional Information Steam Generator Tube Inspection Report ML0802800722008-01-0808 January 2008 Update on North Anna Zirlo Characterization and LOCA Embrittlement Testing ML0732002342007-11-15015 November 2007 Steam Generator Tube Inspection Report ML0728205762007-10-0909 October 2007 Steam Generator Tube Inspection Report ML0719704722007-07-13013 July 2007 Owner'S Activity Reports, for Refueling Outage (N2R18) ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0609404202006-03-27027 March 2006 Summary of Facility Changes, Tests and Experiments ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0602600412006-01-25025 January 2006 Virginia Electric and Power Company North Anna Power Station Unit 2 - Owner'S Activity Reports ML0523501142005-08-22022 August 2005 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0514603252005-05-25025 May 2005 .2 & 3, North Anna Power Station Units 1 & 2, Surry Power Station Units 1 & 2 - Nuclear Liability Insurance Endorsement ML0505403042005-02-22022 February 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report Correction of Information ML0505300392005-02-21021 February 2005 Fitness-for-duty Program Semi-Annual Performance Data Report ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement 2024-02-22
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North Anna Independent Spent Fuel Storage Installation Response to Earthquake
Background:
The North Anna Independent Spent Fuel Storage Installation (ISFSI) uses two spent fuel storage systems manufactured by Transnuclear (TN).
- 1) Twenty seven vertical TN-32 metal casks under a 10 CFR Part 72 site specific license.
This system has a bolted closure lid with a pressure monitoring/alarm system, and stands freely on the ISFSI concrete pad. The design/licensing basis for the vertical TN-32 is controlled primarily by the North Anna ISFSI FSAR and NRC license (SNM-2507) and NRC certificate (1021). The FSAR defines the design acceleration values of 0.18g horizontal and 0.12g vertical, and sliding was not predicted to occur at these values.
- 2) Twenty six TN NUHOMS HD-32PTH horizontal storage modules (13 loaded) under a 10 CFR Part 72 general license. This system uses a welded-sealed canister and rests on horizontal rails inside the horizontal storage module. The design/licensing basis for the TN NUHOMS HD is controlled primarily by the separate TN-NUHOMS FSAR and NRC certificate (1030), as supplemented by additional site-specific evaluations that were performed by North Anna under 10 CFR 72.212. NUHOMS-HD components are designed to acceleration values of 0.3g horizontal and 0.2g vertical.
Event:
The North Anna ISFSI suffered minor damage from the earthquake:
- 1) Twenty five of the twenty seven TN-32 casks slid up to 4.5 inches on the concrete pad during the quake. Six cask sets (12 casks) were closer than the 16 foot separation distance specified in the FSAR. There was no damage to the pressure monitors in each cask and no pressure monitoring system alarms during or after the earthquake. There were no crack indications observed in the concrete pad or casks.
- 2) For the TN-NUHOMS modules, some slight damage was identified around the outlet vents and some surface cracking indications were noted. Additionally, some modules showed gaps between them of approximately 1.5" versus the required 1.0" maximum gap.
Preliminary Determination of Safety Significance:
The staff believes there is no immediate safety issue. The cask designs are robust and consider severe natural phenomena. As expected, the casks withstood the earthquake at North Anna. The spent fuel continues to be surrounded by several tons of steel and concrete, and sealed in an inert helium environment. Damage to concrete components appear to be cosmetic, and does not impact structural integrity or radiation shielding capability. Additionally, the fuel assemblies are designed to withstand a maximum of 4 g axial load and 6 g lateral load.
Inlet and outlet vents were inspected and no exterior blockage was found. Radiation surveys indicate no changes to cask surface dose rates. Thermal performance measurements for all loaded casks found no abnormal temperature differences.
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Additionally, for the TN-32 casks, the requirement specifying a minimum distance of 16 feet between casks with a heat load greater than 27.1 kW was conservatively established so that the casks do not influence each other thermally and to allow for emplacement on the pad by the cask transporter. Currently, the two casks with the least separation (15 feet, 3.5 inches) are casks that had decay heats of 15.4 kW and 18.0 kW when loaded in 2000 and 2001, both well below the 27.1 kW requirement.
Licensee Response:
The licensee is following RG 1.166, "Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post-Earthquake Actions," as a guide to perform their post-event assessment and has completed walkdowns of the ISFSIs.
The licensee reviewed this event for reportability under 10 CFR 72.75 (significant reduction in effectiveness of any spent fuel storage cask confinement system) and determined that the TN-32 displacement and NUHOMS-HD damage described above was not reportable.
The licensee contacted TN and provided them with all available pictures, data, and inspection results. TN requested that the licensee perform a more detailed inspection and evaluation of the current condition and sent a team to support this inspection.
NRC Response:
Item 10 of the AIT charter requires the AIT to "Assess the extent of any impact or damage to the Independent Spent Fuel Storage Installation from the seismic event." NMSS and Region II will continue to support the AIT and evaluate information related to the ISFSI to determine whether longer-term licensing or inspection actions are warranted for North Anna or generically.
On September 1, 2011, AIT completed a walk-down of the ISFSI Pads and has concluded that there are no indications of immediate safety issues associated with the movement of the vertical and horizontal ISFSI modules. Radiological conditions are normal and monitoring systems are functional. Damage as a result of the earthquake did not seem detrimental for the integrity of the casks.
On September 7, 2011, NMSS and Region II participated in technical discussions with the licensee to discuss near and long term ISFSI plans. NMSS will determine appropriate vehicle to ensure that the licensee takes appropriate action.
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