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MONTHYEARML0913206392009-05-12012 May 2009 Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025 Project stage: Request ML0916204232009-06-11011 June 2009 Unit 2, N1-13-NDE-024 and N2-13-NDE-025: Acceptance of Requested Licensing Action Relief Request-Reactor Coolant Pressure Boundary Visual Inspection Project stage: Acceptance Review ML0923706462009-08-24024 August 2009 Response to Request for Additional Information Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-nde-024 and N2-I3-NDE-025 Project stage: Response to RAI ML0927902102009-10-0909 October 2009 Third 10-Year Interval Inservice Inspection Program, Reactor Coolant Pressure Boundary Visual Inspections - N1-I3-NDE-024 and N2-I3-NDE-025 Project stage: Other 2009-05-12
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Category:Letter
MONTHYEARML24302A2402024-10-28028 October 2024 CFR 21 Report 1-BY-BC-1-LV Battery Charger IR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24302A2342024-10-23023 October 2024 Request for Project Number Related to Dominion Energy Services New Nuclear Program at North Anna Power Station ML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report 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 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 2024-09-24
[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 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 Owners 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 Owners 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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10 CFR 50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 12, 2009 U.S. Nuclear Regulatory Commission Serial No.09-253 Attention: Document Control Desk NL&OS/ETS RO Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2 REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE - N1-13-NDE-024 AND N2-13-NDE-025 Pursuant to 10 CFR 50.55a(a)(3)(i), Dominion requests approval of an alternative to the inspection requirements of footnote 1 included in 10 CFR50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Visual Inspections, for North Anna Units 1 and 2. The requested alternative will permit the inspections performed during the Unit 1 fall 2007 and Unit 2 fall 2008 refueling outages on the bottom mounted instrument tubes (8MI) to be used as the initial reactor coolant pressure boundary visual inspection in place of the footnote requirement for the initial inspection to be performed at the next refueling outage after January 1,2009. Alternatives N1-13-NDE-024 and N2-13-NDE-025 are included in the attachment to this letter as well as the basis for the alternative.
The 8MI inspections performed during the fall 2007 and 2008 refueling outages for North Anna Units 1 and 2, respectively, conformed to the requirements of Code Case N-722 and met the requirements of 10 CFR50.55a(g)(6)(ii)(E). Therefore, Dominion considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1,2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E).
If you should have any questions regarding this submittal, please contact Mr. Thomas Shaub at (804) 273-2763.
Sincerely,
~~ci Leslie Hartz Vice President - Nuclear Support Services
Attachment:
Proposed Alternatives - N1-13-NDE-024 and N2-13-NDE-025 Commitments made in this letter: None
Serial No.09-253 Docket Nos. 50-338/339 Alternative for BMI Baseline Inspections Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Ms. D. N. Wright NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 H4A 11555 Rockville Pike Rockville, Maryland 20852 Mr. J. F. Stang, Jr.
NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852
Serial No.09-253 Docket Nos. 50-338/339 ATTACHMENT REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE N1-13-NDE-024 and N2-13-NDE-025 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative BMI Visual Examinations Requirement Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
- Alternative Provides Acceptable Level of Quality or Safety --
1.0 ASME Code Components Affected
Code components associated with this request are Class 1 Reactor Pressure Vessel (RPV) bottom-mounted instrument penetrations (BMI) having pressure retaining partial or full penetration welds in components fabricated with Alloy 600/82/182 material.
1.1 Category and System Details:
Code Class: Class 1 System: Reactor Pressure Vessel Examination Category: B-P Item Number: B15.80 1.2 Component Descriptions:
Reactor Vessel - RPV bottom-mounted instrument penetrations 2.0 Applicable Code Edition And Addenda North Anna Power Station Units 1 and 2 are completing their third 10-year lSI Intervals. Unit 1's third interval began on May 1, 1999 and ends on April 30, 2009 and Unit 2's third interval began on December 14, 2001 and ends on December 13, 2010. The ASME Boiler and Pressure Vessel Code (ASME Code) of record for the applicable interval is the 1989 Edition for Unit 1 and the 1995 Edition, 1996 Addenda for Unit 2.
3.0 Applicable Code Requirements 10 CFR 50.55a(g)(6)(ii)(E), Reactor coolant pressure boundary visual inspections, was recently incorporated into the 10 CFR 50.55a. The new regulations augmented the inservice inspection requirements (effective date October 10,2008).
Specifically, 10 CFR 50.55a(g)(6)(ii)(E) requires that "Alllicensees of pressurized water reactors shall augment their inservice inspection program by implementing ASME Code Case N-722 subject to the conditions specified in 10 CFR 50.55a(g)(6)(ii)(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement."
Page 1 of 4
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement In addition, footnote one to 10 CFR 50.55a(g)(6)(ii)(E) states in part: "For inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009."
4.0 Reason For Request North Anna Power Station (NAPS) Unit 1 and Unit 2 completed bare metal visual examination of RPV bottom-mounted instrument penetrations prior to the "initial inspection" indicated by 10 CFR 50.55a(g)(6)(ii)(E), which became effective October 10, 2008. NAPS Unit 1 inspections were performed during the fall 2007 refueling outage, and NAPS Unit 2 inspections were performed during the fall 2008 refueling outage. These bare metal visual inspections met the intent of ASME Code Case N-722.
Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Material," establishes additional requirements to the examination requirements of Table IWB-2500-1 for pressurized water reactor plants having partial or full penetration welds in Class 1 components fabricated with Alloy 600/82/182 material.
For Reactor Vessel Item Number B15.80, RPV bottom-mounted instrument penetrations, all penetrations require Visual Examination (VE) to the requirements of IWB-3522, every other refueling outage.
ASME Code Case N-722 includes specific requirements for the VE and the qualification of personnel performing the VE:
(3) The Visual Examination (VE) performed on Alloy 600/82/182 components for evidence of pressure boundary leakage and corrosion on adjacent ferritic steel components shall consist of the following:
(a) A direct VE of the bare-metal surface performed with the insulation removed. Alternatively, the VE may be performed with insulation in place using remote visual inspection equipment that provides resolution of the component metal surface equivalent to a bare-metal direct VE.
(b) The VE may be performed when the system or component is depressurized.
(c) The direct VE shall be performed at a distance not greater than 4 ft (1.2 m) from the component and with a demonstrated illumination level sufficient to allow resolution of lower case characters having a height of not greater than 0.105 in (2.7 mm).
(4) Personnel performing the VE shall be qualified as VT-2 visual examiners and shall have completed a minimum of four (4) hours of additional training in detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.
Page 2 of 4
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement The bottom-mounted RPV instrument penetrations examinations during the fall 2007 and fall 2008 refueling outages were performed to the enhanced Visual Examination (VE) requirements and the personnel training and qualification requirements as described in Enclosure 1, "Examiner Qualification and Resolutions Requirements."
5.0 Proposed Alternatives And Basis For Use Virginia Electric and Power Company (Dominion) considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1, 2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E). Therefore, the inspection performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 can be considered the initial inspections to meet the 10 CFR 50.55a(g)(6)(ii)(E) footnote requirements for the performance of the initial inspection.
In accordance with ASME Code Case N-722, the bottom-mounted RPV instrument penetration examinations are required to be performed at least every other refueling outage. Therefore, the next examinations of Item No. B15.80 components (bottom-mounted RPV instrument penetration) will be performed no later than the fall 2010 refueling outage for Unit 1 and no later than the fall 2011 refueling outage for Unit 2. Dominion requests approval of this alternative pursuant to the provisions of 10 CFR 50.55a(a)(3)(i).
6.0 Duration Of Proposed Alternative The proposed alternative to the 10 CFR 50.55a(g)(6)(ii)(E) requirements is applicable for the remainder of the third 10-year inservice inspection (lSI) interval at NAPS Units 1 and 2.
7.0 Precedents None 8.0 References None 9.0 Enclosures (1) Examiner Qualification and Resolution Requirements Page 3 of 4
10 CFR 50.55a Request Number N1*13*NDE*024/N2*13*NDE*025 Alternative BMI Visual Examinations Requirement ENCLOSURE 1 Examiner Qualifications and Resolution Requirements This enclosure documents a comparison of the bare metal visual examinations performed on the reactor pressure vessel bottom mounted instrumentation (BMI) nozzles at North Anna Power Station Units 1 & 2 performed during previous outages (N1 R19 and N2R19) with the new requirements of Code Case N-722. Two areas related to examination equivalency were required to be addressed; personnel qualifications and resolution requirements.
Personnel Qualifications The examiners that performed these examinations held current VT-2 (non-alternative) and VT-3 qualifications. In addition, each of the examiners had successfully taken the Dominion Boric Acid Corrosion Control (BACC) Inspector training. The inspection team included at least one VT examiner that has also completed the Dominion BACC Evaluator training and qualification requirements.
The examiners that performed these bare metal visual examinations met the requirements of Code Case N-722 as VT-2 qualified examiners with an additional four hours of training addressing the detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.
Based upon the additional training of the visual examiners; the bare metal visual examinations of the BMI nozzle penetrations performed during the N1 R19 and N2R19 outages are considered equivalent to the personnel qualification requirements of Code Case N-722.
Resolution Requirements The previous bare metal visual examinations were performed using a (VT-2) examination technique and required each penetration to be examined for evidence of leakage for 360 degrees around each nozzle. The bare metal visual examinations were documented in the applicable Engineering Periodic Test Procedure. These periodic test procedures specify the use of inspection equipment to be used for the inspection, which consists of a mirror, portable lights, and a visual testing examination resolution card.
Access to the BMI nozzles for the bare metal visual examination is through removable insulation panels. The bare metal visual examinations of the BMI nozzles were performed in accordance with the direct visual examination requirements of within 4 feet and sufficient illumination to resolve 0.105 inches lower case characters.
Based upon the access for the examiner to perform the bare metal visual examinations of the BMI nozzle penetrations, the equipment used to perform the examination (mirror, flashlight, 0.105 inches low case character resolution card), the previously performed bare metal visual examinations of the BMI nozzle penetration are considered equivalent to the resolution requirements of Code Case N-722.
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