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| | issue date = 04/23/2019 | | | issue date = 04/23/2019 |
| | title = Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage | | | title = Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage |
| | author name = Hall J R | | | author name = Hall J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Stoddard D G | | | addressee name = Stoddard D |
| | addressee affiliation = Virginia Electric & Power Co (VEPCO) | | | addressee affiliation = Virginia Electric & Power Co (VEPCO) |
| | docket = 05000338, 05000339 | | | docket = 05000338, 05000339 |
| | license number = NPF-004, NPF-007 | | | license number = NPF-004, NPF-007 |
| | contact person = Hall J R NRR/DORL 415-4032 | | | contact person = Hall J NRR/DORL 415-4032 |
| | case reference number = EPID L-2018-LRO-0033 | | | case reference number = EPID L-2018-LRO-0033 |
| | document type = Letter, Report, Technical | | | document type = Letter, Report, Technical |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd. Glen Allen, VA 23060-6711 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd. |
| | Glen Allen, VA 23060-6711 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NORTH ANNA POWER STATION, UNIT NO. 1 -REVIEW OF STEAM GENERA TOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033) | | NORTH ANNA POWER STATION, UNIT NO. 1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033) |
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| ==Dear Mr. Stoddard:== | | ==Dear Mr. Stoddard:== |
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| By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18255A061 | | By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018. |
| ), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018. The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033. | | The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033. The enclosure documents the NRC staff's review of the submittal. |
| The enclosure documents the NRC staff's review of the submittal. | | Sincerely, JC.~~,~~ |
| Docket No. 50-338 | | Plant Licensing Branch 11-1 Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-338 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Review of Steam Generator Tube Inspection Report cc: Listserv Sincerely, J C.~~,~~ Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338 | | Review of Steam Generator Tube Inspection Report cc: Listserv |
| * By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML 18255A061
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| ), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26.
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| * North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped.
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| The U-bend regions of the tubes in rows one through eight were stress-relieved after bending. The licensee provided the scope , extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings.
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| Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure
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| ==SUBJECT:==
| | REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338 |
| NORTH ANNA POWER STATION, UNIT NO. 1 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033) | | * By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26. |
| DATED APRIL 23, 2019 DISTRIBUTION:
| | * North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped. The U-bend regions of the tubes in rows one through eight were stress-relieved after bending. |
| PUBLIC PM Reading File RidsNrrLAKGoldstein Resource RidsNrrDorl Resource RidsRgn2MailCenter Resource RidsNrrPMNorthAnna Resource RidsNrrDmlrMccb Resource RidsNrrDmlrMphb Resource PKlein, NRR AJohnson, NRR AHuynh, NRR ADAMS Accession No. ML 19106A356 OFFICE DORL/LPL2-1
| | The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings. |
| /PM DORL/LPL2-1/LA NAME JRHall KGoldstein (JBurkhardt for) DATE 04/17/19 04/17/19 OFFICE DMLR/MPHB/BG* | | Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. |
| DORL/LPL2-1/BC NAME SBloom MMarkley (SWilliams for) DATE 03/06/19 04/18/19 OFFICIAL RECORD COPY *via email DORL/LPL2-1/LAit KZeleznock 04/17/19 DORL/LPL2-1/PM JRHall 04/23/19}} | | Enclosure |
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| | ML19106A356 *via email OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/LA DORL/LPL2-1/LAit NAME JRHall KGoldstein (JBurkhardt for) KZeleznock DATE 04/17/19 04/17/19 04/17/19 OFFICE DMLR/MPHB/BG* DORL/LPL2-1/BC DORL/LPL2-1/PM NAME SBloom MMarkley (SWilliams for) JRHall DATE 03/06/19 04/18/19 04/23/19}} |
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Category:Letter
MONTHYEARIR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 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 ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York 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 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 ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe 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 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 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 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 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 ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report 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 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 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection 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 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: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 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 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 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 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 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 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 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 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 ML13338A4482014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14006A1712014-01-23023 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for North Anna Power Station, Units 1 and 2, TAC Nos.: MF0998 and MF0999 ML13179A0152013-05-31031 May 2013 Units I and 2, Qualification of the ABB-NV and Wlop CHF Correlations in the Dominion VIPRE-D Computer Code ML12200A2162012-06-30030 June 2012 PNNL-21546 Evaluation of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station ML12143A1352012-05-0808 May 2012 NDE Results for Steam Generator Hot Leg Nozzle Full Structural Weld Overlays. Part 1 of 2 ML12143A1362012-05-0808 May 2012 NDE Results for Steam Generator Hot Leg Nozzle Full Structural Weld Overlays. Part 2 of 2 ML11290A1702011-10-12012 October 2011 Root Cause Evaluation Re Dual Unit Trip Following August 23, 2011 Earthquake ML1023904192010-08-31031 August 2010 DOM-NAF-2, Rev. 0.2-A, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code. ML11187A3242010-06-30030 June 2010 Justification for Extension of Temper Bead Limit to 1000 Square Inches for WOL of P1 and P3 Materials ML1016203012010-06-30030 June 2010 Radial-Hydride-Induced Embrittlement of High-Burnup Zirlo Cladding Exposed to Simulated Cask Drying Conditions ML1026002162010-05-13013 May 2010 Engineering Transmittal, ET-CEP-10-0006, Revision 0, Evaluation of Aluminum Conduit Seal Penetration Fire Tests, Dated May 13, 2010, North Anna and Surry Power Stations Units 1 and 2 (Redacted Version), Enclosure 2 ML0930701642009-10-15015 October 2009 Technical Report No. EE-0116, Revision 5 ML0823304742008-08-13013 August 2008 Summary of Two Additional Facility Changes, Tests and Experiments, Not Included in Previous 03/28/2008 Submittal ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 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 ML0806505632008-02-29029 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0727404002007-11-15015 November 2007 Corrective Actions for Generic Letter 2004-02 ML0716905022007-06-15015 June 2007 Order - EA 03-009 Sixty Day Report, Reactor Pressure Vessel (RPV) Head Inspection Results 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 ML0611005122006-04-20020 April 2006 Virginia Electric and Power Company North Anna and Surry Power Stations 30-Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.26 ML0331700242003-10-13013 October 2003 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Relief Request CMP-020 2024-06-10
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NO. 1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033)
Dear Mr. Stoddard:
By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018.
The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033. The enclosure documents the NRC staff's review of the submittal.
Sincerely, JC.~~,~~
Plant Licensing Branch 11-1 Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-338
Enclosure:
Review of Steam Generator Tube Inspection Report cc: Listserv
REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338
- By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26.
- North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped. The U-bend regions of the tubes in rows one through eight were stress-relieved after bending.
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings.
Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
ML19106A356 *via email OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/LA DORL/LPL2-1/LAit NAME JRHall KGoldstein (JBurkhardt for) KZeleznock DATE 04/17/19 04/17/19 04/17/19 OFFICE DMLR/MPHB/BG* DORL/LPL2-1/BC DORL/LPL2-1/PM NAME SBloom MMarkley (SWilliams for) JRHall DATE 03/06/19 04/18/19 04/23/19