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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:Safety Evaluation
MONTHYEARML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative 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 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23181A1352023-08-22022 August 2023 Issuance of Amendment Nos. 295 and 278 License Amendment Request to Remove the Refueling Water Chemical Addition Tank and Change the Containment Sump Ph Buffer ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22196A1972022-07-28028 July 2022 Request for Relief Request N2-I4-LMT-004 Inservice Inspection Limitations ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22068A0712022-03-22022 March 2022 Issuance of Amendment Nos. 292 and 275 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22019A0022022-03-0808 March 2022 Regarding Request to Utilize Code Case OMN-28 ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21323A1742021-12-22022 December 2021 Issuance of Amendment Nos. 289 and 272 to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21264A0112021-10-18018 October 2021 Safety Evaluation Report Related to the Subsequent License Renewal of North Anna Power Station, Units 1 and 2 ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20325A0952021-03-19019 March 2021 Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary) ML20364A0402021-01-15015 January 2021 Request for Relief Request N1-I4-LMT-003 Inservice Inspection Limitations ML20350B8062020-12-28028 December 2020 Request for Relief Request N1-I5-NDE-002 Inservice Inspection Alternative ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology ML20253A3292020-09-30030 September 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20252A0042020-09-23023 September 2020 Request for Relief Request Fifth 10-Year Interval ML20252A0072020-09-15015 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 ML20031E7842020-02-19019 February 2020 Request for Relief Request P-9 to Defer Performance of Comprehensive Pump Test ML19319A5832020-01-17017 January 2020 Issuance of Amendment Nos. 285 and 268 to Revise Technical Specifications Regarding Emergency Diesel Generator Maximum Voltage Limits ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19274C9982019-11-13013 November 2019 Issuance of Amendments Regarding Installation of Water Headers in Flood Protection Dike ML19238A1272019-09-12012 September 2019 Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection ML19143A3422019-05-29029 May 2019 Inservice Inspection Alternative Request N2-I4-LMT-003 ML19140A2882019-05-28028 May 2019 Inservice Inspection Alternative Requests N1-I5-CMP-001 and N2-I5-CMP-001 ML19135A3242019-05-21021 May 2019 Inservice Inspection Alternative Request N1-I4-CS-002 ML19092A4172019-04-15015 April 2019 Unit Nos.1 and 2 Inservice Inspection Alternative Requests N1-I5-NDE-001 and N2 I5 NDE 001 ML19093B2742019-04-15015 April 2019 Inservice Inspection Alternative Requests N1-I5-SPT-001 and N2 I5 Spt 001 ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes ML19039A2362019-02-14014 February 2019 Inservice Inspection Alternative N2-I4-NDE-007 ML18290A8522018-11-27027 November 2018 Issuance of Amendments 280, 263 to Revise Technical Specifications Regarding Ventilation System Surveillance Requirements in Accordance with TSTF-522 ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML18180A1972018-07-27027 July 2018 Issuance of Amendments to Revise Technical Specifications Regarding New and Spent Fuel Storage (CAC Nos. MF9712 and MF9713, EPID L-2017-LLA-0240) ML18031A2222018-02-0606 February 2018 Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2017-RNW-0010 and 000993/L-2017-LNE-0008) ML18029A1842018-02-0202 February 2018 Proposed Inservice Inspection Alternatives N1-I4-NDE-010 and N2-I4-NDE-005 (CAC Nos. MF9534 and MF9535; EPID L-2017-LLR-0029) ML18019A1952018-01-24024 January 2018 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination (CAC Nos. MF9923, MF9924, MF9925, MF9926, MF9927, and MF9928; EPID L-2017-LLR-0060) ML18005A1092018-01-10010 January 2018 Relief Request (RR) N1-I4-LMT-002, Limited Coverage Examinations for the Fourth Ten-Year Inspection Interval (CAC No. MF9689; EPID L-2017-LLR-0024) ML17332A0782017-12-12012 December 2017 ISFSI; Millstone and ISFSI; North Anna and ISFSI; Surry and ISFSI - Request for Approval of Revision 24 of the Nuclear Facility Quality Assurance Program Description Topical Report, DOM-QA-1 (CAC Nos. MF9732-MF9739; EPID L-2017-LLQ-0001) ML17332A6632017-12-0606 December 2017 Proposed Inservice Inspection Alternatives N1-I4-NDE-009 and N2-I4-NDE-004 (CAC Nos. MF9298 and MF9299; EPID L-2016-LLR-0018) ML17221A2522017-08-17017 August 2017 Proposed Alternative to Implement Code Case N-839 ML17053A2432017-07-21021 July 2017 Relief Request (RR) N1-I4-NDE-008, and N2-I4-NDE-003 Inservice Inspection Program ML17046A3162017-04-0606 April 2017 Connecticut, Virginia, Millstone, North Anna, Surry, Submission of Revision 21 of the Quality Assurance Topical Report for NRC Approval and Submission Revision 22 for Information Only (CAC Nos. MF8128 - MF8234) ML16252A4782016-10-17017 October 2016 Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0 ML16209A4132016-07-27027 July 2016 Safety Evaluation For North Anna Power Station, Units 1 And 2, Proposed License Amendment To Revise The Technical Specifications To Address The Issue Identified In Westinghouse Documents NSAL-09-5. Rev. 1 and NSAL-15-I (TAC No. MF7186 and MF7187) ML16028A4342016-03-0101 March 2016 Relief Request (RR) N1-I4-SPT-006, Inservice Inspection Program 2024-08-08
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Text
September 30, 2020 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - REVISED LICENSE RENEWAL COMMITMENT PRESSURIZER SURGE LINE WELD INSPECTION FREQUENCY (EPID L-2020-LLL-0017)
Dear Mr. Stoddard:
By letter dated March 26, 2020, Virginia Electric and Power Company (Dominion Energy Virginia, Dominion, or the licensee) submitted a document titled Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency, for the North Anna Power Station (NAPS), Units 1 and 2, to the U.S. Nuclear Regulatory Commission (NRC), for review and approval.
As stated in the March 26, 2020, submittal, Dominion requested approval to revise the inspection frequency of NAPS Units 1 and 2, pressurizer surge line welds from once every 40 months, to once every 10 years. Dominion stated that its proposed inspection interval is applicable to both the first license renewal period as well as subsequent license renewal.
A copy of the related Safety Evaluation is enclosed.
If you have any questions, please contact me at (301) 415-2481, or via email at ed.miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISED LICENSE RENEWAL COMMITMENT PRESSURIZER SURGE LINE WELD INSPECTION FREQUENCY
1.0 INTRODUCTION
By letter dated March 26, 2020, (Agency Documents Access and Management System (ADAMS) Accession Nos. ML20090B397), Virginia Electric and Power Company (Dominion Energy Virginia, Dominion, or the licensee) submitted a document titled Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency, for the North Anna Power Station (NAPS), Units 1 and 2, to the U.S. Nuclear Regulatory Commission (NRC), for review and approval. The licensee had previously submitted its Pressurizer Surge Line Weld Inspection Plan Summary, to the NRC by letter dated July 1, 2014 (ADAMS Accession No. ML14189A129). Dominions July 1, 2014, submittal met its license renewal commitment, documented in NUREG-1766, Safety Evaluation Report Related to the License Renewal North Anna Power Station Units 1 and 2, and Surry Power Station, Units 1 and 2 (ADAMS Accession No. ML030160853), December 2002. Specifically, in its submittal dated July 1, 2014 Dominion stated that it would perform baseline volumetric and surface examinations of the pressurizer surge line welds at the NAPS, Units 1 and 2, prior to entry into the period of extended operation (PEO), and once every 40 months thereafter.
As stated in the licensees submittal dated March 26, 2020, Dominion requested approval to revise the inspection frequency of the NAPS, Units 1 and 2, pressurizer surge line welds from once every 40 months, to once every 10 years. Dominion stated that its proposed inspection interval is applicable to both the first license renewal period as well as subsequent license renewal.
2.0 REGULATORY EVALUATION
By letter dated May 29, 2001 (ADAMS Accession No. ML011500496), Dominion submitted a license renewal application for the NAPS, Units 1 and 2. Title 10 of the Code of Federal Regulations (10 CFR) Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, addresses the requirements for plant license renewal. Pursuant to 10 CFR 54.21, each application for license renewal must contain an integrated plant assessment (IPA) and an evaluation of time limited aging analyses (TLAAs). The plant-specific IPA shall identify and list those structures and components subject to an aging management review and demonstrate that the effects of aging (e.g., cracking, loss of material, loss of fracture toughness, dimensional changes, and loss of preload) will be adequately managed so that their intended functions will be maintained consistent with the current licensing basis (CLB) for the PEO as Enclosure
required by 10 CFR 54.21(a)(3). In addition, 10 CFR 54.21(d) requires that the final safety analysis report (FSAR) supplement for the facility, must contain a summary description of programs and activities for managing the effects of aging and TLAAs for the PEO.
On March 20, 2003 (ADAMS Accession No. ML030710581), NRC issued renewed facility operating licenses to the NAPS Units 1 and 2. The technical basis for NRC staffs review and issuance of the renewed operating facility licenses was documented by NUREG-1766. As stated earlier, NUREG-1766 also documented the licensees commitment regarding future activities to be completed by the licensee, related to the aging management of the NAPS, Units 1 and 2, pressurizer surge line welds.
Pursuant to 10 CFR 54.21(d), Dominions most recent Updated Final Safety Analysis Report (UFSAR) Section 18.3.2.4, and Table 18-1, (Item 24) for NAPS, Units 1 and 2, summarizes the licensees current inspection frequency of the NAPS, Units 1 and 2 pressurizer surge line welds.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to review and approve the licensees revised inspection frequency for the NAPS Units 1 and 2, pressurizer surge line welds. The scope of this review is limited to the NAPS, Units 1 and 2, revision of the inspection frequency of Dominions previously submitted aging management program for the pressurizer surge line welds, applicable to the PEO.
TECHNICAL EVALUATION 3.1 Summary of Submittal Information By letter dated July 1, 2014, as part of its license renewal commitments, Dominion provided the NRC its inspection plan summary to inspect the pressurizer surge line welds once every 40 months for each of the NAPS, Units 1 and 2. In its current submittal. Dominion stated that when it submitted its inspection plan summary, the once every 40 months inspection frequency was selected because no guidance was available at the time. Dominion further stated that in 2012, Florida Power and Light (FPL) proposed using an inspection frequency of 120 months for its pressurizer surge nozzle welds, based on use of American Society Of Mechanical Engineers Boiler and Pressure Vessel Code (ASME),Section X;, Appendix L, Operating Plant Fatigue Assessment, dated May 16, 2012 for Turkey Point Units 3 and 4 (ADAMS Accession No. ML12152A156). The NRC approved FPLs inspection program by letter dated May 29, 2013 (ADAMS Accession No. ML13141A595). Dominion further noted a similar submittal dated October 29, 2015, for St. Lucie Units 1 and 2 (ADAMS Accession No. ML15314A160), and was approved by the NRC on October 13, 2016 (ADAMS Accession No. ML16235A138). The licensee stated that it performed a flaw evaluation for the NAPS pressurizer surge line welds using the 2013 Edition of ASME Section XI, Appendix L. These evaluations assumed a postulated flaw and used a bounding stress, which demonstrated that the crack growth for a postulated circumferential flaw reached the allowable flaw size after an operating period of 60 years. Dominion included the NAPS Unit 1 and 2, technical report as .
The licensee stated that upon receipt of NRCs approval, the NAPS UFSAR will be revised to reflect the new inspection frequency for the NAPS Units 1 and 2 pressurizer surge line welds.
The scheduling of the welds will be based upon the date of completion of the last weld inspection not to exceed 10 years. The licensee further stated that the proposed inspection frequency for the NAPS Units 1 and 2, pressurizer surge line weld is applicable to both the first
license renewal period (i.e., PEO), as well as subsequent license renewal. The NRC staff will review the program as part of its subsequent license renewal review for NAPS, Units 1 and 2.
3.2 NRC Staff Technical Evaluation The NRC staff reviewed the NAPS, Units 1 and 2, Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency, to determine if the inspection frequency would be adequate in managing the effects of aging so that the components intended functions would be maintained consistent with the CLB during the PEO, in accordance with 10 CFR 54.21(a)(3). The NRC staff notes that all ASME Code,Section XI, Inservice Inspection (ISI) and 10 CFR 50.55a requirements continue to apply during the term of a renewed license, unless a relief request is submitted by the licensee and subsequently approved by NRC staff in accordance with 10 CFR 50.55a. The NRC staff noted that the proposed inspection frequency (i.e., once every 10 years) for surface and volumetric examinations is consistent with the ASME Code,Section XI, examinations for reactor coolant piping.
During its review, the NRC staff noted that the licensee performed the flaw evaluation for the NAPS pressurizer surge line welds using the 2013 Edition of ASME Section XI, Appendix L, Operating Plant Fatigue Assessment. The NRC staff further notes the 2013 Edition of ASME Section XI is endorsed by reference in 10 CFR 50.55a, and includes Appendix L without any conditions.
As part of its the review the NRC staff verified that the values for the material properties, dimensions, design temperatures, thermal transients, and pressures used for the NAPS pressurizer surge line flaw tolerance evaluation matched the UFSAR provided values for the two units. By letter dated September 3, 2020 (ADAMS Accession No. ML20252A220), the licensee confirmed that the baseline examinations for the NAPS Units 1 and 2 had been completed (N1R25 - fall 2016 and N2R26 - spring 2018, respectively). Those examinations confirmed that there were no recordable indications present on the pressurizer surge line welds.
Based on the above, the NRC staff confirmed that the revised inspection frequency would provide an acceptable level of safety. This was, in part, because the projected growth rate for a postulated crack to challenge the leak tightness of the pressurizer surge line exceeds 60 years of operation. The 10-year inspection interval proposed by the licensee provides reasonable assurance that indications, if they are present, will be detected before they become unacceptable indications. Therefore, the NRC staff concludes that Dominion has demonstrated that the effects of aging for the NAPS Units 1 and 2 pressurizer surge line welds will be adequately managed so that the intended function(s) will be maintained consistent with the CLB for the PEO, as required by 10 CFR 54.21(a)(3).
4.0 CONCLUSION
The NRC staff reviewed the NAPS, Units 1 and 2, Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency. Based on its review, the NRC staff concludes that there is reasonable assurance that the license will manage the aging effects of the pressurizer surge line welds for the NAPS, Units 1 and 2, through the implementation of the revised proposed inspection frequency. Therefore, the NRC staff approves the licensees request to extend the inspection interval from 40 months to 10 years for NAPS, Units 1 and 2.
The licensee may inspect these welds based upon the date of completion of the last weld inspection not to exceed 10 years during the PEO.
Principal Contributor: Roger Kalikian Date: September 30, 2020
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - REVISED LICENSE RENEWAL COMMITMENT PRESSURIZER SURGE LINE WELD INSPECTION FREQUENCY (EPID L-2020-LLL-0017) DATED SEPTEMBER 30 2020 DISTRIBUTION:
PUBLIC LPL2-1 File Copy RidsAcrs_MailCTR Resource RidsNrrDorlLpl2-1 Resource RidsNrrLAKGoldstein Resource RidsNrrPMNorthAnna Resource RidsRgn2MailCenter Resource ADAMS Accession No. ML20253A329 *via e-mail OFFICE NRR/DORL/LPL2-1/PM* NRR/DORL/LPL2-1/LA* NRR/DORL/LPL2-1/BC*
NAME GEMiller* KGoldstein* MMarkley*
DATE 09/23/2020 09/10/2020 09/29/2020 OFFICE NRR/DRL/NPHP/BC* NRR/DORL/LPL2-1/PM*
NAME MMitchell* GEMiller*
DATE 09/23/2020 09/30/2020