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MONTHYEARML16196A2922016-07-11011 July 2016 ISFSI, Millstone, Units 1, 2 & 3, and ISFSI, North Anna, Units 1 & 2, and ISFSI, Surry, Units 1 & 2, and ISFSI Submission of Rev. 21 of Quality Assurance Topical Report for NRC Approval and Submission of Revision 22 for Information Only Project stage: Request ML16321A4542016-11-10010 November 2016 Connecticut and Virginia Electric & Power Company Response to Request for Additional Information Revision 22 of Quality Assurance Program Description Topical Report Project stage: Response to RAI 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) Project stage: Other 2016-07-11
[Table View] |
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)ML17046A316 |
Person / Time |
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Site: |
Millstone, Kewaunee, Surry, North Anna, 07200002, 07200055 |
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Issue date: |
04/06/2017 |
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From: |
Markley M Plant Licensing Branch II |
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To: |
Stoddard D Virginia Electric & Power Co (VEPCO) |
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Mozafari B, DORL/LPLII-1, 415-2020 |
References |
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CAC MF8128, CAC MF8129, CAC MF8130, CAC MF8131, CAC MF8132, CAC MF8133, CAC MF8134, DOM-QA-1 |
Download: ML17046A316 (7) |
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Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 ML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages ML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24017A0802024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000338/2024301 and 05000339/2024301 ML23332A7272024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8352024-01-0909 January 2024 Letter to Acee Watt, Thpo, United Keetoowah Band of Cherokee Indians in Oklahoma Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8362024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8372024-01-0909 January 2024 Letter to Elizabeth Toombs, Thpo, Cherokee Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8382024-01-0909 January 2024 Letter to G. Anne Richardson, Chief, Rappahannock Tribe, Inc., Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8392024-01-0909 January 2024 Letter to Gerald Stewart, Chief, Chickahominy Indian Tribe, Eastern Division Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8402024-01-0909 January 2024 Letter to Katelyn Lucas, Thpo, Delaware Nation, Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8412024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8422024-01-0909 January 2024 Letter to Paul Barton, Thpo, Eastern Shawnee Tribe of Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8432024-01-0909 January 2024 Letter to Robert Gray, Chief, Pamunkey Indian Tribe, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8442024-01-0909 January 2024 Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians ML24003A8452024-01-0909 January 2024 Letter to Stephen Adkins, Chief, Chickahominy Indian Tribe, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8462024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8472024-01-0909 January 2024 Letter to Tom Jonathan, Chief, Tuscarora Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8482024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8492024-01-0909 January 2024 Letter to W. Frank Adams, Chief, Upper Mattaponi Tribe Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8502024-01-0909 January 2024 Letter to Wenonah Haire, Thpo, Catawba Indian Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A0872024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23332A1852024-01-0404 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML23360A6352024-01-0404 January 2024 Letter to Dominion Availability for North Anna Units 1 and 2 Draft Site Specific Environmental Impact Statement ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23332A1472023-12-21021 December 2023 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal 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) ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change 2024-02-06
[Table view] Category:Safety Evaluation
MONTHYEARML23339A1362024-01-26026 January 2024 Safety Evaluation Re NRC Issuance of Exemption for Site Restoration ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures 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) ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations 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 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 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 ML23102A2832023-04-25025 April 2023 ASME OM Code Inservice Testing Program Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML23100A0652023-04-25025 April 2023 Issuance of Amendment Nos. 310 and 310, Regarding Turbine Building Tornado Classification ML23058A4542023-03-16016 March 2023 Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints ML23030B8472023-03-10010 March 2023 Issuance of Amendment Nos. 309 and 309, License Amendment Request Regarding a 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring 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) ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation ML22201A5082022-07-28028 July 2022 Authorization and Safety Evaluation for Alternative Request No. IR-04-09 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 ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure 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 ML22039A3392022-03-0303 March 2022 Request for Alternative Frequency to Supplemental Valve Position Verification Testing Requirements in the Fourth 10-year Valve Inservice Testing Program 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 ML22007A1512022-02-16016 February 2022 Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements ML21326A0992022-01-0707 January 2022 Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21323A1742021-12-22022 December 2021 Issuance of Amendment Nos. 289 and 272 to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML21262A0012021-11-0909 November 2021 Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate ML21284A0062021-10-29029 October 2021 Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02 ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 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 ML21227A0002021-10-0505 October 2021 Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident ML21222A2302021-09-0909 September 2021 Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227) ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines ML21201A1172021-08-0606 August 2021 Proposed Alternative Requests S1-I5-ISI-05 and S2-I5-ISI-06 to Eliminate Examination of Threads in Reactor Pressure Vessel Flange ML21174A0202021-08-0202 August 2021 Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval 2024-01-26
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 6, 2017 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glenn Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION AND ISFSI; MILLSTONE POWER STATION UNITS 1, 2 AND 3 AND ISFSI; NORTH ANNA POWER STATION UNITS 1 AND 2 AND ISFSI; AND SURRY POWER STATION UNITS 1 AND 2 AND ISFSI; REQUEST FOR APPROVAL OF REVISION 21 OF THE NUCLEAR FACILITY QUALITY ASSURANCE PROGRAM DESCRIPTION TOPICAL REPORT, DOM-QA-1 (CAC NOS. MF8128, MF8129, MF8130, MF8131, MF8132, MF8133, MF8134)
Dear Mr. Stoddard:
By letter dated July 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16196A292), as supplemented by letter dated November 10, 2016 (ADAMS Accession No. ML16321A454), Dominion Energy Kewaunee, Inc. (DEK), Dominion Nuclear Connecticut, Inc. (DNC), and Virginia Electric and Power Company (VEPCO),
submitted for the U.S. Nuclear Regulatory Commission (NRC) staff's review, a revision to the Nuclear Facility Quality Assurance Program Description (QAPD) Topical Report, DOM-QA-1, in accordance with 10 CFR 50.54(a)(4).
The proposed DOM-QA-1 revision reflects changes and simplification based on the Kewaunee site's decommissioning status. The proposed changes to DOM-QA-1 are considered to be a reduction in commitments. The changes included restructuring the Kewaunee organization consistent with the reduced quality activities in the decommissioning phase, adding exceptions to American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," for the qualifications required for management positions, replacing the functions of the Kewaunee Independent Review Committee with an Independent Review Group, and adding an exception to Regulatory Guide 1.28, "Quality Assurance Program Requirements (Design and Construction)," Revision 3 for the retention of security plans, procedures, and activity records.
The NRC staff has reviewed Dominion's submittal. Based on its review, the NRC staff concludes that the quality assurance program described in DOM-QA-1, Revision 21 meets the criteria of Appendix B to 10 CFR Part 50, and is, therefore, acceptable.
D. Stoddard If questions arise on this matter, feel free to contact me, Brenda Mozafari, Senior Project Manager, at (301) 415-2020 or Brenda.Mozafari@nrc.gov.
Sincerely,
~/Lx{ hr Michael T. Markley, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-305, 50-245; 50-336, 50-423; 50-338, 50-339; 50-280, 50-281; 72-47, 72-16, 72-56; 72-2, 72-55; 72-64
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv
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- -1r:.._ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REVISION 21 OF THE NUCLEAR FACILITY QUALITY ASSURANCE PROGRAM DESCRIPTION TOPICAL REPORT DOM-QA-1 DOMINION ENERGY KEWAUNEE KEWAUNEE POWER STATION DOCKET NO. 50-305 AND 72-64 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION, UNITS 1, 2 AND 3 DOCKET NOS. 50-245. 50-336. 50-423 AND 72-47 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-338, 50-339, 72-16 AND 72-56 SURRY POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-280, 50-281 72-2 AND 72-55 I
1.0 INTRODUCTION
By letter dated July 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16196A292), Dominion Energy Kewaunee, Inc., Dominion Nuclear Connecticut, Inc., and Virginia Electric and Power Company submitted for the U.S. Nuclear Regulatory Commission (NRC) staff's review, Revision 21 of the Nuclear Facility Quality Assurance Program Description (QAPD) Topical Report, DOM-QA-1, in accordance with 10 CFR 50.54(a)(4).
DOM-QA-1 provides a top-level overview of the quality program controls applied to quality related items and activities at the Millstone, North Anna, and Surry power stations during the operating phase and the Kewaunee power station during the decommissioning phase. DOM QA-1 is based on the applicable portions of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste," Subpart G, "Quality
Assurance," and 10 CFR Part 71, "Packaging and Transportation of Radioactive Material,"
Subpart H, "Quality Assurance."
2.0 REGULATORY EVALUATION
The Commission's regulatory requirements related to Quality Assurance (QA) programs are set forth in Appendix B to 10 CFR Part 50 (Appendix 8), 10 CFR 50.34(b)(6)(ii), and 10 CFR 50.54(a). In addition, the Commission's regulatory requirements related to QA programs for the independent storage of spent nuclear fuel and packaging and transportation of radioactive material are addressed in 10 CFR Part 71, Subpart H, and 10 CFR Part 72, Subpart G.
Appendix B establishes the requirements for the design, fabrication, construction, and testing of structures, systems, and components (SSCs) of the facility. The pertinent requirements of Appendix B apply to all activities affecting the safety-related functions of those SSCs and include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying SSCs.
The regulations in 10 CFR 50.34, "Content of applications; technical information," require that every applicant for an operating license include information in its Final Safety Analysis Report (FSAR) on the managerial and administrative controls to be used to ensure safe operation.
The information on the controls shall also include a discussion on how the applicable requirements of Appendix B will be satisfied.
The regulations in 10 CFR 50.54 require each power plant subject to the requirements to implement a QA program and 10 CFR 50.54(a)(4) require licensees to submit to the NRC, changes to their QA Program that reduce commitments.
The regulations in 10 CFR Part 71, Subpart H, establishes the quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging that are important to safety.
The regulations in 10 CFR Part 72, Subpart G, establishes the quality assurance requirements that apply to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, modification of SSCs, and decommissioning that are important to safety.
3.0 TECHNICAL EVALUATION
By letter dated July 11, 2016, the licensee requested approval of DOM-QA-1, Revision 21, because the proposed changes are considered a reduction in commitment in accordance with the provisions of 10 CFR 50.54(a)(4). The licensee also provided changes in Revision 22 for information but did not request NRC approval.
In evaluating the adequacy of the revisions to DOM-QA-1, Revision 21, the NRC staff used the guidance contained in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 17.3, "Quality Assurance Program Description,"
dated August 1990 (ADAMS Accession No. ML052350376), which provides acceptance criteria for QAPDs.
The changes made to Revision 21 of DOM-QA-1 include the following:
(1) Changes to the Kewaunee organization consistent with the reduced amount of quality related activities after the cessation of power operation. This included combining the Maintenance and Operations functions under the responsibility of a single manager and adding a Facilities Program and Processes group. The proposed changes to DOM-QA-1 include the functional responsibilities, levels of authority, and provide independence between persons and organizations executing performance activities and those executing verification and self-assessment activities.
(2) Changes involving adding exceptions to ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," for: (1) the experience requirements for the management position for the combined Operations and Maintenance group and the management position for Technical Services to be reduced from eight years to seven years; (2) work experience gained at a decommissioning nuclear facility may be credited as nuclear power plant experience; and (3) removing the requirement for the management position for the combined Operations and Maintenance group to hold a Senior Operator's license. The proposed changes maintain assurance that personnel assigned to implement elements of the QA program are capable of performing their assigned task.
(3) Changes involving transitioning from a Facility Safety Review Committee (FSRC) to a Facility Safety Review Group (FSRG). The proposed changes to DOM-QA-1 include a description of the independent review body organizational structure, functional responsibilities, level of authorities and interfaces. The proposed organizational changes provide sufficient authority and organizational freedom.
(4) Changes involving adding an exception to NRC Regulatory Position C.2 of Regulatory Guide (RG) 1.28, Revision 3 for the retention of security plans, procedures, and activity records. The proposed change requires that records related to security plans, procedures and activities will be maintained in the accordance with the applicable NRC security regulations and orders. RG 1.28 requires that security plans, procedures, and activity records be retained as lifetime records, while 10 CFR 37 .103, "Record Retention," states that, "Licensees shall maintain the records that are required by the regulations in this part for the period specified by the appropriate regulation. If a retention period is not otherwise specified, these records must be retained until the Commission terminates the facility's license."
The NRC staff reviewed the above changes in accordance with NUREG-0800, Section 17.3; 10 CFR 50, Appendix B; 10 CFR 71, Subpart H; and 10 CFR 72, Subpart G, and concludes that the proposed changes to DOM-QA-1, Revision 21, continue to meet the regulations and are, therefore, acceptable.
4.0 CONCLUSION
Based on the above, the NRC concludes that the proposed changes in QAPD DOM-QA-1, meet the applicable portions of 10 CFR Part 50, Appendix B, 10 CFR 71, Subpart H and 10 CFR 72, Subpart G. The program description adequately describes the provisions to meet regulatory requirements.
- 5. REFERENCES
- 1. NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 17.3, "Quality Assurance Program Description" dated August 1990 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052350376).
- 2. RG 1.28, "Quality Assurance Program Requirements (Design and Construction)" Revision 3, dated August 1985 (ADAMS Accession No. ML003739981 ).
- 3. Heacock, David A., Virginia Electric and Power Company, Dominion Nuclear Connecticut, Inc., Dominion Energy Kewaunee, Inc., letter to the U.S. Nuclear Regulatory Commission, "Kewaunee, and ISFSI, Millstone, Units 1, 2 & 3, and ISFSI, North Anna, Units 1 & 2, and ISFSI, Surry, Units 1 & 2, and ISFSI Submission of Rev. 21 of Quality Assurance Topical Report for NRC Approval and Submission of Revision 22 for information Only," dated July 11, 2016 (ADAMS Accession No. ML16196A292).
- 4. Sreenivas, V., U.S Nuclear Regulatory Commission, email to Heacock, David A.,
Virginia Electric and Power Company, Dominion Nuclear Connecticut, Inc.,
Dominion Energy Kewaunee, Inc., Request for Additional Information:
DOMINION ENERGY KEWAUNEE, DOMINION NUCLEAR CONNECTICUT AND VIRGINIA ELECTRIC POWER COMPANY NUCLEAR FACILITY QUALITY ASSURANCE PROGRAM DESCRIPTION TOPICAL REPORT DOM-QA-1,"
dated October 10, 2016 (ADAMS Accession No. ML16287A714).
- 5. Heacock, David A., Virginia Electric and Power Company, Dominion Nuclear Connecticut, Inc., Dominion Energy Kewaunee, Inc., letter to the U.S. Nuclear Regulatory Commission, "Dominion Energy Kewaunee, Dominion Nuclear Connecticut and Virginia Electric & Power Company Response to Request for Additional Information RE: Revision 22 of Quality Assurance Program Description Topical Report," dated November 10, 2016 (ADAMS Accession No. ML16321A454).
- 6. American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel, New York, New York, 1971.
ML17046A316 *Memo dated 01/12/17 OFFICE N RR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1/LA NRO/DCIP/QVIB-3/BC*
NAME BMozafari KGoldstein KKavanagh*
DATE 02/13/17 03/30/17 01/12/17 OFFICE NMSS/DUWP/BC NMSS/DSFM/SFLB/BC NRR/DORL/LPL2-1 /BC NAME BWatson**
- JMcKirQan** MMarkley DATE 03/13/17 03/24/17 04/06/17 OFFICE NRO/DCIP/QVIB3 NRR/DORL/LPL2-1/PM NAME AFerQuson BMozafari DATE 01/12/17 03/24/17