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MONTHYEARBSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid Project stage: Response to RAI BSEP 14-0087, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report2014-08-14014 August 2014 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report Project stage: Response to RAI ML14231A9642014-09-17017 September 2014 Screening and Prioritization Results of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 Fukushima Project stage: Other BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident Project stage: Request ML15231A0222015-09-0808 September 2015 Nuclear Regulatory Commission Plan for the Audit of Duke Energy Progress, Inc. Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 - Seismic for Brunswick Steam Electric Plant, Project stage: Other ML15279A4502015-12-0909 December 2015 NRC Report for the Audit of Duke Entergy Progress, Inc. Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 -- Seismic for: Brunswick Steam Electric Plant, Units 1 and 2 (TACs M Project stage: Other 2014-08-14
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MONTHYEARIR 05000324/20253012024-10-17017 October 2024 Notification of Licensed Operator Initial Examination 05000325/2025301 and 05000324/2025301 IR 05000324/20244012024-10-15015 October 2024 Security Baseline Inspection Report 05000324/2024401 and 05000325/2024401 ML24297A6262024-10-11011 October 2024 PCA Letter to NRC Brunswick Potential Tropical Storm Eight IR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 IR 05000324/20243012024-04-0303 April 2024 NRC Operator License Examination Report 05000325/2024301 and 05000324/2024301 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) 2024-09-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 17, 2014 Mr. George T. Hamrick, Vice President Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2-SCREENING AND PRIORITIZATION RESULTS OF INFORMATION PROVIDED PURSUANT TO TITLE 10 OF THE CODE OF FEDERAL REGULATIONS PART 50, SECTION 50.54(f), SEISMIC HAZARD REEVALUATIONS FOR RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT (TAC NOS. MF3824 AND MF3825)
Dear Mr. Hamrick:
The purpose of this letter is to inform Duke Energy Progress, Inc. (Duke Energy) of the results for Brunswick Steam Electric Plant (BSEP), Units 1 and 2, regarding the U.S. Nuclear Regulatory Commission's (NRC) seismic screening and prioritization review. The staff has determined that BSEP screens out of conducting a seismic risk evaluation since the Individual Plant Examination for External Events (IPEEE) demonstrates plant seismic capacity to levels higher than the ground motion response spectra (GMRS) in the 1-10 Hertz (Hz) range and Duke Energy demonstrated that the IPEEE-related screening criteria in the NRC-approved industry guidance was met. The NRC staff concurs with Duke Energy's determination to conduct the high frequency and spent fuel pool seismic evaluation which is consistent with commitments contained in the March 31, 2014, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 141 06A461 ). The high frequency evaluation will be performed because the GMRS exceeds the existing safe shutdown earthquake (SSE) in the greater than 10 Hz range. The spent fuel pool evaluation will be performed because spent fuel pools were not included in the original scope of the IPEEE evaluation. This letter only transmits the NRC staff's result of the screening and prioritization of the seismic hazard submittal for BSEP. The NRC staff is continuing its review of the seismic hazard reevaluation submittal and may request additional plant-specific information to support this review. The NRC staff plans to issue an assessment for BSEP on the reevaluated seismic hazard no later than the third quarter 2015. BACKGROUND On March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter) (ADAMS Accession No. ML 12053A340). The purpose of that request was to gather information concerning, in part, seismic hazards at each operating reactor site and to enable the NRC staff to determine whether licenses should be modified, suspended, or revoked. Further, the 50.54(f) letter stated that the NRC would provide screening and prioritization results to indicate deadlines, if necessary, for individual plants to complete seismic risk evaluations that assess the total plant response to the reevaluated seismic hazard. In response to the 50.54(f) letter, all G. Hamrick addressees committed to follow the Electric Power Research Institute Report (EPRI), "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic,"1 as supplemented by the EPRI Report, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic"2 (referred to as the expedited approach). In response to the 50.54(f) letter, Duke Energy submitted their reevaluated hazard for BSEP in March 2014. The Report specified that BSEP screens out for performing a seismic risk evaluation, however screens in for performing a high frequency and spent fuel pool seismic evaluation. Subsequently, by letter dated May 9, 2014 (ADAMS Accession No. ML 14111 A 147), the NRC staff informed all licensees of operating reactors in the central and eastern United States of the screening and prioritization results to support completing seismic risk and limited-scope evaluations, as described in Enclosure 1 of the 50.54(f) letter. In the May 2014 letter, the NRC staff identified that BSEP conditionally screens in to perform a seismic risk (Prioritization Group 3), high frequency, and spent fuel pool evaluation for the purposes of the screening and prioritization review because additional information was needed to demonstrate BSEP's IPEEE adequacy for the purpose of seismic screening. SCREENING PROCESS As discussed in the May 2014 letter, the NRC staff's screening review was performed using the SPID guidance. The SPID provides guidance on seismic screening when the ground motion response spectra (GMRS) is above the safe shutdown earthquake (SSE), but bounded by the IPEEE capacity spectrum. To use the IPEEE capacity spectrum for seismic screening, Duke Energy needed to demonstrate the adequacy of BSEP's IPEEE evaluation by satisfying specific criteria in the SPID. If the IPEEE capacity is greater than the GMRS in the 1-10 Hz range and meets the IPEEE-related screening criteria in the SPID, a plant would screen out of conducting a seismic risk evaluation. SCREENING REVIEW ASSESSMENT A public meeting (Meeting Summary available in ADAMS Accession No. ML 1421 OAOSO) was conducted on June 30, 2014, between the NRC staff and Duke Energy, in part, to address the staff's questions regarding adequacy of BSEP's IPEEE evaluation to demonstrate plant seismic capacity and meet the corresponding screening criteria in the SPID. The NRC staff issued Duke Energy a request for additional information (RAI) on July 16, 2014 (ADAMS Accession No. ML 14195A071) to support the NRC's final screening and prioritization determination for BSEP. Duke Energy submitted its response to the RAis by letter dated August 14, 2014, (ADAMS Accession No. ML 14241 A432). The RAI response clarifies a reference within the seismic reevaluated hazard submittal and describes the basis for screening out slope stability along the cooling intake canal under the 1 The SPID guidance document is found in ADAMS under Accession No. ML 12333A 170. The staff endorsement letter for the SPID guidance is found in ADAMS under Accession No. ML 12319A074. 2 The Expedited Approach guidance document is found in ADAMS under Accession No. ML 131 02A 142.
G. Hamrick review level earthquake loading. Based on the NRC staff's review of the March 2014 Seismic Hazard Evaluation and Screening Report and information provided in the RAI response, BSEP meets the IPEEE-related screening standards. FINAL SCREENING AND PRIORITIZATION Seismic Risk Limited-scope Evaluations Plant name Screening Expedited Evaluation High Low Spent Result Approach (Prioritization Frequency Frequency Fuel Pool Evaluation Group) Evaluation Evaluation Evaluation Brunswick Steam Electric Out x3 X X Plant, Units 1 and 2 If you have any questions on this matter, please contact Michael Balazik, Project Manager for the Japan Lessons-Learned Division at (301) 415-2856 or at Michaei.Balazik@nrc.gov. Docket Nos. 50-325 and 50-324 cc: Listserv Sincerely, Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation 3 As committed in the March 31,2014, letter (ADAMS Accession No. ML 14106A461).
ML 14231A964 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NAME MBalazik SLent DATE 08/21/14 08/21/14 OFFICE NRR/DORL!LPL2-2/PM* OGC NAME AHon BHarris DATE 08/ /14 08/29/14 Sincerely, IRA! Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation JLD R/F RidsNrrOd LRegner, NRR RidsNrrLASLent RidsAcrsAcnw_MaiiCTR RidsEdoMaiiCenter NRO/DSEA/RGS2/BC DJackson 08/26/14 NRR/JLD/0 JDavis (JMcHale for) 09/15/14 NRR/JLD/JHMB/BC SWhaley 08/25/14 NRR/AD DOorman 09/17/14