Letter Sequence Request |
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CAC:MF8363, Clarify Use and Application Rules (Approved, Closed) CAC:MF8364, Clarify Use and Application Rules (Approved, Closed) |
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MONTHYEARML16294A2262016-10-27027 October 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Acceptance Review ML16330A5052016-11-0909 November 2016 Response to Request for Supplemental Information in Support of MELLLA + LAR, Non-Proprietary Information - Class I (Public) Project stage: Supplement BSEP 16-0101, Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion2016-11-0909 November 2016 Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion Project stage: Supplement ML16319A4232016-11-14014 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16319A4242016-11-14014 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16327A0232016-11-21021 November 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Core Flow Operating Range (Melllla+), Project stage: Approval ML16342B6002016-12-0707 December 2016 NRR E-mail Capture - Accepted for Review of License Amendment Request Regarding Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Project stage: Approval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Request BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Request ML18010A8472018-04-0505 April 2018 Request for Withholding Information from Public Disclosure for Brunswick Steam Electric Plant, Units 1 and 2, Regarding Core Flow Operating Range Expansion (CAC No. MF8363 and MF8364; EPID L-2016-LLA-0009) Project stage: Withholding Request Acceptance 2016-11-09
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Category:Letter
MONTHYEARIR 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) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) 2024-09-04
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{{#Wiki_filter:-I': t. I J* ~"-)DUKE ENERGY William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.832.3698 November 1, 2017 Serial: BSEP 17-0089 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Updates to Request for License Amendment Regarding Core Flow Opertaing Range Expansion (CAC Nos. MF8363 and MF8364)
References:
1. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment Regarding Core Flow Operating Range Expansion, dated September 6, 2016, ADAMS Accession Number ML 16257 A410 2. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Response to Request for Supplemental Information for License Amendment Regarding Core Flow Operating Range Expansion, dated November 9, 2016, ADAMS Accession Number ML 16330A504 Ladies and Gentlemen: By letter dated September 6, 2016 (i.e., Reference 1 ), Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would revise the Technical Specifications to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). By letter dated November 9, 2016 (i.e., Reference 2), Duke Energy provided supplemental information in support of the proposed amendment. During preparation for an NRC audit of MELLLA+ methodologies, which was conducted *July 21-24, 2017, General Electric Hitachi (GEH) determined that the original Anticipated Transient Without Scram (A TWS) calculations supporting the BSEP MELLLA+ LAR were performed using some design inputs that were different than current procedures.would dictate. These design inputs were related to the time steps within the TRACG software and a parameter tolerance associated with the fuel reactivity. Correction of these design inputs has resulted in changes to the Peak Clad Temperature (PCT) values reported in the MELLLA+ Safety Analysis Report (SAR) for the limiting Turbine Trip Without Bypass (TTWBP) event. An editorial correction to the Standby Liquid Control initiation time for this event was also identified. The NRC was verbally informed of these changes during the July 2017 audit. f D D I rJ~tv
' U.S. Nuclear Regulatory Commission Page 2 of 3 These design input changes have resulted in updates to selected pages of the MELLLA+ SAR (i.e., Enclosure 5 of Reference 1) and to the Request for Supplemental Information response (i.e., Enclosure 2 of Reference 2). Enclosure 1 of this letter provides updated pages for the BSEP MELLLA+ SAR (i.e., Duke Report DUKE-OB21-1104-000(P)) with mark-ups showing the necessary changes. The affected pages contain proprietary information covered by the affidavit previously included as Enclosure 7 of Duke Energy's LAR (i.e., Reference 1 ). The changes do . not affect the non-proprietary version of the pages that were provided in Enclosure 6 of Reference 1. / Enclosure 2 of this letter provides an updated page for the GEH Document ] GEH-PGN-MPLUS-143 (i.e., Enclosure 2 of Reference 2). The affected page contains proprietary information covered by the affidavit previously included in Enclosure 3 ofi Reference 2. The changes to the page from GEH Document GEH-PGN-MPLUS-143 do not affect the non-proprietary version of the corresponding page that was provided in En losure 4 of Reference 2. Enclosure 3 provides a revision to page 3-7 of Duke Energy Document DUKE-OB21-1104-000(P), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus (M+ SAR), which was provided as Enclosure 5 of Reference 1. The page is being revised to remove proprietary information markings for the discussion of Annulus Pressurization in the table of reactor internals load categories. The Annulus Pressurization summary in the table is no longer being marked as proprietary because the associated discussion in Section 4.1.3.2 does not contain proprietary information. The affidavit provided in Enclosure 7 of Reference 1 remains applicable to the updated page. A non-proprietary version of the revised page is provided in Enclosure 4. Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager -Regulatory Affairs, at (910) 832-2487. I declare, under penalty of perjury, that the foregoing is true and correct. Executed on November 1, 2017. Sincerely, wuPJ2 William R. Gideon U.S. Nuclear Regulatory Commission Page 3 of 3 WRM/wrm
Enclosures:
1. Revised Pages for DUKE-0821-1104-000(P), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus (M+SAR), July 2016 [Proprietary Information -Withhold from Public Disclosure in Accordance With 10 CFR 2.390] 2. Revised Page for GEH Document GEH-PGN-MPLUS-143, Response to Request for Supplemental Information in Support of Brunswick Steam Electric Plant MELLLA + LAR, dated November 9, 2016 (ADAMS Accession Number ML 16330A504) [Proprietary Information -Withhold from Public Disclosure in Accordance With 10 CFR 2.390] 3. Revised Page 3-7 to Duke Energy Document DUKE-0821-1104-000(P), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus (M+ SAR) [Proprietary Information -Withhold from Public Disclosure in Accordance With 10 CFR 2.390] 4. Revised Page 3-7 to Duke Energy Document DUKE-0821-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus (M+ SAR) cc (with all enclosures): U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 84 70 River Road Southport, NC 28461-8869 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov cc (with Enclosure .4 only): Chair -North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, Ill, Section Chief (Electronic Copy Only) Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov BSEP 17-0089 Enclosure 4 Revised Page 3-7 to Duke Energy Document DUKE-0821-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus (M+ SAR)
DUKE-OB21-1l04-001 (NP) NON-PROPRIETARY INFORMATION 3.3.2 Reactor Internals Structural Evaluation Structural integrity evaluations for MELLLA+ operating domain expans10n are performed consistent with the existing design basis of the components. [[ ]] Therefore, no further structural evaluation of the reactor internals is required. An evaluation of the load categories applicable to the reactor internals under normal, upset, emergency, and faulted conditions is presented below: Load Category MELLLA+ Results for Normal, Upset, Emergency, and Faulted Conditions Dead Weight Seismic RIPDs (including Acoustic and Flow-Induced Loads) Fuel Assembly Lift Forces Hydrodynamic Containment Dynamic Loads -(LOCA and SRV) Section 4.1.3.2 concludes that the AP loads m the Annulus Pressurization (AP) MELLLA + operating domain are bounded by the loads in the current licensed operation domain. [[ Jet Reaction Thermal Effects 3-7
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