Letter Sequence RAI |
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CAC:MF8864, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (Approved, Closed) CAC:MF8865, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (Approved, Closed) |
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MONTHYEARML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. Project stage: Request ML16257A4102016-09-0606 September 2016 Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Request BSEP 16-0083, Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs.2016-11-18018 November 2016 Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs. Project stage: Request ML16362A0752016-12-23023 December 2016 NRR E-mail Capture - Brunswick, Units 1 and 2 - Acceptance of License Amendment Request Regarding Application to Revise Technical Specifications to Adopt TSTF-535 Project stage: Acceptance Review ML17082A3042017-03-0909 March 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CACs MF8864 and MF8865) Project stage: RAI BSEP 17-0029, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-04-0606 April 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Response to RAI ML17088A3962017-06-0707 June 2017 Issuance of Amendments Regarding Revisions of Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs Project stage: Approval ML17275A2772017-10-0202 October 2017 E-mail, Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CAC Nos. MF8864 and MF8865) (Non-Proprietary) Project stage: RAI BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Response to RAI ML18010A0512018-01-0505 January 2018 Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) (Nonproprietary) Project stage: RAI ML18010A0502018-01-0505 January 2018 E-mail Re. Brunswick Units 1 and Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) Project stage: RAI BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure Project stage: Response to RAI ML18045A8592018-02-14014 February 2018 Withdrawal of Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion Project stage: Withdrawal BSEP 18-0027, ANP-3655NP, Revision 0, Brunswick Mellla+ CRDA Assessment with Draft Criteria.2018-02-28028 February 2018 ANP-3655NP, Revision 0, Brunswick Mellla+ CRDA Assessment with Draft Criteria. Project stage: Draft Other ML18075A3302018-03-0101 March 2018 Response to Request for Additional Information SNPB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865) Project stage: Response to RAI ML18067A1032018-03-0808 March 2018 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) Project stage: RAI ML18071A3732018-03-12012 March 2018 NRR E-mail Capture - Correction: Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) Project stage: RAI 2017-04-06
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Category:E-Mail
MONTHYEARML23248A2612023-09-0505 September 2023 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise the 10 CFR 50.69 Categorization Process ML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23006A0642023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML23006A1892023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21357A0472021-12-23023 December 2021 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Adoption of TSTF-580 ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21200A1582021-07-16016 July 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ML21168A0042021-06-17017 June 2021 Notification of Inspection and Request for Information ML21137A1622021-04-26026 April 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-505 Risk-Informed Completion Time (L-2021-LLA-0060) ML21082A0162021-03-22022 March 2021 Accepted for Review - Brunswick License Amendment Request to Change Tech Spec Limit for Standby Liquid Control System Boron Solution Storage Tank Volume L-2021-LLA-0022 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information Request ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20294A0642020-10-20020 October 2020 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-582 RPV Water Inventory Control Enhancements(L-2020-LLA-0218) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML21033A8562020-08-0505 August 2020 NRR E-mail Capture - Accepted for Review - Brunswick Relief Request for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements EPID-L-2020-LLR-0091 ML20121A1262020-04-29029 April 2020 Radiation Safety Baseline Inspection Information Request ML20111A1212020-04-20020 April 2020 NRR E-mail Capture - Accepted for Review - Brunswick Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior - EPID: L-2020-LLR-0048 ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19252A4572019-09-0808 September 2019 (FEMA Email 09-08-19) Tentative Notification of Brunswick Preliminary Capability Assessment Results ML19252A4092019-09-0606 September 2019 (E-mail to FEMA 09-06-19) FEMA Notification for Planned Restart of Brunswick Units 1 and 2 ML19219A2132019-08-0707 August 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Amendment Requests to Relocate the TSs Staff Qualification Requirements to the Duke Energy Corporation QAPD ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19162A3902019-06-11011 June 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Fourth 10-Year Inservice Inspection Interval ISI-12 ML19162A3912019-06-11011 June 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Relief Request (19-GO-001) Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19092A1152019-04-0101 April 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirements for Safety Relief Valves (L-2019-LLA-0043) ML19092A1142019-04-0101 April 2019 NRR E-mail Capture - Brunswick Plant, Unit 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify TS 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (L-2019-LLA-0031) ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2023-09-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML22192A0862022-07-12012 July 2022 RQ Inspection Notification Letter ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21239A0652021-09-0808 September 2021 Request for Additional Information Regarding Proposed Alternative to ASME Section XI Requirements for Repair - Replacement of Buried Service Water Piping (EPID L-021-LLR-0014) - Public ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information Request ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283C5532019-10-18018 October 2019 Redacted - Brunswick Steam Electric Plant, Units 1 and 2 - Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19081A0722019-03-21021 March 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19015A0302019-01-14014 January 2019 NRR E-mail Capture - Brunswick 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19010A3872019-01-10010 January 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TSs to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML18360A0352018-12-21021 December 2018 NRR E-mail Capture - Brunswick Draft 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18360A0362018-12-21021 December 2018 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TSs to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML18282A1492018-10-0909 October 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18263A3042018-09-20020 September 2018 NRR E-mail Capture - Brunswick Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML18250A3082018-08-31031 August 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report ML18225A0122018-08-10010 August 2018 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18130A8262018-05-15015 May 2018 Supplemental Information Needed for Acceptance. Amendment Request to Revise the Technical Specifications to Relocate the Pressure Temperature Limit Curves to a Pressure and Temperature Limits Report ML18088A0072018-03-27027 March 2018 NRR E-mail Capture - Brunswick Units 1 & 2 Request for Additional Information - Relief Request for RPV Shell Circumferential Weld Examination (L-2018-LLR-0001) ML18071A3732018-03-12012 March 2018 NRR E-mail Capture - Correction: Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) ML18067A1032018-03-0808 March 2018 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Human Factors in the Mellla+ LAR (CACs MF8864 and MF8865, EPID: L-2016-LLA-0009) ML18010A0502018-01-0505 January 2018 E-mail Re. Brunswick Units 1 and Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) ML18010A0512018-01-0505 January 2018 Unit 2 - Request for Additional Information Related to the Mellla+ LAR (CACs MF8864 and MF8865) (Nonproprietary) ML17339A9132017-12-0505 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - Human Factors (EPID: L- 2017- LLA- 0398) ML17339A0702017-12-0404 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - Electrical Engineering (EPID: L- 2017- LLA- 0398) ML17317B0022017-12-0404 December 2017 Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MF9905 and MF9906; EPID L-2017-LLA-0242) ML17339A0732017-12-0404 December 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related the Exigent Amendment Request for One-Time Extension of EDG Completions Time - PRA (EPID: L- 2017- LLA- 0398) ML17328A4872017-11-24024 November 2017 Unit 2 - Request for Additional Information Related the Emergency Amendment Request for One-Time Extension of EDG Completions Time ML17275A2772017-10-0202 October 2017 E-mail, Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CAC Nos. MF8864 and MF8865) (Non-Proprietary) ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17082A3042017-03-0909 March 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CACs MF8864 and MF8865) ML17037A0022017-02-0303 February 2017 NRR E-mail Capture - Brunswick Unit 1 and Unit 2 Request for Additional Information Related to LAR to Modify the TS Requirements for End States Associated with the Implementation of the Approved TSTF Traveler TSTF-423-A (MF8466 and MF8467) ML16020A2632016-01-20020 January 2016 Brunswick Steam Electric Plant - Notification Of Inspection And Request For Information 2023-07-19
[Table view] |
Text
From: Hon, Andrew To: Murray, William R. (Bill) (Bill.Murray@duke-energy.com) (Bill.Murray@duke-energy.com)
Subject:
Brunswick Unit 1 and Unit 2 Request for Additional Information related Containment Accident Pressure in the MELLLA+ LAR (CACs MF8864 and MF8865) (Non-Proprietary)
Date: Monday, October 02, 2017 10:05:00 AM Attachments: BRUNSWICK 12 MELLLA PLUS - SRXB RAIs on CONTAINMENT Public.pdf In a letter dated November 18, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16343A521), Duke Energy Progress (the licensee) requested the subject amendment to Operating Licenses OLs DPR-71 and DPR-62.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is attached. The proposed questions related to containment review were discussed by telephone with your staff on September 14, 2017. Your staff confirmed that the attached request for additional information (RAI):
- 1. was understood,
- 2. the NRC staff proposed proprietary information redaction is appropriate, and
- 3. you will provide a response in 30 days after receiving this request.
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me.
Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2)
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN O8E06 Mail Stop O8B1A andrew.hon@nrc.gov
OFFICIAL USE ONLY PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION BY REACTOR SYSTEMS BRANCH MAXIMUM EXTENDED LOAD LINE LIMIT PLUS ANALYSIS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 By application dated September 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16257A410) (Reference 1), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR 50.90), Duke Energy Progress, Inc. (Duke Energy, or the licensee) submitted a License Amendment Request (LAR) proposing revisions to the Brunswick Steam Electric Plant (BSEP) Units 1 and 2 operating license. The proposed request would allow a change in the BSEP Units 1 and 2 Technical Specifications from operating in the currently licensed Maximum Extended Load Line Limit Analysis (MELLLA) domain to operating in the expanded MELLLA Plus (MELLLA+) operating domain at the currently licensed thermal power.
The Nuclear Regulatory Commission (NRC) staff has reviewed the containment related portions in Section 4.0, "Engineered Safety Features" in Enclosure 5 or M+SAR (MELLLA+ Safety Evaluation Report) (Reference 2), and Enclosure 11 (Reference 3) of the licensee's letter dated September 6, 2016 (Reference 1). In order to complete its review, the staff requests responses to the following Requests for Additional Information (RAls). Note that the response to SRXB-C-RAI 1 was received by the NRC in licensee's letter dated April 6, 2017 (ADAMS Accession No. ML17096A482). The proprietary information, pursuant to 10 CFR Section 2.390, in the RAls is identified by underlined text (in red font) enclosed within double brackets as shown here ((example proprietary text)).
SRXB-C-RAI 2 Regulatory Basis: Title 10 of the U.S. Code of Federal Regulations (10 CFR), Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 16 (i.e., GDC 16) states: "Reactor containment and associated systems shall be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require."
To assure that the containment design conditions, i.e., its design pressure and temperature are not exceeded during a Loss-of-Coolant Accident (LOCA) in the MELLLA+ operating domain, it is necessary to determine their peak values of these conditions for a bounding case.
Refer to Section 4.1.1 of the M+SAR (Reference 2); provide the list of the analyzed cases for the recirculation and main steam line break Loss-of-Coolant Accidents (LOCAs) that formed the basis for the limiting primary containment response due to a postulated LOCA as initiated from 102% power I 85% core flow) (Figure 1-1 in M+SAR (Reference 2), MELLLA+ state point N).
Include the calculated primary containment pressure and temperature results corresponding to each case analyzed in the list. Provide justification that the list is complete and no further cases are necessary to be analyzed.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION If the MELLLA+ state point Nin Figure 1-1 of M+SAR (Reference 2) does not generate the limiting primary containment temperature and pressure responses, please include the analysis cases and results from the other state points that determined the limiting case.
SRXB-C-RAI 3 Regulatory Basis: 10 CFR, Part 50, Appendix A, GDC 4 requires in part, Structures, Systems, and Components (SSCs) important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with postulated accidents, including LOCAs. These SSCs shall be appropriately protected against dynamic effects of discharging fluids that may result from equipment failures.
In order to meet the above requirement of GDC 4, it is necessary to assure that the Condensation Oscillation (CO) load, which is one of the dynamic load imposed on the containment and its internal SSCs, during a LOCA in the MELLLA+ operating domain is within the design limits and the SSCs are adequately protected.
Section 4.1.1 of M+SAR (Reference 2) under heading "Condensation Oscillation Loads" states:
The Mark I CO [Condensation Oscillation] load definition was developed from test data from Full Scale Test Facility (FSTF) tests (Reference 33 [GE Nuclear Energy, "Mark I Containment Program, Full Scale Test Program Final Report, Task Number 5.11,"
NEDE-24539-P, April 1979]) to simulate LOCA thermal-hydraulic conditions (i.e., ((
)). The tests are bounding for all US Mark I plants, including the BSEP, considering MELLLA+ conditions.
Explain why the FSTF tests results are bounding for the BSEP Units 1 and 2 LOCA CO loads in the MELLLA+ operating domain.
SRXB-C-RAI 4 Regulatory Basis: 10 CFR, Part 50, Appendix A, GDC 4 requires in part, SSCs important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with postulated accidents, including LOCAs. These SSCs shall be appropriately protected against dynamic effects of discharging fluids that may result from equipment failures.
In order to meet the above requirement of GDC 4, it is necessary to assure that the chugging load, which is one of the dynamic load imposed on the containment and its internal SSCs during a LOCA in the MELLLA+ operating domain is within the design limits and the SSCs are adequately protected.
Section 4.1.1 of M+SAR (Reference 2) under heading "Chugging Loads" states:
The thermal-hydraulic conditions for these tests ((
)) were selected to produce maximum chugging amplitudes so that it bounds all Mark I plants. Therefore, the current chugging load definitions remain applicable at MELLLA+ conditions for BSEP.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION Explain why the FSTF tests results are bounding for the BSEP Units 1 and 2 LOCA chugging loads in the MELLLA+ operating domain.
SRXB-C-RAI 5 Regulatory Basis: 10 CFR, Part 50, Appendix A, GDC 38 states in part, the containment heat removal system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any LOCA and maintain them at acceptably low levels.
To assure that the containment heat removal function is adequately performed during a design basis LOCA, the pumps that draw water from suppression pool during the LOCA should have a positive margin for the Net Positive Suction Head (NPSH). In order to determine the minimum margin, the limiting (maximum) LOCA suppression pool temperature response should be analyzed with biased inputs for calculating the available NPSH at the pump inlet using the SHEX and GOTHIC computer codes for the conservative and realistic analyses.
Refer to Enclosure 11 (Reference 3), response to SECY-11-0014 (Reference 4) Criteria 1.
(a) Confirm that the same inputs and assumptions, including containment heat sinks and their associated heat transfer coefficients, were used for the conservative suppression pool temperature response (that maximizes the temperature) analysis using GOTHIC 8.0 and SHEX. Provide justification for the differences in those cases where any of the inputs, assumptions, heat sinks and the associated heat transfer coefficients were different in the two analyses.
(b) Please identify which of the input parameters and assumptions were assumed to be different in the GOTHIC 8.0 realistic analysis from the GOTHIC 8.0 and SHEX conservative analyses.
(c) Provide the basis of the input values selected for the GOTHIC 8.0 realistic analysis.
SRXB-C-RAI 6 Regulatory Basis: 10 CFR, Part 50, Appendix A, GDC 38 states in part, the containment heat removal system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any LOCA and maintain them at acceptably low levels.
To assure that the containment heat removal function is adequately performed during a design basis LOCA, the pumps that draw water from the suppression pool during LOCA should have a positive margin for the Net Positive Suction Head (NPSH). SECY-11-0014, Enclosure 1 (Reference 4), Section 6.6.6 states it is possible that the available NPSH may be less than the required NPSH (NPSHreff). It further states that the operation in this mode is acceptable if appropriate tests are done to demonstrate that the pump will continue to perform its safety functions under the applicable conditions given in Section 6.6.6 of Reference 4.
Refer to the following statement in Enclosure 11 (Reference 3) under the heading "Design Basis LOCA" in response to SECY-11-0014 (Reference 4) Criteria 2:
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OFFICIAL USE ONLY PROPRIETARY INFORMATION However, it was found that the limiting short term (<600 sec) RHR flow (i.e. two RHR pumps delivering a total of 21, 100 gpm into a broken recirculation line) could not be maintained due to degraded NPSH margin. Input from the RHR pump manufacturer was obtained, which showed that the RHR pumps could operate at a reduced flow rate until the pumps could be throttled at 600 seconds. Since cavitation would occur during the initial 600 seconds, there is a concern of related damage. The manufacturer evaluated this condition and provided qualitative assurance the pumps could operate for this short time without damage.
Provide the pump manufacturer's input, such as test reports, including the basis for qualifying the RHR pumps to operate satisfactorily while cavitating without any damage with the short term
(<600 sec from LOCA initiation) flow rate of 21, 100 gpm.
SRXB-C-RAI 7 Regulatory Basis: 10 CFR, Part 50, Appendix A, GDC 38 states in part, the containment heat removal system safety function shall be to reduce rapidly, consistent with the functioning of other associated systems, the containment pressure and temperature following any LOCA and maintain them at acceptably low levels. To assure that the containment heat removal function is adequately performed during a design basis LOCA, the pumps that draw water from the suppression pool during LOCA should have a positive margin for the Net Positive Suction Head (NPSH). SECY-11-0014, Enclosure 1 (Reference 4), Section 6.6.9 states:
A realistic calculation of NPSHa [available NPSH] should be performed to compare with the NPSHa determined from the Monte Carlo 95/95 calculation.
Refer to the following statement in Enclosure 11 (Reference 3) under heading "Design Basis LOCA" in response to SECY-11-0014 (Reference 4) Criteria 3:
The 95/95 analysis is performed to quantify uncertainties in the containment response evaluation by randomly selecting values of critical parameters within a probable range of values.
Please justify the validity/applicability of the results of 95/95 analysis that: (a) quantified uncertainties in the containment response; and (b) the critical input parameters that were randomly selected with the basis of selection and their range of values.
REFERENCES
- 1. Letter from Duke Energy to NRC dated September 6, 2016, "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 Request for License Amendment Regarding Core Flow Operating Range Expansion," (ADAMS Accession Number ML16257A410).
- 2. Enclosure 5 of Reference 1, "Safety Analysis Report for Brunswick Steam Electric Plant Units 1 and 2 Maximum Extended Load Line Limit Analysis Plus," Proprietary (ADAMS Accession Number ML16257A413).
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- 3. Enclosure 11 of Reference 1, "SECY-11-0014 Discussion - Use of Containment Accident Pressure (CAP) in Analyzing ECCS and Containment Heat Removal System Pump Performance," (ADAMS Accession Number ML16257A411 ).
- 4. SECY 11-0014, Enclosure 1, "The Use of Containment Accident Pressure in Reactor Safety Analysis," (ADAMS Accession Number ML102110167).
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