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| | number = ML17082A304 | | | number = ML17082A304 |
| | issue date = 03/09/2017 | | | issue date = 03/09/2017 |
| | title = Unit 2 Request for Additional Information Related Containment Accident Pressure in the Mellla+ LAR (CACs MF8864 and MF8865) | | | title = 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) |
| | author name = Hon A | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
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| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | project = | | | project = CAC:MF8864 |
| | stage = RAI | | | stage = RAI |
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Letter Sequence RAI |
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CAC:MF8864, 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
[Table View] |
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Category:E-Mail
MONTHYEARML24249A1362024-09-0404 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 ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML23248A2612023-09-0505 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 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 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 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 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) 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) ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2024-09-04
[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
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NRR-PMDAPEm Resource From: Hon, Andrew Sent: Thursday, March 09, 2017 1:25 PM 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)
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 addressed below. The proposed questions were discussed by telephone with your staff on March 8, 2017. Your staff confirmed that request for additional information (RAI) was understood and did not include proprietary or security-related information, and agreed to provide a response in 30 days of 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 O8H19 Mail Stop O8G-9a andrew.hon@nrc.gov The requests for additional information are provided below:
SRXB-C-RAI-1 Regulatory Basis 10 CFR 50 Appendix A, Criterion 38, Containment heat removal
Background
Reference 2 states that the Brunswick Steam Electric Plant (BSEP) Units 1 and 2 depend on the Containment Accident Pressure (CAP) developed during postulated accidents for assuring a positive Net Positive Suction Head (NPSH) margin for the Emergency Core Cooling System (ECCS) and the containment heat removal system pumps. In a letter dated May 31, 2002, the Nuclear Regulatory Commission (NRC) staff Safety Evaluation Report (SER) for the Extended Power Uprate (EPU) for BSEP, Units 1 and 2 (i.e., Amendment No.
1
222 to Facility Operating License No. DPR-71 and Amendment No. 247 to Facility Operating License No. DPR-
- 62) approved use of CAP of up to 5.0 psig for NPSH requirements from the available post-LOCA containment pressure of 11.3 psig at EPU conditions. Subsequent to issuance of the SER for EPU, the NRC staff issued SECY-11-0014 (Reference 7) for addressing the Advisory Committee for Reactor Safeguards (ACRS) concerns for the use of CAP. Enclosure 1, (Reference 8) of SECY-11-0014, Section 6.0 provides staff guidance on the use of CAP in determining the NPSH margins of ECCS and containment heat removal system pumps.
Requested additional information:
Since the BSEP Units 1 and 2 use CAP for assuring positive NPSH margins for the ECCS and the containment heat removal system pumps, the guidance in SECY-11-0014 is applicable for quantifying NPSH margins and supersedes the previously approved use of CAP in which the margins were not quantified. Sections 6.6.3 and Section 6.6.9 of Enclosure 1 (Reference 8) of SECY-11-0014 states:
A 95/95 lower tolerance limit should be used to calculate the containment accident pressure used to determine the NPSHa [NPSH available].
A realistic calculation of NPSHa should be performed to compare with the NPSHa determined from the Monte Carlo 95/95 calculation.
The licensee has not addressed Section 6.6.3 and 6.6.9 of Enclosure 1 (Reference 8) of SECY-11-0014.
Specifically, the statistical analysis proposed by the Boiling Water Reactor Owners Group (BWROG) described in References 3 and 4, approved by NRC in Reference 5 and 6, has not been performed by the licensee to demonstrate and quantify NPSH margin for the postulated design basis Loss of Coolant Accident (LOCA) in the Analysis of Record (AOR). Please provide the statistical analysis as described in Reference 4 to satisfactorily address the criteria in Sections 6.6.3 and 6.6.9 in Reference 8.
The licensee may note the Monticello EPU and Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
CAP document (Reference 9) as a precedent which addressed all criteria of Section 6.6 of Reference 8 including performing the statistical analysis described in Sections 6.6.3 and 6.6.9.
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 11 to 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)
- 3. BWROG letter to NRC dated November 21, 2014, Submittal of Revised BWROG Topical Reports NEDC-33347P Revision 1 (Proprietary Version) and NEDO-33347 Revision 1 (Non-Proprietary Version), "Containment Overpressure Credit for Net Positive Suction Head (NPSH), (ADAMS Accession number ML14325A626)
- 4. Attachment 1 to Reference 1, NEDC-33347P Revision 1 Proprietary Version Containment Overpressure Credit for Net Positive Suction Head (NPSH), (ADAMS Accession Number ML14325A625)
- 5. Letter from NRC to BWROG dated December 21, 2016, Final Safety Evaluation for Boiling Water Reactor Owners Group Topical Report NEDC-33347P/NEDO-33347, Revision 1, Containment Overpressure Credit for Net Positive Suction Head (NPSH) (CAC No. Mf6708), (ADAMS Accession Number ML16351A176) 2
- 6. Enclosure to Reference 5, U.S. Nuclear Regulatory Commission Final Safety Evaluation for Topical Report NEDC-33347P/NEDO-33347, Revision 1, Containment Overpressure Credit For Net Positive Suction Head (NPSH) CAC NO. MF6708, (ADAMS Accession Number ML16351A179)
- 7. SECY 11-0014, Use of Containment Accident Pressure in Analyzing Emergency Core Cooling System and Containment Heat Removal System Pump Performance in Postulated Accidents, (ADAMS Accession Number ML1025901961)
- 8. Enclosure 1 to SECY-11-0014, The Use of Containment Accident Pressure in Reactor Safety Analysis ADAMS ML102110167, (ADAMS Accession Number ML102110167)
- 9. Letter from Northern States Power Company to NRC dated September 28, 2012, Monticello Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests:
Supplement to Address SECY 11-0014 Use of Containment Accident Pressure (TAC Nos. MD9990 and ME3145),(ADAMS Accession Number ML12276A057) 3
Hearing Identifier: NRR_PMDA Email Number: 3414 Mail Envelope Properties (Andrew.Hon@nrc.gov20170309132400)
Subject:
Brunswick Unit 1 and Unit 2 Request for Additional Information related Containment Accident Pressure in the MELLLA+ LAR (CACs MF8864 and MF8865)
Sent Date: 3/9/2017 1:24:58 PM Received Date: 3/9/2017 1:24:00 PM From: Hon, Andrew Created By: Andrew.Hon@nrc.gov Recipients:
"Murray, William R. (Bill) (Bill.Murray@duke-energy.com) (Bill.Murray@duke-energy.com)"
<Bill.Murray@duke-energy.com>
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