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| | issue date = 07/24/2014 | | | issue date = 07/24/2014 |
| | title = Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (TAC Nos. ME9623 and ME9624) | | | title = Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (TAC Nos. ME9623 and ME9624) |
| | author name = Hon A L | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Hamrick G T, Murray W R | | | addressee name = Hamrick G, Murray W |
| | addressee affiliation = Duke Energy Progress, Inc | | | addressee affiliation = Duke Energy Progress, Inc |
| | docket = 05000324, 05000325 | | | docket = 05000324, 05000325 |
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| ==Dear Mr. Hamrick:== | | ==Dear Mr. Hamrick:== |
| By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12285A428), Duke Energy Progress, Inc. (the licensee) proposed to amend the operating license for the Brunswick Steam Electric Plant, Units 1 and 2, by adopting a new risk-informed based fire protection licensing basis in accordance with National Fire Protection Association Standard 805. The NRC staff has reviewed your application and responses to our request for additional information (RAI) dated June 26, 2014, ADAMS Accession No. ML 14191 A672. We determined that further information is needed to complete our evaluation of the proposed change. On July 10, 2014, the NRC staff and your representatives held a conference call to provide you with an opportunity to clarify the proposed RAI related to probabilistic risk assessment. | | By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12285A428), Duke Energy Progress, Inc. (the licensee) proposed to amend the operating license for the Brunswick Steam Electric Plant, Units 1 and 2, by adopting a new risk-informed based fire protection licensing basis in accordance with National Fire Protection Association Standard 805. The NRC staff has reviewed your application and responses to our request for additional information (RAI) dated June 26, 2014, ADAMS Accession No. ML14191A672. We determined that further information is needed to complete our evaluation of the proposed change. On July 10, 2014, the NRC staff and your representatives held a conference call to provide you with an opportunity to clarify the proposed RAI related to probabilistic risk assessment. |
| The NRC staff's finalized this set of RAis is shown below which were discussed with Mr. Bill Murray and others of your representatives on July 24, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 15, 2014. The NRC staff considers that timely responses to RAis help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | The NRC staff's finalized this set of RAis is shown below which were discussed with Mr. Bill Murray and others of your representatives on July 24, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 15, 2014. The NRC staff considers that timely responses to RAis help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08. Please also note that review efforts on this task are continuing and additional RAis may be forthcoming. | | Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08. Please also note that review efforts on this task are continuing and additional RAis may be forthcoming. |
| 1 If you have any questions regarding this letter, please contact me. Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2) Plant Licensing Branch 1/-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN08E5 Mail Stop 08G-9a andrew.hon@nrc.gov cc: Distribution via ListServ ADAMS Accession No.: ML 14205A592 REQUEST FOR ADDITIONAL INFORMATON VOLUNTARY FIRE PROTECTION RISK INITIATIVE DUKE ENERGY PROGRESS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 Probabilistic Risk Assessment (PRA) RAI 01.f.ii.03 In a letter dated June 26, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 14191 A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that to "assess the risk due to loss of control, the applicable bin-specific ignition frequency was apportioned to each ignition source in the main control room." The term "loss of control" implies to NRC staff that failure of main control room (MCR) functionality from fire-induced failures, including ones due to fires outside the MCR, leads to the need to abandon the MCR and perform alternate shutdown. | | 1 If you have any questions regarding this letter, please contact me. Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2) Plant Licensing Branch 1/-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN08E5 Mail Stop 08G-9a andrew.hon@nrc.gov cc: Distribution via ListServ ADAMS Accession No.: ML14205A592 REQUEST FOR ADDITIONAL INFORMATON VOLUNTARY FIRE PROTECTION RISK INITIATIVE DUKE ENERGY PROGRESS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 Probabilistic Risk Assessment (PRA) RAI 01.f.ii.03 In a letter dated June 26, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14191A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that to "assess the risk due to loss of control, the applicable bin-specific ignition frequency was apportioned to each ignition source in the main control room." The term "loss of control" implies to NRC staff that failure of main control room (MCR) functionality from fire-induced failures, including ones due to fires outside the MCR, leads to the need to abandon the MCR and perform alternate shutdown. |
| Given previous statements that Brunswick Steam Electric Plant (BSEP) does not credit MCR abandonment upon loss of control, please explain what the term "loss of control" means in the cited statement. | | Given previous statements that Brunswick Steam Electric Plant (BSEP) does not credit MCR abandonment upon loss of control, please explain what the term "loss of control" means in the cited statement. |
| Please confirm that loss of functionality of components, instruments, etc., in the MCR due to fires outside the MCR are included in the risk and delta-risk estimates. | | Please confirm that loss of functionality of components, instruments, etc., in the MCR due to fires outside the MCR are included in the risk and delta-risk estimates. |
| Probabilistic Risk Assessment (PRA) RAI 01.f.ii.04 In a letter dated June 26,2014 (ADAMS Accession No. ML14191A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that their "ASSD [Alternate Safe Shutdown] | | Probabilistic Risk Assessment (PRA) RAI 01.f.ii.04 In a letter dated June 26,2014 (ADAMS Accession No. ML14191A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that their "ASSD [Alternate Safe Shutdown] |
| strategy is not affected by fire-induced equipment failures in the main control room." Please confirm that BSEP's ASSD strategy and modeling of that strategy for the Fire PRA accounts for fire-induced equipment impacts in the MCR, including potential spurious operations, particularly ones that may not be "recoverable," if needed, upon transfer of control to the ASSD panel. If modeling of BSEP's ASSD strategy does not account for fire-induced MCR equipment impacts on success of ASSD, including spurious operations as cited above, then address these impacts as part of the integrated analysis performed in response to PRA RAI 23 and, to the extent applicable PRA RAI 24. PRA RAI25 2 The recent License Event Report (LEA) 14-004-00, "Fire Related Unanalyzed Condition that Could Impact Equipment Credited in Safe Shutdown Analysis," (ADAMS Accession No. ML 14149A244) stated that: On March 20, 2014, as a result of the transition process from 10 CFR 50, Appendix R, to NFPA 805, a review of the Brunswick Steam Electric Plant Safe Shutdown Analysis determined that a postulated fire in specific fire areas could disable critical components, potentially resulting in equipment required for safe shutdown being inoperable. | | strategy is not affected by fire-induced equipment failures in the main control room." Please confirm that BSEP's ASSD strategy and modeling of that strategy for the Fire PRA accounts for fire-induced equipment impacts in the MCR, including potential spurious operations, particularly ones that may not be "recoverable," if needed, upon transfer of control to the ASSD panel. If modeling of BSEP's ASSD strategy does not account for fire-induced MCR equipment impacts on success of ASSD, including spurious operations as cited above, then address these impacts as part of the integrated analysis performed in response to PRA RAI 23 and, to the extent applicable PRA RAI 24. PRA RAI25 2 The recent License Event Report (LEA) 14-004-00, "Fire Related Unanalyzed Condition that Could Impact Equipment Credited in Safe Shutdown Analysis," (ADAMS Accession No. ML14149A244) stated that: On March 20, 2014, as a result of the transition process from 10 CFR 50, Appendix R, to NFPA 805, a review of the Brunswick Steam Electric Plant Safe Shutdown Analysis determined that a postulated fire in specific fire areas could disable critical components, potentially resulting in equipment required for safe shutdown being inoperable. |
| The safety significance of this event is minimal. Deterministic analysis methods used to comply with Appendix R require every possible fire scenario to be addressed; however, the risk posed by these hypothetical events has been determined by analysis to be minimal ... This condition is being reported per 10 CFR 50.73(a)(2)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety ... The safety significance of this event is minimal. Fire watches had previously been established in affected areas prior to the time of discovery for reasons other than this event. The conditions identified here are based on hypothetical fire scenarios that have not actually occurred. | | The safety significance of this event is minimal. Deterministic analysis methods used to comply with Appendix R require every possible fire scenario to be addressed; however, the risk posed by these hypothetical events has been determined by analysis to be minimal ... This condition is being reported per 10 CFR 50.73(a)(2)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety ... The safety significance of this event is minimal. Fire watches had previously been established in affected areas prior to the time of discovery for reasons other than this event. The conditions identified here are based on hypothetical fire scenarios that have not actually occurred. |
| A probabilistic safety assessment developed to analyze this event shows that the core damage frequency (CDF) and large early release frequency (LEAF) are less than red per the significance determination process ... Applicable procedures will be revised by July 31, 2014, to prescribe the required actions for mitigating the effects of a fire in the affected areas. This represents the discovery of new fire-induced accident scenarios that may not have been modeled in the Fire PRA. a. Please explain whether the conditions described in LEA 14-004-00 could impact fire core damage frequency (CDF), large early release frequency (LEAF), change in (.1) CDF, or .1 LEAF. b. Please explain whether these conditions are currently addressed in the Fire PRA. c. If the conditions described by LEA 14-004-00 are not currently addressed in the Fire PRA, please provide justification, or update the Fire PRA to include these scenarios. | | A probabilistic safety assessment developed to analyze this event shows that the core damage frequency (CDF) and large early release frequency (LEAF) are less than red per the significance determination process ... Applicable procedures will be revised by July 31, 2014, to prescribe the required actions for mitigating the effects of a fire in the affected areas. This represents the discovery of new fire-induced accident scenarios that may not have been modeled in the Fire PRA. a. Please explain whether the conditions described in LEA 14-004-00 could impact fire core damage frequency (CDF), large early release frequency (LEAF), change in (.1) CDF, or .1 LEAF. b. Please explain whether these conditions are currently addressed in the Fire PRA. c. If the conditions described by LEA 14-004-00 are not currently addressed in the Fire PRA, please provide justification, or update the Fire PRA to include these scenarios. |
| If this update is performed prior to transition, please ensure that the responses to PRA RAI 23 and PRA RAI 24 capture the effects of the update. This request can also be addressed by an alternative sensitivity study that incorporates the anticipated effects of the model update and add an implementation item to update the model transition, including an assessment of the potential need for a focused-scope peer review if this update qualifies as a PRA "upgrade" as defined by the ASME/ANS PRA Standard. | | If this update is performed prior to transition, please ensure that the responses to PRA RAI 23 and PRA RAI 24 capture the effects of the update. This request can also be addressed by an alternative sensitivity study that incorporates the anticipated effects of the model update and add an implementation item to update the model transition, including an assessment of the potential need for a focused-scope peer review if this update qualifies as a PRA "upgrade" as defined by the ASME/ANS PRA Standard. |
| If this option is selected, please include the results of the sensitivity in the aggregate analysis described by PRA RAI 23 and, to the extent applicable PRA RAI 24. 3}} | | If this option is selected, please include the results of the sensitivity in the aggregate analysis described by PRA RAI 23 and, to the extent applicable PRA RAI 24. 3}} |
Letter Sequence RAI |
|---|
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MONTHYEARBSEP 12-0106, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2012-09-25025 September 2012
License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
Project stage: Request
ML13004A3382013-01-0808 January 2013
Acceptance for Review of License Amendment Request for NFPA Standard 805 (TAC Nos. ME9623 and Me9624)
Project stage: Acceptance Review
ML13123A2312013-05-15015 May 2013
Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: RAI
ML13141A6222013-05-23023 May 2013
RAI Re. Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051)
Project stage: RAI
BSEP 13-0066, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052013-06-28028 June 2013
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Response to RAI
BSEP 13-0070, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052013-07-15015 July 2013
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Response to RAI
ML14079A2372013-07-16016 July 2013
Fourth Quarter 2011 Fire Protection Program Health Report, Enclosure 5
Project stage: Other
ML14079A2382013-07-16016 July 2013
Fourth Quarter 2012 Fire Protection Program Health Report, Enclosure 6
Project stage: Other
BSEP 13-0083, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052013-07-31031 July 2013
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Response to RAI
ML13246A2772013-08-28028 August 2013
Enclosure 3 - Revised Brunswick NFPA 805 Transition Report, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, Transition Report, August
Project stage: Other
BSEP 13-0097, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard (NFPA) 8052013-08-29029 August 2013
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard (NFPA) 805
Project stage: Response to RAI
ML13277A0412013-09-19019 September 2013
Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition
Project stage: Other
BSEP 13-0107, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard (NFPA) 805 (NRC TAC Nos. ME9623 and ME9624)2013-09-30030 September 2013
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard (NFPA) 805 (NRC TAC Nos. ME9623 and ME9624)
Project stage: Response to RAI
ML14079A2352014-01-0909 January 2014
FIR-NGGC-0009, NFPA 805 Transient Combustibles and Ignition Source Controls Program, Enclosure 3
Project stage: Other
ML13365A3202014-01-14014 January 2014
Second Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: RAI
ML14079A2362014-01-24024 January 2014
Fourth Quarter 2013 Fire Protection Program Health Report, Enclosure 4
Project stage: Other
ML14028A1782014-02-12012 February 2014
Second Set of Probabilistic Risk Assessment Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: RAI
BSEP 14-0023, Response to Second Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)2014-02-28028 February 2014
Response to Second Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)
Project stage: Request
BSEP 14-0029, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052014-03-14014 March 2014
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Response to RAI
BSEP 14-0035, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052014-04-10010 April 2014
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Response to RAI
ML14079A2342014-04-30030 April 2014
BNP-PSA-086, Bnp Fire PRA - Fire Scenario Data, Enclosure 2, Attachment 25
Project stage: Other
ML14155A2092014-06-0404 June 2014
E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: RAI
BSEP 14-0076, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)2014-06-26026 June 2014
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)
Project stage: Response to RAI
ML14205A5922014-07-24024 July 2014
Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (TAC Nos. ME9623 and ME9624)
Project stage: RAI
ML14220A2132014-08-0808 August 2014
E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: RAI
BSEP 14-0092, Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC ME9623 and ME9624)2014-08-15015 August 2014
Response to Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC ME9623 and ME9624)
Project stage: Response to RAI
BSEP 14-0100, Response to Request Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 8052014-08-29029 August 2014
Response to Request Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Other
ML14297A2662014-10-24024 October 2014
Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14
Project stage: Other
BSEP 14-0122, Additional Information Regarding License Amendment Request to Adopt Voluntary Risk Initiative National Fire Protection Association Standard 8052014-11-20020 November 2014
Additional Information Regarding License Amendment Request to Adopt Voluntary Risk Initiative National Fire Protection Association Standard 805
Project stage: Request
BSEP 14-0134, Additional Information Regarding License Amendment Request to Adopt Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)2014-12-18018 December 2014
Additional Information Regarding License Amendment Request to Adopt Voluntary Risk Initiative National Fire Protection Association Standard 805 (NRC TAC Nos. ME9623 and ME9624)
Project stage: Request
ML14310A8082015-01-28028 January 2015
Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(C)
Project stage: Approval
2014-01-09
[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
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)
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
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
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
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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Text
From: Sent: To: Cc:
Subject:
Hon, Andrew Thursday, July 24, 2014 3:10 PM Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com)
Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Hamzehee, Hossein BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION REGARDING VOLUNTARY RISK INITIATIVE NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME9623 AND ME9624) Mr. George T. Hamrick, Vice President Brunswick Steam Electric Plant Duke Energy Progress, Inc. Post Office Box 1 0429 Southport, North Carolina 28461
Dear Mr. Hamrick:
By letter dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12285A428), Duke Energy Progress, Inc. (the licensee) proposed to amend the operating license for the Brunswick Steam Electric Plant, Units 1 and 2, by adopting a new risk-informed based fire protection licensing basis in accordance with National Fire Protection Association Standard 805. The NRC staff has reviewed your application and responses to our request for additional information (RAI) dated June 26, 2014, ADAMS Accession No. ML14191A672. We determined that further information is needed to complete our evaluation of the proposed change. On July 10, 2014, the NRC staff and your representatives held a conference call to provide you with an opportunity to clarify the proposed RAI related to probabilistic risk assessment.
The NRC staff's finalized this set of RAis is shown below which were discussed with Mr. Bill Murray and others of your representatives on July 24, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 15, 2014. The NRC staff considers that timely responses to RAis help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08. Please also note that review efforts on this task are continuing and additional RAis may be forthcoming.
1 If you have any questions regarding this letter, please contact me. Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2) Plant Licensing Branch 1/-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN08E5 Mail Stop 08G-9a andrew.hon@nrc.gov cc: Distribution via ListServ ADAMS Accession No.: ML14205A592 REQUEST FOR ADDITIONAL INFORMATON VOLUNTARY FIRE PROTECTION RISK INITIATIVE DUKE ENERGY PROGRESS BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 Probabilistic Risk Assessment (PRA) RAI 01.f.ii.03 In a letter dated June 26, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14191A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that to "assess the risk due to loss of control, the applicable bin-specific ignition frequency was apportioned to each ignition source in the main control room." The term "loss of control" implies to NRC staff that failure of main control room (MCR) functionality from fire-induced failures, including ones due to fires outside the MCR, leads to the need to abandon the MCR and perform alternate shutdown.
Given previous statements that Brunswick Steam Electric Plant (BSEP) does not credit MCR abandonment upon loss of control, please explain what the term "loss of control" means in the cited statement.
Please confirm that loss of functionality of components, instruments, etc., in the MCR due to fires outside the MCR are included in the risk and delta-risk estimates.
Probabilistic Risk Assessment (PRA) RAI 01.f.ii.04 In a letter dated June 26,2014 (ADAMS Accession No. ML14191A672) the licensee responded to PRA RAI 01.f.ii.02 and stated that their "ASSD [Alternate Safe Shutdown]
strategy is not affected by fire-induced equipment failures in the main control room." Please confirm that BSEP's ASSD strategy and modeling of that strategy for the Fire PRA accounts for fire-induced equipment impacts in the MCR, including potential spurious operations, particularly ones that may not be "recoverable," if needed, upon transfer of control to the ASSD panel. If modeling of BSEP's ASSD strategy does not account for fire-induced MCR equipment impacts on success of ASSD, including spurious operations as cited above, then address these impacts as part of the integrated analysis performed in response to PRA RAI 23 and, to the extent applicable PRA RAI 24. PRA RAI25 2 The recent License Event Report (LEA) 14-004-00, "Fire Related Unanalyzed Condition that Could Impact Equipment Credited in Safe Shutdown Analysis," (ADAMS Accession No. ML14149A244) stated that: On March 20, 2014, as a result of the transition process from 10 CFR 50, Appendix R, to NFPA 805, a review of the Brunswick Steam Electric Plant Safe Shutdown Analysis determined that a postulated fire in specific fire areas could disable critical components, potentially resulting in equipment required for safe shutdown being inoperable.
The safety significance of this event is minimal. Deterministic analysis methods used to comply with Appendix R require every possible fire scenario to be addressed; however, the risk posed by these hypothetical events has been determined by analysis to be minimal ... This condition is being reported per 10 CFR 50.73(a)(2)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety ... The safety significance of this event is minimal. Fire watches had previously been established in affected areas prior to the time of discovery for reasons other than this event. The conditions identified here are based on hypothetical fire scenarios that have not actually occurred.
A probabilistic safety assessment developed to analyze this event shows that the core damage frequency (CDF) and large early release frequency (LEAF) are less than red per the significance determination process ... Applicable procedures will be revised by July 31, 2014, to prescribe the required actions for mitigating the effects of a fire in the affected areas. This represents the discovery of new fire-induced accident scenarios that may not have been modeled in the Fire PRA. a. Please explain whether the conditions described in LEA 14-004-00 could impact fire core damage frequency (CDF), large early release frequency (LEAF), change in (.1) CDF, or .1 LEAF. b. Please explain whether these conditions are currently addressed in the Fire PRA. c. If the conditions described by LEA 14-004-00 are not currently addressed in the Fire PRA, please provide justification, or update the Fire PRA to include these scenarios.
If this update is performed prior to transition, please ensure that the responses to PRA RAI 23 and PRA RAI 24 capture the effects of the update. This request can also be addressed by an alternative sensitivity study that incorporates the anticipated effects of the model update and add an implementation item to update the model transition, including an assessment of the potential need for a focused-scope peer review if this update qualifies as a PRA "upgrade" as defined by the ASME/ANS PRA Standard.
If this option is selected, please include the results of the sensitivity in the aggregate analysis described by PRA RAI 23 and, to the extent applicable PRA RAI 24. 3
