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| | number = ML14220A213 | | | number = ML14220A213 |
| | issue date = 08/08/2014 | | | issue date = 08/08/2014 |
| | title = Brunswick Steam Electric Plant, Units 1 and 2 - E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 (TAC ME9623 and ME9624) | | | title = E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 |
| | author name = Hon A | | | 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, 05000327, 05000328 | | | docket = 05000324, 05000325, 05000327, 05000328 |
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| | page count = 2 | | | page count = 2 |
| | project = TAC:ME9623, TAC:ME9624 | | | project = TAC:ME9623, TAC:ME9624 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Hon, Andrew From: Sent: To: Cc: Subject: Han, Andrew Friday, August 08, 2014 11:11 AM Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com) Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Jimenez, Manuel 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. 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 determined that further information is needed to complete our evaluation of the proposed change. On July 16, 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 of your representatives on August 6, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 29, 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 1 0 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 14220A213 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 Radiation Release RAI 02.01 For the outside areas listed in Attachment E where radioactive materials may be stored, please provide the following information: a. Identify the type of container used (e.g., sea land type containers) to store the radioactive material. b. Describe the administrative controls that limit the amount of activity which may be present in these containers. c. Provide a bounding calculation that demonstrates that the radioactive releases from a fire in a container stored in outside areas will not exceed the applicable 10 CFR Part 20 limits. The analysis should include the assumptions, a summary of the methodology and calculations, and resulting doses. d. Provide any administrative controls that will be used to control the release of liquids which may become contaminated from fire-fighting activities. 2 | | {{#Wiki_filter:Hon, Andrew From: Han, Andrew Sent: Friday, August 08, 2014 11:11 AM To: Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com) |
| }} | | Cc: Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Jimenez, Manuel |
| | |
| | ==Subject:== |
| | 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 10429 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 performance-based fire protection licensing basis in accordance with National Fire Protection Association Standard 805. |
| | The NRC staff has reviewed your application and determined that further information is needed to complete our evaluation of the proposed change. |
| | On July 16, 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 of your representatives on August 6, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 29, 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.: ML14220A213 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 Radiation Release RAI 02.01 For the outside areas listed in Attachment E where radioactive materials may be stored, please provide the following information: |
| | : a. Identify the type of container used (e.g., sea land type containers) to store the radioactive material. |
| | : b. Describe the administrative controls that limit the amount of activity which may be present in these containers. |
| | : c. Provide a bounding calculation that demonstrates that the radioactive releases from a fire in a container stored in outside areas will not exceed the applicable 10 CFR Part 20 limits. The analysis should include the assumptions, a summary of the methodology and calculations, and resulting doses. |
| | : d. Provide any administrative controls that will be used to control the release of liquids which may become contaminated from fire-fighting activities. |
| | 2}} |
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
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Category:E-Mail
MONTHYEARML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24128A1802024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review for Sequoyah License Amendment Request to Modify TS 3.8.1 and TS 3.8.2 (L-2024-LLA-0047) ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24074A4252024-03-14014 March 2024 NRR E-mail Capture - Sequoyah Hydrologic Analysis License Amendment Request - Notification of Change to Estimated Completion and Hours ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24059A4052024-02-28028 February 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02 ML24053A0302024-02-21021 February 2024 NRR E-mail Capture - Request for Steam Generator (SG) Tube Inspection Call for Sequoyah, Unit 1 ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 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 ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) 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) ML23165A2862023-06-14014 June 2023 Tennessee Multi-Sector Permit (Tmsp), 2023 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, SW-17, SW-18, SW-19, and SW-21 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 ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23046A3552023-02-15015 February 2023 Annual Water Withdrawal Report 2022 ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23019A3442023-01-19019 January 2023 Tennessee Multi-Sector Permit (Tmsp), 2022 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, and SW-19 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) 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 ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22348A0432022-11-28028 November 2022 NRR E-mail Capture - State Consultation - Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Modify the Approved 10 CFR 50.69 Categorization Process (L-2022-LLA-0033) 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) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22196A0732022-07-15015 July 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - TSTF-505 RICT (L-2021-LLA-0145) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 2024-06-24
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation 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) ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions 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 ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22192A0862022-07-12012 July 2022 RQ Inspection Notification Letter ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans 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 ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment 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 ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information 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) 2024-05-31
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Hon, Andrew From: Han, Andrew Sent: Friday, August 08, 2014 11:11 AM To: Murray, William R. (Bill) (Biii.Murray@duke-energy.com) (Biii.Murray@duke-energy.com)
Cc: Fields, Leslie; Wall, Scott; Miller, Barry; Regner, Lisa; Wall, Scott; Jimenez, Manuel
Subject:
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 10429 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 performance-based fire protection licensing basis in accordance with National Fire Protection Association Standard 805.
The NRC staff has reviewed your application and determined that further information is needed to complete our evaluation of the proposed change.
On July 16, 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 of your representatives on August 6, 2014, to confirm that these RAis do not contain sensitive information that should be withheld from the public and you would respond by August 29, 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.
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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.: ML14220A213 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 Radiation Release RAI 02.01 For the outside areas listed in Attachment E where radioactive materials may be stored, please provide the following information:
- a. Identify the type of container used (e.g., sea land type containers) to store the radioactive material.
- b. Describe the administrative controls that limit the amount of activity which may be present in these containers.
- c. Provide a bounding calculation that demonstrates that the radioactive releases from a fire in a container stored in outside areas will not exceed the applicable 10 CFR Part 20 limits. The analysis should include the assumptions, a summary of the methodology and calculations, and resulting doses.
- d. Provide any administrative controls that will be used to control the release of liquids which may become contaminated from fire-fighting activities.
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