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MONTHYEARRNP-RA/14-0134, Response (90-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052014-12-22022 December 2014 Response (90-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 Project stage: Request RNP-RA/15-0023, Response (60-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052015-03-16016 March 2015 Response (60-Day) to Request for Additional Information Associated with License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 Project stage: Request RNP-RA/15-0071, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2015-07-31031 July 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Project stage: Response to RAI ML15281A1982015-11-10010 November 2015 Summary of Meeting with Duke Energy Progress Inc., to Discuss the H. B. Robinson Steam Electric Plant Unit No. 2, License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Meeting ML15343A0712015-12-23023 December 2015 September 22-26, 2014, Summary of H. B. Robinson Steam Electric Plant, Unit 2 - Audit Associated with License Amendment Request to Transition to the National Fire Protection Association 805 Standard Project stage: Other ML15342A2052016-01-0808 January 2016 Regulatory Audit in Support of License Amendment Request to Adopt NFPA 805 Project stage: Other ML16048A3492016-03-0202 March 2016 RAI Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants Project stage: RAI RNP-RA/16-0017, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-03-16016 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Project stage: Response to RAI ML16158A0062016-05-25025 May 2016 Response to Request for Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Pages 1-21 Project stage: Response to RAI RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 Project stage: Request ML16230A2342016-07-25025 July 2016 Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Project stage: Response to RAI ML16337A2642017-02-0303 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard 805 Project stage: Approval 2016-01-08
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Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22125A1942022-05-12012 May 2022 Request for Withholding Information from Public Disclosure for H.B. Robinson Steam Electric Plant, Unit 2 IR 05000261/20220012022-05-0202 May 2022 Integrated Inspection Report 05000261/2022001 IR 05000261/20224012022-04-19019 April 2022 Security Baseline Inspection Report 05000261/2022401 ML22098A2262022-04-11011 April 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22083A0032022-03-29029 March 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System IR 05000261/20210062022-03-0202 March 2022 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 (Report No. 05000261/2021006) 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 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) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1312020-12-18018 December 2020 2021 Hbr 50.59 Info 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) ML20191A2122020-07-0909 July 2020 012 FPTI Notification Letter ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20022A1942020-01-22022 January 2020 Emergency Preparedness Program Inspection Request for Information ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19288A2462019-09-26026 September 2019 Request for Additional Information Regarding Change to Surveillance Requirement 3.8.2.1 H.B. Robinson Unit No. 2 ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19072A0292019-03-13013 March 2019 50.69 LAR RAIs ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18291A6442018-10-17017 October 2018 NRR E-mail Capture - Robinson RAIs - Duke Energy 10 CFR 50.46 Annual Report ML18288A0192018-10-12012 October 2018 NRR E-mail Capture - Robinson RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18274A2632018-09-28028 September 2018 NRR E-mail Capture - Robinson Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18211A6042018-07-30030 July 2018 NRR E-mail Capture - Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L-2017-LLA-0308) ML18206B0612018-07-25025 July 2018 NRR E-mail Capture - Draft Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7592018-04-18018 April 2018 NRR E-mail Capture - Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18102B0812018-04-12012 April 2018 NRR E-mail Capture - Draft Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18074A0052018-03-15015 March 2018 Heat Sink Emailed Heat Sink RFI Request 2018 ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17248A0182017-08-31031 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17235A2612017-08-22022 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17114A0462017-04-21021 April 2017 Notification of Inspection and Request for Information ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16130A5982016-05-0505 May 2016 Notification of Inspection and Request for Information ML16048A3492016-03-0202 March 2016 RAI Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML16019A0532016-02-0808 February 2016 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals ML16026A0512016-01-25025 January 2016 Robinson EP RFI 2016-001 ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) ML15215A6512015-08-10010 August 2015 Duke Energy Progress, Inc., for H. B. Robinson, Unit 2 and Shearon Harris, Unit 1, Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 (TAC Nos. MF5872 ML15009A3352015-01-0808 January 2015 Requalification Program Inspection - H.B. Robinson Nuclear Plant RNP-RA/14-0118, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes2014-11-12012 November 2014 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes ML14268A5162014-10-23023 October 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-evaluation Related to Southeastern Catalog Changes ML14057A6502014-02-26026 February 2014 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 2024-01-02
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard Michael Glover Site Vice President H. B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, SC 29550 IY13rdl 2, 2016
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS" (CAC NO. MF2746)
Dear Mr. Glover:
By letter dated September 16, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13267 A211 ), Duke Energy Progress, Inc., (the licensee) submitted a license amendment request (LAR) for H. B. Robinson Steam Electric Plant Unit No. 2 (Robinson). This LAR would adopt a new fire protection licensing basis that complies with the requirements of Title 10 of the Code of Federal Regulations, Sections 50.48(a) and (c); the guidance in Regulatory Guide 1.205, Revision 1, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants"; and National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" (2001 Edition). By letter dated July 31, 2015 (ADAMS Accession No. ML 15212A 136), the licensee provided a response to a staff request for additional information (RAI). The NRC staff has determined that additional information is needed to complete its review related to probabilistic risk assessment (PRA). The enclosed RAls were e-mailed to the licensee in draft form on November 20, 2015 (ADAMS Accession No. ML 15324A328). An RAI clarification call was held on December 7, 2015. The NRC staff also held an onsite audit February 9 -10, 2016, to establish a proposed resolution of outstanding issues associated with the Robinson NFPA 805 review, including the the attached RAls. The audit plan, dated January 8, 2016, is available at ADAMS Accession No. ML 15342A205. During the audit, the licensee agreed to a schedule for providing RAI responses. By March 18, 2016, the licensee will provide responses to PR.A RAls 03.b.01, 05.c.01, and 30.02 and revised responses to FM RAI 01.b.01.02 and PRA RAls 1.c, 18.01, 23.a, 24.01, 24.b, and 24.c. By May 27, 2016, the licensee will provide responses to PRA RAls 03 and 16.01.01 and a revised response to PRA RAI 15.01.01.01. The licensee will also update the LAR submittal and R. Glover -:2 -Attachments C, G, H, J, M, S, V, and W, as applicable, by this date. The NRC staff agreed with these dates. If you have any questions, please contact me at 301-415-2760 or Martha.Barillas@nrc.gov. Docket No. 50-261
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS" DUKE ENERGY PROGRESS. INC. H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 DOCKET NO. 50-261 Probabilistic Risk Assessment (PRA) Request for Additional Information (RAI) 03.b.01 Confirm and modify as necessary the information in the following table that summarizes the resolution of the referenced RAls as requested in PRA RAI 03.b (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14289A260). The following table includes (1) RAls referenced by PRA RAI 03, (2) RAls added based on the RAI responses, and (3) applicable follow-up RAls. The "Reference" column refers to the date of the RAI response. As PRA RAI 03.b.01 is a supplement to PRA 03.b, a combined response to PRA RAI 03.b and PRA RAI 03.b.01 may be designated PRA RAI 03.b.01. Note that the resolution of some referenced RAls includes performing confirmatory sensitivity analyses demonstrating that an issue is negligible with respect to transition or additional changes to the PRA should be proposed. In performing such sensitivity studies, synergistic impacts, as described in PRA RAI 03.b, must also be addressed. If the results of the sensitivity study cannot demonstrate that the associated issue is also negligible with respect to future self-approval, then provide an implementation item that resolves the unacceptable method. These sensitivity analyses are identified with PRA RAI 01.c, PRA RAI 02.c, and PRA RAI 15.01.01. RAI Reference* Resolution of referenced RAI in PRA PRA RAI 01.a January 22, 2015 RAI associated with Facts and Observations (F&Os) CF-A2-01 and FSS-E1-01. A description of what was done for addressing state of knowledge in the response to PRA RAI 03 should be provided. If mean values will not be generated post-transition, the response to PRA RAI 03 should also clarify how parametric uncertainty, including the state-of-knowledge correlation, will be addressed in the self-approval evaluation of post-transition changes. PRA RAI 01.b March 16, 2015 RAI associated with F&O CS-A 1-01. No change to PRA methods. Confirm PRA is updated consistent with referenced RAI response. Enclosure PRA RAI 01.c December 22, 2014 RAI associated with F&Os CS-A 11-01 and FSS-E4-01. Describe and complete the confirmatory sensitivity analysis. PRA RAI 01.g March 16, 2015 RAI associated with F&O FSS-C7-01. No change to PRA methods. PRA RAI 01.h December 22, 2014 RAI associated with F&Os FSS-D7-01 and FSS-F3-02. No change to PRA methods. PRA RAI 01.i RAI associated with F&O FSS-G1-01. No change March 16, 2015 to PRA methods. PRA RAI 01.j RAI associated with FSS-G6-02. No change to March 16, 2015 PRA methods. PRA RAI 01.k.01 July 31, 2015 RAI associated with MCR abandonment methods. No change to PRA methods. PRA RAI 02.a March 16, 2015 RAI associated with F&O IE-C3-01. No change to PRA methods. Confirm PRA is updated consistent with RAI response. PRA RAI 02.c March 16, 2015 RAI associated with F&O LE-E1-01. Describe and complete the confirmatory sensitivity analysis. PRA RAI 04 March 16, 2015 See PRA RAls 05, 06, 11, 14, 16 and 18 as well as associated follow-up RAls: 05.a.01, 05.c.01, 06.01, 16.01, 16.02 and 18.01. Two issues are under review (refer to PRA RAls 05.c.01.01 and 16.01.01). PRA RAI 05.a March 16, 2015 No change to PRA methods. PRA RAI 05.a.01 April 1, 2015 RAI associated with Frequently Asked Question (FAQ) 14-0009 guidance. No change to PRA methods. PRA RAI 05.b March 16, 2015 RAI associated with NUREG/CR-6850, "EPRl/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology," September 2005 (ADAMS Accession No. ML052580118) and FAQ 08-0042 guidance. Confirm PRA method is changed consistent with the referenced RAI response. PRA RAI 05.c March 16, 2015 RAI associated with FAQ 14-0009 guidance. No change to PRA methods with regard to motor control centers (MCCs). Confirm methodology is consistent with final FAQ 14-0009. For non-MCC cabinets, see PRA RAI 05.c.01. PRA RAI 05.c.01 July 31, 2015 RAI associated with NUREG/CR-6850 guidance and the inapplicability of FAQ 14-0009 guidance. This issue is under evaluation (refer to PRA RAI 05.c.01.01 ). PRA RAI 06 January 22, 2015 RAI associated with FAQ 13-0004 guidance. Confirm PRA method is changed consistent with the referenced RAI response.
PRA RAI 06.01 July 31, 2015 RAI associated with sensitive electronics outside of FAQ 13-0004 guidance. Confirm PRA method is changed consistent with the referenced RAI response. PRA RAI 07 March 16, 2015 No change to PRA methods. PRA RAI 10 January 22, 2015 RAI associated with FAQ 13-0006 guidance. Confirm PRA method is changed consistent with FAQ 13-0006 guidance (as suggested by the referenced RAI response). PRA RAI 11 March 16, 2015 No chanoe to PRA methods. PRA RAIS 12 and January 22, 2015, RAI associated with guidance in Supplement 1 to 12.01 and NUREG/CR-6850. Confirm PRA method is July 31, 2015 changed consistent with the referenced RAI responses. PRA RAI 14 December 22, 2014 RAI associated with Volume 2 of NUREG/CR-7150, "Joint Assessment of Cable Damage and Quantification of Effects from Fire," May 2014 (ADAMS Accession No. ML 14141A129) guidance. Confirm PRA method is changed consistent with the referenced RAI response. PRA RAls 15, March 16, 2015, RAI related to fire probabilistic risk assessment 15.01, and April 1, 2015, and (FPRA) modeling associated with the lack of 15.01.01 July 31, 2015 breaker coordination. Consistent with the response to Part (a) of PRA RAI 15.01.01, PRA method is changed. This issue is still under evaluation (refer to PRA RA 15.01.01.01 ). Describe and complete any confirmatory sensitivity analysis. PRA RAI 16 January 22, 2015 No change to PRA methods with regard to in-cabinet incipient detection credit. For area-wide and main control room (MCR) incipient detection credit, see PRA RAls 16.01 and 16.02, respectively. PRA RAI 16.01 July 31, 2015 RAI associated with area-wide incipient detection credit. This issue is still under evaluation (refer to PRA RAI 16.01.01). Describe and complete any confirmatory sensitivity analysis. PRA RAI 16.02 July 31, 2015 RAI associated with MCR incipient detection credit. Confirm PRA method is changed consistent with the referenced RAI response. PRA RAls 18 and March 16, 2015, and No change to PRA methods. 18.01 April 1, 2015 PRA RAI 19 March 16, 2015 No change to PRA methods. PRA RAI 26 March 16, 2015 No chanoe to PRA methods. PRA RAI 29 December 22, 2014 RAI associated with FAQ 09-0057 guidance. No change to PRA methods. Confirm PRA is updated consistent with RAI response.
PRA RAIS 30 and March 16, 2015, and RAI associated with Reactor Coolant Pump (RCP) 30.01 July 31, 2015 Shutdown Seals (SDS). Confirm PRA used in support of the License Amendment Request (LAR) is consistent with the response to PRA RAI 30 and PRA used in support of self-approval will be updated consistent with the implementation item proposed in the response to PRA RAI 30.01. PRA RAI 34 March 16, 2015 RAI associated with use of fire ignition frequencies from Supplement 1 to NUREG/CR-6850. Sensitivity analysis required. The results of the sensitivity study, which were requested in PRA RAI 34 but not provided in the March 16, 2015 letter, are to be included in the response to PRA RAI 03. Fire Modeling (FM) July 31, 2015 RAI associated with fire propagation and zone of RAI 01.b.01.01 influence modeling changes to be updated in the FPRA. Describe and confirm the fire modeling update for the FPRA consistent with the RAI response. FM RAI 01.b.01.02 July 31, 2015 RAI associated with a fire modeling method related to hot gas layer. Confirm that the acceptable method described in the supplement to FM RAI 01.b.01.02 and any follow-on FM RAls is included in the response to PRA RAI 03. *ADAMS Nos. associated with RAI Responses in Table December 22, 2014 -ADAMS Accession No. ML 15005A073 January 22, 2015 -ADAMS Accession No. ML 15036A059 March 16, 2015 -ADAMS Accession No. ML 15079A025 April 1, 2015 -ADAMS Accession No. ML 15099A454 July 31, 2015-ADAMS Accession No. ML 15212A136 PRA RAI 05.c.01.01 The response to PRA RAI 05.c.01 (ADAMS Accession No. ML 15079A025) states that the treatment of well-sealed and robustly secured cabinets that are not MCCs is consistent with NUREG/CR-6850, as clarified by FAQ 08-0042. The response does not, however, appear to address the statement in Chapter 6 of NUREG/CR-6850 that indicates that for cabinets housing circuits of above 440 Volts (V), "an arcing fault could compromise panel integrity (an arcing fault could burn through the panel sides, but this should not be confused with the high energy arcing fault type fires)." Justify the Fire PRA's (FPRA's) treatment of such arcing faults for well-sealed and robustly secured cabinets that are not MCCs and that operate at 440V or greater.
i--,) -PRA RAI 15.01.01.01 PRA RAI 15 (ADAMS Accession No. ML 14289A260) requested information about how inadequate breaker fuse coordination was accounted for in the FPRA. The response to PRA RAI 15 (ADAMS Accession No. ML 15079A.025) did not mention secondary fires. PRA RAI 15.01 (ADAMS Accession No. ML 15057 A403) requested clarification about how ignition of cables (secondary fires) is addressed and will be modeled in the FPRA. The response to PRA RAI 15.01 (ADAMS Accession No. ML 15099A454) stated that the FPRA does not "currently" model these secondary fires. The response also stated that cable protection against overloads is a consideration in the general design criteria (GDC) but "is limited in application." The response did not state whether or not secondary fires will be modelled in the PRA. PRA RAI 15.01.01 (ADAMS Accession No. ML 15182A 193) requested clarification if the GDC reference precluded secondary fires and, if not, requested that secondary fires be modeled in the FPRA. The response to PRA RAI 15.01.01 (ADAMS Accession No. ML 15212A 136) indicated that all secondary fires are not precluded by the GDC reference and stated that (1) the risk of secondary fires due to cables associated with "SSA [safe shutdown analysis] and FPRA equipment and other equipment important to plant operations" will be included in the updated risk results to be provided in response to PRA RAI 03 and (2) the risk of secondary fires due to cables associated with equipment "not identified as important for plant safety and operation" will be assessed as part of a separate sensitivity study using "bounding engineering analyses." a) Please confirm that secondary fires are not caused by lack of breaker coordination. b) Describe and justify the modeling approaches used to assess the risk of secondary fires for the FPRA and the supporting sensitivity study. PRA RAI 16.01.01 The response to PRA RAI 16. 01 (ADAMS Accession No. ML 15212A 136) did not address the question related to the use of Appendix P. The response cites draft NUREG-2180, "Determining the Effectiveness, Limitations, ancl Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities (DELORES-VEWFIRE)," for incorporating area-wide incipient detection credit into the FPRA. Therefore, currently, no acceptable method has been demonstrated for including area-wide incipient detection credit in the FPRA. The NRC staff requests the following information to evaluate for transition: a. Provide the results of a sensitivity study (core damage frequency (CDF), delta (.0.) CDF, large early release frequency (LERF), .0.LERF), which removes credit for area-wide incipient detection although credit for the Halon system could be retained consistent with current acceptable guidance. If the FPRA credits the Halon system for this fire area, discuss the approach for modeling it consistent with acceptable guidance. b. Provide an implementation item to update the FPRA with an NRC-accepted method prior to self-approval to credit area-wide incipient detection.
PRA RAI 30.02 The response to PRA RAI 30 (ADAMS Accession No. ML 15079A025) revises Implementation Item 11 of LAR Table S-3 to reference Table S-2; however, while Table S-2 addresses planned modifications, it does not include procedure updates, which appear to be in Table S-3. Risk and change-in-risk results should be re-evaluated after both modifications and procedure updates are completed. Clarify that Implementation Item 11 will also include procedure updates as described in Table S-3.
R. Glover Attachments C, G, H, J, M, S, V, and W, as applicable, by this date. The NRC staff agreed with these dates. If you have any questions, please contact me at 301-415-2760 or Martha.Barillas@nrc.gov. Docket No. 50-261
Enclosure:
Sincerely, IRA! Dennis Galvin for Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrLABClayton Resource JRobinson, NRR HBarrett, NRR LPL2-2 R/F RidsNrrDorllpl2-2 Resource RidsNrrPMRobinson Resource RidsNrrDraAfpb Resource LFields, NRR DO'Neal, NRR DGalvin, NRR BMetzger, NRR SDinsmore, NRR RidsNrrDraApla Resource AWu, NRR AKlein, NRR ADAMS A ccess1on N o.: ML 16048A349 *b *1 1y e-ma1 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DRA/APLA/BC NAME DGalvin BClayton SRosenberg* DATE 3/1/16 2/29/16 2/17/16 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BBeasley MBarillas (DGalvin for) DATE 3/2/16 3/2/16 OFFICIAL RECORD COPY