Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition, LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition, LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition, LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition, ML11276A118, ML113260423, ML13256A110, ML14163A002, ML16103A348
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MONTHYEARML11276A1182011-09-28028 September 2011 Fort Calhoun Station - License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Other ML1132604232011-12-13013 December 2011 Online Reference Portal for National Fire Protection Association Standard (NFPA) 805 License Amendment Request Project stage: Other ML1135403342011-12-19019 December 2011 Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement LIC-11-0136, Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition)2011-12-22022 December 2011 Clarification of Supplement to License Amendment Request (LAR) 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2011 Edition) Project stage: Supplement ML1136300832011-12-29029 December 2011 Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants, Project stage: Acceptance Review LIC-12-0033, Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station2012-03-20020 March 2012 Submittal of Fire Dynamic Simulator (FDS) Input Files in Response to NRC NFPA 805 Transition License Amendment Request Audit Team Request at Fort Calhoun Station Project stage: Request ML1210205742012-04-11011 April 2012 Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: Draft RAI ML1210205612012-04-11011 April 2012 Draft Request for Additional Information Email, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition). Project stage: Draft RAI ML1210400482012-04-26026 April 2012 Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: RAI LIC-12-0083, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition2012-07-24024 July 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition Project stage: Response to RAI LIC-12-0120, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-08-24024 August 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station Project stage: Response to RAI LIC-12-0135, Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station2012-09-27027 September 2012 Responses to Requests for Additional Information License Amendment Request 10-07 to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition, at Fort Calhoun Station Project stage: Response to RAI ML13016A4322013-01-16016 January 2013 E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI ML13053A2262013-02-22022 February 2013 Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. Project stage: Draft RAI LIC-13-0033, Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-04-23023 April 2013 Omaha Public Power District'S, Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station Project stage: Request W3F1-2013-0022, Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 8052013-05-16016 May 2013 Response to 2nd Round Request for Additional Information Regarding Adoption of National Fire Protection Association Standard NFPA 805 Project stage: Request LIC-13-0060, Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station2013-05-21021 May 2013 Omaha Public Power District - Remaining Responses to Second Request for Additional Information License Amendment Request to Adopt NFPA 805 at Fort Calhoun Station Project stage: Request ML13178A0352013-06-27027 June 2013 Email Request for Additional Information Round 3 (Afpb), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition). Project stage: RAI LIC-13-0096, Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 8052013-07-29029 July 2013 Responses to Third Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Project stage: Request ML13226A1222013-08-14014 August 2013 Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI ML13256A1102013-09-12012 September 2013 Safe Shutdown Analysis (SSA) RAI Response - NFPA-805 Transition (ME7244) Project stage: Other ML13270A2872013-09-27027 September 2013 Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: RAI LIC-13-0142, Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition2013-10-11011 October 2013 Probabilistic Risk Assessment (PRA) RAI Response - NFPA-805 Transition Project stage: Other LIC-13-0158, Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition2013-11-0404 November 2013 Probabilistic Risk Assessment (PRA) RAI Responses 19.01, 24, and 26 - NFPA-805 Transition Project stage: Other LIC-13-0167, Safe Shutdown Analysis (SSA) RAI 17.02 Response - NFPA-805 Transition (ME7244)2013-11-11011 November 2013 Safe Shutdown Analysis (SSA) RAI 17.02 Response - NFPA-805 Transition (ME7244) Project stage: Request LIC-13-0179, Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition2013-12-18018 December 2013 Probabilistic Risk Assessment (PRA) RAI Responses 01.j.04, 01.j.05, and 01.j.06 - NFPA-805 Transition Project stage: Other LIC-14-0004, Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition2014-01-24024 January 2014 Probabilistic Risk Assessment (PRA) RAI Responses 26.01 and 24.01 - NPFA-805 Transition Project stage: Other ML14036A0682014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 12/9/11 Affidavit Executed by C. M. Molnar, Westinghouse, LTR-RAM-II-10-046, Revision 1, Dated 4/22/2011 Project stage: Withholding Request Acceptance ML14036A0832014-02-18018 February 2014 Request for Withholding Information from Public Disclosure, 3/14/12 Affidavit Executed by J. A. Gresham, Westinghouse, Re.: Compact Containing Fire Dynamic Simulator Input Project stage: Withholding Request Acceptance ML14051A3972014-02-20020 February 2014 NFPA 805 IE PRA F&O Tables Project stage: Request ML14051A3882014-02-20020 February 2014 NFPA 805 Fpra F&O Tables Project stage: Request ML14070A5912014-02-28028 February 2014 Supplemental Response to Safe Shutdown Analyses (SSA) Request for Additional Information (RAI) 06 - NFPA-805 Transition Project stage: Supplement ML14115A2972014-04-10010 April 2014 Enclosure 1: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement ML14115A2982014-04-10010 April 2014 Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance -Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement LIC-14-0042, Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-04-10010 April 2014 Enclosure 2: Fort Calhoun Station, Unit 1 - Supplement to License Amendment Request 10-07, Proposed Changes to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Supplement ML14122A2452014-05-22022 May 2014 Request for Withholding Information from Public Disclosure, 3/26/13 Affidavit Executed by C. M. Molnar, Westinghouse, Re.: LTR-RAM-II-10-046, Rev. 3 Project stage: Withholding Request Acceptance LIC-14-0075, Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report2014-06-11011 June 2014 Request Clarifications to Draft National Fire Protection Association (NFPA) 805 Safety Evaluation Report Project stage: Request ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) Project stage: Approval ML14163A0022014-06-16016 June 2014 Summary of Audit Conducted March 5-9, 2012, Request to Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants Project stage: Other ML16103A3482016-04-0404 April 2016 Ft. Calhoun, Unit 1 - License Amendment Request (LAR) 16-01; Revised Commitment to Modify FCS Plant Systems as Part of the Implementation of NFPA 805 Project stage: Other LIC-16-0099, License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program2016-11-18018 November 2016 License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program Project stage: Request 2013-04-23
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Category:E-Mail
MONTHYEARML24025A1792024-01-23023 January 2024 State Consultation Response e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment (License No. DPR-40, Docket No. 50-285) ML24024A2242024-01-22022 January 2024 State Consultation e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment- (License No. DPR-40, Docket No. 50-285) ML23311A0862023-11-0505 November 2023 Letter to M Morales Re Ft Calhoun License Termination Section 7 Determination for Ipac 2022-0029456 ML23038A1882023-01-31031 January 2023 Request for Additional Time to Respond to Request for Additional Information on License Amendment Request for Approval of License Termination Plan (License No. DPR-40, Docket No. 50-285) ML22222A1192022-08-0808 August 2022 Email Section 106 NHPA- Ft Calhoun Station License Termination Plan ML21069A2482021-03-10010 March 2021 Umax, 07200054, 05000361, 05000362, FSAR Revision 4 for San Onofre ISFSI ML21335A3352021-01-25025 January 2021 January 25, 2021 e-mail from J. Parrott, NRC to C. Cameron, OPPD Use of Resrad Model to Represent Well Water Concentrations in a Basement Substructure (License No. DPR-40, Docket No. 50-285) ML20204B0782020-07-22022 July 2020 Donna Gilmore Email Holtec Umax Materials (07200054, 05000361, 05000362) ML20113F0622020-04-22022 April 2020 E-mail Results of Acceptance Review of OPPD Request for Exemption from 10 CFR 20, App G, Section Iii.E (License No. DPR-40, Docket No. 50-285) ML20100J2272020-03-26026 March 2020 E-mail Notification to the State of Nebraska on the Issuance of the License Amendment for Revised Security Plans to Reflect an ISFSI-only Configuration (License No. DPR-40, Docket Nos. 50-285 and 72-54) ML20100L7232020-03-15015 March 2020 Email: Town of Desoto National Register of Historic Places Eligibility ML19353C3612019-12-11011 December 2019 E-mail to State of Nebraska Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status (License DPR-40, Docket Nos. 50-285 and 72-054) ML19309F1112019-10-11011 October 2019 ISFSI-Only Tech Specs ML19241A1812019-08-21021 August 2019 Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status ML19175A0212019-06-19019 June 2019 Acceptance Review - License Amendment Request to Revise Security and Safeguards Requirements to Reflect ISFSI-Only Configuration ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML19126A2802019-05-0101 May 2019 Acceptance Review - License Amendment Request for ISFSI-Only EP and EAL Scheme ML18100A2712018-04-0909 April 2018 04-09-18 OPPD E-Mail (FCS Permanently Defueled Emergency Plan Implementation) ML17236A3462017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567) ML17236A3442017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664) ML17234A4692017-08-22022 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831) ML17194A9732017-07-13013 July 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) ML17191B0212017-07-10010 July 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Modification of LC 3.C to Delete Commission-approved CSP ML17184A0042017-06-30030 June 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits ML17142A0202017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 to TQ-DC-FC-101 ML17144A0132017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun PSDAR - Findings and Concerns ML17139C5082017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 for LIC-17-0043 ML17139C8342017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Partial Exemption from Record Retention Requirements ML17139B6782017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 50.54(w)(1), On-Site Property Damage Insurance ML17139B6762017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 140.11(a)(4), Off-Site Liability Insurance ML17136A1692017-05-16016 May 2017 NRR E-mail Capture - (External_Sender) OPPD FCS Decommissioning Financial Reports ML17115A4722017-04-25025 April 2017 NRR E-mail Capture - (External_Sender) Corrected Page 18 to TQ-DC-FC-201 ML17114A3112017-04-24024 April 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review TS Changes to Align for Decommissioning ML17112A0362017-04-20020 April 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR ML17090A3942017-03-31031 March 2017 NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437) ML17082A0022017-03-22022 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption ML17081A0192017-03-21021 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption ML17052A0272017-02-15015 February 2017 NRR E-mail Capture - Fort Calhoun Station, Unit No. 1 - Acceptance of Requested Amendment Revise Permanently Defueled Emergency Plan and EAL Scheme ML17033A9692017-02-0202 February 2017 NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment ML16350A0392016-12-15015 December 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8858) Fort Calhoun, Unit 1 - License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program ML16351A0432016-12-15015 December 2016 NRR E-mail Capture - (External_Sender) Fort Calhoun Station Offsite Response Organizations ML16334A3002016-11-29029 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8525) Fort Calhoun, Unit 1 - License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements ML16333A0992016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8452), Fort Calhoun, Unit 1 - Request for Exemption from Specific Provisions in 10 CFR 73.55 ML16333A2312016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8843)Fort Calhoun, Unit 1, Request for Rescission of Interim Compensatory Measure B.1.a from EA-02-026, Order for Interim Safeguards and Security Compensatory Measures. ML16286A0812016-10-12012 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station, Unit 1, License Amendment Request 16-03, Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning ML16278A0292016-10-0303 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station Radiological Emergency Response Plan (RERP) for Decommissioning ML16257A0262016-09-12012 September 2016 NRR E-mail Capture - (External_Sender) OPPD Slides for 9/13/16 Pre-Application Meeting on Class 1 Structures ML16207A0182016-07-22022 July 2016 NRR E-mail Capture - Acceptance Review ML16137A0092016-05-16016 May 2016 NRR E-mail Capture - Acceptance Review CAC No. MF7574 ML16131A7312016-05-10010 May 2016 NRR E-mail Capture - (External_Sender) Question Rvi Inspection Results 2024-01-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23151A0042023-06-0606 June 2023 Second Set RAIs Rev 4 ML22357A0672022-12-30030 December 2022 Enclosure RAI Re Approval of License Termination Plan ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review ML20111A2162020-05-20020 May 2020 Revised PSDAR Request for Additional Information - RAI ML19241A1812019-08-21021 August 2019 Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status ML18067A1432018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to M. J. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI) ML17236A3442017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664) ML17236A3462017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567) ML17234A4692017-08-22022 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831) ML17194A9732017-07-13013 July 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) ML17112A0362017-04-20020 April 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR ML17090A3942017-03-31031 March 2017 NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437) ML17082A0022017-03-22022 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption ML17081A0192017-03-21021 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption ML17067A3862017-03-15015 March 2017 Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17033A9692017-02-0202 February 2017 NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment ML16263A0492016-09-20020 September 2016 Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML16174A1502016-06-27027 June 2016 Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML16146A1782016-05-27027 May 2016 Request for Additional Information, Round 2, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16106A0232016-04-29029 April 2016 Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML16104A2872016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements ML16048A1542016-02-23023 February 2016 Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16048A0242016-02-23023 February 2016 Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML15343A1082015-12-15015 December 2015 Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15323A0362015-11-24024 November 2015 Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval ML15194A2722015-07-14014 July 2015 Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15057A0152015-03-0303 March 2015 Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review ML15043A0612015-02-25025 February 2015 Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML14353A0512014-12-22022 December 2014 Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra ML14259A3652014-09-24024 September 2014 Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML14195A0862014-07-16016 July 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML13317A5832013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13282A5362013-10-0909 October 2013 Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) ML13290A0022013-10-0909 October 2013 Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks ML13270A2872013-09-27027 September 2013 Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML13261A2122013-09-18018 September 2013 Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) ML13233A2482013-08-26026 August 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7) ML13235A1682013-08-23023 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13234A4352013-08-22022 August 2013 Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source ML13226A1222013-08-14014 August 2013 Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML13212A0092013-07-30030 July 2013 Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source ML13205A1252013-07-24024 July 2013 Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13205A0182013-07-23023 July 2013 Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13144A4822013-05-23023 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13100A1752013-04-10010 April 2013 Request for Additional Information Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup ML13086A4732013-03-27027 March 2013 Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13120A0842013-03-22022 March 2013 Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660) ML13053A2262013-02-22022 February 2013 Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. ML13016A4322013-01-16016 January 2013 E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) 2023-06-06
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1Burkhardt, JanetFrom:Wilkins, LynneaSent:Wednesday, August 14, 2013 9:31 AMTo:LIPPY, DONNA L (dllippy@oppd.com)Cc:Sebrosky, Joseph; EDWARDS, MICHAEL L (medwards@oppd.com); HANSHER, BILL R (bhansher@oppd.com); Burkhardt, JanetSubject:Fort Calhoun NFPA 805, Third Round, Second Part, of RAIs (ME7244)Donna, By letter dated September 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112760660), as supplemented by letters dated December 19 and 22, 2011, and March 20, 2012 (ADAMS Accession Nos. ML113540334, ML11363A077, and ML12083A147, respectively), Omaha Public Power District, (the Licensee), submitted a license amendment request (LAR) to transition their fire protection licensing basis at the Fort Calhoun Station, Unit 1, from Title 10 of the Code of Federal Regulations (CFR), Section 50.48(b), to 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805). A review team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff and contractors from Pacific Northwest National Laboratory (PNNL) and the Center for Nuclear Waste Regulatory Analyses (CNWRA) participated in a regulatory audit of Fort Calhoun in Blair, NE from March 5 -9, 2012. By letter dated April 26, 2012, (ADAMS Accession No. ML12198A406) the NRC issued requests for additional information (RAls). By letters dated July 24, 2012 (ADAMS Accession No. ML12208A131), August 24,2012 (ADAMS Accession No. ML12240A151), and September 27,2012 (ADAMS Accession No. ML12276A046) the licensee provided responses to the RAls. The NRC staff reviewed the information provided by the licensee in response to the first set of RAIs and determined that additional information was needed for the staff to complete its evaluation. Consequently, the staff issued a second round of RAIs on February 22, 2013, (ADAMS Accession No. ML13053A226) and a third round of RAIs on June 27, 2013 (ADAMS Accession No. ML13178A035). The licensee responded to these RAIs in letters dated April 23, 2013 (ADAMS Accession No. ML13116A015), May 21, 2013 (ADAMS Accession No. ML13144A814), and July 29, 2013 (ADAMS Accession No. ML13211A055).
The U.S. NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. These RAIs can be found below. The NRC considers these RAIs to be the second set of the third round of RAIs. Based on discussions with you on August 13, 2013, it was agreed that a response to the RAIs found below will be provided in accordance with the following schedule:
- PRA RAIs 01.i.02, 01.j.02, 01.j.03, 23.01, and 27 responses to be provided by October 7, 2013
- PRA RAIs 07.02, 19.01, 24, 25, and 26 responses to be provided by November 6, 2013. In addition, as discussed with you during the August 13, 2013, phone call the staff has determined that you no longer need to provide a response to SSA RAI 07.01 that was issued to you on June 27, 2013 (ADAMS Accession No. ML13178A035). The staff determined that SSA RAI 07.01 response is not needed in order for the staff to complete its safety evaluation. The staff also discussed with you during the August 13, 2013, phone call that the response to PRA RAI 24 should include two additional sensitivity studies as a result of issues that were raised during a July 22 through July 24, inspection at your site. Should the NRC determine that the RAIs found below are no longer necessary prior to the dates found above, the request will be withdrawn. If circumstances result in the need to revise the requested response date, please contact me or Joe Sebrosky.
REQUEST FOR ADDITIONAL INFORMATION 2LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS FORT CALHOUN STATION, UNIT 1 (TAC NO. ME7244) SSA RAI 17.01 License Amendment Request, Attachment S, Table S-2, "Plant Modifications Committed," Item REC-117, states:
"Modification to change the normal operating alignment for 480 V load center tie breakers BT-1B4A, BT-1B3B, and BT-1B4C from normally open and racked-in, to normally racked-out (or otherwise disabled from spuriously closing due to fire damage to DC breaker control circuits in the opposite Train 4kV switchgear room, main control room, or cable spreading room). This modification addresses the issue associated with electrical failure resulting from spurious connection of out-of-synch power sources (offsite power to diesel generator, diesel generator to diesel generator)." It is further stated that: "The proposed modification will maintain breaker manual trip capability from main control room, protective trip, automatic load shed trip and accident signal trip for fire areas 36A, 36B, 41 and 42."
According to NRC Special Inspection Report dated March 12, 2012 (ADAMS Accession No. ML12072A128),
there are interconnecting control wires (operated at 125 V DC) between 480V tie breakers in Electrical Switchgear Fire Areas 36A (East Switchgear) and 36B (West Switchgear) (typical - between breakers BT-1B3A and BT-1B4A). These wires are used in the control circuitry of the breakers. A fire in these breakers in either Switchgear Fire Area 36A or 36B can cause damage to the control wires (such as shorts to ground) in the opposite area breakers.
During a recent inspection conducted from July 22, 2013 to July 24, 2013, Office of Nuclear Reactor Regulation (NRR) reviewers questioned the plant technical staff about the potential negative impact of performing the design change (modification) to rack out the normally open cross-tie breakers on the 480VAC switchgear. Discussions with plant staff indicate that a contingency plan exists to modify the control circuit to preclude spurious closure should the modification to rack out the breaker be deemed impractical. By letter dated September 18, 2011, the licensee stated, "-(or otherwise disabled from spuriously closing due to fire damage to the DC breaker control circuits in the opposite train 4kV switchgear room-)." The committed modification is not specified in sufficient detail for the NRC staff to determine its acceptability due to the open-ended parenthetical. Please provide a written description of the specific modification that will be implemented as part of the NFPA 805 transition as well as conceptual circuit design sketches indicating the existing portions of the circuit as well as those parts being added/modified. Probabilistic Risk Assessment (PRA) RAI 01.i.02 By letter dated April 23, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13116A015) the licensee responded to RAI 01.i.01.b and stated that the change in risk reported from the sensitivity study on increased ignition frequencies resulted in lower (not the expected higher) change in risk values because new credit for human actions in alternative shutdown process (in abnormal operating procedure (AOP) 06) was simultaneously added into the PRA. No acceptable approach for the human reliability analysis (HRA) for abandonment due to loss of control has been developed and thus no technical basis for this new credit exists, (i.e., for the human error probability/conditional core damage probability (HEP/CCDP) for abandoning the main control room (MCR) due to loss of control. No description or justification for the HRA method was provided. Please provide the results of the requested sensitivity study on ignition frequencies by removing the credit of the new operator action.
3Please clarify whether credit will be retained in the PRA for abandonment of the MCR on loss of control for fires in the cable spreading room (CSR), and, if so, describe and justify the HRA methods applied and their relation to current HRA methods. Currently, these actions are listed as being retained as defense-in-depth (DID) actions in FC41 per license amendment request (LAR) Attachment G (ADAMS Accession No. ML11376A072, non-publicly available) and not credited in the PRA. Update the information as necessary. PRA RAI 01.j.02 By letter dated May 21, 2013 (ADAMS Accession No. ML13144A814), the licensee responded to RAI 01.j.01.a.iv and provided a HEP of 1.50E-02 and CCDP/conditional large early release probability (CLERP) of 1.41E-01 for abandoning the MCR due to loss of habitability with no explanation of how these values were developed.
a. Please provide a summary of how the HEP of 1.50E-02 was developed. The discussion should include whether each of the performance shaping factors identified in Section 4.6 of NUREG-1921, "EPRI/NRC-RES Fire Human Reliability Analysis Guidelines," and if each of the large number of MCR abandonment recovery actions (RAs) identified in LAR Attachment G were addressed in the detailed HRA. b. In light of the large number of primary control station (PCS) activities and RAs identified in LAR Attachment G, identify the actions that are the significant contributors to the HEP and discuss their timing and complexity. Also discuss the timing and complexity of the non-significant actions. PRA RAI 01.j.03 By letter dated May 21, 2013 (ADAMS Accession No. ML13144A814), the licensee responded to RAI 01.j.01.a.iv and indicated that the sensitivity analysis results reflect a change in the optical density criterion for abandoning the MCR due to loss of habitability from 0.3 m-1 to 3.0 m-1. Please clarify if the resultant abandonment time/probability bounds the NUREG/CR-6850, ""EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," Section 11.5.2.11, heat flux criterion of 1 kW/m2 at 6' above the floor, corresponding to a smoke layer temperature of 95°C. If not, provide a sensitivity analysis of core damage frequency/large early release frequency (CDF/LERF), delta () CDF and LERF from using the abandonment time/probability based on the heat flux criterion. PRA RAI 07.02 By letter dated May 21, 2013 (ADAMS Accession No. ML13144A814), the licensee responded to PRA RAI 07.01.d, and proposed an administrative limit to require a continuous fire watch when transient combustibles with the potential to damage targets are stored in the CSR, FC41. However, the process to determine when transient combustibles can cause damage, and thus require a continuous fire watch, was not explained. The response did imply that a permitting process already exists to establish when transient combustibles might damage targets. Please describe the permitting process and indicate how this process provides confidence that no targets would be damaged by a transient fire. The response also indicated that this new proposed administrative limit is already modeled in the fire PRA (FPRA). Describe how the existing PRA captures this new proposed administrative limit. Specifically indicate if the severity factor applied in the analysis encompasses those heat release rates (HRRs) from transient combustibles which can cause damage, yet are less than the 5 pound combustible limit originally employed in FC41. PRA RAI 19.01 4By letter dated April 23, 2013 (ADAMS Accession No. ML13116A015) the licensee responded to PRA RAI 19 and stated that high concentrations of conduits were considered when identifying pinch points. However, the highest concentration of cables is not necessarily correlated with the locations with high CCDP which may have fewer cables. Please describe the criteria used to identify high concentrations of conduits and justify how implementation of this criteria ensures that pinch points are identified. PRA RAI 23.01 By letter dated April 23, 2013 (ADAMS Accession No. ML13116A015) the licensee responded to PRA RAI 23 and described plans to upgrade the fire HRA to NUREG-1921 during the National Fire Protection Association Standard 805 "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants", 2001 Edition, (NFPA 805) implementation period, and to notify the NRC and provide a resolution plan if the upgrade causes the risk acceptance guidelines to be exceeded. Propose a regulatory mechanism that provides confidence that this upgrade will be completed. One regulatory mechanism used in NFPA-805 transition are the implementation items in LAR Attachment S, Table S-3. Since this is a PRA upgrade which could have a substantive impact on the PRA, the upgrade and a focused scope peer review should be completed prior to self approval.
PRA RAI 24 Section 2.4.3.3 of NFPA 805 states that the probabilistic safety assessment (PSA) (PSA is also referred to as PRA) approach, methods, and data shall be acceptable to the authority having jurisdiction (AHJ). Section 2.4.4.1 of NFPA-805 states that the change in public health risk from any plant change shall be acceptable to the AHJ. Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework for determine the acceptability of risk-informed changes.
The responses to the following RAIs provided sensitivity analyses to show the impact on fire risk of the indicated PRA modeling, and this included PRA upgrades to meet Capability Category II (CC-II) requirements:
- LAR Section 4.5.1.2 regarding the use of four methods that are deviations from the guidance in NUREG/CR-6850 and NRC-approved frequently asked questions (FAQs), with a composite sensitivity analysis of these four methods provided in Section W.2 of the LAR. The four methods are 1) generic severity factor/non-suppression probability for electrical cabinets, 2) pump fire frequency apportioning, 3) diesel generator generic severity factor/non-suppression probability, and 4) application of a draft version of FAQ 08-0050, "Manual Non-Suppression Probability," (ADAMS Accession No. ML092190555, closure memo).
- PRA RAI 01.e.01 regarding unavailability of the Halon system.
- PRA RAI 01.h.i, ii, and iii regarding manual suppression for multi-compartment analysis (MCA) with integration of MCA into the risk estimates.
- PRA RAI 01.h.01 regarding inappropriate crediting of gaseous suppression systems in the MCA.
- PRA RAI 01.h.02 regarding time available for manual fire suppression for non-rated fire barriers in the MCA.
- PRA RAI 01.i.02 regarding credit for MCR abandonment on loss of control
- PRA RAI 01.j.01 regarding both MCR abandonment, CCDP and main control board (MCB) fire spread that threatens MCR abandonment. The sensitivity analysis provided in response to RAI 01.j.01 5encompassed both of these issues. If the MCR abandonment CCDP is revised in response to RAI 01.j.02, the revised CCDP should be used in response to this RAI.
- PRA RAI 01.j.03 regarding use of optical density criterion for abandonment. If the MCR abandonment probability is revised in response to RAI 01.j.03, the revised probability should be used in response to this RAI.
- PRA RAI 07.02 regarding treatment of transient fires in the CSR (FC41). If the treatment of transient fires in FC41 is revised in the response to RAI 07.02, the revised treatment should be used in response to this RAI.
- PRA RAI 08 regarding credit for Control Power Transformers (CPTs).
- PRA RAI 15.c regarding component boundary definitions.
- PRA RAI 15.d regarding state-of knowledge correlations (SOKC) including consideration of correlated fire related factors.
- PRA RAI 27 on update of fire frequencies with potentially challenging event data.
- FM RAI 01.a regarding wall and corner effects.
- FM RAI 01.b regarding non-cable intervening combustibles.
- FM RAI 01.d.iii regarding use of Beyler's correlation in closed compartments.
- FM RAI 05.c.i regarding soot yield. a. Consistent with the requirement that the change in risk is developed using acceptable methods and meets the acceptance guidelines, provide the results of a composite sensitivity analysis that shows the integrated impact on the fire risk (CDF, LERF, CDF, LERF). The composite sensitivity analysis should utilize the accepted method that was substituted for the proposed method in all the above studies. In this composite analysis, for those cases where the individual issues have a synergistic impact on the results, a simultaneous analysis must be performed. For those cases where no synergy exists, a one at a time analysis may be done. In addition, an additional composite sensitivity analysis that includes only the sensitivity analyses believed appropriate may be provided. b. If the acceptance guidelines are exceeded, please provide justification of how RG 1.174 is nevertheless satisfied and, if applicable, a description of any new modifications or operator actions being credited to reduce risk and the associated impacts to the fire protection program (FPP). c. Self-approval based on the results of the PRA after transition also requires the use of acceptable methods. For each of the above methods, identify which method is intended to be used in the PRA that will be used to support post-transition change in risk evaluations. Continued use of unacceptable methods will prohibit the staff from completing its review for self approval.
6 PRA RAI 25 Section 2.4.3.3 of NFPA 805 states that the PSA (PSA is also referred to as PRA) approach, methods, and data shall be acceptable to the AHJ. Section 2.4.4.1 of NFPA-805 states that the change in public health risk from any plant change shall be acceptable to the AHJ. RG 1.174, provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework for determine the acceptability of risk-informed changes.
The responses to the following RAIs provided sensitivity analyses to show the impact on fire risk of the indicated PRA modeling:
- PRA RAI 01.c.01 regarding analysis of hot work-induced cable fires.
- PRA RAI 01.g.01 regarding cable routing assumptions for cables EB12191G and 7700A-B.
- PRA RAI 07.01.c regarding combustible control violations.
- PRA RAI 21 regarding qualitative screening of MCR heating ventilation and air conditioning (HVAC) scenarios.
- FM RAI 01.d.ii regarding fire modeling of vent opening size.
- FM RAI 01.e regarding fire modeling of open door cabinets with non-qualified cable.
- FM RAI 01.03 regarding inappropriate use of the McCaffrey, Quintiere, Harkleroad (MQH) method. The responses to the above RAIs indicate that these analyses individually and collectively do not have a potentially significant impact on the risk for the transition based on the results of the individual sensitivity analysis. However, the self-approval guidelines are two orders of magnitude smaller than the transition acceptance guidelines and all future changes to the FPP must be adequately evaluated. For each of the above methods, identify which method is intended to be used in the PRA that will be used to support post-transition change in risk evaluations. Continued use of unacceptable methods will prohibit the staff from completing its review for self approval. PRA RAI 26 Section 2.4.3.3 of NFPA 805 states that the PSA (PSA is also referred to as PRA) approach, methods, and data shall be acceptable to the AHJ. Section 2.4.4.1 of NFPA-805 states that the change in public health risk from any plant change shall be acceptable to the AHJ. RG 1.174, provides quantitative guidelines on CDF and LERF, and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework for determine the acceptability of risk-informed changes.
With regard to the responses to PRA RAI 01.i (July 24, 2012, ADAMS Accession No. ML12208A131) and PRA RAI 01.i.01.a (April 23, 2013, ADAMS Accession No. ML13116A015), regarding use of fire ignition frequencies from NUREG/CR-6850, Supplement 1, indicate if the acceptance guidelines of RG 1.174 may be exceeded when this sensitivity study is applied to the integrated sensitivity study of PRA RAI 24 (above). If these guidelines may be exceeded, provide a description of fire protection, or related, measures that can be taken to 7provide additional DID, as directed in the resolution of FAQ 08-0048, "Revised Fire Ignition Frequencies," (ADAMS Accession No. ML092190457, closure memo).
PRA RAI 27 By letter dated May 21, 2013 (ADAMS Accession No. ML13144A814) the licensee responded to PRA RAI 22 and indicated that no Bayesian Update is necessary for those fires self-identified as potentially challenging. Three past plant events appear to be candidates for input into a Baysean update. The response indicated that the control room fire is within the range of data considered by EPRI 1019259 (NUREG/CR-6850, Supplement 1, "Fire Probabilistic Risk Assessment Methods Enhancements." However, the control room fire, dated 11/29/1997, is not in the database upon which the frequencies for NUREG/CR-6850 were established. Updating the generic bin 4 MCB frequencies from EPRI 1019259 with this event will make a substantial increase to the bin 4 fire frequency (approximately a factor of 2).
For the transient fire and electrical cabinet events, the update of each generic frequency will increase the frequency. Electrical cabinet fires include all events, at power and not at power. For bin 15.1, the addition of another event over 10 years will also approximately double the fire frequency for that bin. For bin 7, the increase is of a lesser amount, yet an increase will occur in frequency for bin 7 also. Thus, in each case, the plant has experienced more fires than would be expected from the generic industry database. As a result, please perform a sensitivity study through updating the frequency bins for those events. Provide the impact on CDF/LERF/ CDF/ Delta LERF. More information may also be provided regarding the statement that the plant does not have a particular susceptibility to the fire type, as compared to the industry operating experience, and therefore the generic frequency is applicable.