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| | number = ML12345A327 | | | number = ML12345A327 |
| | issue date = 12/13/2012 | | | issue date = 12/13/2012 |
| | title = D. C. Cook Nuclear Plant, Units 1 and 2, Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 | | | title = Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Weber L J | | | addressee name = Weber L |
| | addressee affiliation = Nuclear Generation Group | | | addressee affiliation = Nuclear Generation Group |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
| | license number = DPR-058, DPR-074 | | | license number = DPR-058, DPR-074 |
| | contact person = Wengert T J | | | contact person = Wengert T |
| | case reference number = TAC ME6629, TAC ME6630 | | | case reference number = TAC ME6629, TAC ME6630 |
| | document type = Request for Additional Information (RAI), Letter | | | document type = Request for Additional Information (RAI), Letter |
| | page count = 5 | | | page count = 5 |
| | project = TAC:ME6629, TAC:ME6630 | | | project = TAC:ME6629, TAC:ME6630 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 13, 2012 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION ON THE APPLICATION FOR AMENDMENT TO TRANSITION THE FIRE PROTECTION PROGRAM TO NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME6629 AND ME6630) Dear Mr. Weber: By letter dated July 1, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11188A145), as supplemented by letters dated September 2,2011, April 27, 2012, June 29,2012, August 9,2012, October 15,2012, and November 9,2012, Indiana Michigan Power Company (I&M) submitted an application for a license amendment to transition the Donald C. Cook Nuclear Plant, Units 1 and 2, fire protection program, from Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48(b), to 10 CFR 50.48(c), National Fire Protection Association Standard (NFPA) 805. Some portions of the supplemental information contain security related information and are therefore withheld from public disclosure. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittals and determined that additional information is needed to complete the review, as described in the enclosure, request for additional information (RAI). The NRC staff had discussed the RAI in draft form with your staff on December 6, 2012. During that discussion, the NRC staff agreed to revise certain draft questions. Your staff also agreed to formally submit your response within 30 days from the date of this letter. Please note that the NRC staff's review efforts are continuing and additional RAls may be forthcoming. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 13, 2012 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUB~IECT: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION ON THE APPLICATION FOR AMENDMENT TO TRANSITION THE FIRE PROTECTION PROGRAM TO NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME6629 AND ME6630) |
| L. Weber -Please feel free to contact me if you need any further clarification of the questions in the enclosure. Sincerely. Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and Request for Additional Information cc: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION (RAil LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 RAI 20.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 and the enclosure, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12242A246) and the non-public enclosure, you responded to RAI-20, Probabilistic Risk Assessment (PRA), Internal Events PRA (lEPRA), explaining that a gap assessment was performed on the differences in supporting requirements (SRs) between PRA Standard RA-Sa-2009, as clarified by Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Result for Risk-Informed Activities", Rev, 2, and RA-Sa-2003, "Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications," (which was initially used to review the internal events PRA). As part of the assessment, gap findings were generated and a sensitivity study was performed to address a subset of the issues. Clarify the following gap finding: A finding against SR LE-B3, which requires using engineering analysis to support PRA modeling, identifies two large early release frequency (LERF) modeling assumptions that were not justified with engineering assessment but have beneficial impacts on the LERF estimate. The dispOSition for this gap finding states that these assumptions are expected to be confirmed by analysis. The assumptions are not identified. Identify the assumptions made, and explain why they are expected to be confirmed by analysis. A finding against SR LE-A4, which requires dependencies between the Level 1 and Level 2 PRA to be properly treated, identifies that in some cases, assumptions were made that may yield non-conservative results. The disposition to this finding states that the licensee's use of NUREG/CR-6595, "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events," produces a bounding model but also states that a sensitivity study examines the impact of this issue. The finding against LE-A4 is not identified in the sensitivity study identified for this RAI on page 22 of the response. Clarify how the finding against LE-A4 is being dispositioned. Include in this description how dependencies between Level 1 and Level 2 are treated and clarify how SR LE-A4 is met. Enclosure | | |
| -RAI 30.01 Probabilistic Risk Assessment In your letter dated April 27, 2012 (ADAMS Accession No. ML 12132A390) you responded to RAI-30, Probabilistic Risk Assessment, Uncertainty, discussing the results of sensitivity analyses using frequently asked question (FAQ) 08-0048 (ADAMS Accession No. ML092190457) fire ignition frequencies and the substantial risk reduction obtained from crediting a local operator action to restore the turbine driven auxiliary feedwater pump N train battery charger after it is tripped following loss of offsite power or after a safety injection signal. Given that including this action reduces the sensitivity study results to below the risk acceptance criteria in RG 1.174, discuss whether the RA is or will be included in the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," fire protection program. If included, provide the additional risk of this RA. If not included in the NFPA 805 fire protection program, provide justification for not including it. RAI 34.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 (ADAMS Accession No. ML 12242A246) and the non-public enclosure, you responded to RAI-34e, Probabilistic Risk Assessment, Peer Review F&Os, discussing the results of sensitivity analyses that shows that using the "Special Weighting Factors" for transient fire frequency apportionment compared to using the nominal 6850, "EPRIINRC-RES Fire PRA Methodology for Nuclear Power Facilities," (no fractional values) method will result in the delta core damage frequency (CDF) exceeding the RG 1.174 risk acceptance criteria. Provide the corresponding results for LERF and delta LERF. | | ==Dear Mr. Weber:== |
| L. Weber -2 Please feel free to contact me if you need any further clarification of the questions in the enclosure. Sincerely, IRA! Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and Request for Additional Information cc: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDCCook Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsAcrsAcnw _MaiICTR Resource RidsNrrDraAfpb Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrDraApla Resource MSnodderly, NRR DHarrison, NRR AKlein, NRR LFields, NRR SDinsmore, NRR HBarrett, NRR JRobinson, NRR . db)y J R b' Inson e-mal 0 ADAMS A ccesslon N0.: ML 12345A327 '"RAI transmltte , o 'I f11/27/12 OFFICE LPL3-1/PM LPL3-1LAit LPL3-21lA DRAlAPLAlBC LPL3-1/BC LPL3-1/PM NAME lWenQert ELee SRohrer DHarrison* RCarlson MChaw/a for lWenQert DATE 12/13/12 12/13/12 12/13/12 11/27/12 12/13/12 12/13/12 OFFICIAL RECORD | | |
| }} | | By letter dated July 1, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11188A145), as supplemented by letters dated September 2,2011, April 27, 2012, June 29,2012, August 9,2012, October 15,2012, and November 9,2012, Indiana Michigan Power Company (I&M) submitted an application for a license amendment to transition the Donald C. Cook Nuclear Plant, Units 1 and 2, fire protection program, from Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48(b), to 10 CFR 50.48(c), National Fire Protection Association Standard (NFPA) 805. Some portions of the supplemental information contain security related information and are therefore withheld from public disclosure. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittals and determined that additional information is needed to complete the review, as described in the enclosure, request for additional information (RAI). The NRC staff had discussed the RAI in draft form with your staff on December 6, 2012. During that discussion, the NRC staff agreed to revise certain draft questions. Your staff also agreed to formally submit your response within 30 days from the date of this letter. |
| | Please note that the NRC staff's review efforts are continuing and additional RAls may be forthcoming. |
| | |
| | L. Weber - 2 Please feel free to contact me if you need any further clarification of the questions in the enclosure. |
| | Sincerely. |
| | ~~::~M.n.ger Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information (RAI) cc: Distribution via ListServ |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION (RAil LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 RAI 20.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 and the enclosure, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12242A246) and the non-public enclosure, you responded to RAI-20, Probabilistic Risk Assessment (PRA), Internal Events PRA (lEPRA), |
| | explaining that a gap assessment was performed on the differences in supporting requirements (SRs) between PRA Standard RA-Sa-2009, as clarified by Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Result for Risk-Informed Activities", Rev, 2, and RA-Sa-2003, "Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications," (which was initially used to review the internal events PRA). As part of the assessment, gap findings were generated and a sensitivity study was performed to address a subset of the issues. Clarify the following gap finding: |
| | : a. A finding against SR LE-B3, which requires using engineering analysis to support PRA modeling, identifies two large early release frequency (LERF) modeling assumptions that were not justified with engineering assessment but have beneficial impacts on the LERF estimate. The dispOSition for this gap finding states that these assumptions are expected to be confirmed by analysis. The assumptions are not identified. Identify the assumptions made, and explain why they are expected to be confirmed by analysis. |
| | : b. A finding against SR LE-A4, which requires dependencies between the Level 1 and Level 2 PRA to be properly treated, identifies that in some cases, assumptions were made that may yield non-conservative results. The disposition to this finding states that the licensee's use of NUREG/CR-6595, "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events," produces a bounding model but also states that a sensitivity study examines the impact of this issue. The finding against LE-A4 is not identified in the sensitivity study identified for this RAI on page 22 of the response. Clarify how the finding against LE-A4 is being dispositioned. Include in this description how dependencies between Level 1 and Level 2 are treated and clarify how SR LE-A4 is met. |
| | Enclosure |
| | |
| | - 2 RAI 30.01 Probabilistic Risk Assessment In your letter dated April 27, 2012 (ADAMS Accession No. ML12132A390) you responded to RAI-30, Probabilistic Risk Assessment, Uncertainty, discussing the results of sensitivity analyses using frequently asked question (FAQ) 08-0048 (ADAMS Accession No. ML092190457) fire ignition frequencies and the substantial risk reduction obtained from crediting a local operator action to restore the turbine driven auxiliary feedwater pump N train battery charger after it is tripped following loss of offsite power or after a safety injection signal. |
| | Given that including this action reduces the sensitivity study results to below the risk acceptance criteria in RG 1.174, discuss whether the RA is or will be included in the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," fire protection program. If included, provide the additional risk of this RA. If not included in the NFPA 805 fire protection program, provide justification for not including it. |
| | RAI 34.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 (ADAMS Accession No. ML12242A246) and the non-public enclosure, you responded to RAI-34e, Probabilistic Risk Assessment, Peer Review F&Os, discussing the results of sensitivity analyses that shows that using the "Special Weighting Factors" for transient fire frequency apportionment compared to using the nominal NUREG/CR 6850, "EPRIINRC-RES Fire PRA Methodology for Nuclear Power Facilities," (no fractional values) method will result in the delta core damage frequency (CDF) exceeding the RG 1.174 risk acceptance criteria. Provide the corresponding results for LERF and delta LERF. |
| | |
| | L. Weber -2 Please feel free to contact me if you need any further clarification of the questions in the enclosure. |
| | Sincerely, IRA! |
| | Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information (RAI) cc: Distribution via ListServ DISTRIBUTION: |
| | PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsNrrPMDCCook Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsAcrsAcnw_MaiICTR Resource RidsNrrDraAfpb Resource RidsNrrDorlDpr Resource RidsRgn3MailCenter Resource RidsNrrDraApla Resource MSnodderly, NRR DHarrison, NRR AKlein, NRR LFields, NRR SDinsmore, NRR HBarrett, NRR JRobinson, NRR ADAMS Accesslon N0.: ML12345A327 '"RAI transmltte |
| | . db)y J , Rob'Inson e-mal'I 0f11/27/12 OFFICE LPL3-1/PM LPL3-1LAit LPL3-21lA DRAlAPLAlBC LPL3-1/BC LPL3-1/PM NAME lWenQert ELee SRohrer DHarrison* RCarlson MChaw/a for lWenQert DATE 12/13/12 12/13/12 12/13/12 11/27/12 12/13/12 12/13/12 OFFICIAL RECORD COPY}} |
Letter Sequence RAI |
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MONTHYEARML11188A1452011-07-0101 July 2011 Request for License Amendment to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Request ML11256A0302011-09-0202 September 2011 Supplement to Request for License Amendment to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML11255A0222011-09-13013 September 2011 Informs Licensee That Application for Amendment to Change Fire Protection Licensing Basis to NFPA 805 Is Acceptable for Review Project stage: Other ML1131302622011-11-0808 November 2011 List of Plant Components for Walkdown Project stage: Other ML1131302612011-11-0808 November 2011 Additional Questions/Comments on the Monitoring Program, Documentation, Etc Project stage: Other ML1131302602011-11-0808 November 2011 Questions and Comments About the Probabilistic Risk Analysis Project stage: Acceptance Review ML1131302592011-11-0808 November 2011 Questions and Issues to Be Addressed During the Audit Project stage: Acceptance Review ML1131302492011-11-0808 November 2011 E-mail Transmitting 4 NRC Staff Documents to Support the Audit of the Proposed Conversion of the Fire Protection Program to NFPA 805 Project stage: Other ML1131204962011-11-0808 November 2011 Transmit Audit Plan for the Proposed Amendment Converting the Fire Protection Program to NFPA 805 Project stage: Other ML1131205002011-11-0808 November 2011 Audit Plan - D.C. Cook Proposed Amendment to Convert Fire Protection Program to NFPA 805 Project stage: Other ML1135607092012-01-27027 January 2012 Letter Transmitting an RAI on the Application for Amendment to Transition the Fire Protection Program to NFPA 805 Project stage: RAI ML12017A2512012-01-27027 January 2012 RAI for the Proposed Amendment to Transition the Fire Protection Program to NFPA 805 Project stage: RAI AEP-NRC-2012-29, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052012-04-27027 April 2012 Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Response to RAI AEP-NRC-2012-58, Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052012-08-0909 August 2012 Response to Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Response to RAI ML12230A3032012-08-14014 August 2012 Draft Redacted Second-round RAI Re NFPA 805 Amendment Project stage: Draft RAI ML12255A3952012-09-0606 September 2012 Redacted Draft Second-Round RAI the Proposed NFPA 805 Amendment Project stage: Draft Approval ML12285A1792012-10-11011 October 2012 D C Cook NFPA 805 RAI Project stage: Other ML12276A3002012-10-11011 October 2012 RAI on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Standard 805 Project stage: RAI AEP-NRC-2012-92, Response to Second Round Request for Additional Information Regarding Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052012-10-15015 October 2012 Response to Second Round Request for Additional Information Regarding Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Request ML12326A9992012-11-0909 November 2012 Donald C, Cook, Units 1 and 2 - Enclosure 1, 2 & 4 to AEP-NRC-2012-101, Response to Second-Round RAI Item 54.b, and Submittal of Revised Tables Re the Application for Amendment to Transition to National Fire Protection Association Standard Project stage: Request ML12326B0002012-11-0909 November 2012 Donald C, Cook, Units 1 and 2 - Enclosure 4 (Cont.) to AEP-NRC-2012-101, Response to Second-Round RAI Item 54.b, and Submittal of Revised Tables Re the Application for Amendment to Transition to National Fire Protection Association Standard Project stage: Request ML12326A9982012-11-0909 November 2012 Donald C. Cook, Units 1 and 2 - Response to Second-Round Request for Additional Information Item 54.b and Submittal of Revised Tables Re the Application for Amendment to Transition to National Fire Protection Association Standard 805 Project stage: Request ML12345A3272012-12-13013 December 2012 Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: RAI ML13028A1132013-01-14014 January 2013 Response to Third Round Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Request AEP-NRC-2013-09, Revised Response to First Round Request for Additional Information Re Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052013-02-0101 February 2013 Revised Response to First Round Request for Additional Information Re Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Request ML13014A5492013-02-0101 February 2013 Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: RAI ML13085A1842013-04-22022 April 2013 Review and Conclusion of Indiana Michigan Power Company'S Resolution of Facts and Observations in Support of DC Cook'S Transition to NFPA 805 Project stage: Other ML13085A2462013-04-22022 April 2013 DC Cook Table V-1 & V-2 Record of Review March 22 2013 Project stage: Request ML13085A1902013-04-22022 April 2013 DC Cook Table U Record of Review March 22 2013 Project stage: Other AEP-NRC-2013-17, Response to a Request for Additional Information (RAI 29.01, 61, and 62) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052013-05-0101 May 2013 Response to a Request for Additional Information (RAI 29.01, 61, and 62) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Response to RAI AEP-NRC-2013-55, Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630).2013-06-21021 June 2013 Response to a Request for Additional Information Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 TAC (ME6629 and ME6630). Project stage: Response to RAI ML13210A2042013-09-0606 September 2013 Request for Additional Information on the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: RAI AEP-NRC-2013-75, Response to a Request for Additional Information (RAI 63) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 8052013-09-16016 September 2013 Response to a Request for Additional Information (RAI 63) Regarding the Application for Amendment to Transition the Fire Protection Program to National Fire Protection Association Standard 805 Project stage: Response to RAI ML13140A3982013-10-24024 October 2013 Issuance of Amendment Nos. 322 and 305 - Transition to NFPA 805 Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) and NFPA 805 Project stage: Approval 2012-08-14
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Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh) ML17108A7772017-04-18018 April 2017 17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh) ML17068A0652017-03-0808 March 2017 Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj) ML17027A0192017-01-26026 January 2017 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484) ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control IR 05000315/20160042016-07-11011 July 2016 Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16193A6542016-07-11011 July 2016 Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML16025A0552016-01-22022 January 2016 Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316 ML15267A6832015-10-0505 October 2015 Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15231A5542015-08-18018 August 2015 Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd) ML15225A5772015-08-13013 August 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2 ML15163A1672015-06-15015 June 2015 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15149A3832015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15119A3392015-05-0505 May 2015 Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal ML15055A5702015-02-24024 February 2015 Cyber Security RFI Temporary Instruction 2201/004 ML15022A1532015-01-21021 January 2015 Dccook ISI Request for Information 2024-06-26
[Table view] Category:Letter
MONTHYEARAEP-NRC-2024-62, Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask2024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) AEP-NRC-2024-11, Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation2024-02-27027 February 2024 Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation ML24037A0522024-02-0707 February 2024 NRC Response to DC Cook Triennial Evaluated Force-on-Force Cycle Schedule Change Request AEP-NRC-2024-10, Form OAR-1, Owners Activity Report2024-02-0707 February 2024 Form OAR-1, Owners Activity Report IR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation 2024-08-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 13, 2012 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUB~IECT: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION ON THE APPLICATION FOR AMENDMENT TO TRANSITION THE FIRE PROTECTION PROGRAM TO NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. ME6629 AND ME6630)
Dear Mr. Weber:
By letter dated July 1, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11188A145), as supplemented by letters dated September 2,2011, April 27, 2012, June 29,2012, August 9,2012, October 15,2012, and November 9,2012, Indiana Michigan Power Company (I&M) submitted an application for a license amendment to transition the Donald C. Cook Nuclear Plant, Units 1 and 2, fire protection program, from Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48(b), to 10 CFR 50.48(c), National Fire Protection Association Standard (NFPA) 805. Some portions of the supplemental information contain security related information and are therefore withheld from public disclosure.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittals and determined that additional information is needed to complete the review, as described in the enclosure, request for additional information (RAI). The NRC staff had discussed the RAI in draft form with your staff on December 6, 2012. During that discussion, the NRC staff agreed to revise certain draft questions. Your staff also agreed to formally submit your response within 30 days from the date of this letter.
Please note that the NRC staff's review efforts are continuing and additional RAls may be forthcoming.
L. Weber - 2 Please feel free to contact me if you need any further clarification of the questions in the enclosure.
Sincerely.
~~::~M.n.ger Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information (RAI) cc: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION (RAil LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 RAI 20.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 and the enclosure, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12242A246) and the non-public enclosure, you responded to RAI-20, Probabilistic Risk Assessment (PRA), Internal Events PRA (lEPRA),
explaining that a gap assessment was performed on the differences in supporting requirements (SRs) between PRA Standard RA-Sa-2009, as clarified by Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Result for Risk-Informed Activities", Rev, 2, and RA-Sa-2003, "Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications," (which was initially used to review the internal events PRA). As part of the assessment, gap findings were generated and a sensitivity study was performed to address a subset of the issues. Clarify the following gap finding:
- a. A finding against SR LE-B3, which requires using engineering analysis to support PRA modeling, identifies two large early release frequency (LERF) modeling assumptions that were not justified with engineering assessment but have beneficial impacts on the LERF estimate. The dispOSition for this gap finding states that these assumptions are expected to be confirmed by analysis. The assumptions are not identified. Identify the assumptions made, and explain why they are expected to be confirmed by analysis.
- b. A finding against SR LE-A4, which requires dependencies between the Level 1 and Level 2 PRA to be properly treated, identifies that in some cases, assumptions were made that may yield non-conservative results. The disposition to this finding states that the licensee's use of NUREG/CR-6595, "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events," produces a bounding model but also states that a sensitivity study examines the impact of this issue. The finding against LE-A4 is not identified in the sensitivity study identified for this RAI on page 22 of the response. Clarify how the finding against LE-A4 is being dispositioned. Include in this description how dependencies between Level 1 and Level 2 are treated and clarify how SR LE-A4 is met.
Enclosure
- 2 RAI 30.01 Probabilistic Risk Assessment In your letter dated April 27, 2012 (ADAMS Accession No. ML12132A390) you responded to RAI-30, Probabilistic Risk Assessment, Uncertainty, discussing the results of sensitivity analyses using frequently asked question (FAQ) 08-0048 (ADAMS Accession No. ML092190457) fire ignition frequencies and the substantial risk reduction obtained from crediting a local operator action to restore the turbine driven auxiliary feedwater pump N train battery charger after it is tripped following loss of offsite power or after a safety injection signal.
Given that including this action reduces the sensitivity study results to below the risk acceptance criteria in RG 1.174, discuss whether the RA is or will be included in the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," fire protection program. If included, provide the additional risk of this RA. If not included in the NFPA 805 fire protection program, provide justification for not including it.
RAI 34.01 Probabilistic Risk Assessment In your letter dated August 9, 2012 (ADAMS Accession No. ML12242A246) and the non-public enclosure, you responded to RAI-34e, Probabilistic Risk Assessment, Peer Review F&Os, discussing the results of sensitivity analyses that shows that using the "Special Weighting Factors" for transient fire frequency apportionment compared to using the nominal NUREG/CR 6850, "EPRIINRC-RES Fire PRA Methodology for Nuclear Power Facilities," (no fractional values) method will result in the delta core damage frequency (CDF) exceeding the RG 1.174 risk acceptance criteria. Provide the corresponding results for LERF and delta LERF.
L. Weber -2 Please feel free to contact me if you need any further clarification of the questions in the enclosure.
Sincerely, IRA!
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information (RAI) cc: Distribution via ListServ DISTRIBUTION:
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