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Category:Letter
MONTHYEARIR 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 IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 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 IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Federal Register Notice
MONTHYEARML21251A3692021-09-21021 September 2021 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures: Octobe ML21004A0652021-01-0606 January 2021 Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specifications to Allow One-Time Change to Integrated Leak Rate Test Interval to No Later than Plant Startup After Fall 2022 Refueling Outage ML21004A0442021-01-0606 January 2021 Letter, Individual Notice of Consideration of Issuance of Amendment, Revise Technical Specifications to Allow One-Time Change to Integrated Leak Rate Test Interval to No Later than Plant Startup After Fall 2022 Refueling Outage ML20353A2252020-12-28028 December 2020 FRN, Individual Notice of Consideration of Issuance of Amendment, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing - One-Time Deferral of Steam Generator Inspection ML20353A2242020-12-28028 December 2020 Ltr, Individual Notice of Consideration of Issuance of Amendment, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing - One-Time Deferral of Steam Generator Inspection ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20191A0072020-10-0101 October 2020 Exemptions from Certain Requirements of 10 CFR 54.37 and 10 CFR 50.54 (L-2020-LLE-0052 and L-2020-LLE-0053) ML20035C4082020-02-18018 February 2020 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020 ML19295F0902019-11-0505 November 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/05/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 ML18295A7442018-10-25025 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/06/18 ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 20162016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16257A5172016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16229A2552016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 NRC-2016-0180, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 20162016-08-18018 August 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations- Publication Date: August 30, 2016 ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML15356A5992015-12-29029 December 2015 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016 ML15204A2792015-07-27027 July 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 4, 2015 NRC-2015-0104, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register2015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register ML15106A9162015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML14177A6452014-06-27027 June 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 20142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML14037A4142014-02-10010 February 2014 Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014 ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML12142A2872012-08-23023 August 2012 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo Clad Fuel Rods ML12142A2992012-08-23023 August 2012 Exemption from 10 CFR 50.46 and App. K of 10 CFR 50 to Permit Use of Optimized Zirlo NRC-2012-0199, D. C. Cook: Environmental Assessment for Optimized Zirlo Fuel Amendment and Exemption2012-08-16016 August 2012 D. C. Cook: Environmental Assessment for Optimized Zirlo Fuel Amendment and Exemption ML12124A2512012-08-16016 August 2012 Environmental Assessment for Optimized Zirlo Fuel Amendment and Exemption ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations2011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations ML1126504892011-09-22022 September 2011 FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations NRC-2011-0216, September 20, 2011 Applications and Amendments to Facility Operating License Involving No Significant Hazards Considerations2011-09-0808 September 2011 September 20, 2011 Applications and Amendments to Facility Operating License Involving No Significant Hazards Considerations ML11251A0092011-09-0808 September 2011 September 20, 2011 Applications and Amendments to Facility Operating License Involving No Significant Hazards Considerations NRC-2011-0188, Exemption for Use of Optimized Zirlo as Fuel Rod Cladding Material2011-08-24024 August 2011 Exemption for Use of Optimized Zirlo as Fuel Rod Cladding Material ML1116100442011-08-24024 August 2011 Exemption for Use of Optimized Zirlo as Fuel Rod Cladding Material ML1116100542011-08-24024 August 2011 Letter Transmitting Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML11195A1232011-08-11011 August 2011 Letter Transmitting Environmental Assessment Regarding Fuel Burnup Limit of 62 Gwd/Mtu NRC-2011-0040, Sholly Report for Fr Publication on February 22, 20112011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 ML1104103732011-02-10010 February 2011 Sholly Report for Fr Publication on February 22, 2011 ML1026701882010-09-28028 September 2010 Transmittal Letter Notice of Consideration for Issuance of Amendment, Technical Specification Changes Consistent with TSTF-447, Revision 1, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors ML1026704162010-09-28028 September 2010 Federal Register Notice, Notice of Consideration for Issuance of Amendment, Technical Specification Changes Consistent with TSTF-447, Revision 1, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors 2021-09-21
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 24, 2011 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, UNIT 1, EXEMPTION FROM THE REQUIREMENTS OF 10 CFR SECTION 50.46 AND APPENDIX K TO 10 CFR PART 50 TO ALLOW THE USE OF OPTIMIZED ZIRLOŽ AS FUEL ROD CLADDING MATERIAL (TAC NO. ME5184)
Dear Mr. Weber:
The Nuclear Regulatory Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, "Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors," and Appendix K to 10 CFR Part 50, "ECCS Evaluation Models," for the Donald C. Cook Nuclear Plant, Unit 1. This action is in response to your application dated December 16, 2010, to allow the use of Optimized ZIRLO TM for fuel rod cladding.
A copy of the exemption is enclosed.
The exemption has been forwarded to the Office of the Federal Register for publication. Peter S. Tam, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
Exemption cc w/encl: Distribution via Listserv
UNITED STATES OF NUCLEAR REGULATORY INDIANA MICHIGAN POWER DONALD C. COOK NUCLEAR PLANT, UNIT DOCKET NO.
1.0 BACKGROUND
Indian Michigan Power Company (the licensee) is the holder of Facility Operating License No. DPR-58. which authorizes operation of the Donald C. Cook Nuclear Plant, Unit 1 (CNP-1). The license provides, among other things. that the facility is subject to all rules. regulations, and orders of the Nuclear Regulatory Commission (NRC. the Commission) now or hereafter in effect. The facility consists of a pressurized-water reactor located in Berrien County in Michigan.
2.0 REQUEST/ACTION Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.12, "Specific exemptions," the licensee has, by letter dated December 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 103630358), requested an exemption from 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," and Appendix K to 10 CFR 50, "ECCS Evaluation Models." The regulations in 1 0 CFR 50.46 contain acceptance criteria for the emergency core cooling system (ECCS) for reactors fueled with zircaloy or ZIRLOŽ cladding.
In addition, Appendix K to 10 CFR Part 50 requires that the Baker-Just equation be used to
-predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal/water reaction.
The Baker-Just equation assumes the use of a zirconium alloy, which is a material different from Optimized ZIRLOTM. The licensee's requested exemption relates solely to the specific types of cladding material specified in these regulations.
As written, the regulations presume the use of zircaloy or ZIRLOŽ fuel rod cladding.
Thus, an exemption from the requirements of 1 0 CFR 50.46 and Appendix K is needed to support the use of a different fuel rod cladding material.
Accordingly, the licensee requested an exemption that would allow the use of Optimized ZIRLOŽ fuel rod cladding at CNP-1. 3.0 DISCUSSION Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under 10 CFR 50. 12(a)(2), special circumstances include, among other things, when application of the specific regulation in the particular circumstance would not serve, or is not necessary to achieve, the underlying purpose of the rule. Authorized by Law This exemption would allow the use of Optimized ZIRLO Ž fuel rod cladding material at CNP-1. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR Part 50. The NRC staff has determined that granting of the licensee's proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission's regulations.
Therefore, the exemption is authorized by law.
-No Undue Risk to Public Health and Safety The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for ECCS performance.
Westinghouse topical reports WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLOŽ,
dated July 2006, contain the justification to use Optimized ZIRLOŽ fuel rod cladding material in addition to Zircaloy-4 and ZIRLOŽ (these topical reports are non-publicly available because they contain proprietary information).
The NRC staff approved the use of these topical reports, subject to the conditions stated in the NRC staff's safety evaluation for each topical report. Ring compression tests performed by Westinghouse on Optimized ZIRLOŽ were reviewed and approved by the NRC staff (ADAMS Accession No. ML062080569), and demonstrate an acceptable retention of post-quench ductility up to the 10 CFR 50.46 limits of 2200 degrees Fahrenheit and 17 percent equivalent clad reacted. Furthermore, the NRC staff has concluded that oxidation measurements provided by the licensee (ADAMS Accession No. ML073130560) illustrate that oxide thickness (and associated hydrogen pickup) for Optimized ZIRLOŽ at any given burnup would be less than that for both zircaloy and ZIRLOTM. Hence, the NRC staff concludes that Optimized ZIRLOŽ would be expected to maintain improved post-quench ductility over ZIRLOTM. Finally, the licensee stated that Westinghouse will perform an evaluation to ensure that the Optimized ZIRLOŽ fuel rods continue to satisfy 10 CFR 50.46 acceptance criteria utilizing currently approved loss-of-coolant accident (LOCA) models and methods. The underlying purpose of 10 CFR Part 50, Appendix K, Section I.A.5, "Metal-Water Reaction Rate," is to ensure that cladding oxidation and hydrogen generation are appropriately limited during a LOCA and conservatively accounted for in the ECCS evaluation model. Appendix K of 10 CFR Part 50 requires that the Baker-Just equation be used in the ECCS evaluation model to determine the rate of energy release, cladding oxidation, and hydrogen generation.
Since the use of the Baker-Just equation presumes the use of zircaloy-clad fuel, strict application of the rule would not permit use of the equation for Optimized ZI RLO Ž cladding for determining acceptable fuel performance.
Westinghouse has demonstrated that the Baker-Just model is conservative in all post-LOCA scenarios with respect to the use of the Optimized ZIRLOŽ advanced alloy as a fuel cladding material.
The NRC-approved topical reports have demonstrated that predicted chemical, thermal, and mechanical characteristics of the Optimized ZIRLOŽ alloy cladding are bounded by those approved for ZIRLO Ž under anticipated operational occurrences and postulated accidents.
Reload cores are required to be operated in accordance with the operating limits specified in the technical specifications and the core operating limits report. Based on the above, no new accident precursors are created by using Optimized ZIRLO TM, thus, the probability of postulated accidents is not increased.
Also, based on the above, the consequences of postulated accidents are not increased.
Therefore, there is no undue risk to public health and safety due to using Optimized ZIRLOTM. Consistent with Common Defense and Security The proposed exemption would allow the use of Optimized ZIRLO Ž fuel rod cladding material at CNP-1. This change to the plant configuration has no relation to security issues. Therefore, the common defense and security is not impacted by this exemption.
Special Circumstances Special circumstances, in accordance with 10 CFR 50. 12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 is to establish acceptance criteria for ECCS performance.
The wording of the regulations in 10 CFR 50.46 and Appendix K is not directly applicable to Optimized ZIRLOŽ,
-5 even though the evaluations above show that the intent of the regulation is met. Therefore, since the underlying purposes of 10 CFR 50.46 and Appendix K are achieved through the use of Optimized ZIRLO TM fuel rod cladding material, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption exist.
4.0 CONCLUSION
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security.
Also, special circumstances are present. Therefore, the Commission hereby grants the licensee an exemption from the requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50, to allow the use of Optimized ZIRLOŽ fuel rod cladding material at CNP-1. Pursuant to 10 CFR 51.32, the Commission published an environmental assessmentfor this exemption on August 22, 2011 (76 FR 52356). This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 24th day of August 2011. FOR THE NUCLEAR REGULATORY COMMISSION Louise Lund, Acting Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation August 24, 2011 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1, EXEMPTION FROM THE REQUIREMENTS OF 10 CFR SECTION 50.46 AND APPENDIX K TO 10 CFR PART 50 TO ALLOW THE USE OF OPTIMIZED ZIRLOŽ AS FUEL ROD CLADDING MATERIAL (TAC NO. ME5184)
Dear Mr. Weber:
The Nuclear Regulatory Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, "Acceptance criteria for emergency core cooling systems [ECCS1 for light-water nuclear power reactors," and Appendix K to 10 CFR Part 50, "ECCS Evaluation Models," for Donald C. Cook Nuclear Plant, Unit 1. This action is in response to your application dated December 16, 2010, for exemption and amendment regarding the use of Optimized ZIRLOŽ for fuel rod cladding.
The requested amendment is addressed under separate correspondence.
A copy of the exemption is enclosed.
The exemption has been forwarded to the Office of the Federal Register for publication.
Docket No. 50-315
Enclosure:
Exemption cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-1 rtf RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-1 Resource RidsNrrDssSnpb Resource Package Accession No. ML 11209C033 Letter Accession No.: ML111610054 L Exemption Accession No.: M 111610044 Sincerely, IRA! Peter S. Tam, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLABTully Resource RidsNrrPMDCCook Resource RidsOgcRp Resource RidsRgn3MailCenter Resource DMerzke, EDO Region 3 AProffitt, NRR
- via memo dated 06/01/11 OFFICE DORULPL3-1/PM DORULPL3-1/LA DSS/SNPB/BC (A)
- OGCNLO DORULPL3-1/BC DORUD NAME PTam (TBeltz for) BTuily AAttard LSubin RPascarelli JGiitter (LLund for) DATE 06/23/11 06/01/11 06/01111 08/10/11 08/23/11 08/24/11 OFFICIAL RECORD COPY