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MONTHYEARML12100A1022012-03-30030 March 2012 NRR E-mail Capture - Acceptance Review for CR3 - LAR 312- Departure from a Method of Evaluation for Aux Bldg Over Head Crane, Implementation Schedule Change Project stage: Acceptance Review ML12136A3922012-06-26026 June 2012 Issuance of Amendment Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments Project stage: Approval 2012-03-30
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Category:Letter
MONTHYEARIR 05000302/20240012024-09-23023 September 2024 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, NRC Inspection Report No. 05000302/2024001 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24226B2392024-08-27027 August 2024 Application for License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Acknowledgement of Withdrawal ML24179A0702024-07-26026 July 2024 SHPO S106 Completion Crystal River Unit 3 ML24205A2192024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Muscogee Nation ML24205A2182024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Nation of Oklahoma ML24179A0912024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Tribe of Florida ML24205A2202024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3_Miccosukee Tribe of Florida ML24190A1912024-07-0808 July 2024 Fws Concurrence for Crystal River Unit 3 ML24172A2552024-06-20020 June 2024 Fws to NRC Species List: Florida Ecological Services Field Office 06/20/2024 ML24170A9242024-06-18018 June 2024 024-0023697 Crystal River License Termination Plan Unit 3 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24114A2262024-04-24024 April 2024 Amended Special Package Authorization for the Cr3 Middle Package (Crystal River 3 Middle Package - Docket No. 71-9393) IR 05000302/20230022024-04-17017 April 2024 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2023002 ML24054A0612024-04-0202 April 2024 Request to Initiate Section 106 Consultation Regarding the License Termination Plan for Crystal River Unit 3 in Citrus County, Florida ML24079A2492024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Johnson, Lewis Johnson ML24054A0582024-04-0202 April 2024 Achp S106 Initiation Crystal River Unit 3 - Letter 1 ML24079A2472024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Cypress, Talbert ML24079A2482024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Hill, David Hill ML24054A0812024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Osceola, Marcellus ML24089A0362024-03-29029 March 2024 Response to Audit Plan in Support of Accelerated Decommissioning Partners and Request to Add License Condition to Include License Termination Plan Requirements. W/Enclosures 1 to 5 ML24073A1922024-03-11011 March 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24054A6452024-02-29029 February 2024 Letter - Reply to Request for RAI Extension Related to the Crystal River License Termination Plan ML24030A7482024-02-12012 February 2024 Audit Report Cover Letter and Report - Crystal River Unit 3 Nuclear Generating Plant LTP ML23342A0942024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23345A1882023-12-0606 December 2023 Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML23320A2592023-11-17017 November 2023 STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice ML23313A1322023-11-15015 November 2023 Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant ML23310A0712023-11-0707 November 2023 Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP ML23187A1112023-07-25025 July 2023 Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements ML23107A2722023-06-13013 June 2023 Letter Transmitting NRC Survey Results for East Settling Pond ML23160A2962023-06-0909 June 2023 Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 IR 05000302/20220032023-05-25025 May 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003 ML23103A1902023-04-19019 April 2023 Request for Supplemental Information Cover Letter ML23058A2532023-03-22022 March 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River, Unit 3 - NRC Inspection Report No. 05000302/2022003 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22265A0192022-09-26026 September 2022 Nuclear Generating Plant - U.S. Nuclear Regulatory Commission'S Analysis of ADP CR3, Llc'S Decommissioning Funding Status Report (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20220022022-08-0909 August 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022002 IR 05000302/20220012022-05-0303 May 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022001 ML22116A1752022-04-27027 April 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3- Independent Spent Fuel Storage Installation Security Inspection Report 07201035/2022401 ML22105A3992022-04-18018 April 2022 Nuclear Generating Plant - Change in NRC Project Manager ML22011A1362022-01-31031 January 2022 Independent Spent Fuel Storage Installation Security Inspection Plan ML22024A2142022-01-24024 January 2022 Nuclear Generating Plant - NMFS NRC Letter - Crystal River Energy Complex Biological Opinion Status (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20210042022-01-24024 January 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004 ML21351A0052021-12-20020 December 2021 NRC Analysis of ADP CR3, LLC Decommissioning Funding Status Report for the Crystal River Unit 3 Nuclear Generating Plant (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21322A2702021-11-24024 November 2021 Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3 IR 05000302/20210032021-11-0909 November 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021003 and 07201035/2021001 ML21288A4292021-10-18018 October 2021 Letter - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan 2024-09-23
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML21322A2702021-11-24024 November 2021 Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3 ML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a ML20069A0262020-04-0101 April 2020 CR-3 License Transfer Enc 2 Att 1 FOL Amnd 258.doc ML20069A0252020-04-0101 April 2020 CR-3 License Transfer Enc 2 Amendment ML19129A1412019-05-15015 May 2019 Corrected Page for Amendment No. 257 to License No. DPR-072 for Duke Energy Florida, Inc ML19080A1872019-05-0303 May 2019 Enclosure 1 Amendment No. 257 to License No. DPR-72 Duke Energy Florida, Inc., Crystal River, Unit 3, Docket No. 50-302 ML18017A9882018-02-14014 February 2018 Amendment No. 256 to License No. DPR-72 Duke Energy Florida, LLC Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 ML17027A1612017-06-27027 June 2017 Enclosure 1, Amendment to Crystal River License No. DPR-72 ML17027A1632017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254, Table of Contents ML17027A1642017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254, Section 4.0 ML17027A1652017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254 Section 5.0 ML17027A1602017-06-27027 June 2017 Ltr to T. Hobbs re: Crystal River Unit 3 Nuclear Generating Plant - Amendment to Permanently Defueled Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pools ML17027A1622017-06-27027 June 2017 Facility Operating License Pages ML17096A2812017-06-22022 June 2017 Amendment to License No. DPR-72 Duke Energy Florida, LLC Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 ML17096A2822017-06-22022 June 2017 FOL Amnd 254 ML17048A4782017-03-22022 March 2017 Amendment to License No. DPR-72 for ISFSI Emergency Plan and EAL Bases Manual ML16244A1012016-12-0505 December 2016 Amendment Approving ISFSI Emergency Plan ML16293A2002016-11-30030 November 2016 Operating License Amendment 251 Changed Pages ML16173A0232016-08-10010 August 2016 Revised License Pages for License Transfer, Crystal River Unit 3 ML16173A0212016-08-10010 August 2016 Conforming Amendment for License Transfer, Crystal River Unit 3 ML15261A4522015-11-27027 November 2015 Nuclear Generating Plant - Issuance of Amendment No. 249 Regarding Technical Specification Change of Management Titles to General Manager Decommissioning ML15224B2862015-09-0404 September 2015 Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status ML15121A5702015-05-29029 May 2015 Letter, Safety Evaluation for Order Approving Transfer of Licenses and Conforming Amendments ML15027A2092015-03-31031 March 2015 Issuance of Amendment Regarding Changes to the Emergency Plan and Emergency Action Levels ML14318A9292014-12-19019 December 2014 H. B. Robinson; Shearon Harris Nuclear Power Plant; and Crystal River, Unit 3 - Issuance of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date (TAC Nos. MF3263 - MF3267) ML14097A1452014-07-11011 July 2014 Nuclear Generating Plant - Issuance of Amendment No. 244, Revise Technical Specifications to Remove Certain Requirements from Section 5, Administrative Controls ML13158A2772013-10-18018 October 2013 Issuance of Amendment Regarding the Request to Change the Licensee'S Name ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security ML12136A3922012-06-26026 June 2012 Issuance of Amendment Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML12081A2792012-03-19019 March 2012 License Amendment Request #312, Revision 0, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane - Implementation Schedule Change Request ML11292A0412012-02-24024 February 2012 Nuclear Generating Plant - Issuance of Amendment 240 Regarding Improved Technical Specifications 3.7.19 Diesel Drive Emergency Feedwater Pump Fuel Oil, Lube Oil, and Starting Air ML11321A1652011-12-27027 December 2011 Nuclear Generating Plant - Issuance of Amendment 239 Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML11193A0282011-07-29029 July 2011 Issuance of Amendments Approval of Cyber Security Plan ML0911000562009-05-29029 May 2009 License Amendment, Issuance of Amendment Regarding the Revision of the Steam Generator Portion of the Technical Specifications to Replacement of the Steam Generators ML0834704912009-01-0909 January 2009 Issuance of Amendment Regarding Revisions to Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System ML0820200062008-07-30030 July 2008 Issuance of Amendment 230 Regarding Control Room Envelope Habitability in Accordance with TSTF-448 ML0801403722008-01-14014 January 2008 Cyrstal River Unit 3 - Administrative Correction to Amendment Steam Generator Reporting Requirements (Tac. MD7453) ML0729103172007-10-25025 October 2007 License Amendment 227 Fuel Storage Patterns in the Spent Fuel Pool ML0725501372007-10-24024 October 2007 Issuance of Amendment Regarding Spent Fuel Pool Missile Shields ML0728508942007-10-23023 October 2007 License Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System ML0723400102007-08-23023 August 2007 Revised Pages of Facility Operating License DPR-72 B.5.b ML0715004662007-06-15015 June 2007 License Amendment, Issuance of Amendment to Adopt TSTF-372 ML0713401122007-05-16016 May 2007 Issuance of License Amendment 223 Regarding Steam Generator Tube Inspection Program ML0709401402007-03-27027 March 2007 Administrative Amendment for EA-06-037 ML0529401792005-10-31031 October 2005 License Amendment, Probabilistic Methodology for Tube End Crack Alternate Repair Criteria, TAC No. MC5813 ML0525900462005-09-15015 September 2005 License Amendment, Temporary Extension of the Nuclear Services Seawater System Train Completion Time ML0522101892005-09-0606 September 2005 License Amendment No. 220 Regarding Removal of Obsolete Footnotes from the Technical Specifications ML0517103812005-08-0404 August 2005 License Amendment, Reactor Building Spray Nozzle Surveillance Requirement ML0518903482005-07-27027 July 2005 Amendment 218, Surveillance Requirements for RCP Flywheel Inspection ML0511104972005-04-19019 April 2005 Amendment 217, TS Revision to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Reports Requirements 2021-11-24
[Table view] Category:Safety Evaluation
MONTHYEARML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML20101G5832020-04-10010 April 2020 CR-3 License Transfer SE Corrected ML20101G5822020-04-10010 April 2020 CR-3 License Transfer SE Corrected Cover Letter ML20069A0272020-04-0101 April 2020 CR-3 License Transfer Enc 3 SE ML20009D0432020-01-10010 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility Operating License No. DPR-72 ML20009D2502020-01-10010 January 2020 SER Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility ML19339G5092020-01-0202 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19080A1892019-05-0303 May 2019 Rev 1 Safety Evaluation ML17027A1672017-06-27027 June 2017 Safety Evaluation ML17096A2832017-06-22022 June 2017 Non-Sensitive Safety Evaluation by the Office of Nuclear Material Safety and Safeguards for Crystal River Unit 3 ML17048A4832017-03-22022 March 2017 Safety Evaluation for CR-3 ISFSI Emergency Plan and EAL Bases Manual ML16244A1032016-12-0505 December 2016 Safety Evaluation for Crystal River Unit 3 ISFSI Emergency Plan ML16201A1352016-08-12012 August 2016 Safety Evaluation Input for Independent Spent Fuel Storage Installation Only Emergency Plan ML16173A0222016-08-10010 August 2016 Safety Evaluation for License Transfer, Crystal River Unit 3, from Seminole Electric Corp., Inc. to Duke Energy Florida, Inc ML15261A4522015-11-27027 November 2015 Nuclear Generating Plant - Issuance of Amendment No. 249 Regarding Technical Specification Change of Management Titles to General Manager Decommissioning ML15224B2862015-09-0404 September 2015 Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status ML15121A5702015-05-29029 May 2015 Letter, Safety Evaluation for Order Approving Transfer of Licenses and Conforming Amendments ML15110A1292015-04-22022 April 2015 Correction to the Emergency Planning Exemptions Safety Evaluation ML15027A2092015-03-31031 March 2015 Issuance of Amendment Regarding Changes to the Emergency Plan and Emergency Action Levels ML15058A9062015-03-30030 March 2015 Letter, Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation ML14344A4082014-12-19019 December 2014 Nuclear Generating Plant - Review of Spent Fuel Management Program and the Preliminary Decommissioning Cost Estimate ML14318A9292014-12-19019 December 2014 H. B. Robinson; Shearon Harris Nuclear Power Plant; and Crystal River, Unit 3 - Issuance of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date (TAC Nos. MF3263 - MF3267) ML14097A1452014-07-11011 July 2014 Nuclear Generating Plant - Issuance of Amendment No. 244, Revise Technical Specifications to Remove Certain Requirements from Section 5, Administrative Controls ML14155A1812014-06-26026 June 2014 Review of Certified Fuel Handler Training and Retraining Program ML13158A2772013-10-18018 October 2013 Issuance of Amendment Regarding the Request to Change the Licensee'S Name ML13121A1092013-05-0909 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security ML12249A2362012-10-11011 October 2012 Nuclear Generating Plant - Relief Request #11-001-MX Related to Suspension of Concrete Containment Examination for the Fourth-10-Year Interval of the Inservice Inspection Program ML12136A3922012-06-26026 June 2012 Issuance of Amendment Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML11292A0412012-02-24024 February 2012 Nuclear Generating Plant - Issuance of Amendment 240 Regarding Improved Technical Specifications 3.7.19 Diesel Drive Emergency Feedwater Pump Fuel Oil, Lube Oil, and Starting Air ML11321A1652011-12-27027 December 2011 Nuclear Generating Plant - Issuance of Amendment 239 Regarding Departure from a Method for Evaluating the Auxiliary Building Overhead Crane and Revisions to Associated Commitments ML11255A0552011-12-0202 December 2011 Transmittal Letter - Order Approving Indirect License Transfer ML11193A0282011-07-29029 July 2011 Issuance of Amendments Approval of Cyber Security Plan ML1006400842010-03-19019 March 2010 Relief Requests 09 001 II, 09 002 II, and 09 003 II, Third 10-year Interval Inservice Inspection Program Plan. ML0911000562009-05-29029 May 2009 License Amendment, Issuance of Amendment Regarding the Revision of the Steam Generator Portion of the Technical Specifications to Replacement of the Steam Generators ML0834704912009-01-0909 January 2009 Issuance of Amendment Regarding Revisions to Improved Technical Specification Surveillance Requirement 3.7.5.2, Emergency Feedwater System ML0822103922008-09-0909 September 2008 Request for Relief No. 07-001-SS Regarding the Fourth 10-Year Interval Inservice Inspection Visual Examination of the Reactor Vessel Support Skirt ML0817502522008-07-31031 July 2008 Relief Request No. 07-00-001- Pt Fourth Ten-Year Interval Inservice Inspection on System Pressure Test Boundary Tac MD7738) ML0820200062008-07-30030 July 2008 Issuance of Amendment 230 Regarding Control Room Envelope Habitability in Accordance with TSTF-448 ML0812604712008-05-22022 May 2008 Relief Request #08-001-RR, Revision 1, to Install a Weld Overlay on the Dissimilar Metal Weld in the Decay Heat Drop Line ML0730301322007-11-15015 November 2007 Relief Request #07-003-RR Regarding Structural Weld Overlays ML0729103172007-10-25025 October 2007 License Amendment 227 Fuel Storage Patterns in the Spent Fuel Pool ML0725501372007-10-24024 October 2007 Issuance of Amendment Regarding Spent Fuel Pool Missile Shields ML0728508942007-10-23023 October 2007 License Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System ML0722600082007-08-23023 August 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 (Tac No. MD4524) ML0715004662007-06-15015 June 2007 License Amendment, Issuance of Amendment to Adopt TSTF-372 ML0713401122007-05-16016 May 2007 Issuance of License Amendment 223 Regarding Steam Generator Tube Inspection Program ML0709505032007-04-27027 April 2007 Evaluation of 2005 Steam Generator Tube Inspections at Crystal River Unit 3 ML0622005742006-10-19019 October 2006 Authorization for Use of Delta Protection Mururoa Single-Use, Supplied-Air Suits, Models V4 F1 and V4 Mth 2 2021-06-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 June 26,2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 1S760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING -ISSUANCE OF AMENDMENT REGARDING DEPARTURE FROM A METHOD FOR EVALUATING THE AUXILIARY BUILDING OVERHEAD CRANE AND REVISIONS TO ASSOCIATED COMMITMENTS (TAC NO. ME8234)
Dear Mr. Franke:
The U.S. Nuclear Regulatory Commission (Commission, NRC) has issued the enclosed Amendment No. 241 to Facility Operating License No. DPR-72 for Crystal River Unit 3 Nuclear Generating Plant in response to your license amendment request (LAR) No. 312, in your letter dated March 19, 2012. The NRC issued Amendment No. 239, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane (FHCR-S), on December 27, 2011. Amendment No. 239 was approved to be implemented within 180 days of issuance of the amendment. In LAR No. 312, Revision 0, the licensee requested additional time to complete the implementation of Amendment No. 239 from 180 days to 90 days prior to moving a spent fuel shipping cask with FHCR-S. The licensee requested extending the implementation period to allow for installation and testing of the new single failure proof FHCR-S.
A copy of the safety evaluation is enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, fa~'J..-J. £. ~h~
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. SO-302
Enclosures:
- 1. Amendment No. 241 to DPR-72
- 2. Safety Evaluation cc w/enclosures: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 241 License No. DPR-72
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that A. The application for amendment by Florida Power Corporation, et al. (the licensees),
dated March 19, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (1 0 CFR)
Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance 0) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by approving changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 241 ,are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This amendment revises the completion time for Amendment No. 239 from 180 days to "Implementation shall be completed 90 days prior to moving a spent fuel shipping cask with FHCR-5." This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~~~-
Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License Date of Issuance: June 26) 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 241 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following page of Facility Operating License No. DPR-72 with the attached revised page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove 4
- 4 of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
2.C.(1) Maximum Power Level Florida Power Corporation is authorized to operate the facility at a steady state reactor core power level not in excess of 2609 Megawatts (100 percent of rated core power level).
2.C.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 241, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
The Surveillance Requirements contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment 149. The Surveillance Requirements shall be successfully demonstrated prior to the time and condition specified below for each.
a) SR 3.3.8.2.b shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.
b) SR 3.3.11.2, Function 2, shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.
c) SR 3.3.17.1, Functions 1, 2, 6, 10, 14, & 17 shall be successfully demonstrated no later than 31 days following the implementation date of the ITS.
d) SR 3.3.17.2, Function 10 shall be successfully demonstrated prior to entering MODE 3 on the first plant start-up following Refuel Outage 9.
e) SR 3.6.1.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.
f) SR 3.7.12.2 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up followillg Refuel Outage 9.
g) SR 3.8.1.10 shall be successfully demonstrated prior to entering MODE 2 on the first plant start-up following Refuel Outage 9.
h) SR 3.8.3.3 shall be successfully demonstrated prior to entering MODE 4 on the first plant start-up following Refuel Outage 9.
Facility Operating License No. DPR-72 Amendment No. 241
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 241 TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION. ET AL.
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302
1.0 INTRODUCTION
By letter dated March 19, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12081A279), Florida Power Corporation (FPC, the licensee) submitted a license amendment request (LAR) 312 for the Crystal River Unit 3 Nuclear Generating Plant (CR-3). The U.S. Nuclear Regulatory Commission (Commission, NRC) issued Amendment No. 239, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane (FHCR-5), on December 27,2011. Amendment No. 239 was approved to be implemented within 180 days of issuance of the amendment. In LAR No. 312, Revision 0, the licensee requested additional time to complete the implementation of Amendment No. 239 from 180 days to 90 days prior to moving a spent fuel shipping cask with FHCR-5. The licensee requested extending the implementation period to allow for installation and testing of the new single failure proof FHCR-5. The licensee stated that the future replacement of the crane (FHCR-5) along with the revisions to the Final Safety Analysis Report (FSAR) will not be completed within the currently approved implementation schedule. The licensee further stated that the FSAR revisions are not appropriate until after the crane is replaced and placed in service. Therefore, the licensee requested the NRC's approval to revise the implementation schedule for Amendment No. 239.
2.0 REGULATORY ANALYSIS
In order to maintain full-core offload capacity in the spent fuel pools, CR-3 will be constructing and operating an on-site Independent Spent Fuel Storage Installation as a general licensee under the prOVisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste," Subpart K, "General License for Storage of Spent Fuel at Power Reactor Sites." The spent fuel pools are located in the CR-3 Auxiliary Building (AB). In support of future cask loading operations, FPC is replacing the existing AB FHCR-5 with a new Single failure proof crane designed in accordance with American Society of Mechanical Engineers NOG-1-2004, "Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)."
-2 The requested revision to the implementation schedule has no safety consequences and will not have an impact on the plant's ability to store spent fuel. The proposed LAR implementation schedule change request is administrative in nature and does not change the regulatory evaluation of the NRC approved Amendment No. 239, or the applicable regulatory requirements this was based on.
3.0 TECHNICAL EVALUATION
By letter dated July 20,2011 (ADAMS Accession No. ML11256A074), CR-3 submitted LAR 310, Revision 1, "Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane, Revisions to Associated Commitments, and Response to Request for Additional Information (TAC No. ME5208)." The licensee in LAR 310 stated that it would perform analyses to qualify the new single failure proof AB overhead crane and perform calculations to qualify and upgrade the crane support structure. The NRC approved LAR 310 by letter dated December 27,2011, and issued Amendment No. 239 (ADAMS Accession No. ML11321A165). Amendment No. 239 implementation was identified to be completed within 180 days of issuance of the amendment.
The licensee in the proposed LAR 312 stated that it is proceeding with the implementation of Amendment No. 239 and procedure changes have been issued to implement the regulatory commitment to prohibit/suspend cask handling operations when high wind conditions such as tornadoes, hurricanes, or tropical Storms are forecast. Modifications, as required, to upgrade the crane support structures are ongoing. However, the licensee stated that the installation of the new FHCR-5 and revisions to the CR-3 FSAR will not be completely implemented within 180 days of issuance of Amendment No. 239, due to unforeseen circumstances causing project scope growth.
In LAR 312, the licensee requested additional time to complete the implementation of Amendment No. 239 from 180 days to, "Implementation shall be completed 90 days prior to moving a spent fuel shipping cask with FHCR-5." The licensee stated that the requested revision to the implementation schedule will have no safety consequences because of the current load restrictions on the existing FHCR-5, and the ongoing structural upgrades to the crane support structure. The licensee added that extending the implementation period is needed to allow for installation and testing of the new single failure proof FHCR-5.
Further, the licensee stated that there is no adverse change to the plant configuration or operation as a result of a change request to the Amendment No. 239 implementation schedule.
No fuel will be moved with the existing FHCR-5 and no spent fuel cask loading operations will be performed until after the new single failure proof crane is operational.
The licensee also stated that the requested revision to the implementation schedule is administrative in nature and has no safety consequences. Revising the implementation schedule will allow adequate time to complete all actions necessary for implementation. The proposed amendment implementation schedule change will not adversely impact plant or personal safety. The licensee further stated that the FSAR pages provided in LAR 310, Revision 1, dated July 20, 2011, also remain valid and unchanged.
-3 Based on its review, the NRC staff found the licensee's request acceptable, because implementation will be completed 90 days before moving a spent fuel shipping cask with FHCR-S. No fuel will be moved with the existing FHCR-S, and no spent fuel cask loading operations will be performed until the new single-failure-proof crane is operational. The NRC staff determined that revising the implementation schedule will allow adequate time to complete all actions necessary for implementation, and it will not have an adverse effect on plant or personal safety. Further, the requested revision to the implementation schedule has no safety consequences and will not have an impact on the plant's ability to store spent fuel. In addition, the CR-3 FSAR changes provided in LAR 310, Revision 1, dated July 20, 2011, also remain valid and unchanged. Therefore, the NRC staff concluded that the licensee's proposed license amendment to complete the implementation of Amendment No. 239 from 180 days to, "Implementation shall be completed 90 days prior to moving a spent fuel shipping cask with FHCR-S" is acceptable.
4.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
S.O ENVIRONMENTAL CONSIDERATIONS The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no Significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (April 17, 2012; 77 FR 22814). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR S1.22(c)(9). Pursuant to 10 CFR S1.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Dan Hoang Date: June 26, 2012
June 26, 2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING - ISSUANCE OF AMENDMENT REGARDING DEPARTURE FROM A METHOD FOR EVALUATING THE AUXILIARY BUILDING OVERHEAD CRANE AND REVISIONS TO ASSOCIATED COMMITMENTS (TAC NO. ME8234)
Dear Mr. Franke:
The U.S. Nuclear Regulatory Commission (Commission, NRC) has issued the enclosed Amendment No. 241 to Facility Operating License No. DPR-72 for Crystal River Unit 3 Nuclear Generating Plant in response to your license amendment request (LAR) No. 312, in your letter dated March 19, 2012. The NRC issued Amendment No. 239, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane (FHCR-5), on December 27, 2011.
Amendment No. 239 was approved to be implemented within 180 days of issuance of the amendment. In LAR No. 312, Revision 0, the licensee requested additional time to complete the implementation of Amendment No. 239 from 180 days to 90 days prior to moving a spent fuel shipping cask with FHCR-5. The licensee requested extending the implementation period to allow for installation and testing of the new single failure proof FHCR-5.
A copy of the safety evaluation is enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
- 1. Amendment No. 241 to DPR-72
- 2. Safety Evaluation cc w/enclosures: Distribution via ListServ Distribution:
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