Letter Sequence RAI |
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TAC:ME0274, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors (Approved, Closed) |
Results
Other: 3F1109-06, State of Florida Department of Environmental Protection, Conditions of Certification, 3F1209-04, Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation, ML090090233, ML090210171, ML090350657, ML090420362, ML090780840, ML091200415, ML091660559, ML091820465, ML092600889, ML092610309, ML093200023, ML093520079, ML100050166, ML100980517, ML100980519, ML100980520, ML100980523, ML100980524, ML100980525, ML100980526, ML100980528, ML101110235, ML101320401, ML101460577, ML110250183, ML110410597, ML110460629, ML110820185, ML110880294, ML11137A009, ML11140A100, ML11180A275, ML11343A639, ML12117A260, ML12213A058, ML12346A011
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MONTHYEARHNP-09-016, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors2009-02-26026 February 2009 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Project stage: Request ML0902101712009-02-27027 February 2009 Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. DPR-72 for an Additional 20-year Period Florida Power Corporation Corporation Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 Project stage: Other ML0900902332009-02-27027 February 2009 Determination of Acceptability and Sufficiency for Docketing, and Opportunity for a Hearing Regarding the Application from Florida Power Corp., for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant Project stage: Other ML0907808402009-03-31031 March 2009 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Crystal River Unit 3 Nuclear Generating Plant (TAC No ME0278) FRN Project stage: Other ML0903506572009-03-31031 March 2009 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Crystal River Unit 3 Nuclear Generating Plant Project stage: Other ML0908501762009-04-20020 April 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML0913800232009-05-11011 May 2009 Response to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI ML0912004152009-05-22022 May 2009 Proposed Review Schedule Regarding the Application from Florida Power Corporation for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant Project stage: Other ML1013204012009-05-31031 May 2009 093-89529, Environmental Support Document South Cooling Tower Laydown Area Citrus County, Florida Project stage: Other ML0904203622009-06-10010 June 2009 Nuclear Generating Plant License Renewal Review Project stage: Other ML0915900062009-07-0202 July 2009 License Amendment, Adoption of Technical Specifications Taskforce (TSTF) Standard Technical Specification Change Traveler TSTF-447, Elimination of Hydrogen Recombiners & Change to Hydrogen & Oxygen Monitors. Project stage: Acceptance Review ML0918204652009-07-0808 July 2009 Plan for the Aging Management Program Regulatory Audit Regarding the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Review Project stage: Other ML0916605592009-07-30030 July 2009 Audit Report Regarding the LRA for the Crystal River, Unit 3 Project stage: Other ML0917400702009-08-0303 August 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML0919700682009-08-10010 August 2009 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Project stage: RAI ML0920302082009-08-14014 August 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML0920800452009-08-14014 August 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Project stage: RAI ML0920200122009-08-20020 August 2009 RAI, License Renewal Application Project stage: RAI ML0922507012009-08-20020 August 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI 3F1109-06, State of Florida Department of Environmental Protection, Conditions of Certification2009-08-28028 August 2009 State of Florida Department of Environmental Protection, Conditions of Certification Project stage: Other ML0923300072009-08-31031 August 2009 RAI for the Review of the Crystal River Unit 3 Nuclear Generating Plant, LRA Project stage: RAI ML0923303432009-08-31031 August 2009 Nuclear Generating Plant, RAI, License Renewal Application Project stage: RAI ML0923308312009-08-31031 August 2009 Request for Additional Information Regarding License Renewal Application Project stage: RAI ML0923309042009-09-0202 September 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Project stage: RAI ML0925800952009-09-11011 September 2009 Response to Requests for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application (TAC No. ME0274) and Amendment #2 Project stage: Response to RAI ML0921602132009-09-11011 September 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Project stage: RAI ML0926008882009-09-11011 September 2009 Response to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI ML0926008892009-09-11011 September 2009 Areva Np, Inc., 51-9057252-001, Rev. 1, CR3 Reconciliation of 60-Year Fluence Projections Used in Reactor Vessel Beltline Embrittlement Calculations for License Renewal, Enclosure Attachment 3 Project stage: Other ML0926502722009-09-18018 September 2009 Response to Requests for Additional Information for the Review of the License Renewal Application and Amendment #3 Project stage: Response to RAI ML0923706692009-09-22022 September 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Unit Plant, License Renewal Application Project stage: RAI ML0926103092009-09-29029 September 2009 Scoping and Screening Audit Report Regarding the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Project stage: Other ML0927901502009-09-30030 September 2009 Response to Requests for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application (TAC ME0274) and Amendment #4 Project stage: Response to RAI ML0927901542009-10-0202 October 2009 Response to Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application (TAC No. ME0274) - Sections B.2.37-1, 3.3.2.2, and XI.S8 Project stage: Response to RAI 3F1009-03, Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives2009-10-0909 October 2009 Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives Project stage: Response to RAI ML0928901552009-10-13013 October 2009 Response to Request for Additional Information for the Review of Unit 3 Nuclear Generating Plant License Renewal Application and Amendment #5 Project stage: Response to RAI ML0926405542009-10-15015 October 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML0930005052009-10-22022 October 2009 Response to Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application (TAC No. ME0274) - and Amendment #6 Project stage: Response to RAI ML0929606602009-10-27027 October 2009 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML0929403222009-11-0303 November 2009 Request for Additional Information for the Review of the Crystal River, Unit 3 Nuclear Generating Plant, License Renewal Application Project stage: RAI ML1009805172009-11-0505 November 2009 License Renewal Revised Environmental Site Audit Needs List Hydrology (Additional Reference 8 Through 16) Project stage: Other ML1009805192009-11-0505 November 2009 Nuclear Generating Plant License Renewal, Revised Environmental Site Audit Needs List, Air, Meteorology, Climate Project stage: Other ML1009805282009-11-0505 November 2009 License Renewal Revised Environmental Site Audit Needs List, Non-Radiological Waste Radiation Protection, Socioeconomics Terrestrial Ecology Project stage: Other ML0931704872009-11-0505 November 2009 Response to Request for Additional Information Re Review of License Renewal Application for Environmental Review Project stage: Response to RAI ML1009805202009-11-0505 November 2009 License Renewal Environmental Site Audit Needs List, Aquatic Ecology (Except AQ-3), Archaeology Project stage: Other ML1009805232009-11-0505 November 2009 License Renewal Environmental Site Audit Needs List, Aquatic Ecology, Additional References, Through AR-3, Page 7 Project stage: Other ML1009805242009-11-0505 November 2009 License Renewal Revised Environmental Site Audit Needs List, Aquatic Ecology AQ-3 Project stage: Other ML1009805182009-11-0505 November 2009 Response to Request for Additional Information Regarding the Review of the License Renewal Application - Revised Environmental Site Audit Needs List Project stage: Response to RAI ML1009805252009-11-0505 November 2009 Plant Operating Manual AI-571, Sea Turtle Rescue and Handling Guidance Project stage: Other ML1009805262009-11-0505 November 2009 License Renewal Revised Environmental Site Audit Needs List, Hydrology (Through Additional Reference 6) Project stage: Other ML1011102352009-11-0505 November 2009 License Renewal Environmental Site Audit Needs List, Aquatic Ecology, AR-3 Page 8 Through AR-6 Project stage: Other 2009-06-10
[Table View] |
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Category:Letter
MONTHYEARML24179A0702024-07-26026 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 ML24079A2472024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Cypress, Talbert 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 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 IR 05000302/20210042022-01-24024 January 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004 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) 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 ML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a IR 05000302/20210012021-08-12012 August 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021001 and 05000302/2021002 ML21182A1032021-07-0606 July 2021 Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan 2024-07-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23354A0642023-12-22022 December 2023 Enclosure - Crystal River License Termination Plan Request for Additional Information 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 ML23103A1922023-04-19019 April 2023 Request for Supplemental Information Enclosure ML21182A1032021-07-0606 July 2021 Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan ML16032A1772016-02-0404 February 2016 J. Hickman, NRC, Letter to T. Hobbs, Crystal River 3, Request for Additional Information for Emergency Plan Change ML15026A4162015-02-0202 February 2015 Request for Additional Information Regarding the 10 CFR 50.54(p) Changes to the Security Plans ML14274A1392015-01-0808 January 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications and License Conditions to Create Permanently Defueled Technical Specifications ML14133A5032014-05-14014 May 2014 Correction, Request for Additional Information on the Post Shutdown Decommissioning Activities Report ML14104A0392014-04-28028 April 2014 Request for Additional Information on the Post Shutdown Decommissioning Activities Report ML13175A2152013-06-28028 June 2013 Request for Additional Information Regarding Request to Rescind Fukushima-Related Orders ML13018A3072013-02-0101 February 2013 Request for Additional Information for Extended Power Uprate License Amendment Request ML12355A6592012-12-21021 December 2012 Nuclear Generating Plant - RAI 9.3 of the Near-Term Task Force Fukushima Dai-ichi.. ML12333A0892012-12-19019 December 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12310A2912012-11-15015 November 2012 Request for Additional Information for Changes to Security Plan ML12240A0152012-08-28028 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12219A1912012-08-16016 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12213A3032012-08-0303 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request (Srxb) ML12202A0602012-08-0202 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12125A1622012-08-0101 August 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML12194A4172012-07-17017 July 2012 Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML12174A2922012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12171A3472012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12102A0442012-05-0404 May 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12052A1302012-03-0202 March 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12003A2172012-02-0808 February 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML11326A2312011-12-0707 December 2011 Request for Additional Information for Extended Power Uprate License Amendment Request ML11308A6592011-11-17017 November 2011 Generating Plant - Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies ML11301A1142011-11-0808 November 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1128602942011-10-12012 October 2011 IR 05000302-11-005; 11/14-18/2011; Crystal River Unit 3, Notification of Inspection and Request for Information ML11175A1512011-06-30030 June 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML11137A1742011-06-22022 June 2011 Nuclear Generating Plant; H. B. Robinson Steam Electric Plant, 2; and Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding 2011 Decommissioning Funds ML1115403412011-06-0202 June 2011 Nuclear Generating Plant - Notification of Inspection and Request for Information 05000302/2011501 ML11122A0002011-05-26026 May 2011 Request for Additional Information for the Review of the Crystal River, Unit 3, License Renewal Application ML1112501592011-05-0505 May 2011 Notice of Inspection and Request for Information 05000302/2011003 ML1108202262011-03-31031 March 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1031402722010-11-16016 November 2010 Request for Additional Information for the Review of the Crystal Review Unit 3 Nuclear Generating Plant, License Renewal Application ML1029503292010-11-0808 November 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application ML1030202942010-10-28028 October 2010 Nuclear Generating Plant - Notification of Inspection and Request for Information IR 05000302-10-005 ML1027100652010-10-19019 October 2010 09/27/10 Summary of Telephone Conference Call Held Between NRC and Florida Power Corp., Concerning Draft Request for Information Related to Crystal River, Unit 3, License Renewal Application ML1026002432010-10-14014 October 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1022800102010-08-11011 August 2010 Nuclear Generating Plant - Draft RAIs Regarding Crystal River Unit 3 Part 26 Exemption Request ML1017404972010-07-0808 July 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1015303972010-07-0808 July 2010 RAI for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1014105122010-06-0202 June 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application 2023-04-19
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 8, 2010 Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA 1B)
ATTN : Supervisor, Licensing & Regulatory Programs 15760 W . Power Line Street Crystal River, FL 34428-6708
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERAT! NG PLANT LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
Dear Mr. Franke:
By letter dated December 16, 2009, Florida Power Corporation submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 , to renew the operating license for Crystal River Unit 3 Nuclear Generating Plant, for review by the U.S . Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified , in the enclosure , areas where additional information is needed to complete the review. Further requests for additional information may be issued in th e future .
Items in the enclosure were discussed with Mr. Michael Heath, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3733 or bye-mail at Robert.Kuntz@nrc.gov.
Robert F. Kun ,Sr. Project Manager Projects Branch 2 Division of LicE)nse Renewal Office of Nuclear Reactor Regulation Docket No. 50-302 Enclosure :
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION FOR CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO 50-302 Request for Additional Information (RAI) B.2.22-3
Background:
Given that there have been a number of recent industry events involving leakage from buried or underground piping, the staff required further information to evaluate the impact that these recent industry events might have on the applicant's Buried Piping and Tanks Inspection Program . By letter dated July 8, 2010, the staff issued RAI B.2 .22-2 requesting that the applicant provide information regarding how Crystal River Unit 3 Nuclear Generating Plant (CR-3) will incorporate the recent industry operating experience into its aging management reviews and programs. The applicant responded on August 9,2010. In reviewing the response, the staff determined that additional information is required.
Issue:
- 1. The staff requires further details on leaks that have occurred in the fire protection buried piping and corrosion at the ground to air interface to fully understand plant-specific operating experience at the station. The staff noted that in the first parag raph of the response to Request 1 of RAI B.2.22-2, the applicant separately discussed two instances of buried piping that was damaged during excavations. It is not clear to the staff whether these are two separate or a single instance of damage.
- 2. Beyond stating that a minimum of one inspection of buried fire protection piping will occur every ten years, the license renewal application (LRA) and supplementa l material did not contain enough specifics on the planned inspections for the staff to determine if the inspections would be adequate to manage the aging effect for all material, safety/code class, and potential to contain hazardous material (i .e., material which, if released, could be detrimental to the environment such as diesel fuel and radioi sotopes that exceed U.S. Environmental Protection Agency (EPA) drinking water standards) categories of in-scope buried pipes and tanks.
- 3. The staff does not have enough information to conclude if the condensate storage tank, emergency feedwater tanks, or the buried emergency feedwater or condensate piping contain tritium above the EPA drinking water limit. Given the degraded condition of the
'cathodic protection system for the emergency feedwater and condensate system, the staff believes that augmented inspections might be appropriate if the piping contains hazardous material.
- 4. The RAI response did not state the as-found condition of backfill observed during recent buried piping inspections.
- 5. The LRA and response to the RAI does not provide the staff enough information to determine:
ENCLOSURE
- a. If buried in-scope fuel oil piping is cathodically protected .
- b. What amount of degradation could have occurred during the period beginning 2004 when cathodic protection for condensate system and emergency feedwater system was not maintained.
- c. If the short length of piping from the Condensate Storage Tank to the Turbine Building is cathodically protected and if it has a safety-related function .
- 6. In relation to the nuclear services and decay heat sea water system which is either under water or buried 30 feet below grade:
- a. The staff believes that in instances where it is not possible to expose the program designated length of piping during each inspection, an alternative examination should be proposed. The staff is not aware of a method other than ultrasonic examination that would be effective at providing a reasonable assurance that the buried piping would meet its current licensing basis function(s).
- b. Based on the RAI response it does not appear that the steel piping portions of the nuclear services and decay heat sea water system is cathodically protected.
- 7. The RAI response to RAI B.2.22-2 states in the discussion on the emergency feedwater/condensate system that this system includes some stainless steel associated with the interfacing piping in these systems; however, the staff noted that there does not appear to be any stainless steel aging management review (AMR) line items in the condensate system and emergency feedwater system tables.
- 8. It is not clear to the staff (a) how often the buried fuel oil storage tanks are subjected to internal ultrasonic inspections, (b) how an internal visual inspection can be used to evaluate the external conditions of the tank material, (c) how an internal visual inspection can be used to evaluate the condition of the external coatings on the tank, and (d) how ultrasonic tests of the tank heads and lower shells provides sufficient information to evaluate the condition of all external surfaces of the tank.
- 9. The LRA does not contain details on the availability of the cathodic protection system ,
and what periodic testing is conducted on the cathodic protection system . The staff believes that cathodic protection is an important preventive measure for steel piping.
Request:
- 1. State the cause(s) of the buried fire protection piping leaks described in response to RAI B.2.22-2. State the material of the piping, coating condition and cause of the leak at the ground to air interface. State whether the two instances of buried piping that was damaged during excavations are two separate or a single instance of damage and the basis for why the evaluation concluded that this damage occurred during excavation.
- 2. For buried in-scope piping, respond to the following:
- a. State the minimum number of excavated direct visual inspections of buried in-scope piping which will be conducted during the 30-40, 40-50, and 50-60 year operating periods. When describing the minimum number of inspections, differentiate between material , code/safety-related piping, and potential to contain hazardous material category piping inspection quantities of buried in-scope piping.
- b. For the minimum number of planned inspections, state the length of piping that will be excavated and that will have a direct visual inspection conducted.
- 3. State whether the condensate storage tank, emergency feedwater tanks , or the buried emergency feedwater or condensate piping contain tritium above the EPA drinking water limit. If buried portions of the systems contain hazardous material ,
state what percent of total linear feet of buried in-scope piping will be inspected by excavation and direct inspection during each 1O-year period starting 10 years prior to the period of extended operation. If there are no planned inspections for this piping, justify why it is acceptable to not inspect in-scope buried pipe containing hazardous materials.
- 4. State the as-found condition of backfill observed during recent buried pipe inspections. If the inspections detected the presence of rocks and sharp objects in the backfill around buried pipes justify why the minimum inspections are adequate to detect potential pipe degradation as a result of coating damage or holidays, or damage to the exterior surface of non-coated piping .
- 5. For buried in-scope piping, respond to the following:
- a. State whether the fuel oil piping is protected by cathodic protection. If this piping is not cathodically protected, (a) provide an analysis that demonstrates that this piping will continue to meet or exceed the minimum design wall thickness throughout the period of extended operation, assumi ng that no coatings are applied to the piping, or (b) justify why the number of the planned inspections of this piping is sufficient to reasonably assure that this piping will continue to meet or exceed the minimum design wall thickness throughout the period of extended operation.
- b. Given (a) that the cathodic protection system for the condensate and emergency feedwater system buried piping was not being regularly monitored and maintained since 2004, (b) troubleshooting is ongoing and the cathodic protection system is not yet fully restored , and (c) even though some inspections have been conducted, coating degradation or holidays can be randomly distributed, justify how the minimum design wall thickness will be maintained throughout the period of extended operation including the projected amount of degradation that could have occurred during this period.
- c. State whether the short length of piping from the condensate storage tank to the Turbine Building is cathodically protected and if it has a safety-related function . If this piping is not cathodically protected, (a) provide an analysis that demonstrates that this piping will continue to meet or exceed the minimum design wall thickness throughout the period of extended operation ,
assuming that no coatings are applied to the piping , or (b) justify why the number of the planned inspections of this piping is sufficient to reasonably assure that this piping will continue to meet or exceed the minimum design wall thickness throughout the period of extended operation.
- 6. In relation to the nuclear services and decay heat sea water system buried piping which is either under water or buried 30 feet below grade, respond to the following :
- a. If alternative volumetric examination methods, beyond ultrasonic examinations, will be used for conducting an interior wall thickness measurement, justify why they will be effective at providing a reasonable assurance that the buried in-scope piping systems will meet their current licensing basis function and state what percentage of interior axial length of the pipe will be inspected during each inspection.
- b. If the buried steel portions of this system are not cathodically protected, (a) provide an analysis that demonstrates that this piping will conti nue to meet or exceed the minimum design wall thickness throughout the period of extended operation , assuming that no coatings are applied to the piping , or (b) justify why the number of the planned inspections of this piping is sufficient to reasonably assure that this piping will continue to meet or exceed the minimum design wall thickness throughout the period of extended operation.
- 7. Identify the AMR line item that includes the stainless steel, associated with the interfacing piping in the emergency feedwater/condensate system.
- 8. For the buried in-scope fuel oil storage tanks:
- a. State how often each of the buried fuel oil storage tanks are subjected to internal ultrasonic inspections.
- b. Justify how an internal visual inspection can be used to evaluate the external conditions of the tank material.
- c. Justify how an internal visual inspection can be used to evaluate the condition of the external coatings on the tank.
- d. Justify how ultrasonic tests of the tank heads and lower shells provide sufficient information to evaluate the condition of all external surfaces of the tank .
- 9. In relation to the cathodic protection system:
- a. State the availability of the cathodic protection system, and if portions of the system are not available 90 percent of the time or will be allowed to be out of service for greater than 90 days in any given year, justify how the piping will meet or exceed the minimum design wall thickness throughout the period of extended operation.
- b. State whether annual ground potential surveys of the cathodic protection system are conducted and what acceptance criteria is used, or if annual ground potential surveys are not conducted, justify how the piping will meet or exceed the minimum design wall thickness throughout the period of extended operation.
RAI B.2.25-5
Background:
The applicant is currently performing major repairs to the containment. Since October 8, 2009, a large number of prestressing tendons have been de-tensioned/removed . In addition, concrete has been removed in different areas. Vertical through-wall cracks have been identified in the containment concrete.
Issue:
There is a potential of corrosion in the containment liner plate exposed to humidity and moisture via the through-wall cracks present in the concrete containment. This condition may have introduced corrosion in the liner plate which can affect the containment liner's ability to act as a leak tight barrier during the period of extended operation.
Request:
Provide information related to monitoring the condition of the containment liner plate to capture any potential effects of long term exposure to humidity and moisture that may have occurred during the current long term shutdown.
RAI B.2.25-6
Background:
In response to RAI B2.25-3, provided in letter dated December 30, 2009, the applicant stated that during the 2009 refueling outage, an American Society of Mechanical Engineers (ASME)
Section XI, Subsection IWE (IWE) program examination was performed on the accessible reactor building liner plate. In addition to the bulges of the liner plate previously identified in 2007, additional bulges were identified during the fall 2009 IWE examination . The applicant further stated that a Nuclear Condition Report has been initiated and will be evaluated by the applicant prior to acceptance of the liner plate for continued service. The applicant also stated that the acceptance of the liner plate for continued service shall be in accordance with IWE-3122 by examination , corrective measures or repair/replacement activity, or by engineering
evaluation. The details and basis of this engineering evaluation and/or corrective actions will be available for U.S. Nuclear Regulatory Commission review prior to return to operation of CR-3 from the fall 2009 refueling outage.
Issue:
Presence of bulges can potentially introduce corrosion on the concrete side of the liner plate which may affect its ability to perform its design function during the period of extended operation Request:
Provide information regarding the corrective actions planned/performed for the bulges in the liner plate to demonstrate that the liner plate will be able to perform its intended function during the period of extended operation .
RAI 8.2.26-5
Background:
The applicant is currently in the process of repairing a significant portion of the containment which includes new concrete, removal and re-installation of prestressing tendons, followed by a structural integrity test.
Issue:
LRA Section B.2.26 states that ASME Section XI, Subsection IWL Program is implemented in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55(a) and ASME Section XI, Subsection IWL, 2001 Edition, through the 2003 Addenda. ASME Section XI, IWL 2410 states, "Concrete shall be examined in accordance with IWL-2510 at 1,3, and 5 years following the completion of the Containment Structural Integrity Test CC-6000 and every 5 years thereafter." LRA Section B.2 .26 does not address the containment concrete surface examination frequency after the new structural integrity test.
Request:
Discuss the plans and frequency for performing the containment concrete surface exam ination after the new structural integrity test to establish a new baseline and trend in concrete degradation for the period of extended operation.
RAI 8.2.26-7
Background:
The applicant has removed 64 (44 percent) of vertical tendons and 155 (54 percent) of the hoop tendons from the containment. These tendons will be reinstalled/replaced . In addition, the remaining vertical tendons will be re-tensioned.
Issue:
LRA Section B.2.26 states that the ASME Section XI, Subsection IWL Program is implemented in accordance with 10 CFR 50.55(a) and ASME Section XI , Subsection IWL, 2001 Edition, through the 2003 Addenda . ASME section XI , IWL-2420 states, "Unbonded post-tensioning systems shall be examined in accordance with IWL-2510 at 1, 3, and 5 years following the completion of the containment Structural Integrity Test and 5 years thereafter. " LRA Section B.2.26 does not address the containment post tensioning system examination frequency following the removal , reinstallation , and replacement of 44 percent of vertical tendons and 54 percent of the hoop tendons .
Request:
Discuss the plans and frequency for performing the containment unbonded post-tensioning system examination following the completion of the new structural integrity test to establish a new baseline and trend for the loss of prestress in the hoop and vertical tendons during the period of extended operation .
RAI 8.2.26-8
Background:
During the repair of the containment, vertical cracks of up to 5 mils in width have been recorded in the containment concrete exterior surface. These cracks appear to be through the 42 inch thick containment wa ll at numerous locations.
Issue:
LRA Section B.2.26 states that the ASME Section XI , Subsection IWL Program is an existing program consistent with NUREG-1801 , Generic Aging Lessons Learned (GALL) Report,Section XI.S2 . Element 6 of NUREG-1801 ,Section XI.S2, states that, "IWL-3000 provides acceptance criteria for concrete containments. " IWL-3310 requires that an eng ineering evaluation report shall be prepared if there is evidence of damage or degradation sufficient to warrant further evaluation.
Request:
Discuss the effect of vertical through wall cracks on the containment structure during the period of extended operation. This discussion should include inspection and repairs (if necessary) of the containment required to demonstrate that the effects of these cracks on the containment wil l be adequately managed for the period of extended operation .
RAI 8.2.28-4
Background:
The applicant is currently performing major repairs to the containment wh ich will be followed by a structural integrity test and an integrated leak rate test (ILRT).
Issue:
LRA Section B.2.28 states that "the CR-3 10 CFR 50, Appendix J Program utilizes the performance-based approach of 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," Option B, and includes appropriate guidance from Regu latory Guide 1.163, September 1995, "Performance-Based Containment Leak-Test Program," as modified by NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50 Appendix J.""
Section 9.2.3 of NEI 94-01 , Revision 2, states that Type A testing shall be performed during a period of reactor shutdown at a frequency of at least once per 15 years based on acceptable performance history. Acceptable performance history is defined as successful completion of two consecutive periodic Type A tests where the calculated performance leakage rate was less than the maximum allowable leakage rate at the calculated peak accident pressure .
Considering the extent of containment repairs, the applicant may need to establish a new acceptable performance history to demonstrate that the containment will remain essentially leak tight during the period of extended operation.
Request:
Discuss how an acceptable performance history for the Type A test would be established after the new structural integrity test to ensure that the effects of the aging of the containment will be adequately managed during the period of extended operation.
RAI4.5.1-1
Background:
The applicant is currently performing major repairs to the containment. This includes removal and reinstallation of 44 percent of vertical tendons and 54 percent of the hoop tendons. In addition the remain ing vertical tendons will be re-tensioned to a higher level of prestresing.
Issue:
LRA Section 4.5.1 states that for the purposes of extending the plant operating license, regression analysis was used to extrapolate the tendon prestress forces to the end of the period of extended operation. This regression analysis will have to be revised since the majority of vertical and hoop tendons will be re-tensioned following concrete repairs .
Request:
Provide plans and schedules for performing a regression analysis to account for re-tensioned tendons, changes in tendon relaxation , and changes in the concrete creep of the old versus the new concrete to ensure that the effects of aging of the prestressing tendons will be adequately managed during the period of extended operation .
- ML102950329 *concurred via -ema il OFFICE LARPOB:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB2:DLR RKuntz NAME IKing RKuntz DWrona (Signature)
DATE 10/27/10 10/28/10 10/29/10 11/08/10
Letter to Jon Franke from Robert F. Kuntz dated November 8, 2010
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION (TAC NO. ME0274)
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