ML052440190
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| ML052440190 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/10/2005 |
| From: | Colgan K, Martin C AREVA, Framatome ANP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 3F0805-06 51-5053331-01 | |
| Download: ML052440190 (39) | |
Similar Documents at Crystal River | |
|---|---|
Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEAR3F0623-02, Maintenance Support Building2023-06-0909 June 2023
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Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020 and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization 3F0619-01, Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment2019-06-14014 June 2019 Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition 3F0119-02, License Amendment Request 326, Revision 0, ISFSI Only Emergency Plan, Revision 12019-01-16016 January 2019 License Amendment Request #326, Revision 0, ISFSI Only Emergency Plan, Revision 1 3F0717-01, Submittal of Crystal River Unit 3 - License Amendment Request 321, Revision 1, ISFSI Only Physical Security Plan2017-07-0505 July 2017 Submittal of Crystal River Unit 3 - 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[Table view]Enclosures 10 - 17: Crystal River, Unit 3, Response to Request for Additional Information ML24090A0042024-03-29029 March 2024 Enclosure 6, Part 1: Crystal River, Unit 3 - Appendix E – CHAR-05 Site Characterization of Buildings ML24030A7472024-02-13013 February 2024 Audit Report Attachment - Crystal River Unit 3 Nuclear Generating Plant LTP ML24030A7482024-02-12012 February 2024 Audit Report Cover Letter and Report - Crystal River Unit 3 Nuclear Generating Plant LTP 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 3F0324-03, Enclosure 6, Part 2: Crystal River, Unit 3, DD Survey 23-10-00962023-10-10010 October 2023 Enclosure 6, Part 2: Crystal River, Unit 3, DD Survey 23-10-0096 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 ML23160A2972023-06-0909 June 2023 CR3 Site Characterization Survey Report (CHAR-01) Impacted Open Land Survey Areas 3F0623-02, Maintenance Support Building2023-06-0909 June 2023 Maintenance Support Building ML23160A2982023-06-0909 June 2023 Site Characterization Surveys ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20222022-05-17017 May 2022 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022 3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20202020-05-18018 May 2020 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020 3F0320-01, NRC Commitment Change Report - March 20202020-03-17017 March 2020 NRC Commitment Change Report - March 2020 ML19343A8252019-12-0606 December 2019 Letter from Erika Bailey, Oak Ridge Institute for Science and Education, to John Hickman, NRC, Forwarding Independent Confirmatory Survey Summary and Results for the 3,854-Acre Area Partial Site Release at the Crystal River Energy Complex ML19022A0762019-01-22022 January 2019 Partial Site Release Request ML19029A0092018-11-0707 November 2018 Reference 16 - Defueled Safety Analysis Report DSAR-R002 ML18303A2942018-06-21021 June 2018 Golder Associates, Inc. - Citrus Combined Cycle Project - CFR 122.21(r) Report 3F0518-03, Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20182018-05-24024 May 2018 Safety Analysis Report and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2018 ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML19029A0102016-06-28028 June 2016 Reference 3 - Crystal River, Unit 3, Historical Site Assessment Rev. 00 3F0616-02, Nrg Commitment Change Report - June 20162016-06-14014 June 2016 Nrg Commitment Change Report - June 2016 ML13343A1782013-12-31031 December 2013 Report P23-1680-001, Rev. 0, Site-Specific Decommissioning Cost Estimate for Crystal River Unit 3 Nuclear Generating Plant. 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re2013-01-31031 January 2013 Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Res 3F1112-01, Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan2012-11-0707 November 2012 Alion Technical Report ALION-PLN-ENER-8706-02, Rev. 0, Crystal River 3: Bypass Fiber Quantity Test Plan 3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 2502012-10-31031 October 2012 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250 ML12314A3932012-10-31031 October 2012 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 81 of 250 Through Page 173 of 250 ML12314A3922012-10-31031 October 2012 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 1 of 250 Through Page 80 of 250 3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C2012-09-30030 September 2012 ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.2012-06-30030 June 2012 Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip. ML12314A3912012-05-31031 May 2012 17877-0002-100, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment 2 ML12205A3582012-05-31031 May 2012 Attachment D to 3F0712-03, Technical Report, ANP-3114(NP), Rev. 0, CR-3 EPU - Feedwater Line Break Analysis Sensitivity Studies. ML12284A1382012-05-25025 May 2012 Report EGS-TR-HC589-01, Seismic Qualification Test Report for Structural Verification Testing of Iccms Cabinet Assembly. 3F0512-01, NRC Commitment Change Report - May 20122012-05-14014 May 2012 NRC Commitment Change Report - May 2012 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR ML12205A3572011-12-15015 December 2011 Attachment a to 3F0712-03, CR-3 LOCA Summary Report - EPU/ROTSG/Mark-B-HTP, Revision 4 3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis2011-12-14014 December 2011 Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip2011-10-25025 October 2011 ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip ML11237A0682011-08-0505 August 2011 Siemens Technical Report CT-27438, Missile Probability Analysis Report Progress Energy Crystal River 3, Revision 1A ML11207A4442011-06-15015 June 2011 Attachment 7- Crystal River Unit 3 Extended Power Uprate Technical Report 3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models2011-05-0606 May 2011 Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models ML1101906672010-10-0404 October 2010 Levy, Units 1 and 2, Cola (Sensitive Material), Rev. 2 - Levy County Emergency Plan Part 02 - Draft (Redacted) 3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis2010-09-0808 September 2010 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis ML1019304172010-05-0606 May 2010 Tritium Database Report ML1010603472010-04-0909 April 2010 5.2.2.4.4. Quality Control and Nondestructive Testing ML1028710882010-03-12012 March 2010 7.6 Vibration Due to Cutting Tendons ML1028711112010-02-25025 February 2010 7.11 Added Stress from Pulling Tendons ML1028711102010-02-23023 February 2010 6.3 Thermal Effects of Greasing ML1028804682010-02-19019 February 2010 7.9 Inadequate Hydro Blasting Nozzles Rate Part 3 ML1028711212010-02-19019 February 2010 7.10 Hydrodemolition Induced Cracking 2024-03-31 Category:Miscellaneous MONTHYEARML16176A3392016-10-28028 October 2016
[Table view]Decommissioning Lessons Learned Report and Transmittal Memorandum 3F0616-02, Nrg Commitment Change Report - June 20162016-06-14014 June 2016 Nrg Commitment Change Report - June 2016 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re2013-01-31031 January 2013 Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Res 3F0512-01, NRC Commitment Change Report - May 20122012-05-14014 May 2012 NRC Commitment Change Report - May 2012 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR 3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis2011-12-14014 December 2011 Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis 3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models2011-05-0606 May 2011 Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models 3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis2010-09-0808 September 2010 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis ML1019304172010-05-0606 May 2010 Tritium Database Report ML1028710882010-03-12012 March 2010 7.6 Vibration Due to Cutting Tendons ML1028711112010-02-25025 February 2010 7.11 Added Stress from Pulling Tendons ML1028711102010-02-23023 February 2010 6.3 Thermal Effects of Greasing ML1028702742010-02-0606 February 2010 6.4 Rigid and Flexible Sleeves ML1028804952010-01-20020 January 2010 5.3 Exhibit 1 Interviews Regarding Maintenance ML1028708922010-01-16016 January 2010 Email - from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Lake, Louis; Thomas, George; Carrion, Robert; 'Trowe@Wje.Com' Cc: Williams, Charles R. Dated Saturday, January 16, 2010 1:10 PM Subject: Failure Mode 5.1 for Review and Comment ML1028709832010-01-12012 January 2010 from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:57 PM Subject: FW: Petrographic Report ML1028709862010-01-12012 January 2010 Email - from Thomas, George to Naus, Dan J. Cc: Lake, Louis Dated Tuesday, January 12, 2010 3:56 PM Subject: FW: Petrographic Report Attachments: S&Me Modulus Core 16, 40, 63, 65, 66.pdf; S&Me Density Core 16, 40, 60, 63, 65, 66.pdf... ML1028709792010-01-12012 January 2010 Email - from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:59 PM Subject: FW: Petrographic Report ML1028710352010-01-11011 January 2010 Email - from: Williams, Charles R. to: Lake, Louis; Thomas, George; Carrion, Robert; 'Nausdj@Ornl.Gov'; 'Daniel.Fiorello@Exeloncorp.Com'; Lese, Joseph A. Cc: Miller, Craig L (Charles.Williams@Pgnmail.Com) Dated Monday, January 11, 2010 5:38 ML1028710342010-01-11011 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Trowe@Wje.Com' Dated Monday, January 11, 2010 5:42 PM Subject: Fm 5.4 Draft for Review ML1028709902010-01-11011 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Archer, John C. (Reading)'; 'Wells, Richard P. (Reading)' Cc: Miller, Craig L Subject: F ML1028710402010-01-0606 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Trowe@Wje.Com' Cc: Miller, Craig L Dated Wednesday, January 06, 2010 4:51 PM, Subject: ML1028710462010-01-0101 January 2010 5.5 Exhibit 3a Petrographic Erlin Hime May 19 ML1028710492009-12-31031 December 2009 Email - from: Williams, Charles R. Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Miller, Craig L Dated Thursday, December 31, 2009 5:20 PM Subject: Fm 9.3 Draft and Exhibits for Review ML1029106012009-12-23023 December 2009 5.8 Exhibit 5a Petrographic ML1029106322009-12-18018 December 2009 from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Lake, Louis;Thomas, George; Nausdj@Ornl.Gov; Carrion, Robert Cc: Williams, Charles R. Dated Friday, December 18, 2009 4:47 PM Subject: Draft Fm 3.5 for Review Attachments: Fm 3.5.pptx; Fm 3F1209-11, 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report2009-12-16016 December 2009 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report ML1029107052009-12-11011 December 2009 5.2 Exhibit 2 Mactec Petrographic ML1029201382009-12-0808 December 2009 5.1 Exhibit 6A Petrographic Mactec ML1029201442009-12-0808 December 2009 5.8 Exhibit 5b Petrographic ML1029107272009-10-27027 October 2009 Summary of Results from Comparison.Pdf ML1029205002009-10-13013 October 2009 Condition Report Summary -NCRs Initiated Since Oct 12, 2009 ML1007504262009-10-12012 October 2009 Summary Report ML1028804902009-10-0505 October 2009 Condition Report Summary - Ncrs Initiated Since Sep 28, 2009 ML1029201092009-02-0404 February 2009 5.6 Exhibit 8 Cap Grease Leakage ML1029201072009-02-0404 February 2009 5.6 Exhibit 5 Surveillance Conclusion 3F0508-14, NRC Commitment Change Report - May 20082008-05-28028 May 2008 NRC Commitment Change Report - May 2008 3F1207-03, Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.2007-12-13013 December 2007 Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station. ML0731103812007-05-21021 May 2007 Progress Energy Florida, Inc. Proposed Florida Nuclear Site Transmission Planning Study, Final Report, Attachments Dand F Included 3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report2005-12-12012 December 2005 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report 3F1205-03, Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 42005-12-0303 December 2005 Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4 ML0613806752005-12-0101 December 2005 Report of Independent Auditors ML0613806782005-09-30030 September 2005 Financial Highlights ML0524401902005-08-10010 August 2005 Attachment E, Crystal River Unit 3 - License Amendment Request #290, Revision 1 Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack ML0505301682005-02-17017 February 2005 Background Discussion Material for February 24-25, 2005 NRC Meeting Relating to Replacement for BAW-2374, Revision 1, Evaluation of OTSG Thermal Loads During Hot Leg Loca. ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys 3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service2002-11-19019 November 2002 Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service ML0300701722002-10-25025 October 2002 Summary Report - Ncrs Initiated Since 10/18/2002 3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 32002-09-24024 September 2002 Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3 ML0300701742002-09-23023 September 2002 Summary Report - Ncrs Initiated Since 09/16/2002 2016-06-14 |
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