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Category:Letter
MONTHYEARML23342A0942024-01-0909 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 ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML21060B4142021-04-12012 April 2021 U.S. Nuclear Regulatory Commission Analysis of Duke Energy Florida, Llc'S Initial Decommissioning Funding Plan for the Crystal River Independent Spent Fuel Storage Installation ML21028A5912021-03-0202 March 2021 Letter to Reid Forwarding Exemption from 10 CFR Part 20, Appendix G, Section Iii.E ML21055A7832021-02-25025 February 2021 Letter to Reid, Change in NRC Staff Project Management for Crystal River Unit 3 Nuclear Generating Plant ML21012A3142021-01-13013 January 2021 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000302/20200012020-11-19019 November 2020 NRC Inspection Report No. 05000302/2020001, Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, Crystal River, Florida ML20269A2922020-10-0707 October 2020 NRC Form 311 QA Program Approval Revision 10 Related to Crystal River 3 ML20101G5822020-04-10010 April 2020 CR-3 License Transfer SE Corrected Cover Letter ML20069A0232020-04-0101 April 2020 Order Approving Transfer of Licensed Authority from Duke Energy Florida, LLC, to ADP CR3, LLC, and Draft Conforming Administrative License Amendment ML20050D0142020-02-19019 February 2020 NRC Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2020001, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML20050F7702020-02-14014 February 2020 30-Day Notice of Payment from the City of Tallahassee Trust Fund Non-Qualified Nuclear Decommissioning Trust Fund for Crystal River Unit 3 ML20015A5672020-01-15015 January 2020 Independent Spent Fuel Storage Installation Security Inspection Plan 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 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 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 IR 05000302/20190022019-11-20020 November 2019 NRC Inspection Report No. 05000302/2019002 and Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2019002, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19261A0702019-09-19019 September 2019 VEGP U3 Proficiency Watches Prior to Fuel Load ML19177A0802019-06-26026 June 2019 Nuclear Generating Plant (CR-3) - Notification of Revised Post-Shutdown Decommissioning Activities Report (Revised PSDAR) ML19170A1942019-06-14014 June 2019 Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment ML19129A1402019-05-15015 May 2019 Letter to Hobbs, Correction to Amendment No. 257 Approving Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Revision 1 2024-01-09
[Table view] Category:Report
MONTHYEARML23345A1882023-12-0606 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 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 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 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 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 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 ML1028711212010-02-19019 February 2010 7.10 Hydrodemolition Induced Cracking ML1028711132010-02-19019 February 2010 7.9 Inadequate Hydro Blasting Nozzles Rate Part 2 ML1028711122010-02-19019 February 2010 7.9 Inadequate Hydro Blasting Nozzles Rate Part 1 ML1028804682010-02-19019 February 2010 7.9 Inadequate Hydro Blasting Nozzles Rate Part 3 ML1028804582010-02-18018 February 2010 7.8 Excessive Water Jet Pressure Part 3 ML1028711462010-02-18018 February 2010 7.8 Excessive Water Jet Pressure Part 2 ML1028711452010-02-18018 February 2010 7.8 Excessive Water Jet Pressure Part 1 2023-06-09
[Table view] Category:Miscellaneous
MONTHYEARML16176A3392016-10-28028 October 2016 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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Text
FM 5.1 Exhibit 6a Page 1 of 12 SMACTEC engineering and constructing a better tomorrow December 8, 2009 Mr. Craig Miller Progress Energy (352) 795-6486 ex 1026 Craig.miller@pgnmail.com
Subject:
Report of Petrographic Observations Crystal River Containment Wall and Dome Concrete Samples Steam Generator Replacement Project Crystal River Nuclear Generating Facility, Florida MACTEC Project No. 6468-09-2535
Reference:
Report of Petrographic Observations Crystal River Containment Wall and Dome Concrete Samples Steam Generator Replacement Project Crystal River Nuclear Generating Facility, Florida MACTEC Project No. 6468-09-2535 Dated November 11, 2009
Dear Mr. Miller:
MACTEC Engineering and Consulting is pleased to present this report of our petrographic observations performed on two concrete cores that were shipped to our laboratory under chain of custody. One core, Core #7 (MACTEC laboratory number 21271 A), was previously analyzed and the results were contained in our November 11, 2009 report. An additional core, identified as core #87 was received under chain of custody for petrographic analysis. Core #87 was assigned MACTEC laboratory number 21329. It is our understanding that sample 21271A is from the containment wall near the fracture (as referenced in our November 11, 2009 report. It is our understanding that sample 21329 is from an area in the dome that was repaired several years ago. The purpose of our observations was to evaluate the similarities and/or differences in the coarse aggregate of the two samples to attempt to determine if the coarse aggregate used in sample 21329 is similar to coarse aggregate used in sample 21271A.
Additionally, as requested, parameters of the air void system were evaluated for sample 21271A in general accordance with the ASTM C 457-08 Standard Test Method for Microscopial Determination of Parameters of the Air-Void System In Hardened Concrete.
MACTEC Engineering and Consulting, Inc.
9177 Sky Park Court, San Diego, CA 92123
- Phone: 858-278-3600 ° Fax: 858-278-5300 www.mactec.com Page 1 of 16 DCN CR-017 G9i(10
FM 5.1 Exhibit 6a Page 2 of 12 Crystal River Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC Project No. 6468-09-2535 Crystal River Nuclear GeneratingFacility, Florida In addition to the petrographic observations, the Mohs hardness of the coarse aggregates in samples 21271A and 21329 was evaluated using picks of known hardness.
PETROGRAPHIC OBSERVATIONS A Petrographic Analysis is a visual and microscopic analysis of cementitous materials performed by a qualified petrographer. Petrographic examinations are typically performed on polished sections or thin sections. Polished sections are generally cut sections that have been lapped (ground flat and smooth) and polished and are observed using reflected polarized light microscopes at magnifications of up to 80X.
Thin sections are samples mounted to glass slides and ground to specific thicknesses (generally 20, 30, or 40 microns depending on the application) and observed using transmitted polarized light microscopes at magnifications of up to 600X.
A petrographic evaluation may be performed to identify and describe a specific item of interest such as the presence or extent of distress in concrete, or to provide a general characterization and measure of quality of the materials being evaluated. The petrographic evaluation of concrete examines the constituents of the concrete including coarse aggregates, fine aggregates, embedded items, hardened paste, and air void structure. The examination identifies cracking present in the concrete, indications of corrosion, extent of damage from external sources, aggregate reaction, chemical attack, sulfate attack, freeze thaw cracking, acid attack, and other mechanisms of deterioration. The petrographic examination can also estimate the water to cement ratio, look for indications of mineral additives and unhydrated cement particles in the paste, look for indications of bleed water and excess porosity in the concrete, look for indications of curing procedures used and methods of finishing, observe micro cracking present and other conditions within the concrete which might give information on the overall quality or the quality of any particular constituent material. Aggregate mineralogy, rock types, and mineral crystal structure can be identified when thin sections are viewed under a transmitted polarized light microscope.
TEST RESULTS AND OBSERVATIONS PETROGRAPHIC OBSERVATIONS The petrographic analysis was performed in general accordance with the applicable sections of ASTM C 856-04 Standard Practice for Petrographic Examination of Hardened Concrete. The results of our petrographic analysis are on the attached sheets, Summary of Petrographic Observations of Hardened Concrete. Photographs from our examination are attached. A summary of our observations of the coarse aggregate and discussion are as follows.
2 Page 2 of 16 DCN CR-017
FM 5.1 Exhibit 6a Page 3 of 12 CrystalRiver Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC Project No. 6468-09-2535 Crystal River Nuclear GeneratingFacility, Florida Aggregate Sample 21271A The coarse aggregate generally consisted of a natural carbonate crushed rock with a maximum size of 3/4 inch. The rocks types observed included limestone, fosiliferous limestone, and a few particles of chert and/or limestone and chert. The particles were generally angular to sub-rounded in shape and fairly evenly distributed. The coarse aggregate appeared to comprise approximately 50% of the total aggregate quantity with the remaining fraction being fine aggregate. The coarse aggregate had a moderate amount of void space. The limestone and fosiliferous limestone had a Mohs hardness of approximately 3.
On sample 21271, there were 4 coarse aggregate pieces on the cut surface of the core that retained moisture longer than other portions of the sample. A thin section was prepared from one of these pieces and this piece contained microcrystalline quartz and radial silica and exhibited localized evidence of alkali silica reaction Sample 21329 The coarse aggregate generally consisted of a natural carbonate crushed rock with a maximum size of 3/4 inch. The rocks types observed included limestone and fosiliferous limestone. The particles were generally angular to sub-rounded in shape and fairly evenly distributed. The coarse aggregate appeared to comprise approximately 50% of the total aggregate quantity with the remaining fraction being fine aggregate. The coarse aggregate had a moderate amount of void space. The limestone and fosiliferous limestone had a Moh's hardness of approximately 3.
DISCUSSION Photographs comparing the features of the coarse aggregate in samples 21271A and 21329 are shown on pages 10 and 11.
The aggregates from both samples have the same general similarities.
- Both coarse aggregates have a Moh's hardness of about 3
" Both coarse aggregates are a fosiliferous limestone with similar fossils
- Both coarse aggregates have some particles with a moderate amount of void space
" Both fine aggregates are predominately quartz with a similar particle shape A few limestone particles were observed in sample 21271A that contained microcrystalline quartz and radial silica (chert). Chert was not observed in sample 21329. Chert is found in association with some limestones in Florida. The material is formed by the replacement of calcium carbonate with silica that is carried in the ground water. The lack of chert in sample 21329 does not necessarily mean that the coarse 3
Page 3 of 16 DCN CR-017
FM 5.1 Exhibit 6a Page 4 of 12 Crystal River Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC Project No. 6468-09-2535 Crvstal River Nuclear Generating Facility, Florida aggregate in sample 21329 is from a different source than the coarse aggregate in sample 21271A. In MACTEC's November 11, 2009 report, a petrographic analysis was performed on two samples (2127 IA and 21269A). It is our understanding samples 21271A and 21269A (both from the containment wall) are expected to be from the same source, however, chert was observed in sample 21271A and was not observed in sample 21269A.
It appears the coarse aggregate in both samples (21271 A and 21329) could be from the same source or from the same general geologic deposit. It cannot be said with 100% certainty that both coarse aggregate samples came from the same source, however, we didn't see indications to suggest they are from different sources.
PARAMETERS OF THE AIR VOID SYSTEM The parameters of the air void system were evaluated in general accordance with the ASTM C 457-08 Standard Test Method for Microscopial Determination of Parameters of the Air-Void System In Hardened Concrete. For this evaluation the modified point count method was utilized.
In our analysis, a total of 1,667 points were counted and each point was classified as a void, paste, coarse aggregate, or fine aggregate. Additionally, the number of voids that were traversed when going from point to point was recorded. The results are as follows:
Number Of Voids Intersected 327 Points In voids 52 Points In Paste 434 Points In Coarse Aggregate 683 Points In Fine Aggregate 498 Total Number of Points 1667 Following the calculations in ASTM C 457-08, the parameters of the air void system are as follows:.
Air Content = 3.1%
Air content is the proportion of the total volume of the concrete that is air voids; expressed as a percentage by volume.
Void Frequency = 3.1 per inch Void frequency is the voids per unit length of traverse; the number of air voids interceptedby a traverse line divided by the length of that line; the unit is a reciprocallength.
4 Page 4 of 16 DCN CR-017
FM 5.1 Exhibit 6a Page 5 of 12 CrystalRiver Steam GeneratorReplacementProject December8, 2009 Reportof PetrographicObservations MACTEC ProjectNo. 6468-09-2535 CrystalRiver Nuclear GeneratingFacility,Florida Paste Content = 26.0%
Paste content is the proportionof the total volume of the concrete that is hardenedcement paste expressed as percentage by volume Paste-Air Ratio = 8.34 Paste-Air ratiois the ratio of the volume of hardened cement paste to the volume of the air voids in the concrete Average Chord Lengthr= 0.002 inch Average chord length is the average length of the chordsformed by the transactionof the voids by the line of traverse;the unit is a length Specific Surface = 2000 per inch Specific surface is the surface area of the air voids divided by their volume, expressed in compatible units so that the unit of specific surface is a reciprocallength.
Spacing Factor = 0.0029 inch Spacingfactor is a parameterrelated to the maximum distance in the cement pastefrom the periphery of an air void, the unit is length In addition to the above calculated values, by dividing the points in coarse aggregate by the points in coarse and fine aggregate (added together) we can calculate the volume of aggregate that is coarse aggregate. Based on this, the coarse aggregate fraction as 58% of the total aggregate volume similarly and the volume of aggregate that is fine aggregate as 42%. To equate these values to relative weight (for comparison to a mix design) the specific gravities of the aggregates would need,-to be known and additional calculations would need to be performed.
We trust this information meets your current needs. If more information is needed, or if you have any questions, please contact us.
Sincerely, MACTEC ENGINEERING AND CONSULTING, INC.
David C. Wilson u ilek Ph.D.
Senior Principal Professional ior Principal Professional DCW/UD:pcc Attachments: Photographs #1 - #4 Photomicrographs for Samples 21271 A and 21329 Summary of Petrographic Observations for Cores 21271 A and 21329 5
Page 5 of 16 DCN CR-017
FM 5.1 Exhibit 6a Page 6 of 12
%/MACTEC
SUMMARY
OF PETROGRAPHIC OBSERVATIONS OF HARDENED CONCRETE - ASTM C-856-04 PROJECT NAME Crystal River Core Petrography Project nI PROJECT NUMBER 6468-09-2535 DATE SAMPLED RECEIVED 10-25-09 SAMPLE I.D. 21271 A SAMPLE SIZE AND DESCRIPTION Concrete core, approximately 3 3/4 inches in AS RECEIVED diameter, approximately 7 to 8 inches long.
OBSERVATIONS BY David Wilson IICHRACTERISIC OBSERVATIONS COARSE AGGREGATE:
Shape Angular to sub rounded Grading Approximately 3/ maximum size Distribution Even. Approximately 50% of the aggregates appeared to be coarse aggregates with the remaining fraction being the fine aggregate.
Texture Fine Composition Carbonate, a few with siliceous deposits Rock Types Mostly limestone and fossiliferous limestone. 4 coarse aggregate particles on the cored surface retained moisture much longer than the other particles and one of these particles had a darkened rim Alteration: Not observed
- Degree
- Products Coatings Not observed Rims Not observed except for one particle Internal Cracking Generally not observed except in the vicinity of the fractured surface. One of the particles that retained moisture longer than the other particles (referenced in rock type section) was observed in thin section and contained microcrystalline quartz and PetrographicObservations,Sample LD. 21271A Page 1 of4 Form Reviewed andApproved for Use on CrystalRiver Cores Project 6468-09-2535 J. Allan Tice, ProjectPrinci*al
-- -- DCNCR-017---
FM 5.1 Exhibit 6a Page 7 of 12 0MACTEC radial silica (essentially chert) with the limestone, several cracks were observed going through the portion which was predominately chert. There appeared to be minor amounts of ASR gel but a positive identification could not be made due to the
[ Contamination
__mall amounts Not observed resent.
FINE AGGREGATE:
Shape Generally sub-rounded to sub-angular Grading #4 and smaller Distribution Even Texture Fine Composition Siliceous Rock Types Quartz Alteration: Not Observed
- Degree
- Products Coatings Not Observed Rims Not Observed Internal Crirking A fei *wev, ra fractures were observed FContamination Not observed CHARACTERISTISI OBSERVATIONS CONCRET E:
Air-Entrained or Not Appeared to have some air entrainment.
Total air content based on visual observations appeared to be 2 to 3%
Air Voids: Mostly small and spherical. Some air void
- Shape clustering was observed around a few
- Size coarse aggregate particles. The air void
- Distribution distribution was moderately un-even, some small areas lacked air entrainment. There was some limited mineral growth observed in some of the air voids. Calcium hydroxide was observed lining some air voids.
Bleeding Not Observed Segregation Not Observed Aggregate-Paste Bond Coarse and fine aggregates appeared to have a good bond to the cement paste with few openings. Some aggregate particles had increased calcium hydroxide in the paste surrounding the erimeter of the PetrographicObservations, Sample LD. 21271A Page 2 of4 Form Reviewed and Approved for Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, ProjectPrincipal P ,DCNCR-071f1
FM 5.1 Exhibit 6a Page 8 of 12
%MACTEC particle.
Fractures One end of the core contained a fractured surface. There were some other minor fractures on the end with the fractured surface. There were some fractures associated the chert particle discussed Embedded Items Not observed
- Shape
- Size
- Location
- Type Alteration: Not observed
- Degree & Type
- Reaction Products
- Location
- Identification Nature and Condition of Surface There appeared to be white paint on the Treatments exterior surface of the core Estimated water-cement ratio (based on Appeared to have a moderately low w/c visual observations only) ratio possibly in the range of 0.4 to 0.5 Estimated cement content (based on visual Appeared to have a moderately high observations only) cement content PASTE:
Color (GSA rock color chart 1991) Medium light gray Hardness Appeared moderately hard when scratched with a hardened steel point Porosity Did not appear very porous. It took from 10 minutes to over 20 minutes to absorb 15 micro liter drops of water.
Carbonation The outer 1/4/ to 1/22 inch of the exterior surface was carbonated. The fractured surface was not carbonated.
Residual un-hydrated Cement: Some un-hydrated/partially hydrated
- Distribution cement particles were observed
- Particle Size
- Abundance
- Composition Mineral Admixtures: Fly-ash was not observed
- Size
- Abundance
- Intificatio-fn Contamination:
- Size.
- Abundance
- Identification PetrographicObservations, Sample LD. 21271A Page 3 of4 Form Reviewed and Approvedfor Use on CrystalRiver Cores Project 6468-09-2535 J. Allan Tice, ProjectPrincipal
= of 16
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FM 5.1 Exhibit 6a Page 9 of 12 AMACTEC Equipment Used:
Cannon EOS Digital Rebel with 50mm macro lens and microscope adapters AmScope 7X to 45X stereo zoom microscope (with and without polarized light)
Olympus BH-2 polarized light microscope Zeiss Photomicroscope II polarized light microscope Aven Digital Microscope Starrett 6 inch rule SN 109000003 Note: No M&TE used is subject to calibration requirements.
PetrographicObservations, Sample ID. 21271A Page 4 of4 Form Reviewed and Approvedfor Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, ProjectPrincipal
FM 5.1 Exhibit 6a Page 10 of 12 SMACTEC 1,- 1.ffm I, ,I,
SUMMARY
OF PETROGRAPHIC OBSERC-8ONS6 HARDENED CONCRETE PROJECT NAME
- ASTM C-856-04 VA Crystal River Core Petrography Project O
I PROJECT NUMBER 6468-09-2535 DATE SAMPLED RECEIVED 11-20-09 SAMPLE I.D. '21329 SAMPLE SIZE AND DESCRIPTION Concrete core, approximately 1 3/4 inches in AS RECEIVED diameter, 2 pieces, each approximately 6 inches long.
OBSERVATIONS BY David Wilson CHARACTERISTICS __ OBSERVATIONS COARSE AGGREGATE:
Shape Angular to sub rounded Grading Approximately 3/4 maximum size Distribution Even. Approximately 50% of the aggregates appeared to be coarse aggregates with the remaining fraction being the fine aggregate.
Texture Fine Composition Carbonate Rock Types Limestone and fossiliferous limestone.
Alteration: Not observed
- Degree
- Products Coatings Not observed Rims Not observed Internal Cracking Not observed L Contamination Not observed FINE AGGAy_,GA 1I*:
Shape Generally sub-rounded to sub-angular Grading #4 and smaller Distribution Even Texture Fine Composition Siliceous Rock Types Quartz Alteration: Not Observed PetrographicObservations, Sample ID. 21329 Page 1 of 3 Form Reviewed and Approvedfor Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, Project Princa DCN CR-017
FM 5.1 Exhibit 6a Page 11 of 12 OMACTEC
- Degree
- Products Coatings Not Observed Rims Not Observed Internal Cracking. A fPw internal fracture,, were. onherved Contamination Not observed ICHARACTERISTICS CONCRETE:
OBSERVATIONS 4 Air-Entrained or Not Appeared to have some air entrainment.
Total air content based on visual observations appeared to be 2 to 3%
Air Voids: Mostly small and spherical. Generally
- Shape fairly evenly distributed
- Size
- Distribution Bleeding Not Observed Segregation Not Observed Aggregate-Paste Bond Coarse and fine aggregates appeared to have a good bond to the cement paste with few openings. Some aggregate particles had increased calcium hydroxide in the paste surrounding the perimeter of the particle.
Fractures Not observed Embedded Items Not observed
- Shape
- Size
- Location
-Type _________
Alteration: Not observed
- Degree & Type
- Reaction Products
- Location
- Identification Nature and Condition of Surface Not observed Treatments Estimated water-cement ratio (based on Appeared to have a moderately low w/c visual observations only) ratio possibly in the range of 0.4 to 0.5 Estimated cement content (based on visual Appeared to have a moderately high observations only) cement content PASTE:
Color (GSA rock color chart 1991) Medium light gray Hardness Appeared moderately hard when scratched PetrographicObservations, Sample ID. 21329 Page 2 of3 Form Reviewed and Approved for Use on Crystal River Cores Project 6468-09.2535 J. Allan Tice, P P
- - - - - DCN CR-017
FM 5.1 Exhibit 6a Page 12 of 12 3MACTEC with a hardened steel noint Porosity Did not appear very porous.
Carbonation The '/2 inch of the exterior surface was carbonated.
Residual un-hydrated Cement: Some un-hydrated/partially hydrated
- Distribution cement particles were observed
- Particle Size
- Abundance
- Composition Mineral Admixtures: Fly-ash was not observed
- Size
- Abundance
- Identification Contamination: Not observed
- Size
- Abundance
- Identification Equipment Used:
Cannon EOS Digital Rebel with 50mm macro lens and microscope adapters AmScope 7X to 45X stereo zoom microscope (with and without polarized light)
Olympus BH-2 polarized light microscope Zeiss Photomicroscope H polarized light microscope Aven Digital Microscope Starrett 6 inch rule SN 109000003 Note: No M&TE used is subject to calibration requirements.
PetrographicObservations, Sample LD. 21329 Page 3 of 3 Form Reviewed andApproved for Use on Crystal River Cores Project6468-09-2535 J. Allan Tice, Project Principal
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