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Category:E-Mail
MONTHYEARML24191A4232024-07-0303 July 2024 RAI2 NRC Response to Fws ESA Crystal River Unit 3 LTP ML24190A1382024-06-18018 June 2024 Supplement to NRC Request for Concurrence with ESA Determinations for Crystal River Unit 3 LTP ML24170A9242024-06-18018 June 2024 024-0023697 Crystal River License Termination Plan Unit 3 ML24143A0242024-05-20020 May 2024 Draft EA for Crystal River Unit 3 Opportunity for Flhealth Review and Comment ML24143A0132024-05-20020 May 2024 Achp Response for Crystal River Unit 3 (Achp Project No. 020794) ML24143A0212024-05-20020 May 2024 SHPO Response to Initiate Section 106 Consultation for Crystal River Unit 3 ML24120A3312024-04-24024 April 2024 Seminole Tribe of Florida Email - Initiation ML24054A6462024-02-29029 February 2024 Request for RAI Extension Related to the Crystal River License Termination Plan ML24060A0862024-02-29029 February 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Crystal River Unit 3 Nuclear Generating Plant License Termination Plan (Consultation Code: 2024-0023697) ML24025A0952024-01-24024 January 2024 Clarifications Related to the NRC Staffs EA for Crystal River ML23180A0562023-06-13013 June 2023 ADP-CR3, Crystal River Unit 3 Email from J. Jernigan to Tim Barvitskie Confirmation That Enclosure 22 Radiological Groundwater Characterization Report ML21117A2902021-04-26026 April 2021 Acceptance of License Amendment Request Related to the ISFSI-Only Physical Securityplan ML21096A0432021-04-0505 April 2021 Acceptance of License Amendment Request Related to the ISFSI-Only Emergency Plan ML19344C8052019-11-12012 November 2019 Response from NEIMA Local Community Advisory Board Questionnaire 11-12-2019 H Danenhower ML19310D8602019-10-24024 October 2019 E-Mail Dated October 24, 2019, from Mark Vansicklen, Duke Energy Florida, to John Hickman, NRC, Providing Background Information for the Crystal River Partial Site Release Request ML19344C7872019-10-0303 October 2019 Response from NEIMA Local Community Advisory Board Questionnaire 10-03-2019 D Taylor ML19310D8212019-09-13013 September 2019 E-Mail Dated September 13, 2019, from John Hickman, NRC, to Mark Vansicklen, Duke Energy Florida, Requesting Background Information for the Crystal River Partial Site Release Request ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML19071A0662019-03-0606 March 2019 E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of a Request to Revise the ISFSI Only Emergency Plan for Crystal River Unit 3 ML19070A3112019-03-0606 March 2019 Document Title or Accession No. E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of Partial Site Release Request for Crystal River Unit 3 ML18263A1462018-09-11011 September 2018 NRR E-mail Capture - Logbook Entry: 09/11/2018 a Kemp'S Ridley Sea Turtle (Federal Endangered Species) Carcass Was Recovered from the Crystal River Energy Complex Unit 2 Fossil Unit ML16054A2402015-12-10010 December 2015 E-44108 Attachment 10 E-mail from Steven Edwards (Due Energy) to Don Shaw (Areva) for Brunswick Nuclear Plant, Oconee Nuclear Station, and Robinson Nuclear Plant ML15176A2692015-06-25025 June 2015 NRR E-mail Capture - NRC Acceptance Review for LAR #317 Regarding Changes in Managment Titles ML15043A1042015-02-0505 February 2015 NRR E-mail Capture - Mf Crystal River TAC ML15015A6722015-01-15015 January 2015 NRR E-mail Capture - NRC Acceptance Review for LAR - Application for Order Approving Transfer of License and for Conforming License Amendment ML14344A9992014-12-0909 December 2014 NRR E-mail Capture - Severe Weather Exemption ML14258A7432014-09-0505 September 2014 NRR E-mail Capture - FW: Comparison of Crystal River'S Exemption Secy Paper with Kewaunee'S ML14290A1992014-08-27027 August 2014 NRR E-mail Capture - Draft RAIs for Ep/Eal LAR ML14163A2512014-06-0303 June 2014 NRR E-mail Capture - Request for Additional Information - Exemption for Conducting Annual force-on-force Exercises ML14153A0842014-05-29029 May 2014 NRR E-mail Capture - Logbook Entry: 05/29/2014 ML14153A6912014-05-21021 May 2014 NRR E-mail Capture - Request for Additional Information - Decommissionign Trust Fund Exemption Request ML14132A2052014-05-0909 May 2014 NRR E-mail Capture - MF3089 - Defueled TS Amendment Request for Additrional Information ML14114A2792014-04-10010 April 2014 NRR E-mail Capture - MF3089 Defueled TS Request for Additional Information ML14113A3632014-04-10010 April 2014 NRR E-mail Capture - MF3415/MF2981 RAI on EP Exemptions, EAL Scheme Change and E Plan Amendment ML14118A2872014-02-20020 February 2014 NRR E-mail Capture - Request for Additional Information: Exemptions to the Radiological Emergency Plan Requirements ML14045A0012014-02-12012 February 2014 NRR E-mail Capture - RAI: Adminstrative Controls ML14031A1752014-01-27027 January 2014 NRR E-mail Capture - CR3 Certified Fuel Handler Training and Retraining Program Approval - RAI Request ML14017A0772014-01-16016 January 2014 NRR E-mail Capture - Brunswick 1 and 2, Crystal River Unit 3, Harris Unit 1, and Robinson Unit 2 - Acceptance for Review of License Amendment Request for Cyber Security Plan Implementaion Milestone 8 (TAC Nos. MF3263 - MF3267) ML14027A0332013-12-16016 December 2013 NRR E-mail Capture - Eplan and EAL Scheme Change Request for Additional Information (LAR #315) ML13336A9112013-12-0202 December 2013 NRR E-mail Capture - Periodic Update to the Crystal River 3 Containment Petition ML13198A1422013-07-17017 July 2013 NRR E-mail Capture - Draft RAI - Request to Amend Section 5.0 of the CR-3 Technical Specifications (MF1504) ML13157A2062013-05-31031 May 2013 NRR E-mail Capture - Logbook Entry: 5/31/2013 ML13155A2062013-05-29029 May 2013 NRR E-mail Capture - Petition Status Update - Containment for Crystal River ML13120A0412013-04-29029 April 2013 NRR E-mail Capture - Status Update for Petition on Crystal River 3 ML13095A4002013-04-0505 April 2013 E-mail - Acceptance of Requested Licensing Action Change of Licensee Name ML13052A2402013-02-0808 February 2013 LTR-13-0131 - E-mail Tom Gurdziel Concerns Crystal River, Unit 3 ML13015A2832013-01-14014 January 2013 NRR E-mail Capture - Status of 10 CFR 2.206 Petition Related to Crystal River 3 ML13011A1482013-01-10010 January 2013 NRR E-mail Capture - CR-3 EPU LAR - Additional RAI from Eeeb (ME6527) ML12304A0682012-10-26026 October 2012 NRR E-mail Capture - RAIs Regarding Crystal River 30-day Report for ECCS Model Changes Pursuant to 10 CFR 50.46 Requirements (ME8408) ML12297A3922012-10-23023 October 2012 NRR E-mail Capture - Draft Bypass Test Plan 2024-07-03
[Table view] Category:Letter
MONTHYEARIR 05000302/20240012024-09-23023 September 2024 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, NRC Inspection Report No. 05000302/2024001 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24226B2392024-08-27027 August 2024 Application for License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Acknowledgement of Withdrawal ML24179A0702024-07-26026 July 2024 SHPO S106 Completion Crystal River Unit 3 ML24205A2192024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Muscogee Nation ML24205A2182024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Nation of Oklahoma ML24179A0912024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Tribe of Florida ML24205A2202024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3_Miccosukee Tribe of Florida ML24190A1912024-07-0808 July 2024 Fws Concurrence for Crystal River Unit 3 ML24172A2552024-06-20020 June 2024 Fws to NRC Species List: Florida Ecological Services Field Office 06/20/2024 ML24170A9242024-06-18018 June 2024 024-0023697 Crystal River License Termination Plan Unit 3 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24114A2262024-04-24024 April 2024 Amended Special Package Authorization for the Cr3 Middle Package (Crystal River 3 Middle Package - Docket No. 71-9393) IR 05000302/20230022024-04-17017 April 2024 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2023002 ML24054A0612024-04-0202 April 2024 Request to Initiate Section 106 Consultation Regarding the License Termination Plan for Crystal River Unit 3 in Citrus County, Florida ML24079A2492024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Johnson, Lewis Johnson ML24054A0582024-04-0202 April 2024 Achp S106 Initiation Crystal River Unit 3 - Letter 1 ML24079A2472024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Cypress, Talbert ML24079A2482024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Hill, David Hill ML24054A0812024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Osceola, Marcellus ML24089A0362024-03-29029 March 2024 Response to Audit Plan in Support of Accelerated Decommissioning Partners and Request to Add License Condition to Include License Termination Plan Requirements. W/Enclosures 1 to 5 ML24073A1922024-03-11011 March 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24054A6452024-02-29029 February 2024 Letter - Reply to Request for RAI Extension Related to the Crystal River License Termination Plan ML24030A7482024-02-12012 February 2024 Audit Report Cover Letter and Report - Crystal River Unit 3 Nuclear Generating Plant LTP ML23342A0942024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23345A1882023-12-0606 December 2023 Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML23320A2592023-11-17017 November 2023 STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice ML23313A1322023-11-15015 November 2023 Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant ML23310A0712023-11-0707 November 2023 Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP ML23187A1112023-07-25025 July 2023 Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements ML23107A2722023-06-13013 June 2023 Letter Transmitting NRC Survey Results for East Settling Pond ML23160A2962023-06-0909 June 2023 Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 IR 05000302/20220032023-05-25025 May 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003 ML23103A1902023-04-19019 April 2023 Request for Supplemental Information Cover Letter ML23058A2532023-03-22022 March 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River, Unit 3 - NRC Inspection Report No. 05000302/2022003 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22265A0192022-09-26026 September 2022 Nuclear Generating Plant - U.S. Nuclear Regulatory Commission'S Analysis of ADP CR3, Llc'S Decommissioning Funding Status Report (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20220022022-08-0909 August 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022002 IR 05000302/20220012022-05-0303 May 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022001 ML22116A1752022-04-27027 April 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3- Independent Spent Fuel Storage Installation Security Inspection Report 07201035/2022401 ML22105A3992022-04-18018 April 2022 Nuclear Generating Plant - Change in NRC Project Manager ML22011A1362022-01-31031 January 2022 Independent Spent Fuel Storage Installation Security Inspection Plan ML22024A2142022-01-24024 January 2022 Nuclear Generating Plant - NMFS NRC Letter - Crystal River Energy Complex Biological Opinion Status (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20210042022-01-24024 January 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004 ML21351A0052021-12-20020 December 2021 NRC Analysis of ADP CR3, LLC Decommissioning Funding Status Report for the Crystal River Unit 3 Nuclear Generating Plant (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21322A2702021-11-24024 November 2021 Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3 IR 05000302/20210032021-11-0909 November 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021003 and 07201035/2021001 ML21288A4292021-10-18018 October 2021 Letter - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan 2024-09-23
[Table view] Category:Photograph
MONTHYEARML1029107172010-10-20020 October 2010 Horizontal Tendons Pages 26-39 ML1029205162010-09-20020 September 2010 Photo ML1019304132010-06-0909 June 2010 Photograph - Progress Energy, Storm Drain Stabilization Pond Wells ML1007504722010-03-0404 March 2010 Various Photos - Crystal River 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 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 ML1028710382010-01-0707 January 2010 Email - Subject: Spauling Pictures, Attachments: Spauling 010.jpg; Spauling 001.jpg to Spauling 009.jpg ML1028710392010-01-0707 January 2010 Email - from: Chou, Rich to: Powell, Sid Cc: Franke, Mark; Lake, Louis; Sykes, Marvin; Morrissey, Thomas; Reyes, Rogerio Dated Thursday, January 07, 2010 11:53 Am Subject: FW: Wednesday Ncrs 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: ML1029107012009-12-11011 December 2009 Email - from: Williams, Charles R. to Lake, Louis; Thomas, George; Nausdj@Ornl.Gov; Carrion, Robert Cc: Miller, Craig L (Charles.Williams@Pgnmail.Com) Dated Friday, December 11, 2009 4:14 PM Subject: Fm 2.11 for Review Attachments: Fm 2.11( ML1027204462009-12-0808 December 2009 3.4 Exhibit 7, Petrographic Report ML1028703492009-11-23023 November 2009 2.8 Inadequate Support of Tendons During Pouring ML1029306272009-11-14014 November 2009 Email - Subject: Photos of Core #5 ML1029107202009-10-29029 October 2009 5.6 Exhibit 7 Grease Photos ML1029206172009-10-23023 October 2009 Subject: October 23 2009 Containment Picture ML1029204802009-10-20020 October 2009 Email - Subject: October 20 2009 Containment Pictures ML1029204822009-10-18018 October 2009 Email - Subject: October 18 2009 Core Bore Pictures ML1029204842009-10-16016 October 2009 Photos; Picture007.jpg, Pcture008.jpg, Picture009.jpg, Picture010.jpg, Picture014.jpg, Picture021 .Jpg, Picture022.jpg, Picture023.jpg ML1029204852009-10-15015 October 2009 Subject: October 15 2009 Containment Pictures ML1029204892009-10-15015 October 2009 Subject: October 15 2009 Crack Pictures ML1029204972009-10-14014 October 2009 Photos; Picture021.jpg, Picture022.jpg, Picture023.jpg, Picture024.jpg, Picture025.jpg, Picture026.jpg, Picture027.jpg, Picture028.jpg, Picture029.jpg, Picture030.jpg, Picture031.jpg, Picture032.jpg, Picture033.jpg, Picture034.jpg, Picture0 ML1007504162009-10-14014 October 2009 Email from D. Pelton to S. Lee, Subj: Fyi - Status Update: Crystal River ML1007504282009-10-0808 October 2009 Email from D. Toro-Diaz to D. Weaver, Subj: Additional Photos - Crystal River ML1007504272009-10-0707 October 2009 Email from D. Toro-Diaz to D. Weaver, Subj: Crack Found Exterior Containment Wall ML1028702582009-10-0606 October 2009 Email - October 6 2009 Licensee Pictures ML0904907492009-04-13013 April 2009 Request for Comments Concerning the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application Review 2010-09-20
[Table view] Category:Report
MONTHYEAR3F0324-03, Enclosures 10 - 17: Crystal River, Unit 3, Response to Request for Additional Information2024-03-31031 March 2024 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 ML24090A0052023-10-10010 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
[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
[Table view] |
Text
Senaupta,'Abhijit From: Thomas, George Sent: Tuesday, January 12, 2010 3:57 PM To: Naus, Dan J.
Cc: Lake, Louis
Subject:
FW: Petrographic Report Attachments: MACTEC Petro Core 7 and 87.pdf From: Miller, Craig L [1]
Sent: Tuesday, January 12, 2010 2:29 PM To: Thomas, George
Subject:
FW: Petrographic Report Second one...
From: Miller, Craig L Sent: Tuesday, January 12, 2010 2:23 PM To: Thomas, George'
Subject:
RE: Petrographic Report
- George, Attached are the various test reports from MACTEC and S&ME (excluding the first two reports that you already have).
There have also been some tests that PHI had performed at Photometrics and the University of Colorado. I will send you those final reports as I get them from P11.
Let me know if you have any questions.
- Thanks, Craig From: Thomas, George [2]
Sent: Tuesday, January 12, 2010 1:15 PM To: Miller, Craig L
Subject:
RE: Petrographic Report Yes, Craig. I would like to also have the additional test reports that you have.
Thanks.
George From: Miller, Craig L [3]
Sent: Tuesday, January 12, 2010 11:02 AM To: Thomas, George
Subject:
RE: Petrographic Report Hi George, We do have a couple more petrography reports, but we also have a number of additional test reports (strength, density, modulus of elasticity, etc.). Would you like all of the test reports that we currently have?
1 /-1
Let me know'and I will send them asap.
- Thanks, Craig From: Thomas, George [4]
Sent: Tuesday, January 12, 2010 10:19 AM To: Miller, Craig L
Subject:
RE: Petrographic Report Hello Craig, You had previously provided us with a Mactec Petrography report dated 11-11-09 and a CTL Petrography Report dated 11-2-09. Could you please email me other petrographic reports that have come in since then.
Thanks.
George Thomas Special Inspection Team - USNRC 301-415-6181 From: Miller, Craig L [5]
Sent: Saturday, November 21, 2009 6:20 PM To: Thomas, George
Subject:
FW: Petrographic Report
- George, Here is the reply I received regarding your question on core 2. I have not yet determined if the report will be revised to correct the misleading statements.
- Thanks, Craig From: Wilson, David [6]
Sent: Thursday, November 19, 2009 11:04 AM To: Miller, Craig L
Subject:
RE: Petrographic Report HI Craig-I did do some limited observations on this core but I didn't see anything that would really help in our analysis. The control sample was submitted for comparison, but to compare the existing fracture to a new fracture we made some fresh fractured surfaces in our lab in sample 5 to compare fresh vs. the existing fractured surface. Do you need us to provide a report on the core #2?
Thank you
-David 2
From: Miller,. Craig L [7]
Sent: Wednesday, November 18, 2009 9:27 AM To: Wilson, David
Subject:
Petrographic Report
- David, A question was raised by the NRC on the petrographic report. It mentions that core 2 (MACTEC # 21270) was a "control sample" used for limited observations. However, there is no discussion of how it was used or what was observed in the report. Can you provide any details on this core?
- Thanks, Craig 3
A
,( MACTEC 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. 6468-09r2535
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 21.271A), 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 :isour 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.2t1329 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 2127 IA.
Additionally, as requested, parameters of the air void system weremevaluated 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 4 Phone:ý858-278-3600
- Fax: 858-278-5300 www.mactec.com Page 1 of 16 DCN CR-017
Crystal River Stean GeneratorReplacement Project December 8, 2009 Report of Petrographic..Observations MACTEC Project No. 6468-09-2535 Crnstal River NuclearGeneratingFacility, Florida In addition to the petrographic observations, the Mobs hardness of the coarse aggregates :in samples.
21271A and 2.1329 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
CrystalRiver Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC ProjectNo. 6468-09.2535 Crystal River Nuclear GeneratingFacility, Florida Aggregate.
Sample.212 71A The coarse aggregate generally .consisted of a naturalcarbonate 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 approximately50% 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 2127 1, 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.ý 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 10and 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.
e Both coarse aggregates have some particles with a moderate amount of void space.
a Both fine aggregates are predominately quartzwith 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 isIformed by the replacementof 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
Crystal River Steam. GeneratorReplacementProject December 8, 2009.
Report of PetrographicObservations MACTEC Project No. 6468-09-2535 Crystal River.NuclearGeneratingFacility,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 (21271AA 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 2127IA and was, not.
observed in sample 21 269A.
It appears the coarse aggregate in both .samples (21271A and 21329) could. be from the same source or*
from the same general geologic deposit.. It cannot be said withl00% certainty that both coarse aggregate.
samples cameý 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, altotal 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 proportionof 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 intercepted by a traverse line divided by, the length of that line; the: unit is a reciprocallength.
4 Page 4 of 16 DCN CR-017
Crystal River Steam GeneratorReplacement Project December 8, 2009 Report ofPetrographicObservations MACTEC ProjectNo. 6468-09-2535 Crystal River Nuclear Generating Facility,Florida Paste Content = 26.0%
Pastecontent is the proportionof the total volume of the concrete thatis hardenedcement paste expressedas percentage by volume Paste-Air Ratio = 8.34 Paste-Air ratio is the ratioof the volume of hardened cement paste to.the volume of the airvoids in the concrete Average Chord Length = 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 areaof the airvoids divided by theirvolume, expressed in compatible unitsso that the unitof specific surface is a reciprocallength.
Spacing Factor = 0.0029 inch Spacingfactor is a parameterrelated to the maximum distance in the cement pastefrom the periphery ofan airvoid, 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 needrto be known and additional calculations would need to be performed.
We trust this information meets your current needs. If more informationz is needed, or if you have any questions, please contact us&
Sincerely, MACTEC ENGINEERING AND CONSULTING, INC..
David C. Wilson: Ph.D.
Senior Principal Professional io'r.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
Crystal River Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC Project No. 6468-09-2535 Crystal River Nuclear GeneratingFacility, Florida Remarks Photograph of core as received.
dl M1 Remarks Photograph of core as received.
Page 6 of 16 DCN CR-017
Crystal River Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC ProjectNo. 6468-09-2535 Crystal River Nuclear GeneratingFacility, Florida w
Remarks Photograph of core as received.
Remarks Photographs of polished sections.
a 7
Page 7 of 16 DCN CR-017
CrystalRiver Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC Projec No.
At 6468-09-2535 CrystalRiver NuclearGeneratingFacility, Florida Photomicrographs of both samples (polished sections) showing similarities in aggregates.
Sample 21271 A I Sample 21329 8
Page 8 of 16 DCN CR-017
Crystal River Steam GeneratorReplacement Project December 8, 2009 Report of PetrographicObservations MACTEC ProjectNo. 6468-09-2535 Crystal River Nuclear Generating Facility,Florida Photomicrographs of (thin sections in cross-polarized light) showing similarities in aggregates.
Sample 21271 A I Sample 21329 9
Page 9 of 16 DCN CR-017
fMACTEC
-1..
SUMMARY
OF PETROGRAPHICOBSERVATIONS OF HARDENED CONCRETE - ASTM C-856-04 PROJECT NAME Crystal River Core Petrography Project I
PROJECT NUMBER 6468-09-2535 DATE SAMPLED RECEIVED 10-25-09 SAMPLE I.D. 2127 1A SAMPLE SIZE AND DESCRIPTION Concrete core, approximately 3 33/4 inches in AS RECEIVED diameter, approximately 7 to 8 inches long.
OBSERVATIONS BY David Wilson I CHARACTERISTICS COARSE AGGREGATE:
OBSERVATIONS Shape Angular to sub rounded Grading Approximately 34 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 Peftogrphic Observations,Sample I.D. 21271A Page I o#4 11Fo IrIm".R,evie ,wedand-Ap,prov.ed-fo,r Us,e-o,n Crystal River Cores Project 6468-09-2535 J. Allan Tice, Project P Cincip ll
SMACTEC 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.
small amounts present.
Contamination Not observed 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 Cracking. A few internal, fractures were observed Contamination. Not observed:.
CHARACTERISTICS: OBSERVATIONS
-CONCRETE:
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 fewý
- Size coarse aggregate particles. Theair.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 perimeter of the PetrographicObservations,Sample L.D. 21271A Page2 of4 Form Reviewed and Approved for Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, Project Principal Paa11 of "6 DUN CR-017
JMACTEC 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 previouslv.
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 loWw/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 1,991) 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 '/4 to /2 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 P Size,
- Abundance, Composition.
Mineral Admixtures:, Fly-ash was not observed..
- Size
- Abundance
- Identification_
Contamination: Not observedi
- Size
- Abundance
- Identification PetrographicObservations,Sample LD. 21271A Page 3 of4 Form Reviewed and Approved for Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, Project Principal
MACTEC 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 LD. 21271A Page 4 of4 Form Reviewed and Approved for Use on Crystal River Cores Project 6468-09-2535J. Allan Tice, Project Princi al
................... . . . .. . . ..DC N C R..
.MACTEC I
SUMMARY
OF PETROGRAPHIC OBSERVATIONS OF F
HARDENED CONCRETE 11 PROJECT NAME
- ASTM C-856-04 Crystal River Core Petrography Project 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/ inches in AS RECEIVED, diameter, 2 pieces,. each approximately 6 inches long.
OBSERVATIONS BY David Wilson CHARATERISTIC COARSE AGGREGATE:.
~ BSERVATIONS I Shape Angular to sub rounded Grading Approximately 3/4/4 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.
Contamination Not observed 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:
PetrographicObservations,Sample LD. 21329 Page,l of 3 Form Reviewed and Approved for Use on CrystalRiver Cores.Project 6468-09-2535 J. Allan Tice, Project Principal SP~nn I Aif 1A
~DGN OR-017..
YMACTEC
- Degree
- Products Coatings Not Observed Rims Not Observed Internal Cracking A few internal fractures. were observed Contamination Not observed
( CHARACTERISTICS"i OBSERVATIONS
... .. CONCRETE: . . . . . .
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,tothe 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 7 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 rangeof 0.4 to 0.5 Estimatedcementcontent (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 I.D. 21329 Page 2 of 3 Form Reviewed and Approved for Use on Crystal River Cores Project 6468.09-2535 J. Allan Tice, Project PrincIal
- DCN-CR-017
, i, MACTEC with. a hardened steel~point Porosity Did not appear very porous:*
Carbonation The V2 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 II polarized light microscope.
Aven Digital Microscope Starrett 6 inch rule SN 109000003 Note: No. M&TE used is subjectto calibration requirements.,.
PetrographicObservations,Sample LD. 21329 Page 3of3 Form Reviewed andApproved for Use on Crystal River Cores Project 6468-09-2535 J.Allan Tice, Project Princi pal DCN CR-.17.