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:ML102871040 |
Person / Time |
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Site: |
Crystal River ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
01/06/2010 |
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From: |
Williams C Progress Energy Co |
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To: |
Robert Carrion, Lake L, George Thomas Office of New Reactors, NRC/RGN-II |
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References |
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FOIA/PA-2010-0116 |
Download: ML102871040 (20) |
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Category:E-Mail
MONTHYEARML24025A0952024-01-24024 January 2024 Clarifications Related to the NRC Staff'S 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 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 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 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 ML12268A3592012-09-24024 September 2012 NRR E-mail Capture - Acceptance Review for LAR Regarding Cyber Security Plan Implementation Schedule Milestones ML12208A0142012-07-25025 July 2012 NRR E-mail Capture - State Consultation ML12184A3442012-07-0202 July 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs ML12144A0102012-05-22022 May 2012 NRR E-mail Capture - Acceptance Review Determination: CR-3 - Relief Request #12-001-MX for Option to Use ASME Code Case N-791 for Containment Repair ML12107A0682012-04-0404 April 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb) ML12100A1022012-03-30030 March 2012 NRR E-mail Capture - Acceptance Review for CR3 - LAR 312- Departure from a Method of Evaluation for Aux Bldg Over Head Crane, Implementation Schedule Change ML12023A1272012-01-23023 January 2012 NRR E-mail Capture - Acceptance Review Determination for TAC ME7729: CR3 - Relief Request #11-001-MX, Containment Surveillance Schedule, Fourth 10-Year ISI Interval ML12019A2662012-01-17017 January 2012 NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206 ML12019A2672012-01-17017 January 2012 NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206 2024-01-24
[Table view] Category:Drawing
MONTHYEARML19029A0032018-07-18018 July 2018 Reference 1 - Duke Energy Crystal River Plant Descriptions (Survtech Solutions) ML12054A1992012-01-0505 January 2012 Drawing E-201-141, Rev. 11, (D-201-141), Electrical Main Control Board Integ. Cont. System Assy. ML12054A1962012-01-0505 January 2012 Drawing E-201-151, Rev. 20, (D-201-151), Electrical Main Control Board Primary Secondary Auxiliaries Assembly 3F0112-05, Drawing E-201-141, Rev. 8, (D-201-141), Electrical Main Control Board Integ. Cont. System Assy.2012-01-0505 January 2012 Drawing E-201-141, Rev. 8, (D-201-141), Electrical Main Control Board Integ. Cont. System Assy. ML11314A1392011-09-0101 September 2011 Drawing No. 521-142-001, EC70139, Rev. 0, Attachment Z100R0, Horizontal Bracing Connections at Roof El. 209'-1 (Between Column Line I1 & J1) ML11314A1322011-09-0101 September 2011 Drawing No. 522-041-012, EC70139, Rev. 0, Attachment Z70R0, E-W Member Moment Connections at Floor, El. 162'-0 ML11314A1382011-09-0101 September 2011 Drawing No. 522-041-019, Rev. 0, EC70139, Rev. 0, Attachment Z95R0, Column Connections to Concrete Floor ML11314A1372011-09-0101 September 2011 Drawing No. 522-041-018, EC70139, Rev. 0, Attachment Z93R0, Column Connections to Concrete Floor ML11314A1362011-09-0101 September 2011 Drawing No. 522-041-016, EC70139, Rev. 0, Attachment Z92R0, N-S Member Connections at El. 162'-0 ML11314A1352011-09-0101 September 2011 Drawing No. 522-041-015, EC70139, Rev. 0, Attachment Z91R0, N-S Member Connections at El. 162'-0 ML11314A1342011-09-0101 September 2011 Drawing No. 522-041-014, EC70139, Rev. 0, Attachment Z73R0, N-S Member Connections at El. 162'-0 ML11314A1332011-09-0101 September 2011 Drawing No. 522-041-013, EC70139, Rev. 0, Attachment Z72R0, E-W Member Moment Connections at Floor, El. 162'-0 ML11314A1312011-09-0101 September 2011 Drawing No. 522-041-011, EC70139, Rev. 0, Attachment Z52R0, Crane Girder Bracket Connections ML11314A1302011-09-0101 September 2011 Drawing No. 522-041-010, EC70139, Rev. 0, Attachment Z52R0, E-W Member Moment Connections at Floor El. 162'-0 ML11314A1292011-09-0101 September 2011 Drawing No. 522-041-009, EC70139, Rev. 0, Attachment Z51R0, Vertical Bracing Connections ML11314A1282011-09-0101 September 2011 Drawing No. 522-041-008, EC70139, Rev. 0, Attachment Z50R0, Vertical Bracing Connections ML11314A1272011-09-0101 September 2011 Drawing No. 522-041-007, EC70139, Rev. 0, Attachment Z49R0, Vertical Bracing Connections ML11314A1262011-09-0101 September 2011 Drawing No. 522-041-006, EC70139, Rev. 0, Attachment Z48R0, Vertical Bracing Connections ML11314A1252011-09-0101 September 2011 Drawing No. 522-041-005, EC70139, Rev. 0, Attachment Z47R0, Vertical Bracing Connections ML11314A1242011-09-0101 September 2011 Drawing No. 522-041-004, EC70139, Rev. 0, Attachment Z46R0, Vertical Bracing Connections ML11314A1232011-09-0101 September 2011 Drawing No. 522-041-003, EC70139, Rev. 0, Attachment Z45R0, Vertical Bracing Connections ML11314A1412011-09-0101 September 2011 Drawing No. S-522-003, EC70139, Rev. 0, Attachment Z101R0, E-W Member Moment Connections at Floor El. 162'-0, E-W Member Connections at El. 162'-0 (at Column Line L, at Column Line S1, and Between Column Line M1 and N1), N-S.. 3F0911-01, Drawing No. 522-041-024, EC70139, Rev. 0, Attachment Z122R0, Vertical Bracing Connections2011-09-0101 September 2011 Drawing No. 522-041-024, EC70139, Rev. 0, Attachment Z122R0, Vertical Bracing Connections ML11314A1402011-09-0101 September 2011 Drawing No. S-521-102, EC70139, Rev. 0, Attachment Z96R0, N-S Member Connections (Purlin) at Roof El. 209'-1 ML11314A1562011-09-0101 September 2011 Drawing No. 522-041-023, EC70139, Rev. 0, Attachment Z121R0, E-W Member Moment Connections at Floor El. 162'-0 ML11314A1552011-09-0101 September 2011 Drawing No. 522-041-022, EC70139, Rev. 0, Attachment Z120R0, Crane Girder Bracket Connections ML11314A1542011-09-0101 September 2011 Drawing No. 422-057-001, EC70139, Rev. 0, Attachment Z119R0, Concrete Tie Beam Between 301-S, and 302A-S Concrete Column Pier ML11314A1532011-09-0101 September 2011 Drawing No. 521-142-006, EC70139, Rev. 0, Attachment Z118R0, Crane Girder Bracket Connections ML11314A1522011-09-0101 September 2011 Drawing No. 521-142-005, EC70139, Rev. 0, Attachment Z117R0, Crane Girder Bracket Connection ML11314A1512011-09-0101 September 2011 Drawing No. 522-041-021, EC70139, Rev. 0, Attachment Z111R0, Crane Girder Bracket Connections ML11314A1502011-09-0101 September 2011 Drawing No. 521-142-004, EC70139, Rev. 0, Attachment Z110R0,Column Connections to Concrete Floor ML11314A1492011-09-0101 September 2011 Drawing No. 521-142-003, EC70139, Rev. 0, Attachment Z109R0, Column Connections to Concrete Floor ML11314A1482011-09-0101 September 2011 Drawing No. 522-041-002, EC70139, Rev. 0, Attachment Z108R0, Vertical Bracing Connections ML11314A1472011-09-0101 September 2011 Drawing No. 522-041 Sheet 001, EC 70139, Rev. 0, Attachment Z107R0, Vertical Bracing Member Replacement, Vertical Bracing Connections, N-S Member Connections at Roof El. 209'-1 (Between Column Line P1 & Q1), E-W Member.. ML11314A1462011-09-0101 September 2011 Drawing No. 522-041-020, EC70139, Rev. 0, Attachment Z106R0, Vertical Bracing Member Replacement and Vertical Bracing Connections ML11314A1452011-09-0101 September 2011 Drawing No. 521-142-002, EC70139, Rev. 0, Attachment Z105R0, Crane Girder Bracket Connections ML11314A1442011-09-0101 September 2011 Drawing No. 522-041-017, EC70139, Rev. 0, Attachment Z104R0, Miscellaneous N-S Member Connections and E-W Member Connections at El. 189'-9 (at Column Line S1) ML11314A1432011-09-0101 September 2011 Drawing No. S-522-006, EC70139, Rev. 0, Attachment Z103R0, Vertical Bracing Member Replacement and Vertical Bracing Connections ML11314A1422011-09-0101 September 2011 Drawing No. S-522-004 EC70139, Rev. 0, Attachment Z102R0, E-W Member Connections at Roof El. 209'- 1 (at Column Line S1), N-S Member Connections at Roof El. 209'-1 (Between Column Line P1 & Q1)., N-S Member Connections.. ML11256A0822011-07-20020 July 2011 Drawing 521-142, Revision 0, Auxiliary Building - South Steel Framing Modifications Elevations. Sheet 001 3F0711-04, Drawing 522-041, Revision 0, Auxiliary Building South Steel Framing Modifications Details. Sheet 0222011-01-0606 January 2011 Drawing 522-041, Revision 0, Auxiliary Building South Steel Framing Modifications Details. Sheet 022 ML11256A0862011-01-0606 January 2011 Drawing 522-041, Revision 0, Auxiliary Building South Steel Framing Modifications Details. Sheet 021 ML11256A0872011-01-0606 January 2011 Drawing 521-142, Revision 0, Auxiliary Building North Steel Framing Modifications Details. Sheet 005 ML11256A0882011-01-0606 January 2011 Drawing 521-142, Revision 0, Auxiliary Building North Steel Framing Modifications Details. Sheet 006 ML11256A0842010-12-10010 December 2010 Drawing 521-142, Revision 0, Auxiliary Building North Steel Framing Base Plate Modifications. Sheet 003 ML1029200772010-09-20020 September 2010 Licensee Drawing SC-421-032, Title Illegible ML1029200762010-09-20020 September 2010 Licensee Drawing SC-421-036, Title Illegible ML1029200662010-09-20020 September 2010 Drawing 421-350 - EC 603016 Attachment Z10R24 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: ML1029306522009-11-12012 November 2009 2009 Nov 12 - Containment Unfolded Graphics_Ir Mosaic.Pptx 2018-07-18
[Table view] 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: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
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
[Table view] |
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Sengupta, Abhijit From: Williams, Charles R. [Charles.Williams@pgnmail.com]
Sent: Wednesday, January 06, 2010 4:51 PM To: Lake, Louis; Thomas, George; 'nausdj@ornl.gov'; Carrion, Robert; Souther, Martin;
'trowe@wje.com' ,I,-
MleCraig L '*,
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FM 5.5 - Corrosion of Rebars adSleeves t-,,
Attachments: FM 5.5 - Corrosion Rebars a; Sleeves.pptx; FM 5.5 Exhibit 1 Permeabili v w2c from /
Mehta.pdf; FM 5.5 Exhibit 2'Mix Design- from Dome Repair Report-cgp df; FM 5.5 Exhibit 3a Petrographic Erlin Hime May 1976-1.pdf; FM 5.5 Exhibit 3b Petrograp c CTL.pdf; FM 5.5 Ehibit 3c Petrographic Mactec 2009-1-*1-1 .pdf; FM 5.5 Exhibit 4 WC ratio RB-1 5.pdf; FM 5.5 hibit 5 Cover (etail - Plan 421-036-SHOOO.pdf; FM 5.5 Exhibit 6 Cover photos.pdf\
Mr Lake and Others, Attached for your review is the draft of FM 5.5 and its exhibits. I you have any questions, please contact me or Craig Miller.
Charles Williams 1
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< MACTEC engineering and constructing a better tomorrow November 11 2009 Mr. Craig Miller Progress Energy (352) 795-6486 ex 1026 Craig.miller@pgnmail.com Su.biject: Report of Petrographic Observations Crystal River Containment Wall Steam Generator Replacement Project Crystal River Nuclear Generating Facility, Florida MACTEC Project No. 6468-09-2535 Dear Mr.
MACTEC Engineering and Consulting, Inc. (MACTEC) 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. An additional core was received under chain of custody for limited observations. It is our understanding the two cores submitted for petrographic observations are from an area of the containment wall where a fracture was discovered running parallel to the surface at a depth of approximately 8 to 9 inches. We understand the core that was submitted for limited observations was from an area where the subject fracture had not occurred.
The cores submitted are as follows:
Core Numberl' Laboratory Number Description of the Core Assigned by MACTEC 5 - 2Q269 From an area where the fracture. had. occurred .
2 21270 From an area where the fracture had not occurred 7 21271 From an area where the fracture had occurred.
Each core was photo documented as received and then saw cut longitudinally into halves. Each half was labeled with the same sample number and than A and B were added to designate the halves. As requested the B half for cores 21269 and 21270 were shipped to CTL Group in Skokie Illinois. The B half of core 21271 is being held for possible future use. The A half's of the cores were used for our analysis.
The purpose of our work was to perform a petrographic analysis of samples 21269A and 2127 IA and limited observations of sample 21270A. It is our understanding that you also require specific information MACTEC Engineering and Consulting, Inc.
9177 Sky Park Court, San Diego, CA 92123
- Fax: 858-278-5300 www.mactec.com FM 5.5 Exhibit 3c 01/01/10 page 1 of 5
FM 5.5 Exhibit 3c page 2 of.5 CrYWial River Concrete Core Obseraotions Nov*ember 1I, 2009 Report oa Pettvgraphic Observations
- A CTEC Project NA\,6468-09-2535 Cr-Ystal River Nuclear Generating F*cilitv. Fhlorida relative to the age of the fractured surfaces on samples 21269A and 2127 IA. Sample 21270A was used as a control sample that did not have a fractured surface.
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 8OX.
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 O.f concrete. examines the constituents of the concrete including coarse aggregates, fine dagregates,: 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 petrograph ic examination can also estimate the. water to cement ratioi, 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 finishino, observe micro cracking present and other conditions within the concrete:which might give infortnation 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 C(oncrete. Photographs From our examination are attached. A summary of oui' observations and discussion are as follows.
FM 5.5 Exhibit 3c 01/01/10 page 2 of 5
- - -FM 5.5 Exhibit 3c page 3 of 5 Crystal River Concrete (ore Obse,-vations ,November 1/, 2009 Report of PetrographicObservations tIAT(7 Proie! No, 6468-09-2535 Crystal River Nuclear Generating FocilitY, Florida APggregate 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, fossiliferous 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-On sample 21271, there were 4 coarse aggregate pieces on the cutsurface of the core that retained moisture (and moisture in the surrounding paste) longer than other portions of the sample. These pieces are shown in Photographs 5, 6, 7, and 8K One-of the pieces (Photograph 5 for core 21271) had a darkened rim. A thin section was prepared from the piece in photograph 7 and this piece containedmicrocrystalline quartz and radial silica and exhibited localized evidence of alkali silica reaction.
The fine aggregate. was observed to be a natural.. siliceous sand consisting mostly of quartz. The: particles were generally sub angular to sub-rounded in shape and fairly evenly distributed.
Cement Paste T.he cement paste.was medium light gray (
Reference:
colors from The Geological 'Society. of America Rock-Color Chart, 1991). The paste appeared moderately hard and not easily scratched with a hardened steel point. The concrete, appeared to have: been placed at a moderately low water. to cement ratio, possibly in the range of, 0.4 to 0.5.: Indication of placement, at a high water to cement ratio such as significant bleed channels and water gain.voids were not observed,,.-
Air Voids, Voids, and Cracks The concrete appeared to beair entrained' and had a total air content estimated to bearofUnd2 to 3%. The.
voids were generally:small and spherical. Some 'air void clustering was-observed around a few coarse aggregate particles, The air void distribution was moderately un-even and some small::areas lackedair-entrainment: There was limited.mineral growth observed in some of the air. voids. Calcium hydroxide was observed lining some air voids.
3 FM 5.5 Exhibit 3c 01/01/10 pageý 3 of 5
FM 5.5 Exhibit 3c page 4 of.5.
IMACTEC
- Location
- T yp e . ............. .
Altertion: Not observed
- Degree & Type
- Reaction Products
- Location
- Identification Nature and Condition of Surface There appeared to be white paint on the.
Tra*tm-nt ' -*-vtnir c-Ar:- -F 1,-t-h .r, Estimated water-cement ratio (based on Appeared to have a moderately low w/c
[visual. . observations only) rato p bly in the range of 0.4 to .5.
Lunrted cernett cu,,tent (bacsd 66 6saal Appeared to have a iiomu.eiaiy high observations only) cement content PASTE: .....
Color (GSA rock color chart 1991) Medium lightgray .
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 droAn of water.
The outer 1/4/4 to 1/22 inch of the exterior surface was carbonated. The fractured surface was not carbonated.
1 J*l
- I I . I I .I il l q _ Jl Kesiouai un-nyorateo Cement: i Sorne un-niyarated/partanly nydrated
- 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 subject to calibration requirements.
PetrographicObservations, Sample LD. 21269A rge 3of 3 Form Reviewed and Approvedfor Use on Crystal River Cores Project 6468-09-2535 J. Allan Tice, ProjectPrincipal V I/U IV I/t lIU payt '-t VI ~
I Ml 3.J L -AI MAL~ OU u I/V PJCI3JtE -t" UI
FM 5.5 Exhibit 3c page 5 of 5 SMACTEC 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 exteror surtace ot hte 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 Fsti-nmated rmnipcnmcattnt (hsed oun "ilsl Appeaed to hu"e a wIodvrateIy high observations only) cement content PASTE:
Colo0r (GSA irock .color.cliarl 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 or water.
Carbonation
-ResidLuai uii-liydiaid Distribution Particle Size Ccmiut.
The*outer 1/4 to 1/2/inch of the exterior surface was carbonated. The fractured surface was not carbonated.
SUiii& ut1-hydratedipaitialty liydiated cement particles were observed I
- Abundance
-__COMposition __________________
Mineral AIdnmI ixtires*: .Fl.y .-ash was not observed
-Size
-Abundance
-Identification_________________
Contamination: Not observed
-Size
-Abundance
- Identification______________ _______
PetrographicObservations,Sample ID. 21271A Page 3 of4 Form Reviewed and Approvedfor Use on CrystalRiver (ores Project 6468-09.2535 .. Allan Tice, Project Principal i Lf .11v, .. ,J I IV I _;./* , LJ L I_ I %.#*, k,/ Ilk/ II IU la ZI
- -M. 5.5 Exhibit 3a ~ATTAC11MEN'*.page 1 of 3.
"C"...2.
ERLIN, HIME ASSOCIATES MATERIALS AND CONCRETE CON.SULTANTS l St%C.KtlE BOULEVARD 03121 272-7730 ILLINOtS60062 PETROGRAPHIC STUDIES OF CONCRETE FOR CONSTRUCTION ENGINEERING CONSULTANTS
.1.
SUMMARY
AND DISCUSSION
- The specimen represented air-entrained concrete.
made with crushed fossiliferous coarse aggre-water-cement ratio paste. There was no. evidence that the aggregates had een either chemically or physically unsound.
. The: specimen: was.from an ,are:a where fractures%
had existed for a periodof time and where:,
moisture had been present, That was demon-strated by secondary deposits on fracture surfaces.. .
The specimen was. relatively small. Larger-specimens fr.om ,different areas of. the struc-ture would be desirable for examination in order to obtain a, better representation of. the-concrete.
INTRODUCTION "Reportied herein are the results of petrographic studies of a concrete fragment submitted by*J. Artuso of Con.-
Struction Engineering Consultants. The specimen is from the dome of the containment structure of the Florida Power Corporation, *Crystal River-, Unit. III.
Requested by Mr. Artusowere petrographic studies for evaluating: the specimen, and particularly for evidence of features that would cause :volume instability._
C-12 FM 5.5 Exhibit 3a 01/01/10 page 1 of 3
"F--.---
F 5.5 Exhibi[.3apage2of page 2 of 3 ERLIN, HIME ASSOCIATES - MAT*RIALS.ANO oCOCRETE COwSULTANTS STUDIES-Specimen -The sgecimen was an elongated fragment having nominal lateral dimensions of 5 inches, and a maximum thickness of about 3/4 inch.
All surfaces were fracture surfices except for a shallow channel about 3/32 inch wide and 1/8 inch deep., The channel appears to be the terminal area of a saw cut, Petrographic Studies - Coarse aggregate of the specimen was a buff to light brown, fine-grained, fossiliferous limestone, having a maximum nominal size of 3/4 inch.
The fine aggregate was a siliceous sand composed prin-cipally of quartz.
The aggregates were not partichlarly well graded, as evidenced by deficiencies of the finer sizes of the coarse aggregate and the coarser. sizes -of the fine aggregate.
There was%: no -vidence, that.the aggregates had.,been chemically or physically unsound. Particular attention
- .. directed to alkali-silica reactivity with respect. to
- the coarse aggregate because;'a similar type. of. aggregate doest, contain a highly reactive variety of chert. Neither the.chert nor the product of the reaction of the chert with alkalies (alkali-silica gel) was present.
.Paste of the specimen was, medium dark grey,, firm, and contained abundant residual and relict cement. The+
quality of the paste reflects a low wate+/--cement ratio.
Air occurred-as small, discrete, spherical voids that bccasionally were very slightly distorted, and as coarser irregularly shaped voids. The spherical voids are characteristic. of entrained air voids; thel irregularly.
shaped voids,, of ent-rapped.air.. The air content of :the specimen is estimated to be 51/2 percentand the parameters of the air-void system are judged to be effectiv-. for protecting-critically saturated concrete exposed to cyclic freezing.
On one of the lateral surfaces were secondary deposits composed of tufts of fine.acicularettr1ngit j (3aO .
A120 3 3CaSO 4 '31H 2 0), and7 calcite (CaCO 3 ) . [Ettring-te) was also present as tufts in some air voidsý.juSt below the fracture-surface..-
- The fragment was not uniformly thick; it tapered to a knife-like edge. Along that edge, were fine fractures C-13.
FM 5.5 Exhibit 3a 01/01/10 page 2 of 3 FM 5.5 Exhibit 3a 01/01 / 10 page 2 of 3
FM 5.5 Exhibit 3a page 3 of 3 ERLIN, HIME ASSOCIATES. - MATERIALS ANO CONCRETZ CONSULTANTS oriented subparallel to the long axis: of the fragment.
The fractures transected coarse aggregate particles. On those fracture, s-urfaces were secondary deposits similar to those described above.
The secondary compounds demonstrate that the fragment was from, an area where fractures present for a period of time had been exposed to moisture.
May 10, 1976 Erlin, Hime Associates, Inc.
by Bernard Erlin, President Petrographer c-14 FM 5.5 Exhibit 3a page 3 of 3
page 1 of 1 113
- 0) ~
'JV.VUU VIVUUU I 0 20,0oo 0 6) u CL lac "I
5,000 50 CD 30
-be 2,000 20 1,000 -)0 500 4.8rmm 5 0
- 3 200 U 100 Cement Paste 50 1t0 0
04 0.5 0,6 0,7080-91,0 SWater/Cement Ratio (b)
I Kinlmu aggregate size on concrete
)f water through concrete in cubic*
dic gradient. [(a), From Concrete 5, p, 37, (b), adapted froi Beton.
on th/e water/
- 1. voids) and i
FM 5.5 Exhibit 3b page 1 of 3 Copy No. I Report for Progress Energy CTLGroup Project No. 059169 Petrographic Examination of Concrete Half Core from Delaminated Containment Wall, Crystal River, Florida November 2, 2009 Submitted by:
Derek Brown COA #4731 5400 Old Orchard Road:.
Skokie, Illinois 60077-1030 (847) 965-7500 9030 Red Branch Road, Suite 110 Columbia, Maryland 21045 www.CTLGroup.com K *o w I :&" ýd: -q 1ý D p Ii Ro ut~Jrnc CTLGroup is a registered d/b/a of.Construction Technology Laboratories, Inc.
J 7 9 Ui/U] I] U page i OT i FK/i 3b xhibit JD NVI ~b.b L.XflIDlt U-I/U IU/1u page -I OT J
.3 ,
FM 5.5 Exhibit 3b page 2 of 3 Progress Energy Page3of 10 Crystal River November 2, 2009 CTLGroup Project No. 059169 For thin-section study, small rectangular blocks were cut from the core inner surface fracture region and within the body of the core. One side of each block was lapped to produce a smooth, flat surface. The blocks were cleaned and dried, and the prepared surfaces mounted on separate ground glass microscope slides with epoxy resin. After the epoxy hardened, the thickness of the mounted blocks was reduced to approximately 20 Pm (0.0008 in.). The resulting thin sections were examined using a polarized-light (petrographic) microscope at magnifications up to 400X to study aggregate and paste mineralogy and microstructure.
Estimated water-cement ratio (w/c), when reported, is based on observed concrete and paste properties including, but not limited to: 1) relative amounts of residual (unhydrated and partially hydrated) portland cement clinker particles, 2) amount and size of calcium hydroxide crystals,
- 3) paste hardness, color, and luster, 4) paste-aggregate bond, and 5) relative absorbency of paste as indicated by the readiness of a freshly fractured surface to absorb applied water droplets. These techniques have been widely used by industry professionals to estimate w/c.
Depth and pattern of paste carbonation was initially determined by application of a pH indicator solution (phenolphthalein) to freshly cut and original fractured concrete surfaces. The solution imparts a deep magenta stain to high pH, non-carbonated paste. Carbonated paste does not change color. The extent of paste carbonation was confirmed in thin-section.
Derek Brown Senior Microscopist Microscopy Group DB/DB Notes: 1. Results refer specifically to the sample submitted.
- 2. This report may not be reproduced except in its entirety.
- 3. The sample will be retained for 30 days, after which it will be discarded unless we hear otherwise from you.
F.Jldin9 CnWedMeKOerhqResUt www..TLGroupcorn FM 5.5 Exhibit 3b 01/01/10 page 2 of 3
4, FM 5.5 Exhibit 3b page 3 of 3 Progress Energy Page 10 of 10 Crystal River November 2, 2009 CTLGroup Project No. 059169 to 0.4 in.). Somewhat uneven distribution of voids. Marginally air entrained based on the very low volume of moderate to small sized spherical air voids in the hardened cement paste.
Depth of Carbonation: 4 to 5 mm (0.16 to 0.20 in.) as measured from the outer surface.
Negligible when measured from the inner fractured core surface.
Calcium Hydroxide*: Estimated 6 to 12% of small to medium sized crystals evenly distributed throughout the paste, and around aggregate to paste interfaces. Estimation of the volume is difficult due to the presence of calcite fines in the cement paste.
Residual Portland Cement Clinker Particles*: Estimated 4 to 8%. Some large cement particles, particularly belite clusters, of up to 0.15 mm in size suggest a portland cement as produced more than 30 years ago.
Supplementary Cementitious Materials*: None observed by the core supplied.
Secondary Deposits: None observed either in the body of the core and or near the fracture surface.
MICROCRACKING: A small number of medium length (5 to 10 mm), randomly orientated microcracks are evenly distributed throughout the body of the core. At the fractured end of the core there was no observed increase in microcracking relative to the body of the core.
ESTIMATED WATER-CEMENT RATIO: Moderate to moderately high (0.50 to 0.60) but estimation may be biased upwards due to the well advanced degree of hydration / apparent old age of the concrete.
MISCELLANEOUS:
- 1. Water droplets applied to freshly fractured surfaces were somewhat slowly absorbed by the hardened cement paste.
- 2. Some small areas of the inner fractured surface of the core, as received, exhibit a thin white haze of efflorescence-like substance suggesting leaching of lime in solution from within the core, or alternatively, moisture on or flowing past the fractured surface at the delamination position within the wall.
- 3. A moderate volume of fine calcite particles is present within the hardened cement paste, most likely from coarse aggregate crusher fines.
percent by volume of paste B.-dngKnM1g ;D"" Res:*
ýexA ~W GTtGroupxcin FM 5.5 Exhibit 3b 01/01/10 page 3 of 3
'FM 5.5 Exhibit 2 page 1 of 1 App. A - Att. No. 5 1""
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A-5-1 FM 5.5 Exhibit 2 01/01/10 page 1 of 1