ML102880495
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| ML102880495 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/20/2010 |
| From: | - No Known Affiliation |
| To: | Office of Information Services |
| References | |
| FOIA/PA-2010-0116 | |
| Download: ML102880495 (1) | |
Similar Documents at Crystal River | |
|---|---|
Category:Report
MONTHYEARML23345A1882023-12-0606 December 2023
[Table view]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 Category:Miscellaneous MONTHYEARML16176A3392016-10-28028 October 2016
[Table view]Decommissioning Lessons Learned Report and Transmittal Memorandum 3F0616-02, Nrg Commitment Change Report - June 20162016-06-14014 June 2016 Nrg Commitment Change Report - June 2016 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re2013-01-31031 January 2013 Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Res 3F0512-01, NRC Commitment Change Report - May 20122012-05-14014 May 2012 NRC Commitment Change Report - May 2012 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR 3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis2011-12-14014 December 2011 Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis 3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models2011-05-0606 May 2011 Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models 3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis2010-09-0808 September 2010 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis ML1019304172010-05-0606 May 2010 Tritium Database Report ML1028710882010-03-12012 March 2010 7.6 Vibration Due to Cutting Tendons ML1028711112010-02-25025 February 2010 7.11 Added Stress from Pulling Tendons ML1028711102010-02-23023 February 2010 6.3 Thermal Effects of Greasing ML1028702742010-02-0606 February 2010 6.4 Rigid and Flexible Sleeves ML1028804952010-01-20020 January 2010 5.3 Exhibit 1 Interviews Regarding Maintenance ML1028708922010-01-16016 January 2010 Email - from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Lake, Louis; Thomas, George; Carrion, Robert; 'Trowe@Wje.Com' Cc: Williams, Charles R. Dated Saturday, January 16, 2010 1:10 PM Subject: Failure Mode 5.1 for Review and Comment ML1028709832010-01-12012 January 2010 from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:57 PM Subject: FW: Petrographic Report ML1028709862010-01-12012 January 2010 Email - from Thomas, George to Naus, Dan J. Cc: Lake, Louis Dated Tuesday, January 12, 2010 3:56 PM Subject: FW: Petrographic Report Attachments: S&Me Modulus Core 16, 40, 63, 65, 66.pdf; S&Me Density Core 16, 40, 60, 63, 65, 66.pdf... ML1028709792010-01-12012 January 2010 Email - from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:59 PM Subject: FW: Petrographic Report ML1028710352010-01-11011 January 2010 Email - from: Williams, Charles R. to: Lake, Louis; Thomas, George; Carrion, Robert; 'Nausdj@Ornl.Gov'; 'Daniel.Fiorello@Exeloncorp.Com'; Lese, Joseph A. Cc: Miller, Craig L (Charles.Williams@Pgnmail.Com) Dated Monday, January 11, 2010 5:38 ML1028710342010-01-11011 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Trowe@Wje.Com' Dated Monday, January 11, 2010 5:42 PM Subject: Fm 5.4 Draft for Review ML1028709902010-01-11011 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Archer, John C. (Reading)'; 'Wells, Richard P. (Reading)' Cc: Miller, Craig L Subject: F ML1028710402010-01-0606 January 2010 Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Souther, Martin; 'Trowe@Wje.Com' Cc: Miller, Craig L Dated Wednesday, January 06, 2010 4:51 PM, Subject: ML1028710462010-01-0101 January 2010 5.5 Exhibit 3a Petrographic Erlin Hime May 19 ML1028710492009-12-31031 December 2009 Email - from: Williams, Charles R. Charles.Williams@Pgnmail.Com) to: Lake, Louis; Thomas, George; 'Nausdj@Ornl.Gov'; Carrion, Robert; Miller, Craig L Dated Thursday, December 31, 2009 5:20 PM Subject: Fm 9.3 Draft and Exhibits for Review ML1029106012009-12-23023 December 2009 5.8 Exhibit 5a Petrographic ML1029106322009-12-18018 December 2009 from: Miller, Craig L (Craig.Miller@Pgnmail.Com) to: Lake, Louis;Thomas, George; Nausdj@Ornl.Gov; Carrion, Robert Cc: Williams, Charles R. Dated Friday, December 18, 2009 4:47 PM Subject: Draft Fm 3.5 for Review Attachments: Fm 3.5.pptx; Fm 3F1209-11, 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report2009-12-16016 December 2009 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report ML1029107052009-12-11011 December 2009 5.2 Exhibit 2 Mactec Petrographic ML1029201382009-12-0808 December 2009 5.1 Exhibit 6A Petrographic Mactec ML1029201442009-12-0808 December 2009 5.8 Exhibit 5b Petrographic ML1029107272009-10-27027 October 2009 Summary of Results from Comparison.Pdf ML1029205002009-10-13013 October 2009 Condition Report Summary -NCRs Initiated Since Oct 12, 2009 ML1007504262009-10-12012 October 2009 Summary Report ML1028804902009-10-0505 October 2009 Condition Report Summary - Ncrs Initiated Since Sep 28, 2009 ML1029201092009-02-0404 February 2009 5.6 Exhibit 8 Cap Grease Leakage ML1029201072009-02-0404 February 2009 5.6 Exhibit 5 Surveillance Conclusion 3F0508-14, NRC Commitment Change Report - May 20082008-05-28028 May 2008 NRC Commitment Change Report - May 2008 3F1207-03, Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.2007-12-13013 December 2007 Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station. ML0731103812007-05-21021 May 2007 Progress Energy Florida, Inc. Proposed Florida Nuclear Site Transmission Planning Study, Final Report, Attachments Dand F Included 3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report2005-12-12012 December 2005 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report 3F1205-03, Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 42005-12-0303 December 2005 Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4 ML0613806752005-12-0101 December 2005 Report of Independent Auditors ML0613806782005-09-30030 September 2005 Financial Highlights ML0524401902005-08-10010 August 2005 Attachment E, Crystal River Unit 3 - License Amendment Request #290, Revision 1 Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack ML0505301682005-02-17017 February 2005 Background Discussion Material for February 24-25, 2005 NRC Meeting Relating to Replacement for BAW-2374, Revision 1, Evaluation of OTSG Thermal Loads During Hot Leg Loca. ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys 3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service2002-11-19019 November 2002 Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service ML0300701722002-10-25025 October 2002 Summary Report - Ncrs Initiated Since 10/18/2002 3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 32002-09-24024 September 2002 Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3 ML0300701742002-09-23023 September 2002 Summary Report - Ncrs Initiated Since 09/16/2002 2016-06-14 |
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FM 5.3 Exhibit 1 page 1 of 1 1/20/2010 Interview with Richard Portmann( Tendon Engineer) and Richard Pipin(Maintenance Manager)
Interviewer: Gary Hughes P11 Maintenance Issues S Added Linseed oil to the Dome when damaged in1976(Documents provided to Dr. Avi Mor)
S Have grease leaching out under equipment hatch- no idea where coming from and have not treated it- pictures in Concrete- tendon Interaction #74 Grease below equipment hatch.
0 Wax initially in sleeves I Do not power wash per PII information request 101 from Tommie Sassard.
INo PMs to do any cleaning of the containment I Grease Issues 0 Add Visconorust 2090-p4 grease to tendons per F&Q 17.0 'Grease Replacement" 0 F&Q 17.0 has provisions to report to the NRC if specifically add more grease than take out.
- Have grease leaching out under equipment hatch- no idea where coming from and have not treated it- pictures in Concrete- tendon Interaction #74 Grease below equipment hatch-work order has been written and will be worked soon
- Over the years adding higher density grease to reduce grease loss. Added more to vertical tendons a few years ago to make up for losses. Thought losses were grease settling at the bottom or oil separating from the grease
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