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 Issue dateTitleTopic
ML16176A33928 October 2016Decommissioning Lessons Learned Report and Transmittal MemorandumSafe Shutdown
Fitness for Duty
Anticipated operational occurrence
Cyber Security
Aging Management
Fukushima Dai-Ichi
Containment Hardened Vent
Exemption Request
Fire Protection Program
3F0616-02, Nrg Commitment Change Report - June 201614 June 2016Nrg Commitment Change Report - June 2016Safe Shutdown
Boric Acid
Offsite Dose Calculation Manual
Time to boil
B.5.b
Pressure Boundary Leakage
Backfit
Operability Assessment
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 Re31 January 2013Attachment 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 ResShutdown Margin
Anticipated operational occurrence
Fuel cladding
Power Uprate
Manual Operator Action
3F0512-01, NRC Commitment Change Report - May 201214 May 2012NRC Commitment Change Report - May 2012Stress corrosion cracking
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 LAR5 January 2012Response 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 LARCoatings
Flow Accelerated Corrosion
License Renewal
Power Uprate
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 Analysis14 December 2011Summary 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 Models6 May 2011Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA ModelsPower Uprate
3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis8 September 2010CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis
ML1019304176 May 2010Tritium Database ReportOffsite Dose Calculation Manual
Hydrostatic
ML10287108812 March 20107.6 Vibration Due to Cutting TendonsFire Barrier
Finite Element Analysis
Fire Watch
ML10287111125 February 20107.11 Added Stress from Pulling TendonsOffsite Dose Calculation Manual
Fire Barrier
Coatings
Fire Protection Program
Fire Watch
ML10287111023 February 20106.3 Thermal Effects of Greasing
ML1028702746 February 20106.4 Rigid and Flexible SleevesHydrostatic
Liquid penetrant
ML10288049520 January 20105.3 Exhibit 1 Interviews Regarding Maintenance
ML10287089216 January 2010Email - 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 CommentCoatings
ML10287098312 January 2010from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:57 PM Subject: FW: Petrographic ReportCoatings
ML10287098612 January 2010Email - 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...
ML10287097912 January 2010Email - from: Thomas, George to: Naus, Dan J. CC: Lake, Louis Dated Tuesday, January 12, 2010 3:59 PM Subject: FW: Petrographic ReportCoatings
ML10287103511 January 2010Email - 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
ML10287103411 January 2010Email - 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 ReviewCoatings
ML10287099011 January 2010Email - 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: FCoatings
ML1028710406 January 2010Email - 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:
ML1028710461 January 20105.5 Exhibit 3a Petrographic Erlin Hime May 19
ML10287104931 December 2009Email - 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
ML10291060123 December 20095.8 Exhibit 5a PetrographicCoatings
ML10291063218 December 2009from: 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 Report16 December 200910 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
ML10291070511 December 20095.2 Exhibit 2 Mactec PetrographicCoatings
ML1029201388 December 20095.1 Exhibit 6A Petrographic MactecCoatings
ML1029201448 December 20095.8 Exhibit 5b PetrographicCoatings
ML10291072727 October 2009Summary of Results from Comparison.Pdf
ML10292050013 October 2009Condition Report Summary -NCRs Initiated Since Oct 12, 2009Cyber Security
ML10075042612 October 2009Summary ReportCyber Security
ML1028804905 October 2009Condition Report Summary - Ncrs Initiated Since Sep 28, 2009
ML1029201094 February 20095.6 Exhibit 8 Cap Grease Leakage
ML1029201074 February 20095.6 Exhibit 5 Surveillance Conclusion
3F0508-14, NRC Commitment Change Report - May 200828 May 2008NRC 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.13 December 2007Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.Power Uprate
Measurement Uncertainty Recapture
ML07311038121 May 2007Progress Energy Florida, Inc. Proposed Florida Nuclear Site Transmission Planning Study, Final Report, Attachments Dand F IncludedMeasurement Uncertainty Recapture
Affidavit
3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report12 December 200510 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 43 December 2005Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4Fuel cladding
ML0613806751 December 2005Report of Independent Auditors
ML06138067830 September 2005Financial Highlights
ML05244019010 August 2005Attachment 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
ML05053016817 February 2005Background 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.Nondestructive Examination
Fuel cladding
Operability Assessment
ML03189093610 July 2003Relaxation 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, CrysEnforcement Discretion
3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service19 November 2002Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service
ML03007017225 October 2002Summary Report - Ncrs Initiated Since 10/18/2002
3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 324 September 2002Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3Shutdown Margin
ML03007017423 September 2002Summary Report - Ncrs Initiated Since 09/16/2002