Pages that link to "NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)"
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The following pages link to NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40):
Displayed 50 items.
- NRC 2010-0046, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors (← links)
- NRC 2008-0090, Confirmatory Order EA-06-178 - Section IV.6 2008 Nuclear Safety Culture Survey Results (← links)
- NRC 2008-0070, License Renewal Commitment Alloy 600 Program Submittal (← links)
- NRC 2007-0020, 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval (← links)
- NRC 2007-0015, Nuclear Management Company, LLC Plan to Address the Safety Culture Issues at Point Beach, Units 1 and 2 (← links)
- NRC 2018-0005, Refueling Outage U1R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations (← links)
- NRC 2017-0046, Spring 2017 (U2R35) Steam Generator Tube Inspection Report (← links)
- NRC 2017-0030, Refueling Outage U2R35 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations (← links)
- NRC 2017-0008, Response to Final Request for Additional Information on Steam Generator Tube Inspection Report (← links)
- NRC 2016-0044, Spring 2016 U1R36 180-Day Steam Generator Tube Inspection Report (← links)
- NRC 2016-0026, Refueling Outage U1 R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations (← links)
- NRC 2016-0004, Refueling Outage U2R34 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations (← links)
- NRC 2015-0068, Request for Additional Information for Relief Request 2-RR-11 - MF6615 (← links)
- NRC 2015-0071, Weapons Related Obligations for Material in Reactor and Transfer of Foreign Obligations for Material Processed with Foreign Obligated Equipment (← links)
- NRC 2015-0040, Steam Generator Nozzle to Safe-End Dissimilar Metal (DM) Weld Inspection (← links)
- NRC 2015-0035, Response to Request for Additional Information - RR-1 0- Examination of the SG Feedwater Nozzle Extension to Nozzle Weld Fifth Ten-Year Lsi Program Internal - MF5012 (← links)
- NRC 2015-0034, 10 CFR 50.55a Request, Withdrawal of Relief Request 2-RR-7 Re-Categorization of Steam Generator Nozzle to Safe-End Welds (← links)
- NRC 2014-0070, Core Operating Limits Report Cycle 36 (U1C36) (← links)
- NRC 2014-0049, Submittal of Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueling Outage U2R33 (← links)
- NRC 2014-0048, Submittal of Filing of Owner'S Lnservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R33 (← links)
- NRC 2014-0015, Response to Request for Additional Information Spring 2013 Unit 1 (U1R34) Steam Generator Tube Inspection Report (← links)
- NRC 2013-0097, Response to Request for Additional Information Fall 2012 Unit 2 (U2R32) Steam Generator Tube Inspection Report (← links)
- NRC 2013-0072, 10 CFR 50.55a Request, Relief Request RR-4L2 Lnservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Lnservice Inspection Program Interval, Response to Request for Additional Infomation (← links)
- NRC 2013-0006, Completion of Activities to Support Entry Into the Period of Extended Operation (← links)
- NRC 2013-0016, Filing of Owner'S Inservice Inspection Summary Report, IWE Class Mc and Iwl Class CC for Refueling Outage U2R32 (← links)
- NRC 2013-0015, Filing of Owner'S Lnservice Lnspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R32 (← links)
- NRC 2013-0012, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Lnservice Inspection Program Interval Response to Request for Additional Information (← links)
- NRC 2013-0009, Fall 2011 Refueling Outage (U1R33) Steam Generator Tube Inspection Report (← links)
- NRC 2012-0089, Supplement to 10 CFR 50.55a Request. Relief Request 1 -RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Lndication on the a Lnlet Nozzle Weld Fifth Ten-Year Lnservice Lnspection Program Interval (← links)
- NRC 2012-0088, 10 CFR 50.55a Request, Relief Request 1 -RR-4 Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Lnlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval (← links)
- NRC 2012-0076, Response to Request for Additional Information Fall 2011 Unit I (U1 R33) Steam Generator Tube Inspection Report (← links)
- NRC 2012-0015, Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report (← links)
- NRC 2012-0014, Filing of Owner'S Containment Inservice Inspection Summary Report for Refueling Outage U1R33 (← links)
- NRC 2011-0100, Transmittal of Core Operating Limits Report, Revision 13 (← links)
- NRC 2011-0083, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outrage U2R31 (← links)
- NRC 2011-0084, Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R31 (← links)
- NRC 2011-0035, Cycle 32 (U2C32) Core Operating Limits Report (← links)
- NRC 2010-0142, Completion of Activities to Support Entry Into the Period of Extended Operation (← links)
- NRC 2010-0096, Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R32 (← links)
- NRC 2010-0094, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R32 (← links)
- NRC 2010-0050, Refueling 32 Analytical Evaluation Report for the Reactor Vessel (← links)
- NRC 2010-0041, Cycle 33 (U1C33) Core Operating Limits Report (← links)
- NRC 2010-0026, Nine-Month Supplemental (Post-Outage) Response to NRC Generic Letter 2008-01 (← links)
- NRC 2010-0028, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R30 (← links)
- NRC 2009-0112, Cycle 31 (U2C31) Core Operating Limits Report (← links)
- NRC 2018-0044, Supplement to Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, ... (← links)
- NRC 2018-0039, Registration of Nuhoms -32PT Casks WNHOMS-32-045, WNHOMS-32-047, and WNHOMS-32-049 (← links)
- NRC 2018-0038, Response to Request for Additional Information Regarding License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear (← links)
- NRC 2018-0036, Registration of NUHOMS-32PT Casks, WNHOMS-32-046, WNHOMS-32-048, and WNHOMS-32-050 (← links)
- NRC 2018-0030, Construction Truss License Amendment Request 278 Draft Updated Final Safety Analysis Report (UFSAR) Revision (← links)