Pages that link to "RA-22-0214, 10 CFR 50.54(Q) Review Form for Revisions to the Shearon Harris Nuclear Power Plant, Unit 1, Emergency Action Level (EAL) Technical Basis Document and the EAL Wallchart Document"
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The following pages link to RA-22-0214, 10 CFR 50.54(Q) Review Form for Revisions to the Shearon Harris Nuclear Power Plant, Unit 1, Emergency Action Level (EAL) Technical Basis Document and the EAL Wallchart Document:
Displayed 50 items.
- RA-20-0117, Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits (← links)
- RA-20-0148, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications (← links)
- RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System (← links)
- RA-20-0179, Supplemental Information for License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core. (← links)
- RA-20-0178, Supplement to License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices (← links)
- RA-20-0287, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protectiv (← links)
- RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple (← links)
- RA-20-0312, Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval (← links)
- RA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . (← links)
- RA-20-0381, CFR 50.54( Q) Screening Evaluation Form for Revisions (← links)
- RA-21-0023, 10 CFR 50 .54(q) Screening Evaluation Form and 10 CFR 50 .54(q) Effectiveness Evaluation Form for PLP-201, Revision 73 (← links)
- RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. (← links)
- RA-21-0067, Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval (← links)
- RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications (← links)
- RA-21-0073, Notification of Permit Application for Industrial Stormwater Activities (← links)
- RA-21-0061, Notification of NPDES Permit Renewal Application (← links)
- RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits (← links)
- RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan (← links)
- RA-21-0052, License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency (← links)
- RA-21-0131, Annual Environmental (Non-radiological) Operating Report (← links)
- RA-21-0130, 10 CFR 50.54(q) Evaluations (← links)
- RA-21-0139, Cycle 24 Core Operating Limits Report, Revisions 0 and 1 (← links)
- RA-21-0136, Supplemental Information Regarding License Amendment Request for Common Emergency Plan (← links)
- RA-21-0162, Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative (← links)
- RA-21-0112, License Amendment Request Regarding Administrative Change to Reflect Development of a Technical Requirements Manual (← links)
- RA-21-0164, Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model (← links)
- RA-21-0195, 14-Day Special Report for an Inoperable Post-Accident Radiation Monitor (← links)
- RA-21-0203, Response to Request for Additional Information Regarding License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications (← links)
- RA-21-0200, End of Cycle 23 (H1R23) Inservice Inspection Program Owner'S Activity Report (← links)
- RA-21-0191, License Amendment Request to Revise Technical Specifications Related to Reactor Protection System Instrumentation (← links)
- RA-21-0213, License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown (← links)
- RA-21-0279, Notification of New NPDES Permit Receipt (← links)
- RA-21-0276, Duke Energy Common Emergency Plan and Brunswick Steam Electric Plant and Catawba Nuclear Station Emergency Plan Annexes, Revision 1 Summary of Changes (← links)
- RA-20-0223, Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (← links)
- RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes (← links)
- RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility (← links)
- RA-22-0055, Evacuation Time Estimate Report (← links)
- RA-22-0079, Snubber Program Plan (← links)
- RA-22-0136, Annual Environmental (Nonradiological) Operating Report (← links)
- RA-22-0117, Relief Request for Inservice Testing Program Plan - Fourth Ten-Year Interval (← links)
- RA-22-0172, Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval (← links)
- RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes (← links)
- RA-22-0043, CFR 50.54(q) Evaluation (← links)
- RA-22-0037, Emergency Plan Annex, Revision 1 and Emergency Plan Annex, Revision 1, Emergency Action Level (EAL) Wallchart, Revision 2, and EAL Technical Basis Document (← links)
- RA-22-0197, Reactor and Senior Reactor Operator Initial Examinations 05000400/2022301 (← links)
- RA-22-0213, Notification of Modification to Permit Application for Industrial Stormwater Activities (← links)
- RA-22-0214 (redirect page) (← links)
- ML22193A318 (redirect page) (← links)
- RA-22-0314, Notification of Source Water Resiliency and Response Plan Submission (← links)
- RA-23-0011, End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report (← links)