Pages that link to "L-21-223, Request for Relaxation of Confirmatorv Action Commitment (EA-04-224)"
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The following pages link to L-21-223, Request for Relaxation of Confirmatorv Action Commitment (EA-04-224):
Displayed 50 items.
- L-08-168, Report of Changes to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3) (← links)
- L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 (← links)
- L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0 (← links)
- L-08-175, Response to Request for Additional Information and Supplemental Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate (← links)
- L-08-136, Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report (← links)
- L-08-105, Reactor Head Inspection Report (← links)
- L-08-104, Steam Generator Tube Circumferential Cracking Report for the Fifteenth Refueling Outage (← links)
- L-08-080, Response to Confirmatory Action Letter No. NRR-07-017 (← links)
- L-08-094, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application (← links)
- L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (← links)
- L-08-042, Semiannual Fitness-For-Duty Report, July - December 2007 (← links)
- L-08-065, Response to Request for Additional Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate (← links)
- L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation (← links)
- L-08-034, Summary of Design and Analyses of the Weld Overlays for Pressurizer and Hot Leg Nozzle Large Bore Dissimilar Metal Welds for Alloy 600 Mitigation (← links)
- L-08-049, Summary of Weld Overlay Ultrasonic Examinations (← links)
- L-08-028, Core Operating Limits Reports for Cycle 16, Revision 0 (← links)
- L-08-013, Supplemental Information Regarding Response to Generic Letter 2007-01 (← links)
- L-07-516, Supplemental Information: Condensate Storage Tank (CST) Volume Requirements Relevant to License Amendment Application for Measurement Uncertainty Recapture (Mur) Power Uprate (← links)
- L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan (← links)
- L-18-246, EA-16-022 Davis-Besse Nuclear Power Station, Notification of Completion of Actions for Confirmatory Order (← links)
- L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition (← links)
- L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition (← links)
- L-18-235, Request for Deferral of Actions Related to Beyond-Design-Basis External Events Flooding Actions (← links)
- L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition (← links)
- L-18-159, Station. Unit 1 Cycle 20 and Refueling Outage 20 Inservice Inspection Summary Report (← links)
- L-17-352, No Active Safety Function Anchor Darling Double Disc Gate Valves (← links)
- L-17-233, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident (← links)
- L-17-176, Focused Evaluation Regarding Near-Term Task Force Recommendation 2.1 for Flooding (← links)
- L-16-337, Mitigating Strategies Assessment (MSA) for Flooding (← links)
- L-16-323, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident (← links)
- L-16-123, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (← links)
- L-16-213, Submittal of Post Examination Materials in Support of Recently Completed Initial License Operator Examinations (← links)
- L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation (← links)
- L-16-080, Request for Schedule Relief/Relaxation from NRC Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) (← links)
- L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program. (← links)
- L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- L-15-197, Response to Request for Additional Information Regarding a Request to Amend Technical Specification 5.5.15. Containment Leakage Rate Testing Program (← links)
- L-15-109, ISFSI - Summary Report of Changes, Tests and Experiments for the Period of January 1, 2013 Through December 31, 2014 (← links)
- L-15-117, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements (← links)
- L-15-084, Request to Change Cyber Security Implementation Plan Milestone 8 Completion Date (← links)
- L-14-405, License Amendment Request for Proposed Revision of Technical Specification 3.6.6, Containment Spray and Air Cooling Systems (← links)
- L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program (← links)
- L-14-403, Notification of Significant Errors in or Changes to the Large-Break Loss-of-Coolant Accident Emergency Core Cooling Model in Accordance with 10 CFR 50.46(a)(3)(ii) (← links)
- L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 (← links)
- L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models (← links)
- L-13-287, Program for Management of Irradiated Fuel (← links)
- L-14-107, Core Operating Limits Report, Cycle 19 (← links)
- L-14-088, Submittal of Decommissioning Funding Status Report (← links)
- L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- L-13-404, Supplemental Information Related to Steam Generator Inventory Change (← links)