Pages that link to "ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term"
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The following pages link to ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term:
Displayed 50 items.
- ET 13-0011, Response to RAI Regarding License Amendment Request for Deviation from Fire Protection Program Requirements for Volume Control Tank Outlet Valves (← links)
- ET 13-0009, Clarification of RAI Regarding License Amendment Request to Revise Technical Specification (TS) 3.8.1, AC Sources-Operating (← links)
- ET 13-0004, Withdrawal of License Amendment Request for Deviation from Fire Protection Requirements (← links)
- ET 13-0001, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Flooding, of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- ET 12-0033, License Amendment Request (LAR) for Deviation from Fire Protection Requirements (← links)
- ET 12-0024, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds (← links)
- ET 12-0031, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.3 (Flooding) of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- ET 12-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems. (← links)
- ET 12-0029, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) (← links)
- ET 12-0028, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (← links)
- ET 12-0022, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements - Volume Control Tank Outlet Valves (← links)
- ET 12-0023, 10 CFR 50.46 Thirty Day Report of ECCS Model Changes (← links)
- ET 12-0018, License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement (← links)
- ET 12-0020, Withdrawal of License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology (← links)
- ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds (← links)
- ET 12-0015, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- ET 12-0012, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- ET 12-0013, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (← links)
- ET 12-0006, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process (← links)
- ET 12-0002, License Amendment Request, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criteria (← links)
- ET 12-0001, Supplemental Information Related to Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report, for Large Break Loss-of-Coolant Accident Analysi (← links)
- ET 11-0010, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report for Large Break Loss-of-Coolant Accident Analysis Methodology (← links)
- ET 11-0008, (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection (← links)
- ET 11-0003, Correction to 10 CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1. (← links)
- ET 11-0002, Changes to License Condition 2.C(5) (← links)
- ET 11-0001, Additional Information Related to Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation (← links)
- ET 10-0038, Response to Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation. (← links)
- ET 10-0031, Response to Supplemental Information Request for License Amendment Request Deviation from Fire Protection Requirements - Reactor Coolant System Subcooling During Alternative Shutdown (← links)
- ET 10-0029, Changes to License Condition 2.C(5) Re Fire Protection Criteria as Described in Updated Safety Analysis Report (← links)
- ET 09-0018, Redacted Version of the Wolf Creek, License Amendment Request for Use of Fire-Resistive Electrical Cable (← links)
- ET 10-0025, Application to Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology (← links)
- ET 10-0028, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation (← links)
- ET 10-0026, License Amendment Request for Deviation from Fire Protection Requirements - Reactor Coolant System Subcooling During Alternative Shutdown (← links)
- ET 10-0021, Response to Request for Additional Information Regarding the Sixteenth Steam Generator Tube Inservice Inspection (← links)
- ET 10-0019, CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1. (← links)
- ET 10-0017, Resubmittal of Enclosure Submitted with License Amendment Request for Deviation from Fire Protection Program Requirements (← links)
- ET 10-0012, Results of the Sixteenth Steam Generator Tube Inservice Inspection (← links)
- ET 10-0013, License Amendment Request to the Approved Fire Protection Program to Remove High/Low Pressure Interface Designation from the Pressurizer Power Operated Relief Valves and Their Associated Block Valves (← links)
- ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 (← links)
- ET 10-0005, Response to Request for Additional Information Related to License Amendment Request for Deviation from Fire Protection Program Requirements (← links)
- ET 10-0015, Revision to Commitment Made in Licensee Event Report 2009-002-00 (← links)
- ET 10-0006, Supplement to Request for Extension of Response Date to NRC Request for Additional Information Regarding Responses to Generic Letter (GL) 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis... (← links)
- ET 10-0008, Ltr. Implementation of Beacon Power Distribution Monitoring System (← links)
- ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps (← links)
- ET 10-0003, Application to Revise Technical Specification 3.6.3, Containment Isolation Valves. (← links)
- ET 10-0002, Resubmittal of Request for Exemption from Specific 10 CFR Par 73 Requirements (← links)
- ET 09-0033, Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements (← links)
- ET 09-0030, Application to Revise Technical Specification 3.8.4, DC Sources - Operating, Surveillance Requirements (SR) 3.8.4.2 and SR 3.8.4.5 (← links)
- ET 09-0031, Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02 (← links)
- ET 09-0026, Notification of Deviation from EPRI Pressurized Water Reactor Secondary Water Chemistry Guidelines (← links)