Pages that link to "RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core."
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The following pages link to RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.:
Displayed 50 items.
- RA-16-007, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, Revision 88, 89 and 90 (← links)
- RA-15-0004, Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermalhydraulic Statistical Core Design Methodology (← links)
- RA-10-021, Exemptions Request from Physical Security Requirements (← links)
- RA-19-0175, Submittal of 2018 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 36 (← links)
- RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors (← links)
- RA-19-0145, Revision to Reactor Vessel Surveillance Capsule Removal Schedule (← links)
- RA-18-0245, License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 (← links)
- RNP-RA/06-0095, Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring (← links)
- RA-19-0106, Relief Requested in Accordance with 10 CFR 50.55a(z)(1) for Volumetric or Surface Examination of Code Case N-729-4 Examinations of the Reactor Pressure Vessel Upper Head (← links)
- RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description (← links)
- RA-19-0084, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report (← links)
- RA-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 (← links)
- RA-19-0138, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections (← links)
- RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3 (← links)
- RA-19-0404, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal (← links)
- RA-19-0384, LER 20190-001-00 for H.B. Robinson Steam Electric Plant, Unit 2, Turbine Trip/Reactor Trip Due to Main Generator Lockout (← links)
- RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 (← links)
- RNP-RA/05-0107, Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass (← links)
- RA-05-0104, Transmittal of Core Operating Limits Report (← links)
- RA-05-0089, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks (← links)
- RA-05-0091, Voluntary Response to Regulatory Issue Summary 2005-19, Preparation and Scheduling of Operator Licensing Examinations. (← links)
- RA-05-0093, Independent Spent Fuel Storage Installation, Nuhoms - 24PTH System - Thermal Performance Measurements (← links)
- RA-05-0088, Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (← links)
- ML052200367 (← links)
- RA-19-0427, Emergency Plan PLP-007, Rev. 92 (← links)
- RA-19-0421, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145) (← links)
- ML051110221 (← links)
- RNP-RA/05-0006, Request for Technical Specifications Change to Core Operating Limits Report (COLR) References (← links)
- RNP-RA/05-0005, Request for Technical Specifications Change to Section 3.8.4, DC Sources - Operating (← links)
- RNP-RA/05-0001, License Amendment Request Regarding Implementation of the Alternative Source Term (← links)
- RA-19-0460, Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (← links)
- RA-20-0007, Request to Correct Administrative Renewed Facility Operating License Error (← links)
- RA-19-0428, Relief Request RA-19-0428 for One-Time Pressure Relief Valve Test Frequency Extension (← links)
- RA-20-0050, Emergency Action Levels CSD-EP-RNP-0101-02, Revision 0 (← links)
- RA-19-0468, Emergency Plan PLP-007, Revision 93 (← links)
- ML043280503 (← links)
- RNP-RA/04-0133, Transmittal of Technical Specifications Bases Revisions (← links)
- RNP-RA/04-0098, Request for Technical Specifications Change to Reactor Coolant System Pressure and Temperature Limits (← links)
- RA-04-0049, Independent Spent Fuel Storage Installation, Annual Report of Individual Exposure Monitoring for 2003 (← links)
- ML040780507 (← links)
- ML040780505 (← links)
- ML040780504 (← links)
- ML040780502 (← links)
- ML040780500 (← links)
- ML040780499 (← links)
- ML040780496 (← links)
- ML040780494 (← links)
- ML040780491 (← links)
- ML040570720 (← links)
- ML040570718 (← links)