SR-2D3.6.4.1
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creation date: 2025-12-10T21:33:13-05:00
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SR-3.6.4.1
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IR 05000387/2011004
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NL-14-046, Response to Request for Additional Information Regarding Containment Integrity Analysis
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NL-13-003, Proposed Technical Specification Changes Regarding RWST Temperature and Containment Pressure in Containment Integrity Analysis
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PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
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NRC 2011-0021, License Amendment Request 262 Revision to Technical Specification Operating Limits to Include Measurement Uncertainty
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NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
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NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
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NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
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NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
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NL-11-1812, Edwin I. Hatch, Unit 1 - Technical Requirements Manual
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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PLA-5857, Proposed License Amendment. Numbers 271 for Unit 1 and 239 for Unit 2 for a Change to Technical Specification SR 3.6.4.1.4 and 3.6.4.1.5 Secondary Containment Drawdown Testing
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L-14-343, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Rate Test Frequency
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NL-03-1323, Request to Revise Technical Specifications, DC Sources and TSTF-360, Revision 1
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RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
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NRC 2002-0004, License Amendment Request 223 Re Containment Pressure
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NL-06-0756, E. I. Hatch Operating License Revision to Support Use of Potassium Iodide for an Interim Period, Supplemental Information
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NMP1L3026, License Amendment Request- Proposed Changes to the Technical Specifications to Address Secondary Containment Personnel Access Door Openings
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NL-18-1132, Revision to Technical Specification 3.6.4.1 -Secondary Containment
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1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
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LER-1989-013, :on 890412,discovered That Channel Checks for Containment Hydrogen Monitors Inadequate to Verify Standby Readiness of Monitors.Caused by Deficient Vendor Documentation.Hydrogen Monitor Repaired
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CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
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L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
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NRC 2007-0052, Technical Specification Bases Change Summary
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ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
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IR 05000237/2009301
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DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
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WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
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NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
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CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID
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BSEP-97-0443, Suppl to Application for Amends to Licenses DPR-71 & DPR-62, Converting Current TS to Improved Ts,As Contained in Rev 1 of NUREG-1433.Rev a to Improved TS & Revised Responses to 970808 & 970911 RAIs Also Encl
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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