SR-2D3.3.6.1
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RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)
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PLA-6990, Proposed Amendment No. 314, Change to Allow Only One Manual Trip System to Be Operable for the RHR Shutdown Cooling System in Modes 4 and 5 for Units 1 & 2, Technical Specification 3.3.6.1
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NL-13-007, Supplement to Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications
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00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low
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GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
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NL-12-002, Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications
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ULNRC-05654, Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040)
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NG-11-0299, Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
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RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
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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-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9
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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-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
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10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation
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ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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RS-04-062, Technical Specifications Changes Related to Main Steam Line Flow-High Isolation Instrumentation
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CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
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ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
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GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033
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RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function
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JAFP-02-0124, Revision K to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications
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CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W
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B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
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CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
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3F0595-01, Application for Amend to License DPR-72,revising TSs to Allow Continuous Operation for Up to 24 Month Period
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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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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 4 of 8
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ML23067A157
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05000458/LER-2021-005, Potential Loss of Safety Function Due to Inoperable Reactor Core Isolation Cooling Steam Flow Transmitter
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RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel
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DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
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RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term
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ML20202H829
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NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
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ML20129K388
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RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
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CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
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A08949, Responds to Comments Identified in Insp Rept 50-423/90-80 Re EOP at Millstone Unit 3
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JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
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ML22192A007
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ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
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Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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ML102660554
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05000296/LER-1999-003-01, :on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened
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GO2-97-071, Forwards Response to RAI Related to Response Time Testing. W/Related Info
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RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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ML12338A223
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RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
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ML12200A102
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RS-12-223, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation
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ML18208A191
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
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ML101110355
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TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
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RS-05-039, Response to Request for Additional Information for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
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ML020720299
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ML100350993
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ML17095A117
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IR 05000528/2013002
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ML19052A094
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ML042380250
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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ML020810179
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ML021230239
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ML15257A198
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ML11167A226
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ML100470005
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RS-10-018, Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
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ML050960314
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ML20055D672
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ML20100N107
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L-22-053, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
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ML19070A252
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ML043090047
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ML21053A117
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ML20280A827
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ML21316A236
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ML15110A008
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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ML25112A334
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ML25213A183
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TSTF-22-01, Technical Specifications Task Force - Transmittal of TSTF-589, Revision 0, Eliminate Automatic Diesel Generator Start During Shutdown
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ML101170148
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ML082900780
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ML16125A485
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NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5
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