SR-2D3.3.7.1
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creation date: 2025-12-05T10:33:03-05:00
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SR-3.3.7.1
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05000269/FIN-2010005-05
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RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)
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NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
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ONS-2014-020, License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR No. 2013-05
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WO 14-0024, Changes to Technical Specification Bases - Revisions 57 Through 60
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GO2-13-138, License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
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PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
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NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
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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 3 of 9
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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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ET 18-0018, Supplement to 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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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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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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ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8
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GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)
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WO 18-0044, Clean Revised Technical Specification Pages 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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1CAN121801, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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RS-05-008, Additional Information Supporting Main Steam Line Flow - High Instrumentation Amendment Request
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NL-19-0331, License Amendment Request: Revise Measurement Units Associated with Reactor Trip System Nuclear Instrument Comparison Surveillance and Trip Setpoint for Control Room Air Intake Radiation Monitors
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ND-19-0168, Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification Revision (LAR-19-001)
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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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ULNRC-04856, Technical Specification Bases, Revision 4
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IR 05000413/1999001
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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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IR 05000361/1997011
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3F0996-14, TS Change Request 206 to License DPR-72,revising Engineered Safeguards Actuation Sys Automatic Actuation Logic. Certificate of Svc Encl
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L-22-286, Supplement to 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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IR 05000269/2010005
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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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ONS-2014-020, Oconee, Units 1, 2 and 3 - License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement,
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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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LER-1995-018, :on 950922,inadequate ITS Note Allows Delayed Entry Into ITS Lco,Resulting in Violation of Its.Caused by Personnel Error.Its Not Clarified & Pertinent Procedures & Other ITS Notes Reviewed
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label: 05000302/LER-1995-018, :on 950922,inadequate ITS Note Allows Delayed Entry Into ITS Lco,Resulting in Violation of Its.Caused by Personnel Error.Its Not Clarified & Pertinent Procedures & Other ITS Notes Reviewed
page: https://kanterella.com/05000302/LER-2D1995-2D018-2C_-3Aon_950922-2Cinadequate_ITS_Note_Allows_Delayed_Entry_Into_ITS_Lco-2CResulting_in_Violation_of_Its.Caused_by_Personnel_Error.Its_Not_Clarified_-26…
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Improved Tech Specs.Caused by Personnel error.In-place Testing Performed & CREVS Trains Declared Operable
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label: 05000302/LER-1996-016, :on 960430,review Revealed Control Room Emergency Ventilation Sys (CREVS) Not Consistent W/Improved Tech Specs.Caused by Personnel error.In-place Testing Performed & CREVS Trains Declared Operable
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LER-1996-008, :on 960304,discovered That Ambiguous Note Caused Misinterpretation of Improved TS (ITS) SR 3.4.12.1 & Failure to Perform Required Surveillance Prior to Mode Ascension.Its Bases for SR Will Be Revised
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label: 05000302/LER-1996-008, :on 960304,discovered That Ambiguous Note Caused Misinterpretation of Improved TS (ITS) SR 3.4.12.1 & Failure to Perform Required Surveillance Prior to Mode Ascension.Its Bases for SR Will Be Revised
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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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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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RAIO-0419-65262, LLC - Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
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RAIO-0519-65603, LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
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CNL-15-188, Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Correction to ITS 3.3.7, Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation
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ML14183A367
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AEP-NRC-2009-45, License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System
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RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
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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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