P.7-28f-29
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creation date: 2025-12-07T20:18:02-05:00
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ML16096A217
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ML16243A349
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CNS-16-031, Technical Specification Bases Changes
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RS-14-096, Units 1 and 2 - License Amendment Request to Administratively Clarify Technical Specifications (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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ML073480445
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ML17319B256
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.2-1 Through 7.2-5
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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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RS-14-096, Braidwood & Byron, Units 1 and 2 - License Amendment Request to Administratively Clarify Technical Specifications (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instr
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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 1 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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ML102700197
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NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
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NRC 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
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NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
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NL-09-0154, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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ML072120165
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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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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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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ML19339C045
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ML19254C826
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CPSES-200500155, License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas)
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NL-05-0233, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11. Reactor Coolant Pump Breaker Position
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NL-03-2451, Request for Surveillance Test Interval Extensions for Components of the Reactor Protection System
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ML19332A533
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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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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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WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
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ULNRC-04721, Technical Specification Bases Revision 3
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DCL-02-038, License Amendment Request 02-02, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
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U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With
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AECM-88-0064, Application for Amend to License NPF-29,revising Tech Specs Re Mode Changes,Inconsistent Application of Exceptions & Unnecessary Shutdowns When Surveillance Intervals Inadvertently Exceeded,Per Generic Ltr 87-09.Fee Paid
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Tech Specs
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05000483/LER-1990-012, :on 901003,Tech Spec 3.9.2 Violation Occurred Due to Performance of Core Alteration When Source Range Nuclear Instrument Inoperable Due to Personnel Error. W/
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03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced
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IR 05000272/1990007
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L-91-117, 1990 Annual Radiological Environ Operating Rept St Lucie Plant Units 1 & 2
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CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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RS-11-019, Units 1 & 2 - License Amendment Request to Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, & TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation, to Reflect Installation of Bypass
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RS-04-193, Comment (20) of Jeffrey A. Benjamin on the Implementation of the Reactor Oversight Process (ROP)
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DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
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NL-16-109, Indian Point 2 Improved Technical Specifications Bases
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