SR-2D3.4.13.1
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ENS 52218
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CP-201301426, Response to Finding Documented in NRC Inspection Report 05000445-13-004 & 05000446-13-004
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NL-15-1055, License Amendment Request to Revise Technical Specification 3.4.14, RCS Pressure Isolation Valve Leakage to Eliminate the RHR Autoclosure Interlock Function from the Technical Specifications
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NL-14-1870, 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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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-2014-105, License Amendment Request for Adoption of Technical Specification Task Force (TSTF) - 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation; License Amendment Request No. 2011-03
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NL-11-1960, License Amendment Request to Adopt TSTF-513-A Revision 3, Response to Request for Additional Information Regarding Requiring Performance of Reactor Coolant System Mass Balance
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AEP-NRC-2011-28, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Action for RCS Leakage Instrumentation
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L-11-139, Request for an Amendment to Revise Both the Plants Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Using the Consolidated Line Item Improvement Process
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NL-11-0675, License Amendment Request to Adopt TSTF-513-A, Rev. 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
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L-PI-11-006, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI
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TSTF-09-14, Response to May 6, 2009 Request for Additional Information Regarding TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
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ULNRC-05373, Union Electric Co. Actions for Addressing Concerns Regarding Pressurizer Alloy 82/182 Butt Welds
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CNRO-2007-00003, Arkansas, Units 1 & 2 - Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
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L-2007-003, Reply to Request for Additional Information, Steam Generator Tube Integrity Amendment Request
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DCL-06-130, Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449)
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ULNRC-05307, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
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NL-06-0990, Southern Nuclear Operating Company Response to NRC Questions Regarding the Vogtle Electric Generating Plant Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
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DCL-03-008, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
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ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
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L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13
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CP-202000263, Reactor Vessel Head, Bottom Mounted Instrumentation, and Hot Leg Ultrasonic Testing Examinations Relief Request
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CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests
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AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
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L-20-144, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
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CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations
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CP-202000365, Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump
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CP-202000585, (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump
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ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)
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AEP-NRC-2022-05, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
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CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)
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TXX-2002, Exigent License Amendment Request (LAR) 20-003 Revision to Technical Specification (TS) 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Program
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CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
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CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-
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RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
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CP-201700886, Relief Request 1/2B3-2 for the Third Ten Year Inservice Inspection Interval
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L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
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1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
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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-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes
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L-PI-06-097, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
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IR 05000369/2005002
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TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
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ET 14-0032, Exigent License Amendment Request for Technical Specification 3.4.15, RCS Leakage Detection Instrumentation Completion Time Extension
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NUREG-1434, Forwards Changes Collected by NRC Since Publication of Rev 0 to Sts.Changes Considered Minor & Included Under One Traveler
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ET 05-0007, Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology
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RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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RAIO-0118-58473, LLC - Response to NRC Request for Additional Information No. 306 (Erai No. 9234) on the NuScale Design Certification Application
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ET 15-0008, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
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05000482/LER-2014-004, Regarding Condition Prohibited by Technical Specifications Due to an Instrument Tunnel Sump Level Indication Transmitter Incompatible with the Containment Environment
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RS-15-003, Relief Request I3R-26 Associated with the Third 10-Year Inservice Inspection Program Interval
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RS-14-080, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)- 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
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LER-2013-004, Regarding Technical Specification (TS) Prohibited Condition Due to Leak in the Reactor Coolant Pressure Boundary Caused by Defects in a Weld on Seal Table In-Core Detector Drive E-11
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05000247/LER-2012-003, Regarding Technical Specification (TS) Prohibited Condition Caused by Through Wall Defects in Reactor Coolant Pressure Boundary Branch Lines
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1CAN041102, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)–513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
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L-2004-178, Proposed Change to Emergency Plan Table 3-1: Classification of Emergencies
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RC-11-0052, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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TSTF-10-20, Response to NRC Request for Additional Information Regarding TSTF-432, Revision 0, Change in Technical Specifications End States (WCAP-16294)
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DCL-10-036, Response to NRC RAI Regarding License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for Rcs
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05000390/LER-2008-005, Inoperability of Radiation Monitor Due to Non-Conservative Setpoint
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TSTF-08-21, Transmittal of TSTF-513, Revision 0, Revise Operability Requirements and Actions for RCS Leakage Instrumentation
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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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ULNRC-05321, Withdrawal of Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
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ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
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ULNRC-05314, Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
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TXX-0518, License Amendment Request (LAR) 04-010, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
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2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. Steam Generator (SG) Tube Surveillance Program. & 5.6.10
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DCL-04-089, Response to June 14 and July 6, 2004, NRC Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Tube Surveillance Program, & 5.6.10
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RS-03-116, Request for Technical Specifications Change Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
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3F0502-06, Technical Specifications Bases Control Program
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RNP-RA/02-0041, Submittal of Information Requested by NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
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NL-13-078, Proposed License Amendment Regarding Technical Change Traveler TSTF-432-A Revision 1
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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NL-16-0686, Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294)
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TSTF-18-04, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
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PNP 2025-002, License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis
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ULNRC-06651, License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02
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RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
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NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
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NL-16-109, Indian Point 2 Improved Technical Specifications Bases
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ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
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RNP-RA/02-0072, Submittal of 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
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1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations
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L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
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CNL-25-027, Response to Request for Additional Information Regarding Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the Sequoyah Nuclear Plant, Unit
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NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
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IR 05000361/1997017
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ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology
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