ONS-2017-019, Technical Specification Bases Change 2015-09
CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations
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)
RS-17-081, License Amendment Request to Revise Control Room Ventilation Temperature Control System Technical Specification
NEI 06-02, License Amendment Request (LAR) Guidelines
RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles
NL-15-138, Request for Relief Request IP2-ISI-RR-01 Examination of Upper Pressurizer Welds
3F0515-05, Technical Specifications Bases Control Program
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
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
SBK-L-14202, Response to Request for Additional Information Regarding License Amendment 14-03 Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations
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
PNP 2013-072, Report of Changes, Tests and Experiments and Summary of Commitment Changes
AEP-NRC-2013-25, Annual Radioactive Effluent Release Report
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
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
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
NL-11-0675, License Amendment Request to Adopt TSTF-513-A, Rev. 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
SBK-L-11066, License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RA-14-032, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
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
TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
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
TSTF-09-03, Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
NL-08-117, Report on Inoperable Post Accident Monitoring Instrument LT-3300
TSTF-07-21, Response to NRC Request for Additional Information Regarding TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441), Dated May 3, 2007
NEI 99-01, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa
RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
1CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
CNRO-2007-00003, Arkansas, Units 1 & 2 - Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
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)
RS-06-088, Requested Information Concerning Pressurizer Heater Sleeve Flaw at Braidwood Station
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
ULNRC-05307, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
CPSES-200601056, Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
W3F1-2006-0005, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation
ULNRC-05242, Response to Request for Additional Information on Reactor Coolant System Leakage Detection Instrumentation
NL-04-1408, Request for Technical Specifications Change Steam Generator Program - Revision I
NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011
NRC-2011-0205, FRN: General Notice. Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 9/6/11
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
AEP-NRC-2019-32, Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 2
L-PI-05-081, License Amendment Request (LAR) to Clarify Technical Specification Requirements for Surveillance Requirements for Installed Spare Components and Miscellaneous Corrections
RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ET 14-0034, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
NL-04-2205, Changes to Technical Specification Bases
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-04-040, License Amendment Request Nos. 321 and 193, Modifying Technical Specification Requirements for Mode Change Limitations in Specifications 3.0.4 and 4.0.4 and the Associated Technical Specification Bases
WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-PI-03-089, License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
CPSES-200301485, License Amendment Request (LAR) 03-06 Revision to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
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.
3F0698-25, Advises That FPC May Be Requesting Enforcement Discretion or Other Regulatory Action in Near Future,Based on Review of Industry Operating Experience.Evaluation of Crystal River, Unit 3,operation W/Tube End Anomalies,Encl
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
NSD-NRC-98-5562, 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 Column of Oits, Provided in Table 1
NSD-NRC-98-5556, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses Is Provided in Table 1.FSER Open Item Number, Associated Oits Number & Status to Be Designated in W Status Column of Oits Is Included in Table
3F0198-15, Provides Response to RAI Dtd 971209,re LAR 218 Concerning Rev of Makeup Sys Letdown Line Failure Accident Analysis
NSD-NRC-97-5504, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses Also Encl
AEP-NRC-2022-05, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .
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)
3F0496-23, Provides Addl Info & Commitments on TS Change Request 203, Rev 2 Re Dispositioning Strategy for Dealing W/Iga in First Span of OTSGs
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0808-01, License Amendment Request 301, Revision 0, Application to Modify Improved Technical Specifications for Replacement Steam Generators
3F0109-04, License Amendment Request 301, Revision 1: Application to Modify Improved Technical Specifications for Replacement Steam Generators and Response to Request for Additional Information
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0108-14, License Amendment Request 298, Revision 0: Application to Modify Improved Technical Specifications for Replacement Steam Generators
NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information
3F0209-06, License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification
RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
CP-201700886, Relief Request 1/2B3-2 for the Third Ten Year Inservice Inspection Interval
ND-19-1416, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report
CP-201900393, License Amendment Request (LAR) 19-001, Application to Adopt TSTF-513-A, Revision 3, PWR Operability Requirements and Actions for RCS Leakage Instrumentation
BYRON 2004-0119, Report of Changes, Tests and Experiments
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
RA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)
ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
05000369/LER-2020-001, Condition Prohibited by Technical Specification 3.4.15, Reactor Coolant System (RCS) Leakage Detection Instrumentation
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
L-2019-192, License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements
NSD-NRC-97-5029, Forwards Response to NRC Re TS Comments
ET 14-0032, Exigent License Amendment Request for Technical Specification 3.4.15, RCS Leakage Detection Instrumentation Completion Time Extension
ET 05-0007, Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
CNL-18-078, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Second Ten Year Interval Request for Relief for 1-ISI-21
L-95-228, Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
05000390/LER-2016-001, Regarding Channel Mode Switch in Incorrect Position Renders Lower Containment Atmosphere Particulate Radiation Monitor Inoperable
AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual
05000364/LER-2015-002, Regarding Entry Into Condition Prohibited by Technical Specifications Due to All Containment Cooling Level Monitoring Systems Inoperable
TSTF-15-09, Technical Specifications Task Force - Transmits TSTF-553, Revision 0, Add Action for Two Inoperable (Control Room Emergency Air Temperature Control System) CREATCS Trains
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
05000482/LER-2014-004, Regarding Condition Prohibited by Technical Specifications Due to an Instrument Tunnel Sump Level Indication Transmitter Incompatible with the Containment Environment
RS-15-003, Relief Request I3R-26 Associated with the Third 10-Year Inservice Inspection Program Interval
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
05000269/LER-2011-004-01, Regarding Inability to Detect RCS Leak Rate Using the Particulate Radiation Monitor
AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009
05000482/LER-2012-001, For Wolf Creek Regarding Failure of 345 Kv Switchyard Breaker Due to Internal Fault Resulting in Reactor Trip and Coincident Loss of Offsite Power
05000269/LER-2011-004, Regarding the Inability to Consistently Detect the Required Reactor Coolant System Leak Rate Using the Particulate Radiation Monitor, in All Applicable Modes of Operation, Results in a Condition by the
1CAN041102, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)–513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation
L-2004-178, Proposed Change to Emergency Plan Table 3-1: Classification of Emergencies
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
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
TSTF-10-20, Response to NRC Request for Additional Information Regarding TSTF-432, Revision 0, Change in Technical Specifications End States (WCAP-16294)
DCL-10-085, Commitment Regarding License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation
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
05000390/LER-2008-005, Inoperability of Radiation Monitor Due to Non-Conservative Setpoint
TSTF-08-21, Transmittal of TSTF-513, Revision 0, Revise Operability Requirements and Actions for RCS Leakage Instrumentation
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
ULNRC-05321, Withdrawal of Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
ULNRC-05314, Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
TXX-0518, License Amendment Request (LAR) 04-010, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
DCL-04-141, Response to 09/08/2004 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
RS-04-056, Request for Additional Information Regarding a Proposed License Amendment to Revise Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
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
RS-03-116, Request for Technical Specifications Change Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
ET 05-0022, Response to Request for Additional Information, Reactor Coolant System Leakage Detection Instrumentation
05000529/LER-2000-006-01, Safety Injection Tank Outlet Check Valve Back-Leakage Causes Degraded Safety Injection Flow
TSTF-04-13, TSTF-449, Revision 2, Steam Generator Tube Integrity
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
NL-24-0253, License Amendment Request: Revised Technical Specifications to Adopt TSTF-554, Revised Reactor Coolant Leakage Requirements
CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
BW060119, CFR 50.59 Biennial Report for June 19, 2004 Through June 18, 2006
DCL-15-087, Revision to TS 3.4.15 for License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294)
RA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)
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
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
AEP-NRC-2021-27, Annual Radioactive Effluent Release Report
L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation
NL-25-0152, Propoosed Inservice Alternative FNP-ISI-ALT-05-13 for Reactor Vessel Bottom Head Inspection
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
CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology
TSTF-05-05, Letter Transmitting TSTF-449, Revision 4, Steam Generator Tube Integrity
NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02
PNP 2025-047, Response to Request for Additional Information Regarding License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
TSTF-24-11, TSTF Response to NRC Request for Additional Information on TSTF-600, Revision 0, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency
L-PI-25-026, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
TSTF-24-04, Transmittal of TSTF-600, Revision 0, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency
DCL-24-118, License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology