ONS-2017-019, Technical Specification Bases Change 2015-09
PNP 2016-061, Proposed Alternatives-Relief Requests Numbers RR 5-4, Weld Reference System, and RR 5-5, Under-Vessel Leakage Examination, Pertaining to In-Service Inspection Related Activities for the Fifth 10-Year Interval
NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region
CP-201301426, Response to Finding Documented in NRC Inspection Report 05000445-13-004 & 05000446-13-004
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases
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
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
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
NL-12-2224, Proposed Alternative VEGP-ISI-ALT-08 in Accordance with 10 CFR 50.55a(a)(3)(ii) Response to Request for Additional Information
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
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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
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-10-12, Transmittal of TSTF-525, Revision 0, Post Accident Monitoring Instrumentation Requirements (WCAP-15981-NP-A)
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
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
ULNRC-05373, Union Electric Co. Actions for Addressing Concerns Regarding Pressurizer Alloy 82/182 Butt Welds
CNRO-2007-00003, Arkansas, Units 1 & 2 - Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
L-2007-003, Reply to Request for Additional Information, Steam Generator Tube Integrity Amendment Request
L-2006-229, Response to Request for Additional Information - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
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)
NL-06-089, Reply to Request for Additional Information Regarding Proposed License Amendment for Adoption of TSTF 449
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
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
L-HU-06-023, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions
SBK-L-06064, License Amendment Request 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using the Consolidated Line Item Improvement Process
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
2CAN121801, License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump
1CAN121801, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
NL-19-0307, Response to NRC Request for Additional Information on Relief Request FNP-ISI-RR-02
NL-19-0343, Relief Request FNP-ISI-RR-03: SNC Response to NRC Request for Additional Information
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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
NL-05-0856, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project
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
WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
RNP-RA/03-0139, Submittal of 90-day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
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
ULNRC-04856, Technical Specification Bases, Revision 4
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.
RNP-RA/03-0001, Response to Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
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
CP-202000263, Reactor Vessel Head, Bottom Mounted Instrumentation, and Hot Leg Ultrasonic Testing Examinations Relief Request
CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests
NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
L-20-144, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations
CP-202000365, Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump
CP-202000585, (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump
ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)
AEP-NRC-2022-05, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
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)
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
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)
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-
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
L-2006-212, Reply to Request for Additional Information Steam Generator Tube Integrity Amendment Request
RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
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
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
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
TSTF-17-04, Technical Specifications Task Force - Transmittal of TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
L-PI-06-097, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
ET 14-0032, Exigent License Amendment Request for Technical Specification 3.4.15, RCS Leakage Detection Instrumentation Completion Time Extension
NUREG-1434, Forwards Changes Collected by NRC Since Publication of Rev 0 to Sts.Changes Considered Minor & Included Under One Traveler
ET 05-0007, Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
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
RAIO-0118-58473, LLC - Response to NRC Request for Additional Information No. 306 (Erai No. 9234) on the NuScale Design Certification Application
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
05000286/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
05000247/LER-2012-003, Regarding Technical Specification (TS) Prohibited Condition Caused by Through Wall Defects in Reactor Coolant Pressure Boundary Branch Lines
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-10-036, 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
L-05-144, License Amendment Request Nos. 324 and 196 Re 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
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
3F0502-06, Technical Specifications Bases Control Program
RNP-RA/02-0041, Submittal of Information Requested by NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
TSTF-04-13, TSTF-449, Revision 2, Steam Generator Tube Integrity
NL-13-078, Proposed License Amendment Regarding Technical Change Traveler TSTF-432-A Revision 1
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
NL-16-0686, Response to Request for Additional Information Regarding Adoption of TSTF-432, Rev. 1, Change in Technical Specifications End States (WCAP-16294)
TSTF-18-04, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
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
ULNRC-06651, License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
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
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.
1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations
L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
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
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
ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
TSTF-05-05, Letter Transmitting TSTF-449, Revision 4, Steam Generator Tube Integrity
3F1208-06, License Amendment Request 300, Revision 0 Addition of TSTF 479, Revision 0 and TSTF 497, Revision 0 to the Inservice Testing (IST) Program
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
TSTF-25-03, TSTF Response to NRC Second Request for Additional Information on TSTF-600, Revision 1, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency