05000316/LER-2007-001-01, Regarding As-found Local Leak Rate Tests Not Performed
05000316/LER-2006-005, Re Failure to Comply with Technical Specification Surveillance Requirement 3.6.1.1
ONS-2017-019, Technical Specification Bases Change 2015-09
NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program
NL-16-2335, Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval
CNL-17-131, License Amendment Request to Modify Technical Specification (TS) 3.6.3, Containment Isolation Valves, Surveillance Requirement 3.6.3.5 (WBN-TS-17-01)
RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
L-11-376, Reply to Request for Supplemental Information for the Review of the License Renewal Application
NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 15, Accident Analysis
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 6 of 6
NL-17-107, LER 15-001-02 for Indian Point, Unit 2, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate fo
NL-16-108, LER 15-001-01 for Indian Point 2 Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate for Conta
NL-15-124, LER 15-001-00 for Indian Point 2, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size That Results in Exceeding the Allowed Leakage Rate for Cont
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
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
U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 5 - Containment System Structure
L-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment
NRC 2007-0034, License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves
DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)
L-06-149, Improved Technical Specification (ITS) Conversion License Amendment Request
PLA-6020, Proposed Amendment No. 287 and Proposed Amendment No. 255: Revision to Technical Specifications 5.5.6 & 5.5.12
NL-06-0266, Request for Technical Specification Amendment Re Containment Tendon Surveillance Program
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency
CNL-19-077, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10)
ULNRC-04923, License Application for Revision to Technical Specification 5.5.6, Containment Tendon Surveillance Program, and Technical Specification 5.5.16, Containment Leakage Rate Testing Program
NRC 2002-0108, Technical Specification Bases Revisions
BSEP 02-0163, Revision of Request for License Amendment - Frequency of Performance-Based Leakage Rate Testing
NL-02-130, Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)
RNP-RA/02-0067, Request for Technical Specifications Change, Full Implementation of Alternative Radiological Source Term
ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
NRC 2002-0019, License Amendment Request 224 Control Room Habitability
CNL-20-087, Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017)
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
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
3F0297-09, TS Change Request 212 to License DPR-72,adopting 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water- Cooled Reactors, Option B
U-602596, Provides Addl Info for Amend to Incorporate Proposed Change to CPS Ts, ,be Reviewed on Schedule Sufficient to Support Sixth Refueling Outage Currently Scheduled to Begin 961013
3F0295-06, Submits Plans for Performing Integrated Leak Rate Testing. Current Isi/Ist Interval for Unit 3 Started in Mar 1987 & Ends in Mar 1997
NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)
3F0203-05, License Amendment Request 274, Revision 0, Containment Isolation Valves
U-603543, Part 2 of 2, Clinton Power Station, Annual Radioactive Effluent Release Report, CPS-Offsite Dose Calculation Manual
WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies
NL-16-1128, License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
NL-15-0217, Response to Request for Additional Information Regarding Multiple Technical Specifications Changes
3F0597-21, TS Change Request 212,Rev 1 Replacing Prescriptive Requirements of 10CFR50,App J,Option a w/performance-based Approach to Leakage Testing Contained in 10CFR50,App J, Option B
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
05000482/LER-2021-001-01, Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications
05000482/LER-2021-001, Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications
L-2003-220, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RAIO-0319-64996, LLC Supplemental Response to NRC Request for Additional Information No. 506 (Erai No. 9614) on the NuScale Design Certification Application
RAIO-1218-63828, LLC - Response to NRC Request for Additional Information No. 506 (Erai No. 9614) on the NuScale Design Certification Application
05000286/LER-2016-001, Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Flaw on the 31 Fan Cooler Unit Service Water Return Coil Line Affecting Containment Integrity
05000247/LER-2016-010, Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Through Wall Defect in a Service Water Supply Pipe Elbow to the 24 Fan Cooler Unit
NL-11-1004, License Amendment Request to Revise the Minimum Nitrogen Cover Pressure Specified in Technical Specification Surveillance Requirement 3.5.1.3 and Make an Administrative Change to Technical Specification Surveillance
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000286/LER-2008-005, Regarding Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Out of Position Valve Caused by Personnel Error
L-PI-08-052, License Amendment Request (LAR) to Revise the Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB) Accident Dose Consequences Analyses and Affected Technical Specifications (TS)
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
WO 03-0051, Revision to Technical Specification (TS) 5.5.6, Containment Tendon Surveillance Program, and TS 5.5.16, Containment Leakage Rate Testing Program
ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
3F0502-06, Technical Specifications Bases Control Program
RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency
RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RS-08-118, Additional Information Supporting Request to Revise Containment Tendon Surveillance Program
05000275/LER-2008-001, Potential Accumulator Drain Line Actuation Following a LOCA Due to Solenoid Valve Failure
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
NSD-NRC-97-5263, Forwards W Responses to Comments on AP600 TS Re Containment Sys.Response to Question 68 Re TS 3.6.9 for Ph Adjustment, Is Still in Progress W/Completion Scheduled for 970825
CNL-16-147, Non-Voluntary License Amendment Request to Modify and Clarify Technical Specification 3.6.15, Shield Building, Condition B Note
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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
RA-25-0075, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies