SR-2D3.6.1.1
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creation date: 2025-12-07T05:28:57-05:00
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SR-3.6.1.1
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05000316/LER-2007-001-01, Regarding As-found Local Leak Rate Tests Not Performed
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05000316/LER-2006-005, Re Failure to Comply with Technical Specification Surveillance Requirement 3.6.1.1
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05000318/LER-2001-002
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IR 05000315/2006004
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ONS-2017-019, Technical Specification Bases Change 2015-09
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NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program
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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
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MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval
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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)
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RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area
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ML13339A665
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PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
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L-11-376, Reply to Request for Supplemental Information for the Review of the License Renewal Application
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NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
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L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 15, Accident Analysis
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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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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
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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
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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
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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
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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
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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
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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
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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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RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
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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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U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report
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RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
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TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
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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
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L-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment
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NRC 2007-0034, License Amendment Request 249, Technical Specification 3.6.3, Containment Isolation Valves
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DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)
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L-06-149, Improved Technical Specification (ITS) Conversion License Amendment Request
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PLA-6020, Proposed Amendment No. 287 and Proposed Amendment No. 255: Revision to Technical Specifications 5.5.6 & 5.5.12
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NL-06-0266, Request for Technical Specification Amendment Re Containment Tendon Surveillance Program
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RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
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L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency
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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)
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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
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NRC 2002-0019, License Amendment Request 224 Control Room Habitability
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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)
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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
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3F0203-05, License Amendment Request 274, Revision 0, Containment Isolation Valves
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U-603543, Part 2 of 2, Clinton Power Station, Annual Radioactive Effluent Release Report, CPS-Offsite Dose Calculation Manual
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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
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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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05000482/LER-2021-001-01, Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications
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05000482/LER-2021-001, Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications
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IR 05000315/2006010
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L-2003-220, Proposed License Amendments Regarding Alternate Source Term and Conforming Amendments
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CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
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RAIO-0319-64996, LLC Supplemental Response to NRC Request for Additional Information No. 506 (Erai No. 9614) on the NuScale Design Certification Application
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RAIO-1218-63828, LLC - Response to NRC Request for Additional Information No. 506 (Erai No. 9614) on the NuScale Design Certification Application
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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
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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
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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
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CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
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IR 05000461/2010004
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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
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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)
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TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
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CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program
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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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TSTF-05-07, Submittal and Request for Fee Waiver for Review of TSTF-343, Revision 1, Containment Structural Integrity
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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
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ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
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3F0502-06, Technical Specifications Bases Control Program
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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
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RS-08-036, License Amendment Request to Revise Containment Tendon Surveillance Program
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CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
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RS-08-118, Additional Information Supporting Request to Revise Containment Tendon Surveillance Program
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05000275/LER-2008-001, Potential Accumulator Drain Line Actuation Following a LOCA Due to Solenoid Valve Failure
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TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
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WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
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NL-16-109, Indian Point 2 Improved Technical Specifications Bases
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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
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CNL-16-147, Non-Voluntary License Amendment Request to Modify and Clarify Technical Specification 3.6.15, Shield Building, Condition B Note
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NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
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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
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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
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