05000265/LER-2014-001, Regarding Control Rod Drive Hydraulic Control Unit Scram Inlet Isolation Valve Pressure Boundary Leak
05000498/LER-2004-006, Re Pressurizer Power-Operated Relief Valve Being Inoperable for a Time Period Longer than Allowed by Technical Specifications
CNS-17-033, Technical Specification Bases Changes
L-2017-091, License Amendment Request 252, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ONS-2017-052, Technical Specification Bases Change 2017-03
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
ONS-2016-082, Technical Specification Bases Change for TS Bases 3.4.16, Steam Generator Tube Integrity
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
GO2-16-086, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3
NL-16-1056, Proposed Alternative HNP-ISI-ALT-05-03 Version 1.0 Regarding Reactor Pressure Vessel Flange Seal Leak-off Piping Testing
ONS-2016-022, Response to NRC Request for Information Associated with License Amendment Request to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05, Supplement 2
1CAN021601, Cycle 26 Core Operating Limits Report, Revision 1
L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b
GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
2CAN121502, Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process
1CAN081504, Cycle 26 Core Operating Limits Report (COLR)
GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process
L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
3F0515-05, Technical Specifications Bases Control Program
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
NL-15-0421, J. M. Farley, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement P
NL-15-0422, License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement Process (CLIIP)
L-15-026, License Amendment Request to Steam Generator Technical Specifications
1CAN021501, Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report
1CAN101408, Cycle 25 Core Operating Limits Report
GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
GNRO-2014/00045, Response to Request for Additional Information Regarding Maximum Extended Load Line Limit Plus Amendment Request, Dated 5/19/2014
L-2014-160, Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C, Using the Consolidated Line Item Improvement Process
WO 14-0024, Changes to Technical Specification Bases - Revisions 57 Through 60
NL-14-0059, ISI Program Alternative HNP-ISI-ALT-18, Verson L, Response to NRC Request for Additional Information
RS-13-092, License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure
1CAN081301, Unit 1, ANO-1 Cycle 25 COLR, Revision 1
1CAN061303, Cycle 25 Core Operating Limits Report
RBG-47322, Submittal of Request for Amendment to the Technical Specifications
1CAN101202, Unit 1: Cycle 24 Core Operating Limits Report (Colr), Revision 5
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
1CAN081203, Cycle 24 Core Operating Limits Report (Colr), Revision 4
1CAN041201, Unit 1, ANO-1 Cycle 24 COLR, Revision 3
1CAN111103, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 1
1CAN101101, Submittal of Cycle 24 Core Operating Limits Report (COLR)
BSEP 11-0068, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-18-023, License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs)
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 15, Accident Analyses
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 2 of 6
NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-13-2521, Edwin I. Hatch, Units 1 and 2, ISI Program Alternative HNP-ISI-ALT-18, Version 1
NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the 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
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
RS-10-096, Supplemental Information Concerning Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation
NOC-AE-10002554, Technical Specification Bases Control Program (Section 6.8.3.m)
NLS2010029, Technical Specifications Bases Changes
1CAN041005, Submittal of Rev. 1 to Cycle 23 Core Operating Limits Report
1CAN041001, Cycle 23 Core Operating Limits Report
NG-10-0091, Responses to Requests for Additional Information Regarding the Center License Renewal Application - Batch 4
RS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage
GNRO-2009/00036, Report of 10CFR50.59 Evaluations and Commitment Changes - April 1, 2008 Through June 30, 2009
2CAN060903, License Amendment Request, Technical Specification Changes to Relocate Pressurizer Heater Requirements to Technical Requirements Manual
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
1CAN110801, Cycle 22 Core Operating Limits Report (COLR)
NLS2008001, License Application Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process and Related
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76
RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
1CAN050701, Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report
NOC-AE-07002104, Response to NRC Request for Additional Information on Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
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)
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
NOC-AE-06002040, Technical Specifications, Bases Control Program
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
W3F1-2006-0029, Revision to Amendment Request NPF-38-262 Steam Generator Tube Inservice Inspection Program
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
NOC-AE-06001969, Response to NRC RAI on STPNOC Proposed Risk-Informed Technical Specifications
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
NL-04-1408, Request for Technical Specifications Change Steam Generator Program - Revision I
JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases
05000324/LER-1981-021-03, /03L-0:on 810411,reactor Coolant Conductivity Was Discovered High.Probably Caused by Breakdown of Reactor Water Cleanup Sys Resins Which Accumulated in Vessel Prior to Startup.Resins Allowed to Decompose
1CAN121804, Core Operating Limits Report (COLR) Cycle 28 COLR, Revision 2
NRC-2015-0104, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
1CAN120503, Unit 1, Cycle 20 Core Operating Limits Report (COLR) Per Technical Specification 5.6.5
BSEP 05-0109, Submittal of Technical Specification Bases Revisions
W3F1-2005-0040, License Amendment Request NPF-38-262 Proposed Technical Specification Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process
W3F1-2005-0044, Response to Request for Additional Information Related to Review of Refuel 12 Steam Generator Tube Inservice Inspection Reports
BSEP 05-0082, Submittal of Technical Specification Bases Changes
1CAN060502, Arkansas, Unit 1 - License Amendment Request Response to NRC Request for Additional Information on ANO-1 Proposed Technical Specification Change to Steam Generator Tube Inservice Inspection Program
JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)
NL-05-0532, Third and Fourth 10-Year Interval Inservice Inspection Programs
NOC-AE-05001834, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
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
ND-18-0610, Supplement to Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004S1)
ND-18-0053, Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004)
ND-17-1559, Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034)
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NOC-AE-04001795, Units I and 2 - Proposed Change to Technical Specification Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves.
NRC-04-0005, Application for Technical Specification Change 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
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
NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate
ULNRC-04721, Technical Specification Bases Revision 3
1CAN070203, Submittal of Revision to Arkansas Nuclear One, Unit 1 Core Operating Limits Report
RBG-45946, Entergy Nuclear- South, River Bend Station, Unit-1, License Amendment LAR 2002-11 Modification of the Technical Specification Surveillance Requirements for the Safety/Relief Valves
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
05000395/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl
05000395/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl
CNL-20-042, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-20-05)
AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
05000395/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl
CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)
1CAN042101, Cycle 30 Core Operating Limits Report (COLR)
NLS2021015, (CNS) - Technical Specification Bases Changes
NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
NG-98-0531, Forwards Comments on NRC Draft SE for DAEC Conversion to Improved TS Based Upon NUREG-1433.Draft SE Contains Util Markups & Typed Inserts
B17102, Proposed Tech Specs Changing TSs 3.4.4, RCS - Pressurizer, 3.6.1.5, Containment Sys - Air Temp & 3.7.1.5, Plant Sys - Msli Valves
RBG-45097, Requests Approval of Proposed Alternative to Second Interval Inservice Testing Program,Allowing One Time Extension of Test Interval for 20% of Full Set Main Steam Line Safety Relief Valves
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
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
NRC-99-0032, Forwards Rev 4 to Fermi 2 Its,Per Submittal .Rev Provides Responses to NRC RAI Re ITS Sections 3.4 & 3.9 Contained in Ltr
NSD-NRC-97-5001, Forwards Responses to Listed Ref 1 Comments as Partial Completion of Open Item 4970
PNO-II-97-006, on 970129,Unit 1 Declared Notice of Unusual Event for Reactor Coolant Pressure Boundary Leakage,As Defined in TS 3.4.4.Resident Inspectors on Site Monitoring Licensee Actions.State of Ga Notified
ST-HL-AE-2837, Responds to NRC Re Violations Noted in Insp Rept 50-498/88-54.Corrective actions:off-normal Procedure Enhancement Program Instituted to Upgrade Overall Quality of Procedures.Program Scheduled to Be Completed by 881231
CNL-22-002, Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)
NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
HL-5583, Provides Evaluation of 3rd 10-year Interval ISI Program & Associated Requests for Plant,Units 1 & 2
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)
ELV-03417, Submits Addl Info Re 911118 Application for Amends to Licenses NPF-68 & NPF-81,changing TS 3.4.4 & 3.4.9.3 Re Relief Valves & Cold Overpressure Protection Sys, Respectively
ELV-02517, Application for Amends to License NPF-68 & NPF-81,changing TS 3/4.4.4, Relief Valves, to Make Wording Similar to That Proposed by Generic Ltr 90-06, Resolution of Generic Issue 70... & Generic Issue 94..
ST-HL-AE-3791, Requests Withdrawal of Proposed Tech Spec Changes Based on STPEGS PRA
CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32
BSEP-95-0383, Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages
PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062
JSP-613-92, Application for Amend to License NPF-62,changing TS 3/4.4.4, Chemistry to Add Requirement to Perform Evaluation Prior to Plant Restart of Impact on RCS of Chemistry Parameters Exceeding Limit During Plant Shutdown Conditions
1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
W3P85-0387, Forwards Draft Nuclear Plant Islands Structure Common Foundation Basemat Monitoring Program,Per 841207 Commitment. Meeting Scheduled for 850213 to Discuss Draft & Resolve Differences Prior to Plan Submittal
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
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
RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
NRC-23-0010, License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage
0CAN059603, Application for Amends to Licenses DPR-51 & NPF-6,revising ANO-1 TS 3.7.2 & ANO-2 TS 3.4.4 & 3.8.1.1 to Extend Allowed Outage Time for EDGs from 7 Days to Include Once Per Cycle Extension of Addl 7 Days Per Machine
NOC-AE-05001847, Technical Specification Bases Change
NL-15-177, Watts Bar, Unit 2, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Ma
ND-18-1504, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report
RA89-003, Forwards Review of Technical Content of 890417 Reactor & Senior Reactor Operator Exams Given at Facility,Including Comments & Recommended Actions for Each Question Under Review
05000389/LER-1986-007, Forwards Response to NRC 861001 Request for Addl Info Surrounding Event Reported in LER 86-007 Re Inoperable Pressurizer Safety Valves
1CAN101902, Cycle 29 Core Operating Limits Report (COLR)
1CAN102203, Cycle 31 Core Operating Limits Report
ST-HL-AE-2874, Forwards Revised Response to Violations Noted in Insp Repts 50-498/88-54 & 50-499/88-54.Response Addressed Addl Concerns in Insp Repts 50-498/88-61,50-499/88-61,50-498/88-72 & 50-499/88-72.Corrective Actions:Procedures Revised
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
B17144, Application for Amend to License NPF-49,assuring That PORVs Will Be Capable of Automatic Cycling as Well as Manual Cycling When in TS Action Statements That Allow Indefinite Continued Operation
B10913, Application for Amend to License DPR-65,revising Tech Specs Re Pressurizer Level Band
AECM-83-0481, Responds to 830727 Request for Info Re Intergranular Stress Corrosion Cracking.Rev 1 to Rept, Effects of Intergranular Stress Corrosion Cracking on Operation of Grand Gulf Nuclear Station,Unit 1, Encl
1CAN052401, Cycle 32 Core Operating Limits Report
GNRO-2007/00034, Report of 10 CFR50.59 Safety Evaluations and Commitment Changes - April 1, 2006 Through March 31, 2007
CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F
NL-13-2521, ISI Program Alternative HNP-ISI-ALT-18, Version 1
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NOC-AE-06001994, Response to NRC Requests for Additional Information on STPNOC Proposed Risk-Informed Technical Specifications
NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.
L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open
05000498/LER-2023-001, Pressurizer Power Operated Relief Valve Failed to Open
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
05000277/LER-2020-002, Degraded Condition Due to RPV Instrument Nozzle Leakage
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
05000354/LER-1988-014-02, :on 880511,RWCU Loop Isolated on High Flow Differential ESF Signal During Pressurization of Filter/ Demineralizer.Caused by Design & Procedure Deficiencies. RWCU Sys Operation Procedure Revised
05000443/LER-1998-007, :on 980619,inoperable PORV Channel Calibration Was Noted.Caused by Procedural Technical Inaccuracies.Porv Channel Calibration Surveillance Test Were Changed & Retested for Issues Identified on 980619
05000354/LER-1987-028, :on 870629 & 0701,RWCU Sys Isolation Occurred. Caused by Design Deficiencies.Procedure for Operation of Rwcs Reviewed by Chemistry Dept & Revised to Explicitly Define Valving Sequence
DCL-20-068, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System
05000369/LER-1997-009, :on 970906,reactor Trip Occurred on Both Units Due to Loss of non-vital Power to Plant components.Re-closed Breaker MKA-1B,restored Kxa to Svc,Replaced Breaker MKA-1B & Repaiared Cable Connection
2CAN011301, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
05000482/LER-1987-002, :on 870108,low Steamline Pressure Signal Occurred During Calibr Testing & ESF Actuation Initiated. Caused by Personnel Error.Improved Instrument Identification Tags & Procedural Enhancements Made
05000440/LER-1986-092, :on 861230,reactor Shutdown Conducted to Comply W/Tech Spec 3.4.4,due to High Reactor Coolant Conductivity. Caused by Failure of Three Main Condenser Tubes.Leakage & Damaged Tubes Plugged & Loose Lagging Removed
NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
05000373/LER-1988-006-06, :on 880330,continuous Conductivity Monitor for Reactor Water Samples Declared Inoperable.Caused by Vessel Draindown for Chemical Decontamination.Vessel Flooded Up After Decontamination Work & Svc Resumed
05000317/LER-1997-005, :on 970529,reactor Coolant Sys Leak Occurred. Caused by Failed Compression Fitting.Conducted Review of Compression Fitting Maint Performed on High Pressure Systems & Completed Insps of Compression Fittings
05000354/LER-1987-052, :on 871210,isolation of RWCU Sys Occurred While Pressurizing Filter/Demineralizer (F/D) B.Caused by F/D Design Deficiency.Procedures Changed & Design Change Scheduled for 1988 Outage
05000352/LER-1985-079, :on 851008,standby Liquid Control Sys Received Unexpected Actuation Signal & RWCU Sys Received Automatic Isolation Signal.Caused by Design Deficiency.Rwcu Sys Placed in Svc & Reset
05000321/LER-1997-001-01, :on 970129,pressure Boundary Leakage Results in Condition Prohibited by Tss.Cause of Event Cannot Be Determined Conclusively.Maint Personnel Repaired Line.W/
05000454/LER-1985-017, :on 850119,PORV Block Valves Not Deenergized During RCS Leak Test.Caused by Misinterpretation of Tech Spec Limiting Condition for Operation.Personnel Briefed
05000395/LER-1984-038, :on 840907,second Position Indication Channel for PORV Declared Inoperable.Caused by Procedural Inadequacies in Surveillance Test Procedures 135.001 & 506.010.Channel Calibr
05000325/LER-1978-090-03, /03L-0 on 781230:reactor Vessel Conductivity Exceeded 24-h Limit Due to Organic Compound in Condensate Storage Tank
05000395/LER-1983-100-01, /01T-0:on 830831,PORV PCV-445A Declared Inoperable Due to Possible Inadvertent Opening of Valve Upon Loss of Power to Protection Cabinet Iv.Caused by Design Error. PCV-445A Closed & Deenergized Until Corrected
05000370/LER-1983-011-03, /03L-0:on 830427,PORV Block Valve 2NC-31B Declared Inoperable Due to Steam Leaking Past Shaft to Containment Atmosphere.Caused by Failure of Packing Gland Eye Bolts.Valve Closed & Actuator Deenergized
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
05000387/LER-1983-006-03, /03L-0:on 830108,RCS Conductivity Exceeded 2.0 Micromhos/Cm While in Operational Condition 2.Caused by Inadvertent Isolation of Reactor Water Cleanup Sys Due to Faulty Relay Module in Control Circuitry.Module Replaced
05000324/LER-1982-113-03, /03L-0:on 821003,during Reactor Startup Coolant Analysis,Reactor Coolant Conductivity Exceeded Tech Specs. Caused by Breakdown of Reactor Water Cleanup Sys Resins. Resins Allowed to Decompose & Reactor Conductivity Reduced
05000325/LER-1978-086-03, /03L-0 on 781109:Reactor Vessel Chemistry Exceeded Tech Spec Limits for Conductivity & Concentration Due to Presence of Organic Compounds in Condensate Sys.Organic Filtration & High Concentration of Ion Resin Cleanup Begun
05000270/LER-1982-010-01, /01T-0:on 820722,while Investigating Erroneous Instrument Readings,Upper Surge Tank Water Level Found to Be Less than 5 Ft.Caused by Stuck Suction Relief Valve on Main Feedwater Pump 2B.Valve Reseated.Instrumentation Repaire
05000339/LER-1989-006, :on 890315,pressurizer Code Safety Valves out- of-tolerance
05000369/LER-1990-025, :on 900827,shutdown Because of Unidentified RCS Leakage Greater than TS Limits Occurred Due to Equipment Failure
05000373/LER-1993-015-06, :on 930914,unit 1 Scram Occurred & off-site Power Lossed Due to Bus Duct Water Intrusion.Onsite Review 93-048 Initiated
05000213/LER-1993-007, :on 930525,determined That Pressurizer PORVs Emergency Air Supply Sys Pressure Decay Exceeded TS Acceptance Criterion of 0.3 Psi/H.Caused by Malfunction of Air Dryer.Regulating Valve Replaced
B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06
B14375, Application for Amend to License NPF-49,revising TS 3.4.4 & 3.4.9.3 to Address Issues in GL 90-06,w/regard to Resolution of Generic Issues 70 & 94
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000369/LER-1990-025-01, :on 900827,Unit 1 Shut Down Because of Unidentified RCS Leakage Exceeding Tech Spec Limits.Caused by Equipment Failure.Procedure AP/1/A/5500/10 Implemented. Valve 1NC-33 Will Be Repacked at Next Outage
05000395/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Encl
05000395/LER-1983-057-03, /03L-0:on 830606,nitrogen Low Pressure Alarm on Low Pressure Accumulator for PORV Received in Control Room. Caused by Valve Position Indicator Lights Not Showing Full Actual Position.Limit Switches Adjusted
05000325/LER-1981-057-03, /03L-0:on 810826,reactor Water Chloride Concentration Exceeded Limit.Caused by Personnel Incorrectly Arranging Reactor Bldg Component Cooling Water Sys Piping to Seal Cooler of Reactor Water Cleanup Pump 1B
05000324/LER-1981-068-03, /03L-0:on 810715,reactor Coolant Conductivity Found Greater than Allowable Limits.Caused by Flange Leak in RWCU Sys Effluent Strainer Blowdown Line Which Necessitated Isolating Sys.Leak Repaired.Coolant Conductivity Reduced
05000269/LER-1981-008, Forwards LER 81-008/01T-0.Detailed Event Analysis Encl
05000324/LER-1981-047-03, /03L-0:on 810417,high Reactor Coolant Vessel Conductivity Was Discovered.Caused by Condenser Tube Plugs Isolating Tube Leaks Falling Out Due to Aging & Environ Conditions.Condenser Plugs Being Replaced
05000325/LER-1980-055-03, /03L-0:on 800812,during Startup Preparations, Reactor Vessel Conductivity Measured Excessively High.Caused by Organics Breakdown in Reactor Vessel.Series of Condensate Makeup & Reject Operations Performed Using Charcoal Filt
05000325/LER-1980-092-03, /03L-0:on 801220,reactor Vessel Conductivity Measured Over Tech Spec Level.Caused by Removal of Reactor Water Cleanup Sys from Svc for Valve Maint.Valves Repaired & Sys Returned to Svc
RA-15-019, Attachment 9 - EP-AA-1007, Revised Radiological Emergency Plan Annex Information for Peach Bottom Atomic Power Station
NLS2003056, Emergency Plan Implementing Procedures for Cooper Nuclear Station
ELV-01232, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-424/89-31 & 50-425/89-36.Util Denies Violations
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
05000325/LER-1979-006-03, /03L-0 on 790316:during Refueling Outage,Condenser Tube Leaks Allowed Chlorides to Enter Condensate Sys.Cfd in Svc Became Depleted Due to Entrained Oxygen.Condenser Vacuum Broken & Cfds & Cdds Placed in Svc to Clean Sys
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000324/LER-1979-072-03, /03L-0:on 790812,during Normal Operation,Vessel Conductivity Exceeded 2 Micromhos for Approx 33-h Due to Leaks on Heat Exchanger B.Leaks Sealed W/Furmamite & Vessel Returned to Svc
NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
05000278/LER-2018-002-01, Reactor Coolant System Pressure Boundary Leakage Resulting in Technical Specification Required Shutdown
RAIO-0118-58473, LLC - Response to NRC Request for Additional Information No. 306 (Erai No. 9234) on the NuScale Design Certification Application
L-88-157, Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Spec 3.4.4 to Require Applicability in Modes 1,2,3 & 4 & Allow One CCW HX to Be Out of Svc for 72 H.Action Requirements Revised for Consistency
05000389/LER-1998-005, :on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
05000333/LER-2017-002, Regarding Residual Heat Removal to Reactor Water Recirculation Loop a Weld Flaw Indication
05000333/LER-2017-001, Vent Line Socket Weld Failure
05000387/LER-2016-019, Regarding Pressure Boundary Leakage from an Inadequate Weld Repair in Small Bore Pump Seal Vent Piping
AEP-NRC-2016-07, License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation
05000348/LER-2015-002, Regarding Technical Specification Shutdown Due to Reactor Coolant Pump Trip
05000388/LER-2015-004, Regarding Degraded Condition Due to Reactor Coolant Pressure Boundary Leakage Caused by Vibration and Stiff Pipe Connection
05000374/LER-2015-002, Regarding Two Main Steam Safety Relief Valves Failed Inservice Inspection Pressure Test
05000387/LER-2014-011, Regarding Degraded Condition Due to Reactor Coolant Pressure Boundary Leakage Caused by an Inadequate Weld
05000336/LER-2014-007, Regarding Completion of Plant Shutdown Required by Technical Specifications
05000247/LER-2014-002, Regarding Technical Specification Prohibited Condition Due to an Inoperable 23 Steam Generator (SG) Caused by a Through Wall Defect in 23 SG Drain Line Valve MS-68
05000263/LER-2014-001, Regarding Primary System Leakage Found in Recirculation Pump Upper Seal Heat Exchanger
05000206/LER-1988-017-01, :on 881202,discovered That Calculation Which Provides Basis for Min Tech Spec Vol Did Not Account for Pump G10S Bearing Cooling Water Flow.Caused by Personnel Error.Training Program Initiated
L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6
05000387/LER-2012-007, Regarding Unplanned Shutdown Due to Unidentified Drywell Leakage
SVPLTR 12-0059, Response to NRC Request for a Written Response to NRC Observations and Concerns Regarding Dresden Station Response Plan for External Flooding Events
05000410/LER-2011-001, Regarding As-Found Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable Values
NRC-11-0013, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-24-106, Request RV-04, Proposed Alternative to Modify Reactor Pressure Vessel Safety Relief Valve Testing Sampling Requirements Per Inservice Test Program
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
05000338/LER-2010-002, Regarding Forced Shutdown Due to Un-isolable C Steam Generator Surface Sample Line Leakage
RS-10-025, Supplemental Information Concerning Request for License Amendments to Revise Technical Specifications 3.4.5, RCS Leakage Detection Instrumentation
05000260/LER-2009-004, Regarding Technical Specification Shutdown Due to Rise in Unidentified Drywell Leakage
TSTF-09-18, Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
05000249/LER-2008-001, Regarding Unit 3 Drywell Floor Drain Sump Monitoring System Declared Inoperable
05000366/LER-2008-003, For Edwin I. Hatch, Unit 2 Regarding Crack in Reactor Pressure Boundary Piping Due to High Cycle Fatigue Results in Leakage
RS-07-145, Supplement to Request for Proposed Alternative to Performance of System Pressure Tests and VT-2 Visual Examination Requirements for All Class 2 Instrument Air (IA) Piping and the Class 3 IA Piping Supplying All SRVs & Both Feedwater
05000368/LER-2006-001, Completion of a Plant Shutdown Required by Technical Specifications Due to Loss of Motive Power to Certain Containment Isolation Valves as a Result of a Phase to Ground Short Circuit
RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program
ULNRC-05345, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms)
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
05000324/LER-2005-004, Re Loss of Electrical Power to Emergency Bus E1
BSEP 05-0060, Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation
BSEP 05-0059, Request for Notice of Enforcement Discretion Technical Specification 3.4.5, RCS Leakage Detection Instrumentation
05000341/LER-2005-001, Regarding Manual Reactor Shutdown Due to Containment Cooler Leak
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
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
05000346/LER-1998-002-01, Regarding Plant Trip Due to High Pressurizer Level as a Result of Loss of Letdown Capability
DCL-03-152, Response to NRC Request for Additional Information Regarding License Amendment Request 01-08, Credit for Automatic Actuation of Pressurizer Power Operated Relief Valves; Pressurizer Safety Valve Loop Seal Temperature
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
NLS2003124, 1 to EPIP 5.7.1, Emergency Classification
05000254/LER-2003-001, Reactor Shutdown Due to Reactor Head Vent Steam Leak Consulting Pressure Boundary Leakage
CPSES-200600097, Revision to Technical Specifications 3.3.1, Reactor Trip System Instrumentation, 3.3.2, ESFAS Instrumentation, 3.4.5, RCS Loops-Mode 3, 3.4.6, RCS Loops-Mode 4, and 3.4.7, RCS Loops-Mode 5, Loops Filled
05000249/LER-2002-003, Reactor Recirculation Loop a Sensing Line Socket Weld Vibration Fatigue Failure
NRC-2002-0094, Supplement to License Amendment Request 226, Measurement Uncertainty Recapture (MUR) Power Uprate
05000321/LER-2002-002, Technical Specification Required Plant Shutdown Because of High Unidentified Reactor Coolant System Leakage
NOC-AE-0500, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statements
ULNRC-04883, Proposed Revision to Technical Specification (TS) 3.9.2, Unborated Water Source Isolation Valves, to Revise & Rename Specification 3.9.2, Dilution Source Isolation Valves & Associated Revision to TS 3.3.9, Boron Dilution.
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
TSTF-04-13, TSTF-449, Revision 2, Steam Generator Tube Integrity
05000368/LER-2016-001, Regarding Failure of One Emergency Diesel Generator and Subsequent Required Shutdown
05000498/LER-2024-006, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Pressurizer Power Operated Relief Valve
05000321/LER-2012-003, Regarding Leak in Reactor Pressure Boundary at Small Bore Piping Fillet Weld
NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RS-05-104, Revised Technical Specification Pages for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
CNL-15-181, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 4
CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
1CAN029301, Forwards Response to Addl Info Re Generic Ltr 90-06, Resolution of Generic Issue 70, Power-Operated Relief Valve & Block Valve Reliability, & Generic Issue 94, Addl LTOP for Lwrs
CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision
JAFP-17-0083, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
AEP-NRC-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
1CAN081004, Changes to Technical Specification Related to Completion Times for One Inoperable RCS Cooling Loop
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
PLA-5764, Proposed License Amendment Numbers 267 for Unit 1 and 232 for Unit 2 Mode Change Limitations Using the Consolidated Line Item Improvement (CLIIP) Process PLA-5764
ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
1CAN062102, Cycle 30 Core Operating Limits Report (COLR) Revision 1
05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
CNL-15-177, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Manual
05000336/LER-2014-001, Regarding Completion of Plant Shutdown Required by Technical Specifications
05000206/LER-1988-017, :on 881202,discovered That Calculation Used to Determine Min Auxiliary Feedwater Storage Tank Vol Incorrect.Caused by Deficiencies W/Programs Re Design Basis Documentation.Tech Specs Revised
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2 Decrease in Heat Removal by the Secondary System, Redacted
05000354/LER-1988-018, :on 880725,unanticipated Isolation of RWCU Occurred W/Plant in Operational Condition 1.Caused by Blown Fuse in Channel a of Nuclear Steam Supply Shutoff Sys.Fuse Replaced & Personnel Counseled
05000261/LER-1983-012-03, /03L-0:on 830621,auxiliary Feedwater Pump Discharge Valve V2-16C Breaker Tripped During Performance of Periodic Test 22.1C.Cause Unknown.Circuit Breaker for V2-15C Immediately Reclosed & Valve Cycled
RS-05-070, Response to Request for Additional Information Regarding the Plant Loop Stop Isolation Valve
1CAN111104, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 2
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
TSTF-05-05, Letter Transmitting TSTF-449, Revision 4, Steam Generator Tube Integrity
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Page PBAPS 3-77 Through End
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Cover Through Page PBAPS 3-76
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
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
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-20-08, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirement
L-2025-149, Response to Requests for Additional Information Regarding Seabrook License Amendment Requests to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Time - RITSTF Initiative 4b, and 10 CFR 50.69.
L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change