05000237/LER-2013-007, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously
05000374/LER-2005-003, Re Multiple Containment Isolations Following Loss of 480 Vac Safety Related Buses Due to Failed Neutral Overcurrent Relay
RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
ONS-2017-019, Technical Specification Bases Change 2015-09
ULNRC-06350, Pressure and Temperature Limits Report
CNS-17-033, Technical Specification Bases Changes
ONS-2017-052, Technical Specification Bases Change 2017-03
CNL-17-087, Justification for Performing Extended Technical Specification Surveillances During the First Refueling Outage
NRC-17-0063, License Amendment Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 9
RA-16-0028, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
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
L-PI-16-054, Pressure and Temperature Limits Report, Revision 5
CNL-16-033, Application to Modify Technical Specifications Regarding Steam Generator Minimum Narrow Range Level Error Correction
CNL-16-078, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)
ONS-2016-009, Technical Specification (TS) Bases Change
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases
NL-14-1075, Technical Specifications. Part 4 of 4
MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System
L-MT-15-048, License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, 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
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 4
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
PLA-7285, Revision (X) to EP-RM-004, EAL Classification Bases
L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown
NL-14-1349, 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..
W3F1-2014-0067, Technical Specification Index and Bases Update to the NRC for the Period June 30, 2013 Through November 3, 2014
ULNRC-06145, Pressure and Temperature Limits Report, Revision 6
L-2014-114, Proposed Change to Turkey Point Units 3 and 4 Technical Specifications to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents. License Amendment Request No. 233
L-2014-205, Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents
ONS-2014-080, License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-03
L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report
CNS-14-055, Technical Specification Bases Changes
WO 14-0024, Changes to Technical Specification Bases - Revisions 57 Through 60
MNS-14-003, License Amendment Request for Technical Specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System
0CAN021403, Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report
ULNRC-05975, Revision to TS LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4, 5 and 6 License Amendment Request LDCN 13-0003
1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
NL-13-001, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
NL-12-090, Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank
RS-12-073, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Section 3.5.3, ECCS - Shutdown
L-12-077, Pressure and Temperature Limits Report Revision
NL-12-0403, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)
NL-12-0346, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
NL-10-2144, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well
GO2-11-077, 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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
NL-16-109, Indian Point 2 Technical Requirements Manual
NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4
NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
L-76-301, Letter Regarding a Review of Inspection Report 05000335/1976009 and Informing the NRC That It Contains No Proprietary Information
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases
NL-12-1078, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Technical Requirements Manual
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
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
RS-10-208, Additional Information Supporting the Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation
NL-10-072, Proposed Technical Specification Change Regarding RWST Surveillance Requirement
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
NLS2010029, Technical Specifications Bases Changes
W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program
TSTF-09-24, Technical Specification Task Force Recommended Changes to Be Incorporated in Revision 4 of the Standard Technical Specifications, NUREG-1430 Through 1434
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
LR-N09-0002, Request for Change to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process (Cliip), TSTF-359
L-08-327, Pressure and Temperature Limits Report, Revision 3
NRC 2008-0075, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
WO 08-0019, Application to Revise Technical Specification 3.5.2, ECCS-Operating, in Accordance with TSTF-325-A
NLS2008001, License Application Amendment Request for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process and Related
TSTF-08-13, TSTF-426, Revision 1, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
ULNRC-05520, One-Time Completion Time Extension for Essential Service Water (ESW) System, (OL1281)
NLS2008002, License Amendment Request to Revise Technical Specification 3.7.3, Reactor Equipment Cooling System
2CAN030802, License Amendment Request, Technical Specification Changes to Relocate RCS Chemistry Requirements to TRM
TSTF-06-11, Response to NRC Request for Additional Information Regarding TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, Dated April 7, 2006
RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
NL-07-073, Proposed Change to Indian Point Unit 3 Technical Specifications Regarding Adjustment of the Low-Low Level Alarm Setpoint Range on the Refueling Water Storage Tank (RWST)
1CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
RBG-46606, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (Cliip), and Correct Example 1.4-1 (TSTF-485)
L-07-087, Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report
PLA-6141, Request for an Amendment to the Technical Specifications: Request for Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities Using the Consolidated Line Item Improvement Process (CLIIP)
W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007
GNRO-2007/00009, License Amendment Request, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (Cliip), and Correct Example 1.4-1 (TSTF-485)
NL-07-008, Proposed Changes to Indian Point, Unit 3 Technical Specifications Regarding Updated Pressure-Temperature and Low Temperature Overpressure Protection System Limits
ULNRC-05356, Figure 14.9, Pressure and Temperature Limits Report
NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report
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)
NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
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
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions
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)
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
NRC-89-0273, Application for Amend to License NPF-43,changing Tech Specs 3/4.4.7,3/4.6.3,3/4.6.4.2 & Definition 1.29 Re Containment Isolation Valves
RAIO-0518-60228, LLC Response to NRC Request for Additional Information No. 423 (Erai No. 9252) on the NuScale Design Certification Application
RAIO-0118-58271, LLC Response to NRC Request for Additional Information No. 302 (Erai No. 9276) on the NuScale Design Certification Application
RAIO-0318-59209, LLC Response to NRC Request for Additional Information No. 359 (Erai No. 9321) on the NuScale Design Certification Application
RA-18-0282, Technical Specification Bases Changes
NL-19-0355, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process
L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report
NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown
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
NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval
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)
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-19-1539, Supplement to Request for License Amendment and Exemption: Automatic Depressurization System (ADS) and Core Makeup Tank (Cmt) Design Parameters (LAR-19-009S1)
ND-19-0831, Request for License Amendment and Exemption: Addition of In-Containment Refueling Water Storage Tank to Radiation Analyses (LAR-19-003)
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project
NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases
NL-04-0134, Request to Revise Technical Specifications to Relocate the Cold Overpressure Protection System Arming Temperature
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
GO2-03-167, Revision to Technical Specification LCO 3.0.4 and SR 3.0.4 Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process (CLIIP)
L-PI-03-089, License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NRC 2003-0091, Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submi
NRC 2003-0058, License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report
NRC 2003-0033, Technical Specification Bases Revisions
W3F1-2003-0024, TS Bases Update to NRC for Period January 8, 2003 Through April 7, 2003
RS-03-004, Response to Request for Additional Information Supporting a Relief Request for Alternative Testing of Containment Sump Suction Valves 1/2S18811A/B
NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate
ULNRC-04721, Technical Specification Bases Revision 3
1CAN030201, License Amendment Request Re Proposed Change to Support Implementation of ANO-1 Improved Technical Specifications
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
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
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
NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process
TSTF-20-04, Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections
PLA-7865, Response to Request for Additional Information Regarding Proposed License Amendment Requesting Revision to the Dose Consequence Analysis for a Loss of Coolant Accident (PLA-7865) Loss of Coolant Accident
05000029/LER-1986-005, Forwards LER 86-005-00 Re Primary Coolant Dose Equivalent I-131 Greater than 1 Mci Per G
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)
NL-21-0413, Supplement to Emergency License Amendment Request for Technical Specification 3.5.1 Re One-Time Extension of Completion Time for 2D RHR Pump
NL-21-0411, Emergency License Amendment Request for Technical Specification 3.5.1 Regarding One-Time Extension of Completion Time for 2D RHR Pump
3F1097-07, Forwards Response to Violations Noted in Insp Rept 50-302/97-11.CAs:Health Physics Personnel Assigned Responsibility for Providing Ventilation for OTSG Work Were Counseled for Failing to Secure Temporary Purge Fans
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
NSD-NRC-98-5562, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column of Oits, Provided in Table 1
NSD-NRC-97-5504, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses Also Encl
CY-97-058, Responds to NRC Re Violations Noted in Insp Rept 50-213/97-01.Corrective Actions:Counseled Individuals on Importance of Never Operating Red Tagged Equipment & Wrote Temporary Procedure Change to Wcm 2.1-2, Tr/Job Scoping
NL-21-1037, License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
SNRC-1515, Forwards Change to Initial Test Program Described in Chapter 14 of Facility Updated SAR by Deleting Portions of Startup Test Procedure 25,per 10CFR50.71(e).Addl Changes Will Be Submitted on or Before 881212
NG-96-2322, Application for Amend to License DPR-49,converting Std TS Re NUREG-1433.Detailed Description & Justification for Proposed TS Amend Consists of 20 Vols & Summarized in Attachment 1
SNRC-1075, Forwards Updated Onshift Advisor (OSA) Resume,Osa Exam Key & Summary of OSA Operating Experience.All OSAs Satisfactorily Completed Training.No Survey Done by Util Group on Operating Shift Experience
NL-23-0069, Correction of Technical Specification Omission and Typographical Error
CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4
NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
U-602265, Proposed Tech Spec 3/4.4.3.1, RCS Leakage - Leakage Detection Sys
U-602257, Proposed TS 3/4.4.3.1, RCS Leakage-Leakage Detection Sys
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
TXX-9704, Ses Annual Operating Rept 1996
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
HNP-05-129, Response to the Request for Additional Information on the Proposed License Amendment Request to Technical Specifications 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen
RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems
HNP-05-062, Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen
L-HU-04-033, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process
RA-20-0142, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems
RS-03-060, Request for License Amendment Related to Application of Alternative Source Term
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
NL-19-1455, Emergency License Amendment Request for Technical Specification 3.7.1 Regarding One-Time Extension of Completion Time for RHRSW Pump Inoperable
CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F
CNS-15-098, Technical Specification Bases Changes
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
05000458/LER-2023-003-01, Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion Factors
05000458/LER-2023-003, Drywell Atmosphere Radiation Monitor Particulate and Gaseous Channels Inoperable Due to Out of Tolerance Conversion Factors
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
NL-21-0862, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable - RAI Responses
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
GO2-12-104, Response to Request for Additional Information for License Amendment Request to Make Administrative and Editorial Changes to Technical Specifications and the Operating License
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
05000362/LER-1984-045-01, :on 840719,recognized That Four Iodine Transients Met Reporting Criteria of TS 3.4.7,but Had Not Been Reported.Cause Indeterminate.Nrc Approved TS Amend Which Deleted Reporting Requirement of TS 3.4.7.A
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
05000364/LER-1997-004-04, :on 970910,discovered That Required Containment Atmospheric Grab Samples Had Not Been Taken.Caused by Inoperable Radiation Monitors.Declared Radiation Monitors Operable & Obtained Required Grab Samples
05000410/LER-1986-014-01, :on 861203,scram Experienced to one-quarter of Control Rods During Recovery from Earlier Scram & Containment Isolation.Caused by Personnel Error.Addl Licensed Operator Training Requested
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
05000266/LER-1997-039-01, :on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored
05000318/LER-1997-003, :on 970423,chemistry Sampling Was Not Performed as Required by TS 3.4.7 Due to Insufficient Consideration of Precise Wording of TS on Part of Chemistry Personnel.Ts Will Be Clarified When Improved TS Are Implemented
05000361/LER-1986-006, :on 860315 RCS Sample Analysis Indicated RCS Specific Activity Exceeded 1 Mci/G Dose Equivalent I-131. Caused by Iodine Spike.Rcs Specific Activity Reduced to Acceptable Limit on 860315
05000213/LER-1997-002, :on 970206,RC Surveillance Sample Was Not Taken W/Plant in Defueled Mode.Caused by Personnel Error. Reinitiated Sampling of RCS
05000362/LER-1985-020-01, :on 850524,unit Tripped from 100% Power by Core Protection Calculators in Response to Core Element Assembly Subgroup 15.Caused by Blown Fuse in Hold Bus Logic Circuit.Fuse Replaced & Unit Returned to Svc
05000362/LER-1985-010-01, :on 850329,w/unit at 96% Power,Reactor Tripped. Caused by Two Failures in Reactor Protection Sys Circuitry. Relay from Channel a Steam Generator Low Flow Bistable & Setpoint Card Replaced
05000412/LER-1992-012, :on 921023,identified That Sampling Frequency Between Samples of 72 H Exceeded,Due to Personnel Error.Ts Tracking Sheet Has Been Developed to Enhance SR
05000458/LER-1996-011, :on 960516,personnel Error Resulted in Missed Surveillance & Dry Floor Drain Sump Leakage Detection Monitoring Instrumentation Exceeded TS Allowed Outage Times. Appropriate Disciplinary Actions Taken
05000461/LER-1995-008, :on 951110,design Program Deficiency Identified Resulting in Potentially Erroneous Indication & Inoperable DW Floor Drain Sump Monitoring Sys.Programmable Logic Controller Ladder Logic Revised
05000302/LER-1983-027-03, /03L-0:on 830718,during Routine Sampling,Rcs Dissolved Oxygen Concentration at Approx 4 Ppm.Caused by Personnel Error.Hydrazine Added to Lower Dissolved Oxygen Concentration.Personnel Reinstructed
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
05000353/LER-1994-006-01, :on 940520,identified That B Inboard & Outboard MSIVs Out of Surveillance.Caused by Less than Adequate Evaluation & Review of Procedure.Msiv Surveillance Test Review
05000302/LER-1981-073-03, /03L-0:on 811115,reactor Coolant Chloride Levels Determined Contrary to Tech Specs.Probably Caused by Overfill of RCS on 811113.Chlorides Reduced Utilizing Purification,Drain & Fill Procedures
05000414/LER-1990-011-03, :on 900711,Tech Spec Requiring Operability of Containment Penetration Violated.Caused by Inappropriate Actions & Defective Procedure.Valve Repaired & Replaced & Personnel Trained Re Types of Sys Relief Paths
05000382/LER-1993-006-02, :on 931019,UHS & WCT Water Basins Less than 97% Full.Caused by Failure to Follow Procedure.Logs Revised to Indicate DWST Level Should Be Maintained Higher than Piping Logs
05000445/LER-1990-015, :on 900520,chemistry Sample Special Condition Surveillance Missed.Caused by Procedural Error.Procedures Revised to Provide Appropriate Cautions Re Required Sample
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
05000029/LER-1977-055, Forwards LER 77-055/03L-0.Detailed Event Analysis Encl
05000311/LER-1981-052, Forwards LER 81-052/03L-0.Detailed Event Analysis Encl
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
05000302/LER-1980-026-03, /03L-0:on 800714,while Performing SP-710 Rc Decay Heat Removal & Rc Makeup Sys Chemistry Surveillance Program, Chloride & Fluoride Concentrations Exceeded Limits.Caused by High Temp of Decay Heat Sys & Migration of Elements
05000302/LER-1980-018-03, /03L-0:on 800413,during Chemistry Surveillance, Discovered That RCS Chloride & Fluoride Concentrations Were 0.24 Ppm & 0.274 Ppm.Caused by Chloride & Fluoride Contamination on Walls & Floors of Fuel Transfer Canal
1CAN021101, Supplemental to License Amendment Request Related to Changes to Technical Specification – Completion Times for One Inoperable RCS Cooling Loop
NL-24-0412, License Amendment Request to Increase Flexibility in Mode Restraints
L-MT-24-026, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Usin
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
05000302/LER-1979-023-03, /03L-0 on 790308:discovered RCS C1 Concentration Was .17ppm,contrary to Tech Specs.Caused by Appearance of Suspended Solids During Cooldown When Boron Concentration Increased.Purification Sys Reduced Concentration
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000302/LER-1979-066-03, /03L-0 on 790718:during Mode 5,reported That RCS Chloride,Fluoride,Gross Beta & DEI-131 Analyses Not Performed from 790714-18 Due to Personnel Oversight.Rcs Sampled on 790718 & Parameters Were within Tech Spec Limit
L-19-102, Submittal of Pressure and Temperature Limits Report Revision
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
05000272/LER-2078-021-03, Missed Surveillance of Fluoride Sample
RAIO-0319-64749, LLC Supplemental Response to NRC Request for Additional Information No. 375 (Erai No. 9201) on the NuScale Design Certification Application
05000250/LER-1988-010, :on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced
L-87-272, Advises That Work on Mods Required to Satisfy NUREG-0737, Item III.D.3.4 Re Control Room Habitability Requirements,Per 860825 Application for Amends to Licenses DPR-31 & DPR-41 Will Begin After Both Units Return to Power
05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
05000315/LER-1999-004, :on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
L-98-031, Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A
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
05000259/LER-2014-002, Regarding Diesel Generator Inoperable Due to Fuel Oil Leak
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
05000206/LER-1989-033, :on 900131,discovered That RCS Sample for Gross Activity Determination Not Taken Prior to Entry Into Mode 4 on 890624.Caused by Failure to Incorporate New Chemistry Procedure.Procedures Revised & Incorporated
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
WO 12-0066, License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System
05000529/LER-2012-002, Regarding Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak
05000305/LER-2012-004, Regarding Pressure Boundary Leakage from Socket Weld on 3/4-inch Pipe to Sample Valve RHR-600
NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized ZIRLO Fuel Rod Cladding
RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs
RBG-47135, License Amendment Request 2011-06, Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
GNRO-2011/00004, 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-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
W3F1-2011-0040, License Amendment Request, Technical Specification Change Regarding Steam Generator Tube Integrity
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000334/LER-2010-002-01, Degree Circumferential Flaw Found on Residual Heat Removal System Drain Valve Socket Weld
1CAN111001, Supplement to License Amendment Request Related to Changes to Technical Specification – Completion Times for One Inoperable RCS Cooling Loop
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
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
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-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)
05000361/LER-2006-001, Both Trains of Shutdown Cooling Declared Inoperable Due to the Discovery of a Through Wall Pipe Crack in Common Header
TXX-0518, License Amendment Request (LAR) 04-010, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
TSTF-05-06, TSTF-05-06, Transmit TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities
NRC-2004-0011, To License Amendment Request 236 Pressure Temperature Limits Report
05000323/LER-2003-006, Re Unit 2 Auxiliary Feedwater System Actuation Due to Personnel Error
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
NRC-2002-0094, Supplement to License Amendment Request 226, Measurement Uncertainty Recapture (MUR) Power Uprate
3F0502-06, Technical Specifications Bases Control Program
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
RS-07-117, 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
NLS2002008, License Amendment Request to Revise the Ultimate Heat Sink and Reactor Equipment Cooling Water Temperature Requirements
3F0506-05, 2005 Technical Specifications Bases Control Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
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
NL-24-0253, License Amendment Request: Revised Technical Specifications to Adopt TSTF-554, Revised Reactor Coolant Leakage Requirements
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
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
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
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
NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
05000346/LER-1981-005-03, /03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS
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
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID
L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
RA-21-0239, Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
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
CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line.
PLA-2961, Forwards Rept Summarizing 1986 Approved Safety Evaluations, Per 10CFR50.59
U-602836, Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630
05000362/LER-1983-111-03, /03L-0:on 831222,RCS Specific Activity Exceeded 1.0 Mci/G Dose Equivalent I-131.Caused by Iodine Spiking Following Power Changes Associated W/Two Reactor Trips. Purification Flow Increased
ONS-2015-106, Technical Specification (TS) Bases Change
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
TSTF-05-05, Letter Transmitting TSTF-449, Revision 4, Steam Generator Tube Integrity
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
TSTF-20-08, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirement
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
TSTF-20-07, TSTF Response to NRC Questions on TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections, and Submittal of Revision 1
ULNRC-05219, Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program
NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years