TS-3.3.4 Licensee-identified
ONS-2017-019, Technical Specification Bases Change 2015-09
L-PI-17-002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action
RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
NL-16-0630, Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption
CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)
CNL-18-006, Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)
RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles
B18763, License Basis Document Change Request (LBDCR) 2-18-02 Selective Implementation of the Alternative Source Term - Fuel Handling Accident Analyses
CNL-15-108, Technical Specification (TS) Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (WBN-TS-2015-12)
NL-14-078, Post Accident Monitoring Report on Inoperable Condensate Storage Tank Level Transmitters
CNS-14-035, Submittal of Post Accident Monitoring (PAM) Report
TSTF-13-05, Transmittal of TSTF-536, Revision 0, Resolve CE Digital TS Inconsistencies Regarding CPCs and Ceacs
NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9
ULNRC-05781, Callaway Plant NFPA 805 Transition Report, Attachment N - Technical Specification Changes
NRC 2010-0044, License Amendment Request 261, Extended Power Uprate Implementation of New Auxiliary Feedwater System at Current Licensed Power Level
TSTF-09-24, Technical Specification Task Force Recommended Changes to Be Incorporated in Revision 4 of the Standard Technical Specifications, NUREG-1430 Through 1434
NL-09-148, Report on Inoperable Post Accident Monitoring Instrument Neutron Source Range
NRC 2009-0094, License Amendment Request 261 Extended Power Uprate Expedited Review Request
ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
2CAN040805, Supplemental to License Amendment Request, Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)
2CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments
NRC 2006-0091, License Amendment Request 245, Response to Request for Additional Information; Technical Specification 3.3.4, Loss of Power Diesel Generator Start and Load Sequence Instrumentation
NRC 2006-0033, License Amendment Request 245; Technical Specification 3.3.4, Loss of Power Diesel Generator Start Instrumentation
LR-N18-0098, License Amendment Request: Remote Shutdown System
05000311/LER-1991-017-03, :on 911109,reactor/turbine Trip Occured on Low Auto Stop Oil Pressure Followed by Turbine/Generator Failure.Caused by Failure of 63-3 Auto Stop Oil Protection Pressure Switch.Matrix Review Performed
NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018
CNL-19-031, Request to Expedite NRC Review of the Application to Revise the Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls(WBN
RAIO-0118-58343, LLC Response to NRC Request for Additional Information No. 297 (Erai No. 9213) on the NuScale Design Certification Application
RA-18-0282, Technical Specification Bases Changes
RAIO-0319-64994, LLC Supplemental Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
RAIO-0719-66473, LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application
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
DCL-18-105, Submittal of the Fourth Ten-Year Interval Inservice Testing (1ST) Program Plan, Revision 1
L-04-040, License Amendment Request Nos. 321 and 193, Modifying Technical Specification Requirements for Mode Change Limitations in Specifications 3.0.4 and 4.0.4 and the Associated Technical Specification Bases
WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
NL-03-181, 180-Day Response to NRC Generic Letter 2003-01 Regarding Control Room Habitability
DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
CPSES-200301485, License Amendment Request (LAR) 03-06 Revision to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ULNRC-04721, Technical Specification Bases Revision 3
DCL-02-061, Inservice Testing (IST) Program Plan, Revision 18
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
NSD-NRC-97-4994, Submits W Responses to NRC RAIs Re AP600 Internal Fire SD Analysis Documented in Chapter 57 of AP600 Probabilistic Risk Assessment Rept
1CAN099203, Application for Amend to License DPR-51,changing Sodium Hydroxide Tank Level & Deleting Value for Weight of Sodium Hydroxide Specified in TS 3.3.4(B) & Revising Bases for TS 3.3.4 to Reflect New Level Value.Calculation Encl
ULNRC-03184, Application for Amend to License NPF-30,responding to Concerns Raised by NRC Staff During Review of Final Policy Statement on TS Improvements
1CAN059506, Documents Util Position Discussed on 950512 W/Nrc & Requests Enforcement Discretion from Specific Test Flow Requirement of TS 4.5.2.1.2(a)(1) to Allow Determining Proper Sys Operation by Engineering Evaluation in Bases of TS 3.3
1CAN079105, Application for Amend to License DPR-51,consisting of Bases Change Request to Tech Spec 3.3.4 to Correct Instrument Inaccuracy in Allowed Sodium Hydroxide Tank Level Indication
L-23-036, Report of Facility Changes, Tests and Experiments
JSP-959-90, Application for Amend to License NPF-62,changing Tech Spec 3/4.3.4.1, ATWS Recirculation Pump Trip Sys Instrumentation
1CAN129011, Forwards Schematic of Reactor Bldg Coolers,Per 901213 Telcon W/Nrc.During Cleaning,Leakage Detected in Cooler C. All Coils in Coolers C & D Will Be banked-off to Reduce Potential for Future Leakage
RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications
RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific
L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits
RAIO-0119-64178, LLC - Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
05000361/LER-1982-120, Forwards LER 82-120/03L-0.Detailed Event Analysis Submitted
2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
NL-22-0764, – Units 1 & 2, License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.23 to Use Online Monitoring Methodology
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)
L-PI-14-037, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources- Operating, Emergency Diesel Generator Voltage and Frequency Limits
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
05000220/LER-1998-004-01, :on 980411,identified That Containment Spray Flow Control Valve 80-118 Had Been Left Open Since 980407. Caused by Failure by Chief Shift Operator to Properly Follow Procedure.Procedures Revised
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
05000457/LER-1997-001-13, :on 970916,identified That Scaffolding Had Potentially Blocked Weighted Lever Arm on Extraction Steam non-return Check Valve 2ES015C.Caused by Improper Assumptions.Maint Adjusted Scaffold
DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19
05000400/LER-1987-008, :on 870227,loss of Main Feedwater & Automatic Start of Both motor-driven Auxiliary Feedwater Pumps Occurred.Caused by Transient in Turbine Load.Motor Replaced & Tested & Valve Returned to Svc
05000457/LER-1997-001-12, :on 970916,identified That Scaffolding Had Potentially Blocked Weighted Lever Arm on Extraction Steam non-return Check Valve 2ES015C.Caused by Result of Ack Deficiencies.Maint Adjusted Scaffold
05000220/LER-1998-017-01, :on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With
05000455/LER-1992-005-10, :on 920814,discovered That LCO Action Requirement for Instrumentation,Turbine Overspeed Protection Never Entered During Work on Check Valve on 920813.Caused by Personnel Error.Surveillance Performed
05000325/LER-1983-061-03, /03L-0:on 831127,reactor Power intermediate-range Monitor C51-IRM-K601H Determined Inoperable Due to Downscale Indications.Caused by Signal Preamplifier Low/High Range Gain of K601H Out of Adjustment
05000362/LER-1983-075-03, /03L-0:on 830922,low Pressure Turbine Stop Valve 3UV2200V Declared Inoperable After Insp Revealed Valve 50% Open.Caused by Lodged Piece of Wood Inside Piping Between Disc & Seat.Wood Removed
05000362/LER-1983-085-03, /03L-0:on 831007,low Pressure Turbine 1,intercept Valve 3UV2200L,failed Trip Solenoid a & B Tests During Monthly Surveillance Test S023-3-3.34.Caused by Failed Logic Card in Control Circuit.Logic Card Replaced
05000361/LER-1982-033-03, /03L-0:on 820609,turbine Overspeed Protection Sys Rendered Inoperable.Caused by Need to Repair Oil Leaks on Unitized Actuator.Isolation Immediately Achieved Because MSIV Turbine Stop Valves Closed
05000270/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl
05000389/LER-1983-042-03, /03L-0:on 830801,turbine Intercept Valve C Failed to Close.Caused by Trip Block/Solenoid Encl Box Hanging from Control Leads,Due to Loose Allen Screws.Screws Tightened & Leads Repaired
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
DCL-04-002, Inservice Testing (IST) Program Plan, Revision 20
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
05000289/LER-1977-012, RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RAIO-0119-64111, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
05000306/LER-2018-001-01, Automatic Actuation of Emergency Diesel Generator D5
05000306/LER-2018-001, For Prairie Island Nuclear Generating Plant, Unit 2, Automatic Actuation of Emergency Diesel Generator D5
05000255/LER-2018-001, Safety Injection Inoperable for Longer than Allowed by Technical Specifications Due to Personnel Error
HNP-94-073, Application for Amend to License NPF-63,relocating Selected TS Per NUREG-1431
05000251/LER-1990-009-01, :on 900710,action Requirement of Tech Spec 3.3.1 Re Containment Airlock Pressure Test Not Met.Caused by Work Control Deficiencies.Computer Program Updated to Print Caution Statement on Work Orders
05000251/LER-1987-007-01, :on 870310,air Leakage During Leak Rate Testing of Personnel Hatch Exceeded Tech Spec Requirements.Caused by Malfunctioning Equilizing Valve Not Being Able to Fully Close.Valve Replaced
L-85-216, Forwards Response to 850416 Request for Addl Info on 850128 & 0302 Applications to Amend Licenses DPR-31 & DPR-41, Changing Tech Specs Re Containment Sys
GO2-90-168, Application for Amend to License NPF-21,changing Tech Spec 3.3.4 Re ATWS Recirculation Pump Trip Sys Instrumentation
ST-HL-AE-5521, Forwards Summary of Safety Evaluation of Changes,Tests & Experiments Conducted at STP
DCL-93-114, License Amend Request 93-01 to Licenses DPR-80 & DPR-82, Changing TS 3/4.3.3.5, Remote Shutdown Instrumentation, to Add Remote Shutdown Control Functions & Increase Allowed Outage Time for Inoperable Function from 7 to 30 Days
05000483/LER-2014-003-02, Regarding Inverter NN11 Inadvertently Transferred to Its Alternate AC Source
05000483/LER-2014-003, Inverter NN11 Inadvertantly Transferred to Its Alternate AC Source
05000275/LER-2013-008, Regarding Technical Specification 3.3.4 Not Met Due to Inoperable Remote Shutdown System Function
CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System
05000446/LER-2013-001, (Cnpnpp) Regarding Unit 2 Hot Shutdown Panel Transfer Switch Inoperable Due to Wiring Error
05000425/LER-2011-001, Regarding Inoperable Core Exit Thermocouple Indicator on the B Train Remote Shutdown Panel
L-PI-09-133, License Amendment Request for Measurement Uncertainty Recapture - Power Uprate
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000247/LER-2010-006, For Indian Point 2, Regarding Safety System Functional Failure Due to Inoperable Reactor Coolant Loop 21 and 22 Wide Range Hot Leg Temperature Indicators Credited for Remote Shutdown Per Technical Specification 3.3.4
05000286/LER-2010-001, Regarding SSFF and TS Violation for an Inoperable RCS Wide Range Temperature Cold Leg Instrument TE-413B Credited for TS 3.3.4 Remote Shutdown
05000286/LER-2009-009, Regarding Loss of Single Train Neutron Flux Detector N-38 Required for Plant Shutdown Remote from the Control Room Due to a Power Supply Failure
05000247/LER-2009-004, For Indian Point 2, Regarding Loss of Single Train 23 Charging Pump Required for Remote Plant Shutdown from the Control Room Due to a Failure of a Pump Internal Check Valve
05000247/LER-2009-003, Regarding Loss of Single Train 21 Pressurizer Backup Heater Required for Remote Plant Shutdown from the Control Room Due to an Inoperable Breaker
ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
05000286/LER-2008-002, Regarding Loss of Single Train 31 Pressurizer Backup Heater Bank Required to Function to Shutdown and Maintain the Reactor in a Safe Condition Remote from Control Room
DCL-05-023, Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests
3F0502-06, Technical Specifications Bases Control Program
B18638, License Basis Document Change Request (LBDCR) 2-1-02 Re Limiting Safety System Settings and Instrumentation
05000445/LER-2024-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
05000317/LER-2014-005, Regarding Condition Prohibited by Technical Specifications Due to Human Performance Error
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2
ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ
ONS-2015-106, Technical Specification (TS) Bases Change
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
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
DCL-24-118, License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology
NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5