JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
GNRO-2012/00024, Supplemental Information Extended Power Uprate
RA-15-019, Attachment 3 - EP-AA-1002, Revised Radiological Emergency Plan Annex Information for Byron Station
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3A, 3B, Cover - by 3-74
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 1 of 9
RA-09-065, Application for Technical Specifications Change Regarding Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (Adoption of TSTF-425, Rev 3)
NOC-AE-09002433, Tpdes Permit Renewal Application 01908
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3A, 3B, Cover - by 3-74
RBG-46550, Response to Non-cited Violation in IR 50-458/2005-005
ULNRC-06478, Specifications to Adopt TSTF-545 Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, (LDCN 18-0021)
L-2019-050, License Amendment Request (TSCR-181): Application to Align Technical Specification Staffing and Administrative Requirements for Permanently Defueled Condition
CNL-19-056, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
PLA-7842, Proposed Amendment to Licenses NPF-14 and NPF-22: Revise Technical Specification 3.8.1 to Create a New Condition for an Inoperable Manual Synchronization Circuit PLA-7248
05000000/LER-1986-030, Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted
RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes
IMC 0310, Aspects within the Cross-Cutting Areas
RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location
CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.
ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating
CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)
NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0
CNL-21-020, Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)
NMP2L2780, Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating
DCL-21-060, Response to Request for Additional Information on License Amendment Request 21-03, Request for Revision to Technical Specification 3.8.1, AC Sources - Operating, to Support Diesel Fuel Oil Transfer System.
RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
05000333/LER-1987-010, :on 870723,HPCI Inoperable Due to Low Auxiliary Oil Pump Discharge Pressure.Caused by Failure of Inboard Bearing in Auxiliary Oil Pump.Addl HPCI Turbine Parameters Will Be Monitored,Recorded & Trended
05000247/LER-1986-014, :on 860518,seismic Restraint SR-1092 Disconnected.Caused by Failure of Maint Procedure for Reactor Coolant Pump Seal Overhaul to Assure Reinstallation of SR-1092.Procedure Revised
05000458/LER-1986-037, :on 860505,high Reactor Pressure Scram Occurred Due to Turbine Runback Stator Coolant Trouble Alarm.Caused by Low High Stator Water Cooling Temp Setpoint.Temp Switches Recalibr
VPN-033-99, PGE-1065-98, Trojan Nuclear Plant Radioactive Effluent Release Rept for 1998. with
05000327/LER-1988-035-01, :on 880927,auxiliary Bldg Isolation Occurred When Operator Inadvertently Tripped Circuit Breaker A. Cause Not Determined.Training Ltr Issued to All Licensed Operators Detailing Event
05000370/LER-1988-010, :on 880615 & 27,switchgear Logic Function for Containment Sump Isolation Valve 2NI-184B Inoperable.Caused by Personnel Error in Wiring of Terminal Block.Rev of Maint Procedures & Program Review Planned
05000301/LER-1985-002-03, :on 851017,reactor Coolant Pump Component Cooling Supply Line Check Valve Leakage Exceeded Tech Spec Limits.Caused by Valve Deficiencies.Valve Inspected & Repairs Made on Internal Parts
05000259/LER-1986-016-01, :on 860401,hydraulic Fluid Leakage Problem Observed w/Bergen-Patterson Large Bore Torus Dynamic Restraint Snubbers.Cause Undetermined.Vendor Conducting Study & Personnel Documenting Monthly Insps
NSD-NRC-98-5559, Forwards W Response 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, Included in Table 1
05000498/LER-1988-031, :on 880509,extended Range Neutron Sys Cable Assemblies Mfg by Gamma-Metrics Found Incapable of Performing Required Safety Functions.Caused by Solder Joint Leakage.Cable Assemblies & Detectors Replaced
05000298/LER-1988-006, :on 880316,unplanned Automatic Actuation of Diesel Generator 1 Starting Logic Occurred.Caused by Target Reset Lever Inadvertently Contacting Overcurrent Relay seal-in Contacts.Relay Removed & Inspected
05000413/LER-1987-047, :on 871221,reactor Trip Signal Occurred Due to Steam Generator lo-lo Level.Cause Unknown.Operator Update Issued to Assure All Licensed Operators Aware of Procedure for Equalizing Pressure Across MSIVs
05000267/LER-1988-003, :on 880211,reactor Scram Actuated on Neutron Flux Rate of Change High.Caused by Electrical Noise Induction in Wide Range Nuclear Instrumentation Channels. Noises Will Be Investigated & Suppressed
05000528/LER-1985-066, :on 851012,100-ft Level Emergency Containment Airlock Inner Door Failed Seal Test.Caused by Personnel Error.Procedure Revised to Specify Correct Actions If Inner Door Fails & Requires Repair
05000335/LER-1985-012-02, :on 851219,inservice Insp of Snubbers Revealed Failures.Caused by Design & Personnel Errors.Defective Snubbers Repaired or Replaced.Supplemental Rept Will Be Submitted by 860214
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
05000483/LER-1984-004, :on 840617,ESFAS Inadvertently Actuated.Caused by Spurious Electronic Signals & Incompatibility Between Software & Hardware in RM-80 Microprocessing Unit for Radiation Monitors.Sys Reset
05000373/LER-1984-045, :on 840715,reactor Water Cleanup Sys C Isolated on High Differential Flow.Caused by Improper Positioning of Ball Valves Resulting in Partial Draining of Filter/ Demineralizer.Sign Re Valve Positioning Posted
05000244/LER-1985-013, :on 850531,one Emergency Diesel Generator Started Per Adverse Weather Emergency Plan Due to Notification of Tornado Warning.Generator Removed from Svc When Tornado Warning Rescinded
05000304/LER-1985-008, :on 850317,while at Steady State Power Operation,Reactor Tripped.Caused by Turbine Trip Induced by Actuation of Phase Main Power Transformer back-up Differential Relay
05000249/LER-1985-007-05, :on 850302,during Normal Operation,Two Normally Closed Torus Water Sample Valves Discovered Open W/Water Draining to Sump.Caused by Personnel Error.Valves Locked. Procedures Revised
05000271/LER-1984-016, :on 840728,during Shutdown for Maint,Reactor Scrammed When Recirculation Motor Generator a Started.Caused by Voltage Dip on 480-volt Bus Tripping Alternate Supply Breaker
05000263/LER-1984-004, :on 840110,emergency Filtration Train Transferred to Emergency Mode in Control Room Hvac.Caused by Chlorine Monitor Tape Cassette Running Out,Resulting in Tape Break & Spurious Monitor Trip
05000338/LER-1991-014, :on 910703,determined That ASME Section XI Surveillance Requirements Inadequately Performed for Four Boric Acid Transfer Pumps During Second Quarter 1991.Caused by Personnel Error.Generic Ltr 89-04 Reviewed
NSD-NRC-97-5231, Forwards Formal Transmittal of Correspondence Previously Sent Over Period 970515-970605.W/index
RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
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
CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, and
DCL-2015-532, Discharge Self-Monitoring Report for 2nd Quarter of 2015
NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)
NRC-11-0049, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
NL-14-1870, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
BSEP 09-0019, Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 2
NL-19-0635, End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability
L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006
RNP-RA/08-0006, Request for Technical Specifications Changes Related to Control Room Habitability - Supplement
ET 05-0025, Supplement to Revision to Technical Specifications - Extensions of AC Electrical Power Distribution Completion Times
L-PI-05-081, License Amendment Request (LAR) to Clarify Technical Specification Requirements for Surveillance Requirements for Installed Spare Components and Miscellaneous Corrections
RS-05-001, Request for a License Amendment to Extend the Completion Times Related to Technical Specifications Associated with Residual Heat Removal Service Water, Diesel Generator Cooling Water and the Opposite Unit Division 2 Diesel
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
RS-03-140, Request for Amendment to Technical Specifications Associated with Direct Current Electrical Power
CY-03-046, Annual Radioactive Effluent Report, January-December 2002 & Revision 15 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual & List of Changes
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
HL-6193, Request for Technical Specification Revision of TS 3.8.1 to Add a One Time Extension for Diesel Generator 1B
HL-6195, Request to Revise Technical Specifications: One Time Extension of Hatch Unit 1 and Unit 2 Technical Specification 3.8.1 for Diesel Generator 1B - Rev.1
RNP-RA/03-0074, Supplemental Information Regarding License Renewal Application
WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
RS-17-145, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
NL-07-1130, Technical Specifications Revision to Add a 72 Hour Completion Time for an Inoperable Swing Diesel Generator
NRC-13-0001, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process
RS-22-057, Constellation Radiological Emergency Plan Addendum Revision
CP-202100394, Supplement to License Amendment Request (LAR) 20-006
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
DCL-21-020, Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance
RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
NL-23-0928, Application to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
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.
NRC-98-0043, Application for Amend to License NPF-43 to Convert Current TS to Improved Ts.Meeting Is Requested to Discuss Review Schedule & Contents of Amend.Vol 1 Includes Application & Justification.Vols 2-13 Contain Improved TS
05000374/LER-1984-076-01, :on 841120,turbine Bypass Sys Declared Inoperable When Solenoid on Bypass Valves Showed Infinite Resistance.Caused by Malfunctioning Solenoid.Solenoid Valve Assembly Replaced
05000278/LER-1984-010-01, :on 840816,loss of Power to Portion of Primary Containment Isolation Sys Outboard Isolation Logic Caused Partial Actuation.Caused by Grounded Leads on Primary Side of Unit 2 Pump Transformer A.Logic Reset
LR-N25-0058, License Amendment Request (LAR) - Hope Creek Technical Specification Coversion to NUREG-1433, Revision 5, Supplement 4
TSTF-22-03, Transmittal of TSTF-584, Revision 0, Eliminate Automatic RWCU System Isolation on SLC Initiation