WO 16-0045, Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
PLA-7285, Revision (X) to EP-RM-004, EAL Classification Bases
NRC 2012-0033, License Amendment Request 268, Supplement 1, One-Time Only License Amendment to Add Notes for Technical Specifications 3.8.1 and 3.8.2, Actions to Address Nonconformance with Point Beach Nuclear Plant GDC 2
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Appendices 3A Through 3I
ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
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
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part 4 of 5
NL-13-1503, Farley, Units 1 and 2, Calculation Number: SE-C051326701-008, NFPA 805 Fire Risk Evaluations, Version 1.0. Part of 5
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document
NEI 99-01, Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RBG-47906, Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6
NL-03-052, Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specification (ITS)
L-PI-03-007, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-day Response for Prairie Island Nuclear Generating Plant, Request for Additional Information
IA-97-455, Submits Bases for Plant TSs on Control of Explosive Gas Mixtures in Waste Gas Sys in Order to Aid W/Solution of Related Problems Elsewhere
IA-86-669, Partial Response to FOIA Request for Info Re Generic Safety Issues & Gimcs.Forwards App C Document.App B & C Documents Available in PDR
AECM-84-0150, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1983
HL-4877, Forwards Core Shroud Stabilizer Design Submittal,Providing Analyses & Conclusions Supporting Implementation of Facility Shroud Repair.Ge Proprietary Info Also Encl.Ge Proprietary Info Withheld Per 10CFR2.790
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
RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
05000213/LER-1987-011-08, :on 870721,containment Penetration P-30 Space Heating Steam Supply Failed Type C Local Leak Rate Test. Cause Not Yet Determined.Penetration Modified to Eliminate Two Problem Check Valves from Valve Status
05000352/LER-1987-062, :on 871114,reactor Encl Isolation Occurred. Caused by Personnel Error When Operator Changed Operating Lineup of Reactor Encl Ventilation Fans.Operator Counseled & Operator Aid Posted at Exhaust Control Panel
05000366/LER-1986-026-01, :on 860919,reactor Protection Sys Actuation Occurred Initiating one-half Primary Containment Isolation Sys Valve Group 2 & RHR Shutdown Cooling Sys Isolation. Caused by False Signals
05000327/LER-1987-008, :on 870126,determined Surveillance Instruction Re ERCW Valves Servicing safety-related Equipment Did Not Ensure Compliance W/Tech Spec Surveillance Requirement. Caused by Personnel Error.Instruction Revised
05000440/LER-1988-043, :on 881030,HPCS Pump Room Cooler Inadvertently Started During Performance of Breaker Retest.Caused by Procedural Deficiency.Retest Guidelines Will Be Added to Generic Electrical Instructions for Maint
05000354/LER-1988-026, :on 881006,discovered That Quarterly Surveillance of Emergency Diesel Generator Fuel Oil Storage Tanks Signed on But Not Completed.Caused by Personnel Error. Surveillance Restructured for Multiple Checks
05000414/LER-1986-023, :on 860603,main Feedwater Isolation Occurred During Testing of Solid State Protection Sys When Reactor Trip Breaker Placed in Test Position & Closed.Caused by Personnel Error.Isolation Signal Reset
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
05000312/LER-1988-008, :on 880504,reactor Tripped Automatically on High Pressure.Caused by Mismatch of Reactor Power to Feedwater Flow.Process Stds Data Base Updated to Reflect Correct Adjustment Conditions & Setpoint
05000373/LER-1986-002-06, :on 860120,safety Relief Valves 1B21-F013E,H & U Exceeded Set Pressure Tolerance in Tech Spec 3/4.4.2. Caused by Seat Leakage for Valves 1B21-F013E & U.Setpoints Adjusted & Returned to Util for Installation
05000341/LER-1988-028, :on 880726,HPCI Pump Discharge Inboard Isolation Valve Failed to Open.Caused by Grounded Contactor Coil at Valve Torque Switch by Heater Bracket.Heater Assembly & Nine Other Valves Removed
05000245/LER-1988-004-02, :on 880318,discovered Potential for ECCS Pump Suction Strainers to Foul W/Fibrous Insulation Debris.Caused by Insufficient Area of Existing Strainers.Strainers Replaced
05000440/LER-1988-007, :on 880122,reactor Protection Sys Actuation Occurred Due to High Scram Discharge Vol Level.Caused by Personnel Error.Personnel Involved Counseled on Need to Perform More Thorough Review
05000293/LER-1987-019, :on 871217,RWCU Sys Operation Interrupted Due to Actuation of RWCU Sys Portion of Primary Containment Isolation Control Sys.Caused by Personnel Error.Fuse Replaced & Isolation Reset
05000409/LER-1985-018, :on 851023,high Flux Scram Alarm Received on Nuclear Instrumentation Channel 6.Caused by Malfunction in Oscillator Circuit on Trip Stage.Step Added to Plant Startup Procedure to Ensure Recorders on
05000348/LER-1985-014, :on 850828,ESF Equipment Actuation Occurred When Diesel Generator 2C Started Automatically.Caused by Technician Accidentally Bumping Manual Operator of Emergency Start Relay.Technician Counseled
05000333/LER-1985-016, :on 850524,reactor Scram Signal Initiated During Scheduled Refueling Outage.Caused by Personnel Error. Scram Reset & Personnel Counseled
05000327/LER-1985-024, :on 850524,fire Watch for Supply Air Fan Room Not Conducted Because Door A-123 Inoperable.Caused by Broken Door Handle.Defective Parts Replaced & Hourly Fire Watch Resumed
05000341/LER-1992-009, :on 921021,Wyle Labs Notified Util That Nine SRVs Exceeded TS Acceptance TS Tolerance of Plus or Minus 1% of Pressure Setpoint.Caused by Pilot disc-to-seat Sticking.Srv Pilot Assemblies Replaced
05000440/LER-1992-015, :on 920701,HPCS Sys Declared Inoperable Due to Inoperability of Suppression Pool Suction Valve.Daily Instruction Written to Remind Personnel to Hold Control Switch in Appropriate Position
05000413/LER-1984-008-02, :840822,various ESF Valves Repositioned to Safety Positions.Caused by Inadvertent Actuation of Relay K603 of Train a Solid State Protection Sys
05000374/LER-1984-025-01, :on 840606,reactor Water Level Switches Actuated When Indicating Transmitter Switch Vented.Switches Initiated RCIC Injection Resulting in Full Reactor Scram. Caused by Personnel Error.Personnel Counseled
05000352/LER-1992-011-01, :on 920605,discovered Potential Physical Electrical Separation Deficiency in Panel 10C790.Plant Electrical Maint I&C Technicians Received Training on Electrical Separation Requirements
05000277/LER-1990-011-01, :on 900503,discovered That Tech Spec 3.4.1 Not Performed on 6-wk Frequency as Required.Caused by Personnel Error.Tracking of Surveillance Activities Scheduled to Be Transferred to Improved Software Package
05000327/LER-1989-029, :on 891121,spurious Train B Control Room Isolation Occurred.Caused by Accidental Bumping of Relays & Degraded Fuse in Circuit.Fuses Replaced & Relays Removed & Replaced
B79035, Issue Brief IB79035, Nuclear Power:Tmi Accident & Its Investigation
L-92-162, Forwards Listed Documents,In Response to 920512 RAI to Support Technical Review of 920421 Proposed License Amends Re 480 Volt Load Ctrs Degraded Voltage Protection Scheme. W/One Oversize Drawing
CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement
NRC-17-0067, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
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
CNS-14-052, 2013 Annual Radioactive Effluent Release Report
MNS-14-036, Annual Radioactive Effluent Release Report
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
ONS-2013-044, Ufsar/Selected Licensee Commitments Change
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
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
NRC 2010-0157, License Amendment Request 261, Supplement 10 Extended Power Uprate
L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008
RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability
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
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
CY-04-072, Annual Radioactive Effluent Report for 2003
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
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.)
ONS-2015-107, Updated Final Safety Analysis Report (Ufsar), Selected Licensee Commitments Change
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-22-056, Constellation Radiological Emergency Plan Addendum Revision
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
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.
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
TSTF-22-03, Transmittal of TSTF-584, Revision 0, Eliminate Automatic RWCU System Isolation on SLC Initiation