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CNS-15-058, Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
Press Release-13-090, NRC to Discuss Cumulative Effects of Regulation, Risk Prioritization in Rockville Nov. 6
Press Release-10-107, NRC Honors Employees June 16 in Rockville MD
PMNS20190213, Public Meeting Regarding Task Interface Agreement Program Enhancement and Low Safety Significance Issue Resolution
PMNS20190537, Meeting Regarding Low Safety Significance Issue Resolution and Task Interface Agreement Program Enhancement
PMNS20190774, Meeting Regarding Low Safety Significance Issue Resolution
PMNS20191153, Meeting with Nuclear Energy Institute and Industry Regarding Task Interface Agreements Revitalization
05000369/LER-1991-014, Requests Delay for Submitting LER 91-014-00 Re Mispositioning of Valves,Causing Containment Spray & RHR Sys Inoperability from 911111 to 911211
PMNS20200372, Public Meeting Regarding Draft NUREG-1409, Backfitting Guidelines, Revision 1
PMNS20200824, Public Webinar with the Nuclear Energy Institute (NEI) and Industry Task Interface Agreement (TIA) Program Enhancement- Discussion of Comments on Updated Draft Guidance
NUREG-1477, Discusses Technical Concerns W/Changes to Draft NUREG-1477 Re Probability of Leakage Curves
PMNS20210141, Notice of Meeting with Nuclear Energy Institute/Industry
PMNS20210014, Notice of Meeting with Nuclear Energy Institute/Industry
PMNS20200903, Risk Informed Process for Exemptions (RIPE) Public Meeting
PMNS20200469, Embark - Public Workshop on the Risk-Informed Process for Exemptions (RIPE)
05000369/LER-1992-008-03, :on 920726,reactor Trip/Turbine Trip Experience as Result of Defective Procedure Due to Technical Deficiency.Changes to Valve 1RC-43 Will Be Evaluated.W/ Undated Ltr
05000370/LER-1991-010, :on 910925,reactor Trip Manually Initiated Upon Receipt of Alarm Panel 2AD-4,annunicator C-4.Caused by Damaged Insulation on Trip Solenoid Coil.Maint Procedure Reviewed to Ensure Precautions Incorporated
05000369/LER-1992-012, :on 921116,determined That RWST Level Transmitter Technically Inoperable Due to Possible Inappropriate Action.Iae Personnel Replaced Tube Plug 1FWLT5000
05000369/LER-1992-011, :on 921210,pressure Switches 2CAPS-5380 & 5381 Found Outside Specified Setpoint Limit Due to Inoperable ESFAS Instrumentation.Subj Switches Recalibr to Correct Values
05000369/LER-1992-010-02, :on 920916,discovered That Containment Structure Mechanical Penetration M-309 Developed Steam Leak on 840720.Caused by Design Deficiency & Equipment Failure. Station Problem Rept Initiated
05000369/LER-1992-012-02, :on 921116,RWST Transmitter Determined to Be Past Inoperable.Caused by Possible Inappropriate Action & Defective Procedure.Suppl Rept Will Be Submitted When Investigation Completed
05000370/LER-1992-010-01, :on 920824,reactor Trip/Turbine Trip Experienced on Overtemp Delta Temp.Caused by Loss of Main Generator Excitation Due to Failed Indicating Lamp in Circuit Breaker.Lamp & Switch Replaced
05000369/LER-1992-009, :on 920625,reactor Trip Occurred,Due to Removal of Solid State Protection Sys Fuse.Caused by Inappropriate Action & Mgt Deficiency.Frequency of Preventive Maint Increased
05000370/LER-1992-008, :on 920522,Valve 2NC-36 Declared Inoperable Because Valve Failed Surveillance Test.On 920603,discovered That Valve 2VI-1753 Closed Due to Unknown Cause.Valve 2VI-1753 Opened
05000370/LER-1992-001-03, :on 920205,Unit 2 Train a Experienced Inadvertent Engineered Safety Features Actuation.Caused by Deficient Procedure.Iae Personnel Visually Inspected Relay
05000370/LER-1991-012, :on 911108,automatic Reactor Trip Initiated Due to Control Rod Failure.Caused by Equipment Failure. Iae Personnel Downloaded Traces of Electronic Circuit Performance
05000369/LER-1992-006-02, :on 920502,Units 1 & 2 Turbine Driven CA Pumps Isolated from Potential Source of Air from Rn Discharge Header & Declared Inoperable.Caused by Design Deficiency. Procedure Changes Made
05000369/LER-1992-004-03, :on 920414,Train 1B ESF Actuation Occurred When Performing Train 1B motor-driven Auxiliary Feedwater Pump Removal from Svc.Caused by Mgt Deficiencies.Alert or Flag Will Be Added to Computerized Program
05000370/LER-1992-006, :on 920409,Unit 2 Experienced a Turbine/Reactor Trip.Caused by Equipment Failure.Personnel Manually Exercised Reactor Trip Breakers
05000370/LER-1992-005-01, :on 920401,noticed That Handle on Isolation Valve for Containment Pressure Control Sys Transmitter Was Not Fully Extended in Open Direction.Cause Not Determined. Transmitter Returned to Operable Status
05000370/LER-1992-003-04, :on 920305,Train B of RHR Sys Declared Inoperable Due to Degraded Flow Path Caused by Equipment Failure.Emergency Work Request Generated to Repair Valve 2KC-82B
05000369/LER-1992-001-02, :on 920116,Unit 1 Shutdown Due to Leakage Increased to 235 Gallons Per Day.Caused by Failure to Remove Steam Generator Tube from Svc.Three Tubes Removed from Steam Generator 2c for Lab Analysis
05000369/LER-1992-005, :from 920226-28,diesel Generator 1A Inoperable Due to Fuel Oil Level in Fuel Oil Storage Tank Below 39,500 Gallons.Caused by Inadequate self-checking by Technicians.Fuel Oil Returned to Tank
05000369/LER-1991-014-02, :on 910930,containment Spray Sys Pump 1A Air Handling Unit Outlet Control Found Mispositioned in Closed Position.From 910904-1004,Train a of Containment Spray Sys Inoperable.Cause Unknown.Valve Opened
05000369/LER-1991-017-01, :on 911016,discovered That Smoke Purge Exhaust Fan Would Not Receive Trip Signal on Diesel Generator Sequencer Actuation.Caused by Design Deficiency. Safety Tag Placed on Control Switch
05000370/LER-1991-009-04, :on 910916,discovered That Auxiliary Bldg Ventilation Return Isolation Valve Not Listed in Procedure from 851216-880531.Possibly Caused by Inappropriate Action. Procedure Changed to Add Valve to Checklist
05000370/LER-1992-002-06, :on 920305,train B Experienced Inadvertent Esfa.Caused by Defective Procedure & Inappropriate Actions. Personnel Counselled & Governing Procedure to Be Revised
05000370/LER-1992-001-04, :on 920205,Unit 2 Train a Experienced Inadvertent Engineered Safety Features Actuation Resulting from Deficient Procedure.Iae Personnel Visually Inspected 50 Relay Targets
05000369/LER-1992-002-02, :on 920117,error Detected in Results from Computer Program Used to Perform Power Distribution Surveillance Calculations.Caused by Design Deficiency. Program Corrected
05000369/LER-1992-001-03, :on 920116,orderly Shutdown Commenced as Result of primary-to-secondary Leakage.Caused by Steam Generator Tube 47-46 Leaking 30 Drops Per Minute at Secondary Side.Data Review Conducted
05000369/LER-1991-018-01, :on 911218,both Trains of Annulus Ventilation Sys Inoperable When Bypass Door Latched Open to Allow Personnel Communication.Caused by Mgt Deficiency Due to Lack of Adequate Policy.Chains/Padlocks Installed
05000370/LER-1991-012-04, :on 911108,shutdown Bank C Control Rods Dropped Into Core as Reactor Operator Attempted to Step Bank in, Resulting in Generation of High Negative Flux Rate Trip. Caused by Equipment Failure.Cards Replaced
05000369/LER-1991-016-01, :on 911024,discovered That 11 Fuel Assemblies Stored in Spent Fuel Pool from 900323 to 911023.Caused by Defective Procedure.Fuel Assemblies Immediately Moved to Positions to Establish Required Vacant Row
05000369/LER-1991-009-01, :During Wk of 910708,hardware Limits for Certain Process Control Equipment in Reactor Protection Sys Exceeded.Caused by Design Deficiency Due to Deficient Documentation.Resistors Changed
05000369/LER-1991-015-01, :on 911013,inadvertent ESF Actuation Occurred When Blackout Signal Sent to Diesel Load Sequencer 1A. Caused by Inappropriate Operator Action.Power Restored to Bus 1ETA & Personnel Reviewed Incident
05000370/LER-1991-011-05, :on 911004,CR Personnel Manually Started Motor Driven Auxiliary Feedwater Pumps.Caused by Defective Procedure.Mgt Will Mod Unit Shutdown Procedures OP/1,2/A/6100/02
05000369/LER-1991-005, :on 910515,both Trains of Annulus Ventilation Sys Were Inoperable Due to Inappropriate Action.Caused by Mgt Deficiencies & Deficient Communication.No Personnel Injuries or Radiation Overexposures Noted
05000369/LER-1991-011-02, :on 910724,fuel Discovered Moved in Fuel Pool While Fuel Handling Exhaust Sys Inoperable.Caused by Inappropriate Actions.Personnel Involved Reviewed Event
05000369/LER-1991-009-02, :During Wk of 910708,discovered That Gain Setting to Average Reactor Coolant Temp Input Would Cause Process Control Equipment to Reach Hardware Limit.Caused by Design Defect.Resistors Changed
05000369/LER-1991-008-01, :on 910514,determined That Diesel Generators Could Be Rendered Inoperable Under Certain Postulated Conditions.Caused by Design Deficiency.Piping Erosion Measurements on Drain Lines Will Be Conducted
05000369/LER-1991-012-01, :on 910823,vital Battery Surveillance Missed. Caused by Inappropriate Actions.Planning & Personnel Will Evaluate Changing Day of Wk Surveillance Performed to Ensure Appropriate Interaction
05000370/LER-1991-004, :on 910422,auxiliary Feedwater turbine-driven Pump Declared Inoperable Due to Erroneous Calibr of Pump Suction Pressure Switches.Caused by Mgt & Design Deficiency.Pressure Switches Recalibr
05000370/LER-1991-006-05, :on 910708,emergency Personnel Hatch Between Upper & Lower Containment Discovered Unlatched W/Tamper Seals Intact.Cause Not Determined.New Tamper Seals Installed & Plan Will Be Developed to Adjust Hatches
05000370/LER-1991-008-04, :on 910814,both Trains of Annulus Ventilation Sys Inoperable When Fire Door Serving as Pressure Boundary Not Posted W/Fire Barrier Tag.Caused by Inappropriate Action & Mgt Deficiency.Tagging Modified
05000370/LER-1991-010-04, :on 910925,reactor Manually Tripped.Caused by Possible Design,Mfg,Const/Installation Deficiency.Insp of Surplus Solenoids to Ensure Serviceable Condition of Insulation Conducted
05000370/LER-1991-004-05, :on 910422,auxiliary Feedwater Turbine Driven Pump Declared Inoperable.Caused by Mgt & Design Deficiency. Associated Pressure Switches Subsequently Calibr Under Work Request 6010141AE
05000370/LER-1991-003-06, :on 910606,inadvertent Unit 2 Train B ESF Actuation Occurred.Caused by Inappropriate Action & Mgt Deficiencies.Appropriate Procedure Changes Implemented
05000370/LER-1991-005-05, :on 910628,ESFA Occurred.Caused by Inappropriate Action Due to Lack of Attention to Detail. Operations Mgt Will Review Event W/Appropriate Personnel.W/
05000370/LER-1991-002-06, :on 910515,unit 2 Turbine Driven Auxiliary Feedwater Pump Declared Inoperable Because of Mispositioned Sliding Link.Caused by Possible Inappropriate Action.Event Reviewed W/Instrument & Electrical Personnel
05000369/LER-1991-005-03, :on 910515,both Trains of Annulus Ventilation Sys Declared Inoperable Due to Inappropriate Action.Caused by Mgt Deficiencies & Deficient Communication.Meeting Held Between Mnt Paint Craft Personnel
05000369/LER-1991-007-02, :on 910519,Train B of RHR Sys Inoperable for More than 72 H W/O Knowledge of Operations Control Room Personnel.Caused by Inappropriate Personnel Actions & Installation Deficiency.Work Request Written
05000369/LER-1991-008, :on 910514,concern Raised by Insp Member That, Under Certain Postulated Conditions,Diesel Generators Could Be Rendered Inoperable.Caused by Design Deficiency.Piping on Main Steam Drain Lines Upgraded
05000370/LER-1991-001-06, :on 910311,failure to Comply W/Esf Actuation Sys Instrumentation Tech Spec.Caused by Inappropriate Action & Defective Procedure.Event Reviewed,Procedural Compliance Reemphasized & Station Mgt Notified of Event
05000369/LER-1991-006, :on 910215,containment Air Return & Hydrogen Skimmer Sys Declared Inoperable.Caused by Design Deficiency. to Procedures Revised to Exclude Hydrogen Skimmer Fans & Dampers
05000369/LER-1991-004-01, :on 910219,reactor Trip Occurred Due to Manual Opening of Reactor Trip Breaker.Caused by Mgt Deficiency & Possible Inappropriate Action.Emergency Procedure EP/1/A/5000/01 Implemented
05000369/LER-1991-001-04, :on 910211,reactor Trip Occurred.Caused by Loss of Offsite Power Causing Inappropriate Action,Management Deficiency & Equipment Failure.Emergency Shutdown & Offsite Power Restored
05000369/LER-1990-023, :on 900821,both Trains of Control Room Ventilation Sys Inoperable During Mod & Functional Testing. Caused by Sheared Off Detensioning Bolts on Air Handling Unit Motor Base.Train a Redesigned
05000369/LER-1990-033, :on 901206,operations Personnel Unable to Verify Readings from Power Range Detectors to Thermal Power Best Estimate Value,Per Tech Spec 4.3.1.1.(2).Caused by Procedure Deficiencies.Solder Repaired
05000369/LER-1990-034, :on 901206,both Trains of Control Area Ventilation Sys Declared Inoperable to Change Out Filters. Cause Not Stated.Personnel Access Door Reclosed
05000369/LER-1990-026, :on 901012,removal of Emergency Air Penetration Access Plate Rendered Annulus Ventilation Sys Inoperable. Caused by Design Deficiency.Mods Submitted to Prevent Recurrence
05000369/LER-1990-024, :on 900822,Train a Air Handling Unit Fan Housing Damaged Causing Unfiltered Air Inleakage to Occur. Cause Unknown.Personnel to Investigate Probable Failure or Deficiency
05000369/LER-1990-030, :on 901110,normal Power Supply to Shared Motor Ctr Smxr Tripped.Caused by Inadequate Group Interface. Operations Personnel Shut Down Waste Handling Area Ventilation Sys & Breaker Reset
05000369/LER-1990-035, :on 901101,loop Seal Piping to Each of Facility Pressurizer Code Safety Valves Insulated in Error.Possibly Caused by Mgt Deficiency or Inappropriate Action.Insulation Removed & Personnel Will Be Counseled
05000369/LER-1990-029-01, :on 901109,potential for Loss of RHR Train Discovered.Caused by Design Deficiency Re One Pump W/ Stronger Developed Head to Cause Weaker Parallel Pump to Deadhead & Fail.Caution Added to Procedure
05000369/LER-1990-030-01, :on 901110,Tech Spec Surveillance Requirement Missed Resulting in Potential Unmonitored Release from Contaminated Parts Warehouse Ventilation Sys
05000369/LER-1990-016-01, :on 901030,control Room Ventilation Sys Declared Inoperable Due to Improper Installation
05000369/LER-1990-032, :on 901117,unit Experienced Turbine Trip, Followed by Reactor Trip.Cause Unknown.Control Room Personnel Initiated Turbine Exhaust Hood Spray
05000369/LER-1990-031, :on 901116,train B of Control Room Ventilation Sys Declared Inoperable While Train a Inoperable for Sys Alignments.Caused by Differential Pressure Switch Not Sensing Flow.Switch Replaced
05000369/LER-1990-028-01, :on 901023,ice Basket U-bolts Found Damaged or Missing Due to Matl Deficiency
05000370/LER-1993-001-02, :on 930222,discovered That SG C Feedwater Flow Low & Decreasing Even Though Controller Output Increasing, Resulting in Manual Reactor Trip.Caused by Equipment Failure.All Pneumatic Relays Replaced
05000369/LER-1993-002-01, :on 930216,discovered Portion of Containment Spray Sys Channels Between Process Instrumentation & ESF Actuation Logic Improperly Tested.Caused by Deficient Written Communications.Procedures Changed
05000369/LER-1991-003-02, :on 910219,both Trains of Control Room Ventilation Sys Inoperable.Caused by Design Malfunction & Management Deficiency.Temporary Modifications,Removing Automatic Closure Function Implemented
CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (MUR) Power Uprate
SECY-20-0021, Enclosure 2 - Federal Register Notice to Solicit Public Comments on Draft NUREG-1409, Backfitting Guidelines, Revision 1
05000369/LER-1992-007, :on 920506,ESF Actuation Occurred While Control Room Personnel Performing Wet Layup Evolution on SG 1D. Caused by Defective Procedure & Inappropriate Personnel Action.Procedure Revised
05000370/LER-1992-004-02, :on 920321,reactor Trip Occurred as Result of Hi Hi SG Level on SG 2C.Caused by Equipment Failure & Possible Installation Deficiency.Work Request 146995 Initiated to Investigate & Repair Problem
05000369/LER-1991-013-01, :on 910920,both Trains of Annulus Ventilation Sys Declared Inoperable.Caused by Mgt Deficiency & Inappropriate Actions.Guidelines for Control of Ventilation Sys Will Be Developed
05000370/LER-1990-008-04, :on 901227,during Rod Movement Testing Shutdown Bank E Fell Into Core.Manual Reactor Trip Initiated.Caused by Possible Equipment Failure.Technical Review Performed. Reactor Restarted
DT-19-15, Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests