RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report
SBK-L-16071, Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 0
HBL-16-007, Annual Radiological Environmental Monitoring Report for 2015
Information Notice 1989-03, Potential Electrical Equipment Problems
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E)
NG-10-0265, Duane Arnold, 2009 Annual Radiological Material Release Report
ST-HL-AE-5641, 1996 Envrion Rept:Annual Environ & Annual Radiological Environ Operating Repts
IA-87-732, Package of Abstract of Offers from Solicitation RS-ASB-87-342 in Response to FOIA Request
L-09-100, Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept
U-601120, Responds to NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs. Attachments Provide Info Re Util Program for Verification of Chemical & Mechanical Quality of Fasteners Used at Plant
HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2
AECM-85-0028, Responds to Requesting Addl Info on Seismic Analysis Performed for Deeply Embedded Standby Svc Water Cooling Tower Basin.Details on Principles & Techniques Used in Seismic Analysis Provided
DCL-90-253, Forwards Change 3 to Rev 17 to Physical Security Plan.Change Withheld (Ref 10CFR73.21)
TXX-4232, Forwards Response to Findings in Section IV of BNL Interim Rept on Protective Coatings,Per NRC .No Safety Concerns W/Protective Coatings at Facility.Backfit Program Properly Conceived & Implemented
05000285/LER-1988-038, :on 881231,ESF Actuation Occurred W/Technician Working on Mod to Pressurizer Level Instrumentation Behind Control Panels CB-1/2/3.Affected Sys Returned to Svc & Containment Purge Restarted
05000366/LER-1986-021-01, :on 860828,reactor Protection Sys Motor Generator Set C Cabinet Output Breaker Tripped,Causing Loss of Power to Bus A.Caused by Failed Limit Switch Assembly. Limit Switch Assembly & Torque Switch Replaced
05000219/LER-1985-005-02, :on 850210,during Routine Surveillance Testing, Isolation Condenser Pipe Break Sensors IB05A1,IB05B1,IB11A1, IB11B1 & IB11B2 Tripped at Values Greater than Tech Specs. Caused by Instrument Drift.Sensors Reset
05000333/LER-1987-007, :on 870409,during Pipe Support Program Insp, Reactor Vessel Head Vent Piping Found Inoperable & Pipe Anchor Installed But Not Welded to Piping Per Plant Drawings.Caused by Const Personnel Error
05000219/LER-1986-033, :on 861221,reactor Bldg Ventilation Isolated & Standby Gas Treatment Sys Initiated When Area Radiation Monitor Trip Unit Inadvertently Grounded During Maint.Caused by Personnel Error.Pinched Cable Replaced
05000213/LER-1986-029, :on 860617,MSIV Failed to Meet Surveillance Procedure Acceptance Criteria.Caused by Inadequate Initial Design of MSIV Accumulator.Accumulator Will Be Upgraded to Ensure safety-related Operability
VPN-027-99, Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2
05000483/LER-1985-046, :on 850928,Tech Spec Leak Rate Surveillances for Containment Personnel & Emergency Access Air Locks Not Performed on Due Dates of 850928 & 1005,respectively. Surveillances Completed on 851011
05000461/LER-1986-016, :on 861021,core Alterations Authorized to Begin W/Standby Gas Treatment Sys Inoperable,Violating Tech Specs. Caused by Failure of Operator to Review Operating Conditions.Personnel Counseled,
05000244/LER-1985-019, :on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily
05000352/LER-1988-005, :on 880219,determined One of Four Reactpr Coolant Leakage Monitoring Sys Inoperable in Violation of Tech Spec 3.4.3.1.Investigation Continuing.Wiring Restored to as-built Condition & Sys Declared Operable
05000317/LER-1985-013, :on 851009,unidentified RCS Leakage Determined to Be Greater than 1.0 Gpm.Caused by Cracked Weld Between Reactor Coolant Pump Shaft Seal & Control Bleedoff Line.Line & Flanges Replaced.Design Mod Implemented
05000366/LER-1985-028, :on 850809,12 & 22,surveillance Requirements Including Drywell high-range Radiation Recorder Calibr Not Satisfied.Caused by Not Incorporating Tech Specs Amends Into Procedures.Review Initiated
05000416/LER-1985-028, :on 850717,diesel Generator Tripped.Plant Shutdown Initiated.Caused by Failed Generator Bearing. Bearing Replaced.Generator Returned to Svc Prior to Required Shutdown
05000331/LER-1985-034, :on 850709,reactor Protection Sys a Tripped During Reenergization of Sys B.Caused by Operational Amplifiers Saturating When First Energized.Amplifiers Replaced
05000483/LER-1985-022, :on 850410,output Breaker for Motor Generator Set 2 Tripped Open Causing Shutdown Banks to Drop.Reactor Trip Breakers Manually Opened.Caused by Exciter Overcurrent Condition W/Bus Overvoltage Condition
05000305/LER-1984-018, :on 840928,investigation of Fan Coil Units W/Less than Design Air Flow Revealed Svc Water Side of Cooling Coils Partially Plugged W/Silt.Caused by Equipment Deficiencies.Fan Coil Units Cleaned
05000373/LER-1985-009, :on 850122,no Assigned Calibr or Functional Test Procedure for Calibr RHR Shutdown Cooling Suction Pressure Switch.Caused by Improper Identification on Tech Spec Surveillance Matrix.Procedure Drafted
05000324/LER-1984-014-01, :on 841127,while Attempting to Establish Shutdown Cooling on 100pA of RHR Sys,Water Hammer Event Damaging Supports on Steam Condensing Line Occurred.Caused by Mispositioning of Output Jack
05000397/LER-1984-108, :on 841006,licensed Operator Placed Reactor Mode Switch in Run Mode.Procedure Performed Out of Sequence, Prior to Ensuring Pressure at Rated Conditions.Operators Briefed on Procedures
05000255/LER-1984-027, :on 841122 & 1204,charging Pump Could Not Be Started from Control Room or W/Local Start Button.Caused by Closing Coil Failure in Breaker.Breakers Will Be Included in Preventive Maint Program
05000255/LER-1984-019, :on 840908,overspeeding Auxiliary Feedwater Pump P-8B Discovered.Caused by Failed Mechanical Governor Bearing Assembly & Bent Spindle on Pump Turbine Drive. Damaged Parts Replaced
05000325/LER-1985-001, :on 850103,calibr of Reactor Vessel Shroud Level Instruments 1(2)-B21-LTM-N036-1 & N037-1,did Not Meet Design Intent.Caused by Inconsistency in Data Sheets. Instruments Properly Calibr
2CAN029606, Forwards 1995 Primary Coolant I-131 Dose Equivalent Activity Rept,Providing Results of Activity Analysis in Which Primary Coolant Exceeded Limits of TS 3.4.8 on 950107 & 0901
05000483/LER-1985-014, :on 850227,control Room Ventilation Isolation Signal Occurred.Cause Undetermined.Incident Considered Isolated Event W/No Further Corrective Action Required
05000263/LER-1984-030, :on 841009,EFT Sys Transferred to Emergency Mode When Ammonia & Hydrogen Chloride Monitor Tape Cassettes Ran Out,Resulting in Spurious Trip of Monitors. Replacement Schedule Revised
05000254/LER-1984-014-04, :on 840808,while Starting Shutdown Cooling Mode of RHR Sys,Lpci Valves 1-1001-29A & B Would Not Open. Caused by Personnel Error.Valve Stems Removed & Being Replaced
05000374/LER-1984-007-02, :on 840218,reactor Water Cleanup Isolated on Pump Room a High Differential Temp.Caused by Difference in Room Temp Due to Misconfiguration of Area Ventilation Sys. Review for Corrective Actions in Progress
05000315/LER-1983-031-03, /03L-0:on 830407,while Attempting to Exit Upper Containment,Outer Door of Personnel Airlock Would Not Open. Caused by Interlock Cable Being Out of Adjustment.Cable Replaced
PY-CEI-NRR-1417, Suppls 900717 & 1221 Responses to NRC Bulletin 90-001. Potential Loss of Fill-Oil in Rosemount Transmitters
05000259/LER-1980-072-03, /03L-0:on 800924,during Normal Operation,Rhr Torus Return Valve FCV-74-71 Was Found to Be Inoperable.Caused by Grounded Operator Motor Which Caused Breaker to Trip.Motor Replaced
05000321/LER-1978-076-03, /03L-0:on 780915,refueling Vent Exhaust Sensor Gave False,High & Erratic Indication While at 99% Power. Caused by Failure of G-M Tube.Tube Replaced
ET-NRC-93-3886, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 930126,0218,0312 & 0413 Ltrs.Westinghouse Responses to Remainder of Requests for Addl Info Contained in Will Be Provided Prior to 930529
05000267/LER-1980-001-03, /03X-1:on 800108,leak Found on 1B Helium Circulator Static Seal Internal to Circulator.Caused by Mfg Defect That Acted as Stress Riser & Caused Cyclic Failure of Bellows Matl.Circulator Replaced
ULNRC-02964, Submits Actions Taken to Comply W/Gl 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Note That Attachment Represents Licensee MOV Program to Date
05000348/LER-1981-069-03, /03L-0:on 810929,charging Pump 1B Determined Electronically Aligned to Bus W/No Available Emergency Power Supply & Declared Inoperable.Caused by Personnel Error When Pump Aligned to Wrong Train.Personnel Trained
05000293/LER-1989-036, :on 891122,determined That HPCI Sys Inoperable Due to Inoperable Gland Seal Condenser Blower Motor.Caused by age-related Wear of Motor.Blower Motor Replaced & Blower Tested W/Satisfactory Results
05000348/LER-1981-034-03, /03L-0:on 810509,train a Refueling Water Storage Tank Level Indicator Failed Low.Cause Undetermined. Investigation Underway.Problem Has Not Recurred
05000285/LER-1980-019-03, /03L-0:on 800904,seismic Pipe Restraints SIS-62 & SIS-7 Were Inadvertently Made Inoperable at Same Time. Restraints Were Being Upgraded in Response to IE Bulletin 79-14.Restraint SIS-7 Was Immediately Made Operable
05000336/LER-1980-029-03, /03L-0:on 800812,during Surveillance Test on 12 U diesel,125 Vdc Ground Alarm Received.Caused by Frayed Insulation on Wire in Bendix Connector Allowing Contact Between Bare Wire & Connector Shell.Wire Recovered
05000346/LER-1977-086-03, /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr
05000245/LER-1979-006-03, /03L-0 on 790201:unit Operated in Degraded Mode Due to Deficient Control Rods.Caused by Personnel Oversight. Rods Were Made Operable & Tech Spec Change Submitted
05000338/LER-1979-081-03, /03L-0 on 790608:individual Rod Position Indicators M-10 & D-10 Placed in Test Status,Contrary to Tech Specs.Caused by Repair Work to Remove Previously Installed Jumper.Calibr Performed
05000317/LER-1979-065-03, /03L-0:on 791113,diesel Generator 12 Taken Out of Svc to Inspect & Correct Governor Operation.Caused by Sludge Deposits in Governor Assembly.Governor Cleaned
L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8
2CAN070402, License Amendment Request to Support Cycle 18 Core Reload Arkansas Nuclear One, Unit 2
05000285/LER-1985-003, :on 850321,ventilation Isolation Actuation Signals Occurred.Caused by Increasing Activity Levels as Monitored by Vent Stack Particulate Monitor RM-061.Ion Exchanger Isolated,Decreasing Activity Levels
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
BSEP-98-0090, Provides Comments on Draft SE Re Conversion to Improved Tech Specs.Encl 2 Provides Draft SE pages,marked-up to Reflect Comments as Well as Addl Editorial Comments
05000416/LER-1986-020, :on 860603,discovered That Nonqualified Relay Could Cause Loss of Standby Gas Treatment Sys Safety Function During Accidents.Caused by Approved Design.Circuit Design Will Be Modified to Bypass Fan Contact
05000346/LER-1984-006, :on 840515,unidentified RCS Leakage in Excess of 1 Gpm.Caused by Failure to Perform Surveilance Test on Reactor Protection Sys Shutdown Bypass Channels.Line Permitted to Depressurize Prior to Maint
05000362/LER-1983-016-03, /03L-0:on 830207,plant Tour Revealed Failed Temporary Instrument Line on Auxiliary Feedwater Pump Turbine Stop Valve 3HV-4716.Cause Not Stated.Line Replaced & Pump Declared Operable.Investigation Continuing