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 Issue dateTitleTopic
05000311/LER-1990-0269 July 1990LER 90-026-00:on 900609,radiation Monitoring Sys Channel 2R12B Failed Low.Caused by Design/Equipment Concerns.Failed Components Replaced & Pins Connecting Backplane Replaced W/Longer pins.W/900709 Ltr
05000311/LER-1990-02717 July 1990LER 90-027-00:on 900628,determined That ESF Signal Actuation 2R41C Channel Failed Low Due to 2R45 Interlock.Caused by Design/Equipment Concerns.Engineering Investigated Concerns & Uninterruptable Power Sys installed.W/900717 Ltr
05000311/LER-1990-03024 July 1990LER 90-030-00:on 900703,ESF Actuation Containment Purge/ Pressure Vacuum Relief Sys Isolation Occurred After Channel Function Not Placed in Block.Caused by Personnel Error. Individuals Involved Held accountable.W/900724 Ltr
05000354/LER-1988-022, Special Rept 88-006-00:on 880826,HPCI Injection Occurred. Caused by Low Reactor Vessel Level Signal Following Reactor Scram Described in LER 88-022-00.HPCI Injection Nozzle Usage Factor Not Calculated21 November 1988Special Rept 88-006-00:on 880826,HPCI Injection Occurred. Caused by Low Reactor Vessel Level Signal Following Reactor Scram Described in LER 88-022-00.HPCI Injection Nozzle Usage Factor Not Calculated
05000354/LER-1990-0085 July 1990LER 90-008-00:on 900604,reactor Bldg Exhaust Radiation Monitor Trip Setpoint Found Nonconservatively High.Caused by Personnel Error.Technicians Disciplined,Rept Reviewed W/All Personnel & Setpoint Included in procedure.W/900705 Ltr
05000354/LER-1990-0095 July 1990LER 90-009-00:on 900607,HPCI Sys Oil Samples Indicated High Water Content & Traces of Sediment Contamination.Caused by Design Deficiency in HPCI Turbine Lube Oil Reservoir. Reservoir Cleaned,Flushed & Wiped down.W/900705 Ltr
FVY-86-105, Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl10 November 1986Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl
IA-84-843, Safety Evaluation Supporting Amend 25 to License DPR-7530 August 1984Safety Evaluation Supporting Amend 25 to License DPR-75Fire Barrier
Nondestructive Examination
Liquid penetrant
IR 05000311/197901910 November 1979Updated LER 79-054/01X-1:on 790824,three Snubbers on Main Feedwater 14 During Refueling Outage Per Followup to NRC Insp Rept 50-311/79-19.Caused by Extreme Shock Load.Snubbers Replaced
LR-N966376, Monthly Operating Rept for Oct 1996 for Hope Creek Generation Station Unit 131 October 1996Monthly Operating Rept for Oct 1996 for Hope Creek Generation Station Unit 1Safe Shutdown
Temporary Modification
Fuel cladding
LR-N970110, Monthly Operating Rept for Jan 1997 for Hope Creek Generation Station Unit 131 January 1997Monthly Operating Rept for Jan 1997 for Hope Creek Generation Station Unit 1Safe Shutdown
Offsite Dose Calculation Manual
Tornado Missile
Temporary Modification
Tornado Generated Missile
Fuel cladding
Through Wall Leak
LR-N970247, Special Rept 97-01:on 970317,test Failure of 1D-G-400, D Edg.Caused by Failed Emergency Start Preset Relay. Relay Was Immediately Replaced & Retest of D EDG Was Satisfactory14 April 1997Special Rept 97-01:on 970317,test Failure of 1D-G-400, D Edg.Caused by Failed Emergency Start Preset Relay. Relay Was Immediately Replaced & Retest of D EDG Was Satisfactory
LR-N970321, Monthly Operating Rept for Apr 1997 for Hope Creek Generating Station30 April 1997Monthly Operating Rept for Apr 1997 for Hope Creek Generating StationSafe Shutdown
Safety Limit Minimum Critical Power Ratio
Temporary Modification
LR-N970503, Monthly Operating Rept for Jul 1997 for Hope Creek Generating Plant Unit 131 July 1997Monthly Operating Rept for Jul 1997 for Hope Creek Generating Plant Unit 1Safe Shutdown
Safety Limit Minimum Critical Power Ratio
Ultimate heat sink
Safe Shutdown Earthquake
Temporary Modification
Coast down
LR-N970515, Special Rept 97-03:on 970808,TS Actions Statements 3.3.7.5 & 3.3.7.11 Were Entered Due to Inoperability of SPV Radiation Monitoring Sys.Caused by Failure of Low Range Detector pre- amplifier.Pre-amplifier Was Replaced22 August 1997Special Rept 97-03:on 970808,TS Actions Statements 3.3.7.5 & 3.3.7.11 Were Entered Due to Inoperability of SPV Radiation Monitoring Sys.Caused by Failure of Low Range Detector pre- amplifier.Pre-amplifier Was Replaced
LR-N980104, Monthly Operating Rept for Feb 1998 for Hope Creek Generating Station,Unit 128 February 1998Monthly Operating Rept for Feb 1998 for Hope Creek Generating Station,Unit 1Safe Shutdown
Temporary Modification
LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 131 March 1998Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1
LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 130 April 1998Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1Safe Shutdown
Temporary Modification
LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 131 May 1998Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1
LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 130 June 1998Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1Safe Shutdown
Temporary Modification
LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 131 July 1998Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1Safe Shutdown
Temporary Modification
LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With31 August 1998Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With
LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With30 September 1998Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.WithSafe Shutdown
Temporary Modification
LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with31 October 1998Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. withSafe Shutdown
Temporary Modification
LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With30 November 1998Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.WithSafe Shutdown
Temporary Modification
LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced12 April 1999Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced
ML17264A93810 July 1997Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process
ML17346B35511 March 1986LER 86-004-00:on 860209,required Plant Vent Sampling Not Performed.Caused by Inadequate Means of Scheduling Samples Required by Radiological Eis.Training Programs Updated. W/860311 Ltr
ML17348B49331 July 1990Monthly Operating Rept for Jul 1990 for Salem 2.W/900815 LtrBoric Acid
ML17354B0979 September 1998Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils
ML18038A8977 September 1994Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures
ML18078A2273 October 1978LER#78-062/03L-0 on 780913:during Normal Oper the #12 Reactor Coolant Flow Channel 2 Was Not Indicating Due to Failure of a Hagan Controls Signal Isolator
ML18078A2343 October 1978LER#78-064/03L-0 on 780912:reactor Trip Setpoint Greater than T/S Limit During Check of Pressure Protec Channel 2. Caused by Unstable Output from Comparator Feeding Trip Bistable.Comparator Replaced
ML18078A24410 October 1978Monthly Operating Rept for Sept 1978
ML18078A31923 October 1978RO 78-70/01P:on 781021,reactor Coolant Pump 13 Shaft Seals Failed,Resulting in Excessive Leakage of Primary Coolant Into Containment.Detailed Rept Will Follow
ML18078A32124 October 1978Confirms 781024 Verbal Rept of Ro.Low Pressure in Control Air Sys Caused Operation of Air Operated Deluge Valves, Necessitating Operation of Fire Pumps in Manual Mode.Ler Will Follow
ML18078A32626 October 1978LER 78-067/03L-0:on 780929,missing Fire Barrier in Cable Penetration Identified.Caused by Failure to Ensure Fire Barrier Installation.Cable Penetration Immediately Sealed. Other Barriers Will Be Inspected by 781101Fire Barrier
Continuous fire watch
Fire Watch
ML18078A3472 November 1978LER 78-070/01T-0:on 781021,during Mode 4 Operation,While Heating Up to Enter Mode 3,high Flow Through RCP Seals Noted & Alarms Went Off Indicating RCS Leakage.Cause UnknownPressure Boundary Leakage
ML18078A3501 November 1978LER 78-071/01T-0:on 781023:during Mode 5,fire Pumps 1 & 2 Put in Manual Due to Low Air Pressure Causing Actuation of air-operated Deluge Valves.Station Air Compressors Could Not Be Started Due to Low Cooling Water FlowFire Watch
ML18078A3532 November 1978LER 78-069/03L-0:on 781011,while Investigating Diesel 1B Alarm,Heater Leaking Chromated Water Into pre-lube Pump Motor Discovered.Caused by Corrosion of Element Sheath in Two of Three Heater Elements
ML18078A37623 October 1978RO 78-70/01P:on 781021,#13 Reactor Coolant Pump Shaft Seals Failed,Resulting in Excessive Leakage of Primary Coolant Into Container.Detailed RO Rept Will Be Submitted
ML18078A3899 November 1978Monthly Oper Rept for Oct 1978
ML18078A39914 November 1978LER#78-043/03L-1 on 780808:as Reactor Pwr Was Increased a Deviation Alarm Would Not Clear & a Qpt Calculation Showed a QPTR of 1.03%.Due to Large Load Reduction.Design Change Will Delete the Less than 50% Pwr Alarm
ML18078A41220 November 1978LER#78-072/01T-0 on 781106:during Mode 5 Oper,All Containment Fan Coil Units Were Found Inoper Due to Tripped Svc Water Valves,Caused by Design Deficiency in Detector Installation
ML18078A41520 November 1978Answers NRC Questions 5.62,5.63,5.82,5.83,5.84 & 5.85 Re Analyses of Main Steam Lines Break within Containment of Unisolated Steam in Main Steam Line & Turbine Plant
ML18078A45222 November 1978LER#78-043/03L-0 on 780808:during Normal Oper,After 45% Pwr Reduction to Less than 50% for Maint,Reactor Pwr Increased to 51%.Deviation Alarm Would Not Clear & QPTR Was 1.03%.QPTR Was Not Discovered Sooner Because of Alarm Indications
ML18078A4919 November 1978Monthly Rept Oct 1978
ML18078A49711 December 1978LER#78-073/01T-0 on 781127:1B Vital Instru Bus Was Lost Causing Reactor Trip.Safety Injection Followed & 1B Diesel #11 Charging & #12 RHR Pumps Failed to Start.Caused by Bad Output Transformer in Supply Inverter
ML18078A50311 December 1978Monthly Oper Rept for Nov 1978Packing leak
ML18078A53118 December 1978LER#78-075/03L on 781130:during Oper W/Containment Entry in Progress,Inner Door of Air Lock 130 Would Not Fully Open, Caused by Failed Cam Roller on Inner Door Operating Mechanism.Air Lock Repaired,Tested,Returned to Svc
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