05000443/LER-2002-001-01, Reactor Trip Due to Digital Rod Position Indication Card Failure
LR-N09-0164, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items
HNP-07-178, Shearon Harris, Submittal of Information in Support of NFPA 805 Pilot Observation Reviews
SBK-L-18094, License Amendment Request 18-02, Application to Revise the Technical Specifications Associated with Movable Control Rods
05000346/LER-1979-116-03, /03L-0:on 791123,Control Rod Group 5 Rod 11 Absolute Position Indication Declared Inoperable.Caused by Position Indication Assembly & Cabling Between Electrical Penetration & Rod.Investigation Continues
05000336/LER-1979-031-03, /03L-0:on 790930,control Element Assembly Motion Inhibit Circuit Declared Inoperable Following Loss of Metrascope Indication of Control Element Assembly Position. Caused by Metrascope Component Failure
LR-N03-0533, Revised Core Operating Limits Report, Cycle 12
LR-N03-0250, Core Operating Limits Report - Cycle 12
RBG-28910, Application for Amend to License NPF-47,revising Tech Specs 3.0.4,4.0.3 & 4.0.4 Re Applicability of Limiting Conditions for Operations & Surveillance Requirements Per Generic Ltr 87-09.Fee Paid
3F0292-11, Application for Amend to License DPR-72,appendix a W/Changes to TS 3.1.3.3,4.1.3.3 & Bases 3/4.1.3 W/Revised Operability Requirements for Control Rod Reed Switch or API Channels. Licensee Requests Approval Before Jun 1992 Refuel 8
2CAN049504, Application for Amend to License NPF-6,deleting Requirement Associated W/Part Length CEAs (Plceas) from TS & Replacing Plceas W/Full Length,Full Strength CEAs
B15159, Proposed Tech Spec 3.10.5,allowing More than One Control Bank to Be Fully Withdrawn from Core Simultaneously for Rod Drop Time Response Testing
BSEP-94-0355, Forwards Response to NRC Request for Info During Telcons W/ Util Re 930125 CRD Scram Accumulator Lar.Ref Noted in 930125 Basis for Amend Request (NEDE-14584, Assurance of Acceptable Scram Through CRD Speed Analysis) Also Encl
PY-CEI-NRR-1381, Application for Amend to License NPF-48,changing Tech Spec 3.1.3.3, Control Rod Scram Accumulators to Allow Alternate Method for Determining Whether CRD Pump Operating
3F1191-08, Responds to NRC Re Violations Noted in Insp Rept 50-302/90-18.Corrective actions:PM-126, Electrical Checks of CRD Power Train Performed Correctly on 910905
BSEP-93-0219, Forwards Response to NRC 930826 RAI Re 930125 License Amend Concerning Control Rod Operability.Response Includes Info Discussed in 931123 Telcon W/Nrc
05000424/LER-1987-038, :on 870620 & 25,shutdown Rod Banks Partially Withdrawn & Reactor Manually Tripped After Receipt of RPI Urgent Alarm Annunciator.Caused by Detector/Encoder Card Failure.Card Replaced
05000339/LER-1998-001-02, :on 980405,manual Reactor Trip Was Declared Inoperable Due to Control Bank B Group Step Counter.Caused by Malfunction of Mechanical Drive.Ts Action Statement 3.1.3.3 Initiated
05000338/LER-1986-018-01, :on 860915,w/unit in Hot Shutdown,Reactor Trip Breakers Opened When Individual Rod Position Indicators Determined Inoperable.Caused by Failed Transformer on Firing Card.Firing Card Replaced
05000413/LER-1987-016, :on 870409,urgent Failure Alarm & rod-bottom Alarm for Rod D-14 Received on Digital RPI Sys.Caused by Failure in Data Channel a of Digital RPI Sys for Rod D-14. Work Request Initiated
05000400/LER-1987-001, :on 870111,alarm Received Indicating That Data B Inputs Failed on Rod Withdrawn from Core.Caused by Mfg Deficiency Leading to Unreliable Rod Position Info.Reactor Trip Breakers Opened
05000302/LER-1986-011, :on 860722,control Rod Rendered Inoperable When Electricians Replaced Three Relays That Transfer Rod Position Indication Between Absolute & Relative.Tech Specs Voluntarily Entered Due to Planned Maint
05000413/LER-1997-010-02, :on 971229,reactor Trip Breakers Opened Due to Uncertainty of Rod Position.Caused by Failure of Detector/ Encoder Card in Data a Cabinet of Drpi Sys.Replaced Failed Detector/Encoder Card W/New Card
05000328/LER-1988-013-01, :on 880316 & 17,rod Control Sys Deficiencies Caused Inaccuracies in Rod Group Demand Position Indication Resulting in Manual Reactor Trips.Caused by Demand Step Counter Circuitry Failure & Internal Binding
05000423/LER-1988-007, :on 880203,manual Reactor Trip Initiated Due to Inoperable Digital Rpi.Caused by Equipment Failure.Display Card for Rod N-11 Warped Resulting in Pins on Card to Contact Adjacent Card.Display Card Replaced
05000387/LER-1984-044, :on 840613,average Rod Scram Insertion Time Required by Tech Spec 3.1.3.4 Not Met for All Rods. Apparently Caused by Poor Control Rod Scram Pilot Valve Performance.Valves Modified
05000455/LER-1996-004-01, :on 960922,declared Source Range Detectors Inoperable W/Reactor Trip Breakers Closed.Caused by Poor Communications at Shift Turnover.Placed Source Range N32 Level Trip Switch Position to Normal
05000370/LER-1985-021-02, :on 850729,control Board Position Indication Lost for Shutdown Bank E,Rod D-8 & Reactor Manually Tripped as Specified by Tech Specs.Caused by Data a Encoder Card Failure.Card Replaced
05000455/LER-1996-004-09, :on 960922,source Range Detector Had Been Placed in Bypass as Result of Spurious Radio Noise Induced Spiking.Caused by Poor Communications.Operators Will Receive Training on TS 3.3.1
05000325/LER-1996-002-01, :on 960123,main Turbine Bearings Experienced Increasing Vibration.Caused by Diaphragm Packing Rubbing on Monoblock Turbine Rotors.Addl Monitoring Equipment Installed to Monitor Main Turbine Performance
05000324/LER-1996-001, :on 960202,planned Reactor Manual Scram Inserted to Support Start of Unit 2 B212R1 Refueling Outage. Caused by Accelerated Aging.New Assembilies Replaced & Increased Frequency of Monitoring Performance
05000325/LER-1996-002, :on 960123,manual Reactor Scram Occurred Due to Main Turbine Vibration.Caused by Rubs in the Lpt Diaphram & Shaft Packing.Addl Vibration Monitoring Equipment Installed
05000440/LER-1990-036, :on 901207,control Rod Scram Accumulator Level Switch Inoperable Throughout Second Fuel Cycle in Violation of Tech Spec 3.1.3.3.Caused by Unidentified Sys Interaction. Sys Operating Instruction Revised
05000369/LER-1984-015, :on 840426,during Performance of Rod Control Cluster Assembly Drop Timing,Rod B-12 Failed to Indicate Correct Position.Caused by Defective Detector/Encoder Card. Card Replaced & Drop Timing Completed
05000316/LER-1983-106-03, /03L-0:on 831105,analog Rod B-6 Control Bank B Pegged Low,W/Control Bank B Withdrawn to 228 Steps.Caused by Female Pins Pulling Back from Male Pins at Disconnector. Cable Repositioned to Eliminate Strain on Connector
05000346/LER-1983-054-03, /03L-0:on 830930,discovered Group 8 Relative Position Indication Did Not Respond to Rod Pull & Differed from Absolute Position Indication.Caused by Failure of Group 8 Motor Programmer Phase a
05000370/LER-1984-006, :on 840203,digital RPI Sys Failed,Resulting in Manual Reactor Trip.Caused by Failure of Central Control Card & Display Card.Cards Replaced
05000416/LER-1983-118-03, /03L-0:on 830925,scram Accumulator Trouble Annunciator Alarmed When Nitrogen Pressure in Accumulator 08-25 Fell Below 1,530 Psig.Caused by Normal Sys Leakage. Surveillance Interval Considered Adequate
05000424/LER-1991-012-02, :on 911118,discovered That Digital Rod Position Indication for Shutdown Bank A,Rod D-2 Stopped Moving, Resulting in Manual Actuation of Rps.Cause Undetermined. Addl Troubleshooting Will Be Performed
05000346/LER-1983-071-03, /03L-0:on 831205,control Room Operators Received Sequence Inhibit Alarm & Discovered Diamond Control Panel in Manual.Caused by Fault in Motor Power Return SCR Gate Drive Circuit
05000302/LER-1983-008-03, /03L-0:on 830211,absolute Position Indication for Rod 1,group 1,failed to Indicate +/- 2% Motion.Caused by Failed Reed Switch.Rod Position Verified Via Zone Ref. Position Indicator Tube Containing Faulty Switch Replaced
05000302/LER-1983-006-03, /03L-0:on 830203,during Control Rod Exercise Surveillance,Absolute Position Indication for Rod 6,group 2 Failed to Indicate +/-2% Motion Per Tech Spec Requirements. Caused by Failed Reed Switch.Tube Replaced
05000335/LER-1982-049-03, /03L-0:on 821018,pulse Counting Function of Control Element Assembly 41 Found Deleted.Caused by Operator Error During Setup for Moderator Temp Coefficient Test. Operators Instructed to Run Deletion Log After Readjustment
05000335/LER-1982-044-03, /03L-0:on 820923,pulse Counting Function for 21 Control Element Assemblies Found Deleted During Normal Testing.Caused by Personnel Error.Methods for Alerting Operators Investigated
05000328/LER-1993-005, :on 931018,manual Actuations of RT Breakers Occurred Due to Demand Step Counter Malfunctions.Replaced Demand Step Counter
05000302/LER-1978-062-03, /03L-0:on 781121,during Control Rod Exercise Procedure SP-333,absolute Position Indication for Rod 4 Group 3 Not Observed as Rod Was Moved.Caused by Sticking Reed Switch
05000302/LER-1978-049-03, /03L-0:on 780915,relative Position Indication for Group 7,Rod 8 Found Inoperable.Caused by Improper Termination of Reactimeter to Relative Position Indicator Module for Group 7,Rod 1.Procedure Will Be Revised
05000416/LER-1982-056-03, /03L-0:on 820820,accumulator Trouble Annunciators Alarmed for Hydraulic Control Unit Accumulators 08-37 & 20-53 During Performance of Control Rod Drive Sys Open Vessel Test 1-C11-SU-05-0.Caused by Normal Sys Leakage
05000328/LER-1993-005-02, :on 931018,manual Actuations of RT Breakers Occurred Due to Malfunctioning.Demand Step Counters Manually Opened RT Breakers
05000324/LER-1996-001-02, :on 960202,CR Average 5% Insertion Time Exceeded TS Limits.Caused by Natural Aging of the CR HCU SSPV & Possible Pipe Threads Sealant Intrusion on Diagram. C/A Will Be Reported in Suppl
05000440/LER-1993-014, :on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs Cabinet
05000369/LER-1993-005-02, :on 930612,manual RT in Unit 1 Occurred Due to Equipment Failure Due to Failure of L-13 Field Cable Between Data Cabinet B & Bulkhead for Undetermined Reasons.Replaced Field Cable
05000440/LER-1990-010, :on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage Monitored
05000346/LER-1981-061-03, /03L-0:on 811003,absolute Positive Indication on Group 4,rod 7 Erratic,Fluctuating 5-10% of Full Range.Cause Unknown.Absolute Position Indication Signal Lead Changed to Different Penetration Conductors
05000440/LER-1991-005, :on 910129,discovered That Two Power Supplies Had Excessive Ripple Effect When All Rods Pushbutton Depressed,Resulting in Loss of Scram Accumulator Fault Indication.Caused by Personnel Error
05000346/LER-1978-016-03, /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector
05000346/LER-1978-021-03, /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors
05000346/LER-1981-012-03, /03L-0:on 810212,control Rod 1-3 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals Causing Asymmetric Rod Alarms.Exact Cause Undetermined,But Absolute Position Indication Leads Picking Up Noise
05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel
LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
05000346/LER-1978-034-03, /03L-0:on 780326,group 5, Control Rods 11 & 12 Absolute Position Indication Declared Inoperable.Caused Traced to Penetration Area.Updated Rept Will Be Submitted When Exact Cause Determined
05000346/LER-1978-002-03, /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced
05000346/LER-1979-027-03, /03L-0 on 790216:absolute Position Indication Amplifer for Rod 9 of Group 5 Was Inoperable.Caused by Failure of Integrated Circuit Chip in Amplifier.Integrated Circuit Chip Replaced
05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
05000302/LER-1979-026-03, /03L-0 on 790318:during Reactor Startup,Discovered Absolute Position Indication for Rod 8 Was Inoperable.Caused by Sticking Reed Switch.Variable Ac Frequency,Applied to Reed Switch Circuit,Eliminated Sticking
05000302/LER-1978-068-03, /03L-0 on 781213:noted That Absolute Position Indication for Rod 5,Group 6 Was Fluctuating 10 to 15% Caused by Several Sticking Reed Switches
05000346/LER-1978-122-03, /03L-0 on 781208:control Rod 4 of Group 3 Absolute Position Indication Was Erratic Due to Intermittent Failure of a Component within the Position Indicator Tube
05000346/LER-1978-040-03, /03L-1 on 780422:review of Reactor Operator Log Determined That Group 5 Control Rods 100% Zone Ref Light Had Not Been Checked at Required Frequency.Caused by Personnel Error.Process Computer Reminder Program Developed
05000336/LER-1979-002-03, /03L-0 on 790116:following Return to sub-critical Conditions,Investigations Showed Faulty Position Indication for Control Element Assembly 63,indicating About 6 Steps High.Caused by Position Indication Unit Drift
05000346/LER-1978-127-03, /03L-0 on 781230:asymmetric Rod Indication Was Received for Control Rod 4 of Group 5;unit Was in Mode 2 & Absolute Position Indicator for Rod 4 Was Inoperable.Caused by Dirty Module Contacts
05000346/LER-1978-113-03, /03L-1 on 781110:fluctuating Signals from Absolute Position Indicator for Control Rod 4 of Group 3 Caused Asymmetric Rod Alarms.Caused by Intermittent Failure of Position Indicator Tube.Tube Replaced
05000346/LER-1979-100-03, /03L-0:on 791014,group 7,rod 7 Absolute Position Indication Showed Asymmetric W/O Clearing.Caused by Power Supply Cable.Cable Replaced W/High Temp Cable.Rebuilt Position Indicator Tube Installed
05000346/LER-1979-079-03, /03L-0 on 790712:while Repositioning Group 8, Absolute Position Indication for Rod 4 Shifted from 25% to 0% Position.Caused by Oxide Film Buildup on Reed Switch Contacts.Corrective Maint Performed
05000302/LER-1979-101-03, /03L-0:on 791017,safety Rod 8 Absolute Position Indication Would Not Respond to Rod Movement During Rod Control Exercises.Cause Unknown.Further Investigation Scheduled
05000317/LER-1979-023-03, /03L-0 on 790712:while Withdrawing Group 1 Control Element Assembly,Position Indication for Assembly 65 Stopped Indicating Outward Motion at 42 Inches.Caused by Electronic Failure of Printed Circuit Board.Board Replaced
05000335/LER-2078-022, For St. Lucie Unit 1, on 06/15/78 Concerning During PWR Operation, the Digital Data Processing System Malfunctioned Due to Malfunctioning Multiplexer Card
05000335/LER-2076-019, During Testing, Digital Data Processor Malfunctioned; Resulted in Loss of CEA Pulse Counting Position Indication
LR-N980125, Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2
L-91-142, Application for Amends to Licenses DPR-31 & DPR-41,revising Tech Specs to Remove Outdated Matl,Incorporate Administrative Clarifications & Correct Typos for Consistency w/NUREG-0452 Re STS for Westinghouse PWRs
05000316/LER-1996-003, :on 960305,incorrect Guidance for Shutdown Rod Position Indication Requirements Lead to Condition Prohibited by Plant Ts.Submitted TS Change Request to Remove TS 3.1.3.3
05000335/LER-1980-003-03, During Normal Operations, Control Element Assembly 30 Reed Switch Position Indication Channel Failed.Cause Is Unknown.Channel Repaired & Returned to Svc
05000250/LER-2014-003, Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter
05000251/LER-2010-005, Regarding Failure of Group Step Counter with Valid Manual Actuation of the Reactor Protection System
05000395/LER-2003-006, Regarding Manual Reactor Scram Due to Digital Rod Position Indication Failure
05000346/LER-1979-072-03, /03L-0 on 790708:position Indication on Rod Two of Group Eight Was Inoperable.Caused by Component Failure of Reed Switch within Position Indicator Tube.Part Was Replaced & Returned to Svc
A02456, Application to Amend License DPR-65,revising Tech Specs to Allow Startup & Power Operation W/One Inoperable Reed Switch Position Indicator Per Control Element Assembly Group
LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
LR-N09-0042, License Amendment Request to Revise the Definition of Fully Withdrawn for the Rod Cluster Control Assemblies
05000302/LER-1983-061-03, /03L-0:on 831204,while Performing Control Rod Exercises,Absolute Position Indication for Rod 6,group 2 Failed to Indicate +/- 2% Motion.Caused by Failed Reed Switch.Indicator Tube Will Be Replaced
05000328/LER-1994-008-02, :on 941021,manual Actuation of Reactor Trip Breakers Occurred Due to Failure of Rod Control Demand Step Counter.Caused by Incorrect Step Position Indication on Control Bank a Group 2 Step Counter
05000336/LER-1980-010-03, /03L-0:on 800310,during Surveillance,Control Element Assembly Exhibited Erratic Position Indication & Was Declared Inoperable.Caused by Intermittent Open Conductor in Cable or Connector from Reed Switch
DCL-02-049, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001