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 Calculated
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| ML20206K026 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/21/1988 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-006-00, 88-6, NUDOCS 8811290237 | |
| Download: ML20206K026 (1) | |
Similar Documents at Hope Creek | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20217F1501999-10-12012 October 1999
[Table view]Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence 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 Replaced1999-04-12012 April 1999 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 Replaced 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 Replaced1997-08-22022 August 1997 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 Replaced 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 Satisfactory1997-04-14014 April 1997 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 Satisfactory ML20133M5881997-01-15015 January 1997 Special Rept:On 970102,TS Action Statement 3.3.7.5 & 3.3.7.5 Were Entered to Calibrate an I Detector on Npv Radiation Monitoring Sys Due to High Range Noble Gas Monitor Being Inoperable.Npv Was Declared Operable on 970105 ML20135A9831996-11-27027 November 1996 Special Rept 96-03:on 961118,high Range Noble Gas Monitor Declared Inoperable.Caused by Parts Not Being Readily Available.Completed Repairs,Performed Post Maint Testing & Declared Monitor Operable ML20129F3641996-09-30030 September 1996 Special Rept 96-002:on 960916,TS Action Statements 3.3.7.5, Accident Monitoring Instrumentation & 3.3.7.11, Radioactive Gaseous Effluent Monitoring Instrumentation, Entered Due to Inoperability of SPV Rms ML20115H7611996-07-16016 July 1996 Special Rept:On 960702,South Plant Vent High Range Noble Gas Monitor Was Inoperable for More That 72 H.Caused by Square Root Extractor in Instrument Loop Being Out of Calibr.Flow Instrument Loop Will Be Bench Tested W/New Flow Transmitter ML20117J5471996-05-23023 May 1996 Special Rept 95-04,suppl 1:on 950930,invalid Test Failure Occurred on EDG D.Caused by Oxidation & Corrosion Built Up on Potentiometers.Potentiometers Stroked Prior to Satisfactory Surveillance Run ML20106H0301996-03-12012 March 1996 Special Rept:On 960131,plant CR Ventilation Radiation Monitoring Detectors Declared Inoperable.Rept Retracted on 960223 Due to Results of Engineering Evaluation ML20100A3321996-01-0202 January 1996 Special Rept 95-06:on 951206 & 07,C EDG Failures Occurred Due to Faulty Tachometer Relay Signal Generator.Tachometer Relay Signal Generator Replaced on 951208.C EDG Retested Satisfactorily & Declared Operable on 951209 ML20095K6801995-12-19019 December 1995 Special Rept:On 951126,EDG Failed Due to Defective Bailey Logic Card.Edg Will Be Restored Upon Completion of Scheduled Maint & Testing ML20094A0191995-10-24024 October 1995 Special Rept 95-03:on 950913,filtration Recirculation & Ventilation Sys (FRVS) High Range Noble Gas Monitor Declared Inoperable.Listed Repairs Made & FRVS Will Be Restored to Operable Status Upon Completion of Required Testing ML20093M6631995-10-23023 October 1995 Special Rept 95-02:on 951011,EDG Tripped Due to Personnel Manipulation Error.Ts Surveillance Procedure Revised ML20087G2451995-03-27027 March 1995 Special Rept:On 950223,Free Field,60 Feet Below Grade Seismic Sensor Failed.Caused by Vibrations Induced from Road Work Performed in Support of on-site Const.Decided Not to Restore Sensor Until Completion of Road Work on 950414 ML20078A7361995-01-18018 January 1995 Special Rept 95-01:on 941212,determined That Tape Recorder Associated w/loose-part Detection Sys Malfunctioning.Caused by Aging of Recorder Tape Transport Sys.Detection Channels in Svc & Will Alarm If Loose Parts Detected ML20072G6431994-08-19019 August 1994 Special Rept:On 940812,discovered That Plant Vent Radition Monitor Had Been Inoperable for More than 72 Hours.Cause Under Investigation.Technicians Counselled Re Procedural Compliance ML20064H0231994-03-0808 March 1994 Rev 1 to Special Rept 94-01:on 940113 & 0210,EDG D Load Failures Occurred Due to Oxidized Contacts in Relay Utilized Only During Testing.Both Idr Relays Replaced & EDG Reliability Data Base Reviewed ML20063J5441994-02-11011 February 1994 Special Rept 94-01:on 940113 & 0210,EDG D Load Failures Occurred Due to Inadequate Lubrication of Fuel Racks & Fluctuations in Output of Relay Which Selects Control Signal to Engine Governor,Respectively.Fuel Racks Lubricated ML20058M1201993-12-0909 December 1993 Special Rept 93-01:on 931105,seismic Monitoring Instrumentation Was Removed from Svc to Perform TS Required 18 Month Channel Calibr of Sys & Remained Inoperable for More than 30 Days.Caused by Need for New Test Card ML20141M3241992-08-0404 August 1992 Special Rept:On 900817,discovered That TS Limit for Ultimate Heat Sink Established Nonconservatively.Caused by Design Calculation Error.Actions to Address Svc Water Sys Malfunction Incorporated Into Procedures ML20097E4571992-06-0303 June 1992 Ro:On 920526,leakage Noted at Valve Seating Areas of Three Suppression Chamber Vacuum Breakers.Caused by Loosening of Seat Bolting Ring Hardware.Valve Seats Replaced W/New Matl. Drywell-to-suppression Chamber Will Be Tested by 920912 ML20082M3651991-08-29029 August 1991 Suppl Special Rept 91-03-01:on 910522,emergency Diesel Generator D Failed to Start When Manual Start Signal Initiated from Control Room.Probably Caused by Lack of Fuel Boost.Procedures Re Fuel Boost Position Switch Revised ML20081J9821991-06-19019 June 1991 Special Rept 91-03-00 on 910522,during Monthly Operability Surveillance Run EDG D Failed to Start When Manual Start Initiated from Control Room.Caused by Lack of Fuel Boost. Investigation Into Cause of Lack of Fuel Boost Continuing ML20073E2261991-04-24024 April 1991 Special Rept 91-02:on 910321,determined That Longitudinal Trace of Triaxial time-history Acceloragraph VR-7863 (Channel 3) Not Functioning Properly.Affected Channel Will Be Repaired at First Outage of Sufficient Duration ML20067C7641991-02-0404 February 1991 Special Rept 91-01:on 910107,emergency Diesel Generator D Failed to Start When Manual Channel D ECCS Actuation Test Signal Was Initiated.Cause Unknown.Test Successfully Completed ML20065P5321990-12-10010 December 1990 Special Rept 90-003:on 901029,loose Parts Detection Sys Declared Inoperable Due to Failure of Sys Recorder Power.Sys Remained Inoperable More than 30 Days.Replacement Parts Not Readily Available.Spare Parts Inventory Under Review ML20065M8361990-12-0303 December 1990 Special Rept 90-002:on 901102,fuel Shipment for Facility Did Not Arrive at Expected Time.Driver Delayed Enroute by Fog ML20246N1381989-05-0505 May 1989 Ro:On 880805,spurious Channel B ECCS Signal Generated.No ECCS Injection Into Reactor Vessel Occurred.Caused by Troubleshooting on Channel B Circuitry.No LER Will Be Submitted ML20248E1161989-04-0303 April 1989 Special Rept 89-001-1:on 890222,Triaxial Time-History Accelerograph SG-VE-7871 Declared Inoperable & Required Replacement.Spare Part Was Not Immediately Available Until 890330 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 Calculated1988-11-21021 November 1988 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 Calculated ML20154C1341988-09-0202 September 1988 Special Rept 88-005-01:on 880714,core Spray Sys Seismic Monitor Declared Inoperable After Failing Semiannual Channel Functional Test.Inoperable Monitor Scheduled for Replacement During Next Plant Outage Requiring Access to Drywell ML20153C2981988-08-24024 August 1988 Special Rept 88-003-00:on 880714,core Spray Seismic Monitor Declared Inoperable After Failing Functional Test.Caused by Sticking of Longitudinal & Transverse Accelorometers of Monitor.Monitor to Be Replaced ML20196C5901988-06-24024 June 1988 Special Rept 88-001-01:on 880126,invalid Failure to Start Diesel Generator a Experienced.Caused by Misconfigured Part Received from Vendor.Missing Jumper Wire in Contactor Replaced & Similar Contactors Inspected ML20154L3081988-05-18018 May 1988 Special Rept 88-004-00:on 880409,inoperable Channel 2 Loose Parts Monitor Not Repaired within 30 Days,Per Tech Spec 3.3.7.9.Cause Undetermined.Repair of Monitor Scheduled for Next Planned Cold Shutdown Outage ML20154C8301988-05-12012 May 1988 RO 88-003-00:on 880416,one Air Receiver Failed to Discharge & One Barring Device Interlock Pistons in Flowpath of Control to Air Start Valve Solenoid Stuck in Closed Position.Caused by Failure of Barring Gear Interlock Piston ML20154G8481988-05-11011 May 1988 Ro:On 880226,B Feedwater Check Valve Which Failed LLRT Disassembled & Inspected.Damaged Disk Found & Replaced.Since Repair of B Feedwater Eliminated Noise Signals,A Feedwater Check Valves Will Be Inspected at Future Outage ML20151G6591988-04-12012 April 1988 Ro:On 880320,shift Supervisor Made 4 H Nonemergency Rept to NRC Re Intermediate Range Monitor Upscale Trip Due to Momentary Nosie Spike on Channel ML20150B1831988-03-11011 March 1988 RO 88-002-00:on 880226,pieces of Wire Lodged in Reactor Vessel Feedwater Sparger Nozzles.Caused by Potential Loose Parts Leftover as Const Debris.Wire Pieces Removed & Examined & Vessel Annulus Deck Area Inspected ML20147A7501988-02-25025 February 1988 Special Rept 88-001:on 880126,invalid Failure to Start Emergency Diesel Generator a Experienced.Caused by Installation of Misconfigured Part Received from Vendor. Missing Jumper Wire in Contactor Replaced ML20147C1281988-01-0808 January 1988 Special Rept 87-010-01:on 871218,north Plant Vent Sample Pump Declared Inoperable for More than 72 H Due to Equipment Failure.Caused by Inadequate Documentation.Schematic Drawings of Vent Sample Flow Sys Made Available ML20236T3661987-11-24024 November 1987 Special Rept 87-009-00:on 870829,HPCI Injection Occurred as Result of Low Vessel Water Level Excursion After Reactor Scram.Thermal Cycle Tracking Program Allowing Calculation of Component Usage Factors in Initial Stages of Implementation ML20236L7031987-11-0404 November 1987 Special Rept 87-008-00:on 870816,HPCI Injection Occurred as Result of Low Reactor Vessel Water Level Excursion.Cause Not Stated.Hpci Injection Nozzle Usage Factor Not Calculated Due to Early Life of Plant ML20236J1361987-11-0202 November 1987 Special Rept 87-007-00:on 871001,determined That Electrical Configuration of Two RWCU Sys Valves Not in Compliance W/ FSAR App 9A.Caused by Inadequate Review of Commitments Associated W/Fsar Amend 15.Procedures Revised ML20236J0001987-10-30030 October 1987 Special Rept 87-006-00:on 870730,HPCI Sys Injection Reactor Scram Occurred.Caused by Low Reactor Vessel Water Level Excursion.Plant in Initial Stages of Implementing Thermal Cycle Tracking Program ML20206C5501987-04-0303 April 1987 Special Rept 87-002-00:on 870319,filtration,recirculation & Ventilation Sys post-accident Radiation Monitor Serviced & Inoperable More than 72 H.Caused by Equipment Failure During Test.Alternate Requirements Satisfied ML20211G8491987-02-20020 February 1987 Special Rept 87-001-00:on 870207,north Plant Vent Radiation Monitoring Detector (1SP-RE-4873B) Declared Inoperable Due to Damaged Aluminum Foil Window.Work Order Written to Replace Aluminum Foil Window ML20211G5321987-02-0404 February 1987 Provides Clarification of 861227 four-hour Nonemergency Event Rept Re Unplanned Closure of Excess Flow Check Valve. Caused by Loose Reed Switch Assembly Atop Excess Flow Check Valve,Giving Erroneous Indication.No LER Necessary ML20214P5211986-11-26026 November 1986 Corrected Special Rept 86-005:on 861027,licensee Failed to Submit Suppl II to Dcrdr,Per License Condition 2.C.12.a. Caused by Unexpected Heavy Work Load & Inappropriate Mgt Attention.Suppl II Submitted on 861112 1999-08-13 Category:TEXT-SAFETY REPORT MONTHYEARML20217F1501999-10-12012 October 1999
[Table view]Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) 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 Replaced1999-04-12012 April 1999 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 Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 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 LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08 |
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| 3542088022R00 - NRC Website | |
text
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O PSEG Pubhc Be'vice Electric and Gas Cornpany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Depadment November 21, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, uC 20555
Dear Sir:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 UNIT NO. 1 SPECIAL REPORT 88-006-00 On August 26, 1988, a HPCI injection occurred as a result of a low reactor "essel level signal (level 2. -38") following a reactor scram. For a description of this reactor scram event, refer to LER 354/88-022-00.
HPCI injected to the reactor vessel for approximately 90 seconds. At the onset of the injection, vessel pressure was approximately 900 psig with a vessel temperature of approximately 500 deg. F, and a HPCI discharge flow of 5600 gpr.
A of the date of this event, Hope Creek Generating Station had experienced ten (10) EPCI injections to the reactor vessel. By design, 120 injection cycles are permitted. Because of the early life of the plant, the HPCI injection no::le usage factor has not been calculated.
This Special Report is being submitted pursuant to the requirements of Hope Creek Technical Specification 3.5.1, action g.
Since ely, CL ^ = -
8811290237 DR 001121 J. J. agan ADOCK 05000354 PNU General Manager -
Hope Creek Operations AM:
CD-371F 1 0 Tne Energy People 4 m a, u
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