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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086G2701976-01-0808 January 1976 AO 75-79:on 751229,local Leak Test Identified through- Leakage of B Loop RHR Torus Spray Valve MO-3-10-38B & Torus Cooling Return Valve MO-3-10-34B.Cause Under Investigation ML20086G2721976-01-0505 January 1976 AO 75-78:on 751226,drywell Radiation Monitor Inoperative. Caused by Flow Blockage in on Stream Sample Line.Sample Point Changed to Reestablish Sample Flow to Drywell Radiation Monitor ML20086G2741975-12-30030 December 1975 AO 75-76:on 751220-21,local Leak Rate Test Identified through-leakage on Loop a & B RHR Outboard Injection Valves MO-3-10-154A & B.Cause Not Determined.Inboard Isolation Valves Verified as Leaktight & Closed ML19343C2181975-12-23023 December 1975 AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized ML20090C9991975-12-12012 December 1975 AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo ML19343C2191975-12-11011 December 1975 AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature ML20086H0411975-12-0505 December 1975 AO 75-72:on 751126,core Spray 3A Full Flow Test Valve MO-3-14-26A Failed to Close.Caused by Broken Wire on Closing Torque Switch in Valve Operator.Broken Wire Repaired & Proper Valve Operator Verified ML20086F8431975-12-0505 December 1975 AO 75-77:on 751126,LS-4223 Failed to Operate RHR Head Spray Line High Point Vent SV-4223 on Low Accumulator Level.Caused by Blown Fuse in Solenoid Valve Circuit.Grounded Wire Repaired & Vent Valve Returned to Svc ML20126E8281975-12-0303 December 1975 AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced ML20086F8491975-12-0101 December 1975 Telecopy AO 75-77:on 751126,LS-4223 Failed to Operate SV-4223 on Low Accumulator Level.Caused by Blown Fuse in Solenoid Valve Circuit.Operator Manually Vented Accumulator to Ensure Head Spray Line Maintained Filled ML20086H0461975-11-26026 November 1975 Telecopy AO 75-72:on 751126,core Spray Full Flow Test Valve MO-3-14-26A Failed to Close.Caused by Broken Wire on Closing Torque Switch in Valve Operator.Broken Wire Repaired & Proper Valve Operation Verified ML20086F8551975-11-26026 November 1975 AO 75-76:on 751117,rigid Pipe Support Found Broken on RHR Shutdown Cooling Suction Line.Caused by Component Failure. Pipe Support Replaced.Investigation Continuing ML20086F8711975-11-26026 November 1975 AO 75-75:on 751117,reservoirs of Two Hydraulic Snubbers Found Empty.Caused by Leaking O-rings & Gaskets.Defective gaskets,seals,O-rings & Fittings Will Be Replaced & Snubbers Will Be Checked ML20086F8801975-11-26026 November 1975 AO 75-74:on 751116,setpoint of RCIC Steam Supply Line Area High Temp Switch TE-TS 4939A Found Less Conservative than Specified by Tech Specs.Caused by Slight Setpoint Drift. Switch Recalibr,Tested & Returned to Svc ML20090D0071975-11-25025 November 1975 AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation ML20086F8961975-11-21021 November 1975 AO 75-73:on 751113,leak Observed on RHR Sys Relief Valve RV-35B.Caused by Throttling of MO-2-10-154B Valve Resulting in Crack.Weld Repairs Will Be Made to Relief Valve in Accordance W/Approved Procedures ML20086F8611975-11-18018 November 1975 Telecopy AO 75-76:on 751117,rigid Pipe Support Found Broken on RHR Shutdown Cooling Suction Line.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F8741975-11-18018 November 1975 Telecopy AO 75-75:on 751117,two Outside Drywell Snubbers Found to Have Empty Reservoirs.Cause Under Investigation. Corrective Action to Be Determined After Investigation ML20086F9061975-11-17017 November 1975 AO 75-71:on 751107,cracked Weld on 1-inch Line to Relief Valve RV-35B Observed.Caused by Throttling MO-2-10-154B Resulting in Cracked Weld.Repairs Completed in Accordance W/Approved Procedure ML20086F8901975-11-17017 November 1975 Telecopy AO 75-74:on 751116,setpoint of RCIC Steam Supply Line High Temp Switch TE-TS 4939A Found Less Conservative than Allowed by Tech Specs.Caused by Slight Setpoint Drift. Switch Recalibr & Returned to Svc ML20086F9181975-11-14014 November 1975 AO 75-70:on 751104,reservoirs of Five Hydraulic Snubbers Found Empty.Caused by Leaking O-rings & Gaskets.Defective Gaskets & O-rings Will Be Replaced ML20086F9021975-11-14014 November 1975 Telecopy AO 75-73:on 751113,leak on Body of RV-35B RHR Sys Relief Valve Observed.Caused by Throttling of MO-2-10-154B Valve Resulting in Crack.Rhr Loop B Shut Down in Preparation for Repair of Relief Valve ML20086F9111975-11-10010 November 1975 Telecopy AO 75-71:on 751107,cracked Weld on Line to RV-35B Observed.Caused by Throttling Down on MO-2-10-154B Resulting in Weld Crack.Repairs Completed.Pipe Vibration Readings Taken to Determine If Mods Required ML20086H0521975-11-0707 November 1975 AO 75-71:on 751030,drywell Oxygen Analyzer Sample Sys Outer Isolation Valve SV-3978B Failed.Caused by Dirt on Seat & in Body of Valve.Valve Internals & Seat Cleaned.Valve Disc, Piston Rings & Bonnet O-ring Replaced ML20090D0161975-11-0707 November 1975 AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr ML20090D0601975-11-0606 November 1975 AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch ML20086F9231975-11-0505 November 1975 Telecopy AO 75-70:on 751104,reservoirs of Five Hydraulic Snubbers Found Empty.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086H0621975-11-0303 November 1975 AO 75-70:on 751024,drywell Purge Supply Isolation Valve A0-3520 Operated W/O Manual Initiation.Caused by Incorrect Implementation of Mod.Piping Corrected & Will Be Monitored ML20086H0751975-10-31031 October 1975 AO 75-68:on 751021,torus Makeup Supply Isolation Valve AO-3523 Found to Leak in Excess of 2,000 Cc/Minute.Caused by Closing Spring Not Providing Sufficient Force to Fully Close Valve.Closing Spring Adjusted ML20086H0851975-10-31031 October 1975 AO 75-67:on 751021,torus Makeup Supply Isolation Check Valve 276Y Found Leaking in Excess of 2,000 Cc/Minute.Caused by Valve Piston Being Hung Up During Operation.Check Valve Repaired & Local Rate Test Repeated ML20086H0561975-10-31031 October 1975 Telecopy AO 75-71:on 751030,isolation Valve SV 3978B Failed. Cause Under Investigation.Corrective Action to Be Determined ML20086F9381975-10-31031 October 1975 AO 75-68:on 751021,O-ring Gasket Leak Discovered on Torus Purge Supply Valve AO-2521B.Caused by Use of Improper Connection for Testing Double O-ring Seal.Connection Capped & Leak Checked Successfully ML20086F9291975-10-31031 October 1975 AO 75-69:on 751021,nitrogen Found to Leak Out of Test Connection on Inboard Flange of AO-2519.Caused by Use of Wrong Connection for Testing Double O-ring Seal.Connection Capped & Leak Checked Successfully ML20086F9521975-10-30030 October 1975 AO 75-66:on 751020,APRM B Flow Bias Signal Failed Upscale. Caused by Internal Ground in Channel Flow Transmitter D Combined W/Installed Instrument Loop Ground,Lowering Total Loop Resistance.Defective Components Replaced ML20090D0761975-10-28028 October 1975 AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation ML20086H0741975-10-24024 October 1975 Telecopy AO 75-69:on 751023,O-ring Gasket Leak Found on Drywell Purge Supply Valve AO-3505.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086H0681975-10-24024 October 1975 Telecopy AO 75-70:on 751024,drywell Purge Supply Isolation Valve AO-3520 Operated W/O Manual Initiation.Caused by Incorrect Implementation of Mod.Valve Failed Closed & Will Be Repaired ML20086F9661975-10-24024 October 1975 AO 75-65:on 751015,setpoints on Reactor High Pressure Scram Switches Found Less Conservative than Specified by Tech Specs.Caused by Instrument Setpoint Shift.Channel D Switch Recalibr,Tested & Returned to Svc ML20090D0941975-10-24024 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced ML20086H0901975-10-21021 October 1975 Telecopy AO 75-67:on 751021,torus Makeup Supply Isolation Check Valve 276Y Found Leaking in Excess of 2,000 Cc/Minute. Cause Under Investigation.Corrective Actions to Be Determined After Investigation ML20086H0811975-10-21021 October 1975 Telecopy AO 75-68:on 751021,torus Makeup Sys Isolation Valve AO-3523 Found to Leak in Excess of 2,000 Cc/Minute.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F9581975-10-21021 October 1975 Telecopy AO 75-66:on 751020,logic Aprm/Rbm B Flow Bias Signal from FT-2-2-110D Failed Upscale.Caused by Failure of Second Ground on Recirculation Drive Flow Transmitter Signal Loop.Flow Signal Corrected ML20086F9441975-10-21021 October 1975 Telecopy AO 75-68:on 751021,leak Found on O-ring Gasket on Torus Purge Supply Valve AO 2521A.Cause Under Investigation. Corrective Action to Be Determined After Investigation ML20086F9491975-10-21021 October 1975 Telecopy AO 75-67:on 751021,diesel Generator Breaker E-4 Inoperable.Caused by Inoperative Charging Motor Failing Due to Brush Wear.Breaker Replaced ML20086F9331975-10-21021 October 1975 Telecopy AO 75-69:on 751021,O-ring Gasket Leak Discovered on Drywell & Torus Inerting Nitrogen Supply Valve AO-2519.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20090D1141975-10-17017 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1041975-10-16016 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016 ML20086F9701975-10-16016 October 1975 Telecopy AO 75-65:on 751015,setpoint on Reactor High Pressure Scram Switches Found to Be Less Conservative than Specified by Tech Specs.Caused by Instrument Setpoint Shift. Channel D Switch Recalibr,Tested & Returned to Svc ML20086H0961975-10-16016 October 1975 AO 75-66:on 751006,RCIC Inboard Steam Supply Isolation Valve MO-3-13-15 Failed to Close.Cause Not Identified.Valve Stroked Successfully.Failure Not Repeatable ML20086H1061975-10-10010 October 1975 AO 75-65:on 751002,drywell Radiation Monitor Inoperable. Caused by Rust Blockage of Pressure Control Valve.Valve Cleaned,Reassembled & Returned to Svc 1976-01-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 1999-09-30
[Table view] |
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..,. :n y 631 .: Ark Avenue Ki .; af Prussia, Pennsylvania 19406 Jersr/ Central Power 6 Light Company Ofs r: Creek Nuclear Generating Station Docket #50-219 Foded River, New Jersey 08731 Abn:=lal Occurrence Report No. 50-219/74/ 2(,
The following is a preliminary report being submitted in cripliance with the Technical Specifications pan;raph 6.6.2.
Preliminaiy Approval:
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l Initial Telephone Date of Report Date: 4/12/74 Occurrence:. lll4/12/74 . .,
Initial Written Time of P.cport Date': 4/12/74 Occurrchce: 0855 OYSTER CREEK NUCLEAR GENEP TING STATION FORKED RIVER, NEW JERSEY 08731
. Abnormal Occurrence Report No. 50-219/74/ 26 IDENTIFICATION Violation of the Technical Specifications, paragraph N/A ,
OF OCCURRENCE:
Failure of emergency service water pump (52C) to start when called upon.
This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.15D .
CONDITIONS PRIOR TO OCCURRENCE: X Steady State Power Routine Shutdown Hot Standby Operation ,
Cold Shutdown Load Changes During Refueling Shutdown Routine P.ower. Operation Routine Startup Other (Specify)
Oper tion l
l Power: Core, 1843 MNt i Elec., 637 MNe Flow: Recirc., 61 x 106 lb/hr l Feed., 6.9 x 106 lb/hr -
Stack Gas: 36,600 pCi/Sec l
DESCRIPTION On Friday, April 12, 1974, in attempting a normal start of the OF OCCURRENCE:
containment spray system, the following sequence of events occurred:
- 1) A start signal given to containment spray system II.
- 2) Containment spray pump 51C started.
- 3) Emergency service water pump 52C failed to start and -
" Emergency Service Water Pump C Failure" alarm initiated after the NISO.second time delay. .
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' Abnormal Occurrence Report No. 50-219/74/26 * -
Page 2
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- 4) Emergency service water pump 52D was then started and oper-ated successfully in accordance with requirements of Tech-nical Specification 3.4.C.4.
1
- 5) Containment spray system II was secured.
- 6) An operator was dispatched to the 4160V switchgear room and
- it was discovered that the thermal overload relay had tripped 4
on the 52C breaker. The overload relay was reset.
- 7) Control room operator attempted a restart of containment spray system II.
1
- 8) The system operated properly with no irregularities.
- 9) The system, after this successful operability, was secured.
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The system was given an additional operability check -later in 4 .
the day and operated successfully with no problems or alarms.
Prior to this event on Thursday, April- 11, 1974, the containment spray system II was initiated to obtain torus water sample and to pump torus water. At this time, while running the system, the " Emergency Service Water Pump C Trouble" alarm was received.
The pump continued operating and an operator was dispatched to j the emergency service water pump to investigate. The oil IcVel and the bearing temperatures were normal. However, the operator did not check the thermal overload relay _at the pump breaker
. in the 4160V switchgear room. At this time, it was thought that the alarm was a faulty indication and a job order was issued to have it diecked out. 101en the system was secured,
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the alarm did not c1 ear. This. alarm was' still in when the pump
.. start was attempted at the time of-the incident.
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O O Abnormal Occurrence P.cport No. 50-219/74/26 -
l APPARENT CAUSE Design Procedure OF OCCURRENCE: Fbnu facture. Unusual Service Condition
, Installation / Inc. Environmental Construction Component Failure Operator Other (Specify)
A check of the logic circuit showed that the initial alarm of
" Emergency Service Water Pump C Trouble" should not have pre-
, vented the pump from starting. The incident is still under investigation and the exact cause yet to be determined.
ANALYSIS OF The containment system is designed to provide heat removal t OCCURRENCE:
capability with one containment spray and one cuergency service j water pump in either loop. The safety significance of this event is in the loss of redundancy of the emergency service water pumps in one of the two redundant containment spray systems.
CORRECTIVE The corrective action will be determined by the Plant Operations ACTION:
Review Committee after the appropriate review of all the cir-cunstances associated with this event.
FAILURE DATA: Under investigation. t i
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l Prepared by: T . e es ,-s Date: 4/12/74 l V .
20
. _, o James P. O'Reilly o
To:
Directorate of Regulatory-Operations Region I 631 Park Avenue King of Prussia, Pennsylvania ~1 9406 From: .
Jersey Central Power G Light Company Oyster Creek Nuclear Generating Station Docket #50-219 Forked River, New Jersey 08731
Subject:
Abnormal Occurrence Report No. 50-219/74/ 1 The following is a preliminary report being submitted -
in compliance with the Technical Specifications paragraph 6.6.2. ,
Preliminaiy Approval:
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08731 6F RKED RIVER, NEW JERSEY Abnomal Occurrence O -
Report No. 50-219/74/ 2 (o IDENTIFICATION Violation of the Technical Specifications, paragraph N/4 ,
OP O M R E CE:
p 4 L u g,e o p E M Ec c e p c4 SE RVICE WATcP. Pu MP STA2.T w HV m CALLSO uPS 9 .
(67.c)To m This event is considered to be an abnomal occurrence as de-fined in the Technical Specifications, paragraph 1 1G D .
l CONDITTONS PRIOR TU OCCURRENCE: /_ Steady State Power Routino Shutdown Hot Standby ~ Operation
__ _ Cold Shutdown I,oad Changes During Refueling Shutdown -
Routine Pcwor Operation Routino Startup Other (Specify)
Operation _
Yowri.q toe.a - )984'3 Mwt Et.ec. - G 3'1 Mwe-Flow .
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FESSw. - 4 9 x it ' */ wl, STmc C, G A 5 - 36,6 o o A4ei/ste DESCRIPTION OP OCCURRENCE: ON F#.AbA3 APAiL lti t9'N iiu' A~ttaMpTipG A Wo&4AL SIMT o P T t4E CATAiuMBUT DAj k!YU4,'THE F#LLcwi9s $1EQg;eucs dP BJEUTs oc.c.vea.eo .
g) A StadT qmeA Gitfeu To WAma^ cut % hhI -
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- 0 i) eaucc,eucy hvice wsrse..bp 52.t EAeo T. NF guo" Emac. SE.avice WATag be t %itute"AtmM toibTeo ANT 9? +t 90 Sec.~Ture htAY.
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s) CmTuwucuT SDeAy SysTemT wAs SECOEeo. ,
s) Au OPERAToe wAs DisPaTc.deo 7b THe 4i6o v kirewa
, (loom Auo iT wAs Dscovceco ~The Taie THWL op by gpoTc.gpap ga THE 52. c. 2caAKc7.. T4 ovettono d MLA1 LvAs Reset-
- 7) CowTstst h dpc'a.oTa A'iTe>(reo A Re0rart cr/ CouT**
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- 6) T Me 11tT o w OP r aTc.0~ SP424L1 wtTM uo iP_ctreutu'5es
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'Twe snTerw wa.s Givao A9 AcosTionat O e c e,e m tiTy c a te.g. v t w Twa bq ,suo ope %Teo' 3uccetsPutW W iT H 90 %d8 tem ott. ALAcA1,$,
hoc TO Ti\ls EveJT ou Thuet GA Apgit i t,1crM,THe Co S?e.ng 51 sTamE WAt suTTiaTeo To OSTasu TDcus wTet Sample Aoo Th Phg Toevs ianTee. AT Tthe Time w+1:4 e
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O APPARE!TT CAUSE Design Procedure OF.0CCURPINCE: Manufacture Unusual Service Condition Installation / Inc. Environmental Construction Corponent Failure Operator Other (Specify)
A CRER.C. o9 THE L 0GIC t\EcvF TM0ugO TI%TT+C iMEnAL ALAR OP 'EME2.CEWv( TEctllCe LuAThe 9vMp C. 30l//306 S40ulD.06T Mt/3 l poTeo THE 4Mp ibrm $TmTiuG The iutiDe97 i5 ST LL uuoeg, t kvESTtoETTov Awo s ME 'Exe.T. CAusE. YET Tb h DGTeE.4staeb.
ANALYSIS OF OCCURRENCE:
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seevica tsree bp iu e iTMee 'ooP T"e SWST1 S tud'F" " 8 gg EUaF 15 seu T tt e L e ff o f 600 eon 9c.1 S TMe OnWT 3E6/KB tv,iTaz,9wAPS 5W O92 0F M t. T*to k ovfucowY Cont S N i 34 CORRECTIVB -
AcrION:
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PAILUPE DATA':
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D Prepared by: ) 'e
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, Pii1IAL7Ti!IA ELD 7aIC COMP /M Peach Dottoa Ato:ic Power Station'
. Delta, Pennsylvania
. 17314 .
.o2/f- M N M O
$h* '
April ll,17/4 Mr.. James P. O'Reilly, Di:xetor ' ,
United Statr a Ate nic Energy Co :aicsion- ' '
Directer .te of Ecirulatory Operatienn '
631 Park f.w.:ue i King of Pturcin, Fer.ncylnnia ,'19406 ,
4
.%bject: ~~At'norml C~ currence 2.4-Hour !Totificatirm
. a, r zn" .
. c. ..
, i Confir::ing r.y convercaion with Mr. 2. A. Feil, t..E.C. Region I Regulatory Operationn Office on April 11, 1970 .; ,
Reference:
License iTunbcr DPR '.h Anendnent Husber 1- '
.j Technical. Spcificnica Reference 3-5.D.1 ,.,', :,,i Report Fo.: 50-277-74-20 ,
April 1.1,17/4 Report D.n o: ,
April.20, 1974
. Occurrence Date: l . O" , .!
Facility: Pcach Dotton Atocic Power Stttien'. ,
t -
. . R. D.El,. Delta, Per.utcylvania .17314 >. < .
' ' ', t)e, ts
,. ;i
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6-
' Idedificatien of. Occurrdnce: i f,' '
i '
I hentary trip of DCIC In'icrter in the 7.c,crncncy: Shutdown Panel. '
- ' , i y >
4')ConditionsPriortoOccurrence <
. .M , [,m m. : <
A s y,y; ~.5 . jm , ., , ,
.Recctor van critical at about. N,pcVer.,' n, ./ 2..
o.. ,
Deceription of Occurrence - "
During the canual trip of a reactor feedvater turbine, the ECIC inverter
, 7
' . annunciated.in the control roomlocated The tripped. on the inverter. cuer6ency van iz:chutdown mediately control panel tripped. Utis con
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identificd and cuccconfully rccet. . . , ,
x- ,:
.)4 s; ,l .
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' Derdgnation of Apparent Cause of Occurrence: '
4 Cause of TCPAZ inverter trippings is still under investigation.
Tripping appearn to be associated with possible voltage spikes on the -
j D.C. cyoten. , ,,,, 7, j
. I Analysis of Occurrence: / ' '
Since A.C. powr from the norettl RCIC inverter was never interrupted, the opernbility of the FCIC nycten van r.ot affected. Since the tripped j
, inverter could be renet 1:-_ediately, TCIC operability from the '
i enor6cacy chutdown panel was only out of cervice for a few ninutec.
" Corrective .*ction:
. The inverter irr.tallEdin the! emergency ahutt'ovn panel is being repinced with a rpre unit. Die unit which exparien:ed the trippind will bc hN o F . Vm3g3cny '
[ck
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_ _ _ _ . _ _ _ _ . . . _