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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20012C5131990-03-16016 March 1990 LER 86-029-02:on 860718,19,21 & 870508,loss of Reactor Protection Sys Power Occurred Due to Spurious Tripping of Alternate Feed EPA Breakers.Caused by Low Output Voltage of Alternate Feed Transformer.Output adjusted.W/900316 Ltr ML20006E1571990-02-0909 February 1990 LER 90-001-00:on 900117,unplanned Actuation of ESF Reactor Bldg Standby Ventilation Sys B Occurred,Causing Interlocking Relays in Control Circuits to Deenergize.Caused by Transient Voltage Dip.Procedures Re Bus Loads modified.W/900209 Ltr ML19354D8331990-01-12012 January 1990 LER 89-011-00:on 891222,unplanned Actuation of ESF Primary Containment Isolation Sys Occurred When Performing Sys Layup Implementation Package for Hpci.Caused by Inadequate Procedure.Breaker Positions changed.W/900112 Ltr ML20005F8641990-01-11011 January 1990 LER 89-010-00:on 891212,unplanned Actuation of ESF Control Room Air Conditioning Train a Occurred.Caused by Removal of Leads from Relay During Test to Prevent ESF Sys Actuations. Electrical Relay Replaced & Wiring Mod made.W/900111 Ltr ML20011D2371989-12-15015 December 1989 LER 89-009-00:on 891115,notification Received of Potential Failure Mechanism of Four 3-way Solenoid Operated Pilot Valves.Caused by Incorrect Mounting of Valves.Valves Remounted Vertically & Field Walkdown done.W/891215 Ltr ML19332C5591989-11-15015 November 1989 LER 89-008-00:on 891016,control Room Alarms Received Indicating Fire Pump Had Started & Deluge Valve Had Opened. Caused by Actuation of Manual Pull Station.Deluge Sys Restored to Normal & Personnel interviewed.W/891115 Ltr 1993-06-11
[Table view] Category:RO)
MONTHYEARML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20012C5131990-03-16016 March 1990 LER 86-029-02:on 860718,19,21 & 870508,loss of Reactor Protection Sys Power Occurred Due to Spurious Tripping of Alternate Feed EPA Breakers.Caused by Low Output Voltage of Alternate Feed Transformer.Output adjusted.W/900316 Ltr ML20006E1571990-02-0909 February 1990 LER 90-001-00:on 900117,unplanned Actuation of ESF Reactor Bldg Standby Ventilation Sys B Occurred,Causing Interlocking Relays in Control Circuits to Deenergize.Caused by Transient Voltage Dip.Procedures Re Bus Loads modified.W/900209 Ltr ML19354D8331990-01-12012 January 1990 LER 89-011-00:on 891222,unplanned Actuation of ESF Primary Containment Isolation Sys Occurred When Performing Sys Layup Implementation Package for Hpci.Caused by Inadequate Procedure.Breaker Positions changed.W/900112 Ltr ML20005F8641990-01-11011 January 1990 LER 89-010-00:on 891212,unplanned Actuation of ESF Control Room Air Conditioning Train a Occurred.Caused by Removal of Leads from Relay During Test to Prevent ESF Sys Actuations. Electrical Relay Replaced & Wiring Mod made.W/900111 Ltr ML20011D2371989-12-15015 December 1989 LER 89-009-00:on 891115,notification Received of Potential Failure Mechanism of Four 3-way Solenoid Operated Pilot Valves.Caused by Incorrect Mounting of Valves.Valves Remounted Vertically & Field Walkdown done.W/891215 Ltr ML19332C5591989-11-15015 November 1989 LER 89-008-00:on 891016,control Room Alarms Received Indicating Fire Pump Had Started & Deluge Valve Had Opened. Caused by Actuation of Manual Pull Station.Deluge Sys Restored to Normal & Personnel interviewed.W/891115 Ltr 1993-06-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1988-0151990-05-16016 May 1990 LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed 05000322/LER-1986-0391990-05-16016 May 1990 LER 86-039-01:on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated 05000322/LER-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02:on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 1997-05-01
[Table view] |
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Dear Sir:
In accordance with 10CFR50.73,. enclosed are Shorehara Nuclear Power
-Station's Licensee Event Reports, LER 86-029 Rev 2 and LER 88-015 Rev 1. 1 Sincerely yours, ,
,g Jack A. Notaro Plant Manager JN/RP/jp Enclosure cc: Thomas T. Martin, Regional Administrator Institute of Huolear Power Operations, Records Center American Nuclear Insurers SR2.A21.0200 phf j@h , ,
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F ACILITY NA4 6 H) DOCEL T NUMOtR m FAGE I3i c:hnrnh,m Nein,r tw.nr es% Tw * , OI51010l013I? D 1 l0Fl o la itTLt 144 ESP Actuations Due to EPA breaker Trips While RPS Power was being Supplied by the M rnrnwn vnna mennennwr tVENT DAf t (Si LIR NUMetR tel RIPORT DAf f th OTMin f ACILITits INv0LvtD its 8 ActuT. N Auts DOCKlf NvMtitMist MONTH DAY YEAR veAR " QM k"'
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On five separate occasions while RPS power was being supplied.from the Alternate Feed Transformer (1071-T-001), a loss of RPS power
>>ccurred due to the spurious tripping of the Alternate Feed EPA breakers. The events occurred on the following dates: 7/18/86 at 1406, 7/19/86 at 0554, 7/19/86 at 0821, 7/21/86 at 1404 and on 5/8/87 at 0636. The first three occurred when "A" RPS was on the c2 l
alternate feed and the last two occurred when "B" RPS was on the alternate feed. On each loss of power a half reactor trip occurred along with a half NSSSS isolation, RWCU isolation and RBSVS/CRAC initiation. The plant was in Operational Condition 4 (Cold Shutdown) for all five events with the mode switch in Shutdown and all rods inserted in the core. After each trip, operators took the appropriate actions necessary to restore the affected systems to normal. A temporary procedure was implemented to monitor the system (RPS) when RPS power was being supplied by the alternate feed transformer. No abnormalities were observed during this period. A spare EPA breaker was bench tested to determine if the breaker was the cause of the trips. The voltage regulator output voltage was also checked. This supplemental report is being submitted to outline c2 the results of the investigation and corrective action.
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PLANT AND SYSTEM IDENTIFICAT.10H j General Electric'- Boiling Water Reactor Energy' Industry Identification System (EIIS) codes are identified i in the text as [xx).
.lDEHTIFICATION_OE.,_THE_ EVENT Five unplanned automatic actuations of' ESF systems [ Half RPS, half Nuclear Steam Supply Shutoff System isolation (NSSSS), Reactor Water Cleanup isolation (RWCU), and a Reactor Building Standby Ventilation System (RBSYS) / Control Room Air' Conditioning (CRAC) System- ;
initiation) due to loss of RPS power resulting from spurious tripping of the Alternate Feed EPA breakers.
Event.Date: 7/18/86
<2 Report Date: 3/16/90 CONDITIONS ERIOR TO THE EVENT Operational Condition 4 (Cold Shutdown) (all five events)
Mode Switch - Shutdown (all five events)
RPV Pressure = 0 psig (all five events) RPV Temperature a between 99 degrees F and 108 l
L degrees F for all five events L ' DESCRIPTION _QE;THE EVENT On five separate occasions while RPS power was being supplied from L
the Alternate Feed Transformer (1071-T-001), a loss of RPS power I
occurred due to-the spurious tri:..ing of the Alternate Feed EPA breakers. The events occurred on the following dates: 7/18/86 at 1400, 7/19/86 at 0554, 7/19/86 at 0821', 7/21/86 at-1404 and 5/8/87 at 0636. The first three occurred when "A" RPSRPS was on the alternate was on the feed and the fourth and fifth occurred when "B"
alternate feed. On each loss of power a half reactor trip occurred along with a half NSSSS isolation, a RWCU isolation and an l RBSVS/CRAC initiation. The first incident was thought to have been l
caused by maintenance workers in the area of the EPA breakers who i may have accidentally bumped the breakers. However, after the l
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LICENSEE EVENT REPORT (LER)- ,,lgf#o',f3M"o 'j;f"h,'
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. OF MANAGEMENT AND 9uDGEY,WA$HINGTON, DC 20603.
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1 uccond trip (and after it was determined that no one was in the I vicinity of the EPA breakeru), operators attempted to restore the "A" RPS MG set to operation. It was tagged out of service for the purpose of Instrument and Controls (I&C) surveillance testing.
Before normal "A" RPS power could be restored, the third trip occurred. After the third trip,'the I&C section was requested to check the operation of the EPA breakers lo ensure that they were functioning properly. Technicians found the voltage trip setpoint to be at the high side of the acceptable band and lowered it to try l and correct the problem. At this time the problem seemed to have been corrected. The fourth trip occurred when the "B" RPS MG set L
I was tagged out of service for surveillance testing. After the fourth trip, the problem was believed to be with something other than the EPA breakers. The Operating Engineer directed the Control Room to not use the alternate feed power supply until the root cause could be identified and corrected. Temporary Procedure TP 23.312.02,-Testing of RPS Alternate Supply EPA Breakers, was performed to determine why spurious EPA breaker trips were occurring when an RPS bus was being supplied from the alternate feed transformer. The results of this test indicated that no voltage or current fluctuations were occurring. A spare EPA breaker was bench tested to determine if the breakers were the source of the problem.
However, no failures were observed during these tests. Since a cause for the EPA breaker trips could not be determined and since the investigation had not discovered any problems, the alternate feed supply was allowed to be used again. The fifth trip occurred when the "B" RPS power was being fed from the alternate feed 4 ~1 transformer due to the "B" RPS MG Set being tagged out of service for preventive maintenance. After the fifth trip of an EPA breaker the voltage regulator (installed between the-alternate feed transformer and the EPA) was inspected and found to be working in accordance with the vendor manual. However, the output of the voltage regulator was only 119.7 V. Its output was then adjusted to 121.5 V. TP 23.312.02 was again performed between 7/28/87 and 10/9/87 to determine if the voltage regulator was working properly.
During this period, no voltage fluctuations were observed. Since the adjustment of the alternate feed transformer voltage regulator output, no further trips of its associated EPA breakers have occurred.
After each trip, operators took the appropriate actions necessary to restore the affected systems to normal. In each case, Plant Management was notified of the event and the NRC was notified per 10CFR50.72.
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FACILifY NAuttil 00 CELT Numeun(21 LIR NUMSER 461 Pact (31 viaa "Otl:P. 3*30 Shoreham Nuclear power Station Unit 1 o l5 l0 l0 l0 l 3l2 l 2 8l6 0l2l9 -
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CAUSE OF THE EVENT The cause.of these events was the low output voltage of-the alternate feed transformer (1071-T-001). The output voltage was e2 119.7 V which was too close to the upper limit of the EPA breaker undervoltage trip (118.9 V).
ANALYSIS _OF THE EYEHT These events resulted in unplanned automatic actuations of ESF systems (1/2 RPS, 1/2 NSSSS, RBSYS/CRAC and RWCU) and is reportable per 10CFR50.73(a)(2)(iv). There is minimal safety significance to the events. All systems operated as designed. Operators carried out all required actions. Had this event occurred under a more severe set of circumstances (5% power), the safety significance would still be minimal.
CORRECTIVE ACTIQHS
- 1. The output of the voltage regulator was adjusted from 119.7 to 121.5 V. This latter value is approximately midway between the-EPA undervoltage and overvoltage setpoints.
l l 2. . Station' Procedure SP 44.611.02, RPS " EPA" Breaker Calibration l and Functional Test, was revised to reqaire that the output voltage of the voltage regulator be verified and recorded.
L 3.- Preventive Maintenance activity, 1C71-410E/E-001-4010, was e2 '
written to require periodic cleaning and inspection of the voltage regulator.
- 4. Surge arrestors were installed on the high side of the RPS alternate supply transformer. These devices will prevent most voltage spikes from passing through to the EPAs.
ADDITIONAL _INFORMATION i a. Manuf.ncturer and_model.numher_of_ failed _ component _Lal I
None
- b. LEB_ numbers _sf_nreylons_similar_ey.ents87-011 (2 89-001 1
i tac f.an 3esa (640
,