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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000457/LER-1993-0061993-08-26026 August 1993 LER 93-006-00:on 930727,2A RHR Pump Motor Bearing Oil Reservoir Unable to Be Drained,During Oil Change.Caused by Corrosion Particles Resulting from Previous Seal Leak.Rhr 2A Pump replaced.W/930826 Ltr 05000457/LER-1993-0041993-08-11011 August 1993 LER 93-004-00:on 930712,time Frame for Performing Core Normalization Surveillance Exceeded Due to Personnel Error. Commenced Performance of Required Surveillance.Surveillance Procedure Bwvs 1.1.1.2-1 Will Be revised.W/930811 Ltr 05000457/LER-1990-0101990-07-0303 July 1990 LER 90-010-00:on 900609,reactor Trip Occurred During Plant Startup from Low Steam Generator Water Level.Caused by Malfunctioning Bypass Feedwater Regulating Valve.Operator Training provided.W/900706 Ltr 05000457/LER-1990-0091990-07-0202 July 1990 LER 90-009-00:on 900604,pressures for Active & Standby Accumulators Identified to Be Below 4,800 Psig Required for Operability.Caused by Component Failure.Four Way Valve & Hydraulic Oil Filter Used for MSIV replaced.W/900629 Ltr 05000456/LER-1990-0081990-07-0202 July 1990 LER 90-008-00:on 900608,reactor Trip Occurred Due to High Flux Rate Signal from Power Range Nuclear Instrumentation. Caused by Voltage Transient,Resulting from Lightning Striking Containment.Power Supply reset.W/900629 Ltr 05000456/LER-1990-0071990-06-28028 June 1990 LER 90-007-00:on 900601,during Removal of Ohmmeter Probe, Operator Touched Probe to Exposed Terminal Point,Resulting in Automatic Start of Auxiliary Feedwater Pump 1A.Caused by Methodology Deficiency.Probes modified.W/900628 Ltr 05000457/LER-1990-0061990-06-18018 June 1990 LER 90-006-00:on 900521,containment Fuel Handling Incident Area Radiation Monitor Failed Automatic Checksource Test Due to Low Count Rate.Caused by Component Failure.Detector replaced.W/900618 Ltr 05000457/LER-1990-0051990-05-24024 May 1990 LER 90-005-00:on 900426,discovered That Diesel Generator 2A Starting Air Distribution Sys Tubing Crisscrossed to Cylinders 6L & 9L.Caused by Preservice Mfg Deficiency. Custom-routed Airlines replaced.W/900524 Ltr 05000457/LER-1990-0041990-05-14014 May 1990 LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillations Occurred Due to Defective Resistor.Caused by Failure of One Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr 05000456/LER-1988-012, Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits1989-04-21021 April 1989 Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 1993-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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..- L Commtnwocith Editin Braldwood Nucttar Power Station
.- Route #1, Box 84 sl j'.
Brueville, !!linois 60407 h . Telephone 815/458-2801.
June 29,1990 BW/90-0671 y
.n U.' S, Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Dear Sir:
The enclosed Licensee Event Report from Braidwood Generating -
Station is being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(iv) which requires a 30-day written report.
This report is number 90-008-00; Docket No. 50-456.
Very truly yours, R. E, Querto Station Manager-
- Braldwood Nuclear Station REQ /JDW/sjs
. (7126z)
Enclosure:
Licensee Event Report No. 90-008-00 cc: NRC Region Ill. Administrator NRC Resident inspector INPO Record Center CECO Distribution List
'3 9007090202 900702 7 PDR ADOCK 05000456
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LICENSEE EVENT REPORT (LER)
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Reactor Trip due to Lightning Induced Voltage Transient in the Rod Control System, t
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ABSTRACT (Limit to 1400 spaces, i.e. approximately fif teen single-space typewritten .Ilnes) (16) j
.On lune 8, 1990 there was heavy thunderstorm activity in the Braidwood Station area. At 0618 a reactor trip '
' occurred on Unit I due to a high flux rate trip signal f rom the Power Range Nuclear Instrumentation. - The ~
Reactor Operators verified all automatic actions. All systems functioned as designed. Stable plant '
f c:nditions,were immediately established. An examination of the Rod Drive (RD) Power Cabinets indicated the power supply over voltage protectors (P50VP) had tripped in three of the RD Cabinets. There were no blown fus:s identified in any of the; cabinets. The PSOVP's were reset and all voltages were checked.. The root [
cause of this event was a! voltage transient. It is believed that Ilghtning struck the Unit 1 Containment and
--caused a voltage surge in the station ground system. This caused the activation of PSOVPs in the three RD !
" ' Pow:r Cabinets. This shut of f the current to the stationary gripper coils of the rods powered by the c binets, and caused them to drop, resulting in a negative flux rate. The negative flux rate was of-suf ficient magnitude to activate the reactor trip signal f rom the Power Range Nuclear Instrumentation. No i dtmage.; occurred to the RD system. A review of the station lightning protection system is being conducted.
Th2 Station had made modifications to the RD power supply system and the station grounding system as corrsctive measures from previous events.
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.A.~; PLANT CONU1110NS PRIOR TO EVENT:
EUnit:- Braldwood,1:- Event Date: June 8, 1990; Event Time. 618;.
, _ Hodeth: I f. Power Operation,-
Rx Powert 1007.; ,
- RCS (AB). Temperature / Pressure: ;N01/NOP, e;L (8.'OESCRIPi!0NOF_ EVENT:
'There were no: systems or components' inoperable at the beginning of the event which contributed to the severityLof? N the event.' < y
~
Thtre was heavy thunderstorm activity in the Draldwood Station area at the time of the event.
At. 0618'on June 8.1990 a ReactorL Trip occurred on Unit 1 due to a high flur rate signal f rom the Power RangeL Nuclear Instrumentation (NR) (IG).
hTheNc'learSta'tionOperators(LicensedReactorOperators)verifiedall'automaticactions..-'All. systems' functioned :I
'Jas: designed. : Stable plant conditions were isonediately established.
An' examination of the Rod Drive (RD) [AA) Power. Cabinets indicated the following:
J1RD02Jl(SCDE) .' L'rgent alarm SIRD03J (20D) - Urgent alarm
?tRD04J (2AC): . Nu alarms, both +24 VDC Power Supply (PS) Over Voltage Protectors (OVP) tripped
- 1RD05J (100)'- Non-urgent alarm, with one PS'0VP tripped
- 1RD06J (1AC)
. No alarms, both +24 VDC PS OVP's tripped .
There were no blown fuses identified'in any of the cabinets. The PS OVPs were reset aid all voltages were checked. ,j Ti$eUnit2R0=PowerCabinetswereInspected.' They were not affected by this event. :j E '
. . ~1 E ITh)' appropriate NRC notification vla the ENS phone system was made at 0815 pursuant to 10CFR50.72(b)(2)(li).
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.This event:is being: reported pursuant to 10CFR50.73 (a)(2)(lv) - any event or condition that resulted in manual or j automatic {actuationofanyEngineeredSafetyFeature,includingtheReactorProtection' System. j I
C[CAUSEOFEVENTI
[Tharoot'causeof.thiseventwasavoltagetransient. It is believed that lightning str the Unit 1 Containment Land-caused a voltage surge in the station ground system. This caused activation of the +d s PS OVPs in the 1AC andl2AC-'R0 Power Cabinets which shut of f the current to the stationary gripper coils of Sht. t .i Dank A and !
.Centrol Dank A f. C. This caused -the control rods to drop which resulted in a negative ~ flor ue. The' negative fluxirate was of suf ficient magnitude to activate the reactor trip signal f rom the Power R .. ige Nuclear ;,
Instrumentation, e ,
The exahl, location ~of the 11ghtning strikes and the dissipation path is still unknown. ,
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- TEXi- . Energy Industry Identification System (E!!$) codes are identified in the text as (XX)
D. :$AFETY ANAL.Y$l$1 This event had no effect on the safety of the plant or the public. All systems operated as designed.
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V Both~ trains of Reactor protection and ESI were operable and perf ormed their functions as-designed.
1he' Unit =was operating at 100% power which is the worst case condition for this type of event. Tne RD system
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-is designed to be 1nherently safe as rod insertion results on loss of power as was the case in this event '
t. CORRECTIVE AC110N$1-1hiinviediate corrective actions were to reset the p$ OVPs and verify RD system operability. No damage occurred to the RD system.
Coamionwealth Edison Engineering, Sargent 8 Lundy, and Westinghouse are conducting a review of the station' lightning protection system. -Further investigation and implementation of a lightning protection system is in.
.pregress. The results of this investigation will be tracked to cornpletion by action item no.
! 456-200-90-0230).
FL PREVIOUS OCCURRENCES:
There have been *hree previous occurrences of a lightning induced voltage transient resulting in a reactor trip.;
DVR Nulnher Title 20-1-88-240/88-02's Instrument failures on Unit I and Reactor Trip on Unit 2 as a Result of lightning Induced Voltage Transients 20-1 89-104/C9-0 W Unit 'I and Unit 2 Reactor Trip as a Result of Lightning Induced Voltage Transients Affecting the Rod Control System 20-2-89-075/89-004 Reactor Trip as a Result of Lightning Induced Voltage Translents Af fecting' the Rod Control System.
(The' Station had increased the time delay on the pS OVps and inve roved the station grounding system as icorrective' actions from previous events.
n ..
G. ' COMPONENT FAILURE DATA:
! This event was not the result of component failure, nor did any compenents f all as a result of this event.
L3041m(062690)/4'
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05000457/LER-1990-004 | LER 90-004-00:on 900416,diesel Generator 2A Speed Oscillations Occurred Due to Defective Resistor.Caused by Failure of One Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr | | 05000457/LER-1990-005 | LER 90-005-00:on 900426,discovered That Diesel Generator 2A Starting Air Distribution Sys Tubing Crisscrossed to Cylinders 6L & 9L.Caused by Preservice Mfg Deficiency. Custom-routed Airlines replaced.W/900524 Ltr | | 05000457/LER-1990-006 | LER 90-006-00:on 900521,containment Fuel Handling Incident Area Radiation Monitor Failed Automatic Checksource Test Due to Low Count Rate.Caused by Component Failure.Detector replaced.W/900618 Ltr | | 05000456/LER-1990-007 | LER 90-007-00:on 900601,during Removal of Ohmmeter Probe, Operator Touched Probe to Exposed Terminal Point,Resulting in Automatic Start of Auxiliary Feedwater Pump 1A.Caused by Methodology Deficiency.Probes modified.W/900628 Ltr | | 05000456/LER-1990-008 | LER 90-008-00:on 900608,reactor Trip Occurred Due to High Flux Rate Signal from Power Range Nuclear Instrumentation. Caused by Voltage Transient,Resulting from Lightning Striking Containment.Power Supply reset.W/900629 Ltr | | 05000457/LER-1990-009 | LER 90-009-00:on 900604,pressures for Active & Standby Accumulators Identified to Be Below 4,800 Psig Required for Operability.Caused by Component Failure.Four Way Valve & Hydraulic Oil Filter Used for MSIV replaced.W/900629 Ltr | | 05000457/LER-1990-010 | LER 90-010-00:on 900609,reactor Trip Occurred During Plant Startup from Low Steam Generator Water Level.Caused by Malfunctioning Bypass Feedwater Regulating Valve.Operator Training provided.W/900706 Ltr | |
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