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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Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr 05000456/LER-1988-012, Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits1989-04-21021 April 1989 Advises That LER 88-012-00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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. . - . .
.: .. Commtnwocith Edison
- Brcid food Nucitar Power Stction Route #1, Box 84 Braceville, Illinois 60407 l Telephone 815/458 2801.
June 28,1990 BW/90-0664 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 90-007-00; Docket No. 50-456.
Very truly yours, l
R. E. Querto jd>
Station Manager Braidwood Nuclear Station REQ /JDW/sjs (7126z)
Enclosure:
Licensee Event Report No. 90-007-00 cc: NRC Region 111 Administrator NRC Resident inspector INPO Record Center CECO Distribution List o
9007060250 900628 DR- ADOCK0500g{6 1
I l LICENSEE EVENT REPORT (LER) 7 Facility Name (1) Docket Number (2) _Eagt,(3)
Jtaica : _
J13LD1ola.lJ.lajL.13efjd3 Title (4) Inadverted $ tart of the 1A Auxillary f eedwater Pump due to TestingPethodohyDeficiency a
iranLDt1edi.) LER h'c.ithtf If.} .AtPott_D.a.teJ L 0tbar LasilititLiny.ohed_t61 .
Month . Day Year Year jjj j/
/// Seque0tlal /jj/ Revision Month Day Year _Jacl11t v HAmtL _0.etlti_NahtIhl UL Juektl _ LLI JunktL 1 None ._013LOL010lJ l 1
~~~
0j_L 01 1 91_0_ 9l 0 0 1.0 l 7 _ _0_j_0 0 J }_jI _B 91 0 _0L5.LoJ_0J_01_1 I OPERAllNG LCh'LL'AI~'E-more the N ioyJD9}_{ll)
H0DE (9) 1
_ 20.402(b) ,.__ 20.405(c) .L 50.73(a)(2)(lv) _.,_ 73.71(b)
POWER _ 20.405(a)(1)(1) _ 50.36(c)(1) 50.73(a)(2)(v) __, 13.71(c)
LEVEL 20.405(a)(1)(ll) .__ 50.36(c)(2) _ 50.73(a)(2)(vil) _ Other (Specify l
_L] 0.) D___l ._9_0 _ .___
20,405(a)(1)(1ii) ___ 50.73(a)(2)(t) ._ 50.73(a)(2)(viii)(A) in Abstract mfm - ro *( " "" > - so '3( "z"" > - 5073( "2" "'"" 6' d '"
mfm/
gg///m//m///m//m/gg
/ / _ 20.405(a)(1)(v) _ 50.73(a)(2 Hill) ._ 50.73(a)(2)(x) Text)
LICEMSEL(QtilACT FOR THIS LEB 1J21 Name 1[LLEliONE_lNt91R AREA CODE 11All_(av.utiPESlootdinater Egtu2957 _ e LLil. 41JLeL-12LeLDL1 1 CQMPLETE O!(LLINE FOR EACtLCDtiEDMEN1_ FAILURE DL1[RIBED IN f tilSJ[EQRT (13)
CAUSE SYSTEH COMPONENT HANUFAC- REPORTABLE / CAUSE SY31EH COMPONENT MANUfAC. REPORTABLE l
_ _TURER TO NEED.$ _l#E[R TO NPRD$_ i
. J. JJ_I_ l i I I _ L l .L J _L.I._ l i i i i i I i _
i i i i J.J J _
l
$UPPLEMENTAL REPORT EXPECTED (14) Expected tienth l D.ty_jltar i Submission Date (15) l l
-_ ]Yes H f.ye b somple.it E EE.CIED_SVDtt!S$10M.DAIE) X. l .M _._l I . ! L_L ABSTRACT (Limit to 1400 spaces, i.e. approximately fifteen single-space typewritten lines) (16) ,
1 l
On June I,1990 a Reactor Operator (RO) was performing a $ lave Relay Surveillance that tested the 1A Auxiliary Fe:dwater Pump (AT) Steam Generator low Low Level Auto Start Actuation Relay, K633. This relay was part of the l Solid State Protection System. As part of the restoration portion of the procedure the resistance across the rolcy contacts was measured to verify an open circuit prior to enabling the system. At 0927 the NSO measured the !
r:;sistance across terminals 1 and 2 of relay K633 in accordance with the procedure. While maintaining one of the i ohmetsr probes on terminal 2 the HSO removed the probe from terminal 1. During the removal of the probe the N$0 l In:dvertently touched the probe to the exposed terminal point 13 on relay K633. This created a current path from !
a p:rallel circuit through the ohmeter to the starting relay for the 1A AF pump. This resulted in the auto stcrt of the pump. The 1A AF pump control switch was immediately placed in the " pullout" position and the pump was secured. The cause of this event was a methodology deficiency which is considered a programatic d2ficisncy. Ohmeter probes have been modified to reduce the esposed metal surf aces to a small portion of the tip. Alternate locations for obtaining the readings will be used. Training will be provided, Previous corr ctive actions are not appilcable.
3036a(062190)/2
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tlLEN$LLIYENT _ REPORT f LER) TERII.QKIDfy61]QN f omJty19. .
FACIEliY NAM (1) DOCKET NVPSER (2) = ,1EfLHUtgER (6) Pegg&}_ '
Year g Sequential g Revision
- l-I i.
11r 1Nektr la Haktt-o 0 LLLn_LoJJJaL513_9._Ln JJJJ1 - .0.Ln_ '
3fethatic .
JL2 JL JL3 TEX.i Energy Industry Identification System (fil$) codes are identified in the text as [XX} j A.. PLANT CONDITIONS PRIOR 10 EVENT:
Units' Braidwood 111 Event Date: June 1, 1990: Event ilme 0927; '
iModet .1 - Power Operation; Rx Power: "B%%I !
<RCS (AB) Temperature / Pressure: NOT/NOP q
- B. DESCRIPTION Of EVENT. i There were no systees or components inoperable at the beginning of the event which cor'tributed to the severity of tha event. A Nuclear station Operator (NS0) (Licensed Reactor Operator) was performing Braldwood Operating _
. Surveillance (BwCS 3.2.1-941 Unit One Quarterly Slave Relay Surveillance (Train A - K633)). The procedure tested
.the_1A Aunillary feedwater Pump (Af) (BA) $ team Generator Low Low tevel Auto Start Actuation Relay, K633, which
, w s an output function of the Solid State Protection System (SSP $) (JE). As part of the restoration portion of th> procedure the resistance across the relay contacts was measured to verify an open circuit prior _ to enabling .
the system.
1 .
At 0927 on June 1,1990 the NSO measured the resistance across terminals 'I and 2 of relay K633 in the Train A $$PS
' panel in accordance with the procedure. The value of the measurement indicated an open circuit. While
' maintaining one of the chimmeter probes on terminal 2 the NSO removed the probe f rom terminal 1. During the removal of the probe the NSO inadvertently touched the probe to the exposed terminal point 13 on relay K633. This }
cr:ated a current path frein a parallel circuit through the ohnneter to the starting relay for the 1A AT pump.
This resulted in the. auto start of_ the pump. After verifying the auto start was not required, the IA Af pump control switch was immediately placed in the " pullout" position and the pump was secured.
- The appropriate NRC notification via the ENS phone system was made at 1007 pursuant to 10CfR50.72(b)(2)(ll).
.This event is being reported pursuant to 10CFR50.73(a)(2)(iv) - any event or condition that resulted in manual or automatic actuation of any Engineered Safety feature, including the Reactor Protection System, l -C, CAUSE Of EVENT:.
The root cause of this event was a methodology deficiency. This is considered a programmatic deficiency. The procedure specified taking resistance readings on the relay terminal points 1 and 2. These terminal points are
~ located on the back side of a " dual deck" relay. The spacing between the front row terminal r31nts and the back row terminal points is 2 inches. The spacing between the terminal points on a row either back or f ront, is 3/4 of-an inch. The NSO was provided'wlth an ohnneter with probes that have 9/16 of an inch metal tips. Additionally th; N$0 was required to read a value from the ohmmeter while holding the probes on the terminal points. Due to' the physical layout of the panel the meter cannot be placed near the relay. As a result the NSO was required to. i h31d both a probe. and the ohnneter in one h.and the second probe in the other hand.
A rivlew of the task performance requirements was conducted by personnel tralned in Human Performance Enhancement System-(HPE$) event evaluation techniques. Based on the results of this review it has been concluded that the methodology for task performance places that NSO at a higher than acceptable risk level for creating an Intdvertent actuation such as the one that occurred in this event. The deficiency in the methodology for parforming the task created the event.
3036m(062190)/3
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- [ ' C' L I C ENSELEVENLRLt0RL11LRLICAlf 0HU NUMION rarm.RtL2A
.fACILI,TY NAME.(IL DOCKET NUMBER (2) ._1LR_lNtsIR (61 Page (3)
- Year fj/j Sequential
// /j//
ff Revision UL - 11ektr U1 Uvettet 3raidwood_1 0 L5JJJJJJJ_41_513JJJ_ -
0JJJ 2 -
-0 l _ ct. _ol a _Q L a l_3 TEXI. Energy Industry Identification System (E!!5) codes are identified in the text as (XX) e D. SAFETY ANALYSIS:
'.This event had no effect on the safety of the plant or the public. All systems operated as designed. The safety function provided by the Auxillary Feedwater System was not required and was inappropriate for 4cxisting plant conditions. Discussions on redundant equipment are not appilcable. The AF initiation was n;lther desired or required. There are no reasonsble and credible alternative conditions that would have b2:n more severe.
E. CORRECTIVE ACTIONS:
~Th) 1A AF pump was imediately secured by placing the Control $ witch in the pull out position.
.0hmmeter probes that are used to obtain readings on back row terminal points of dual deck relays have been.
modified to reduce the exposed metal surfaces to a small portion of the probe tip. i l
A review will be conducted to identify the procedures that require readings obtained by placing probes on back: row contacts of dual deck relays. Alternate locations for obtaining the readings on the relays- , ;
id ntified by the review will be used if available. .This action will be tracked to completion by action item l 456-200-90-02201.
< ihis event will be covered in a training tailgate session for appropriate Operating Dept personnel. This f action item will be tracked to completion by action item 456-200-90-02202. i
- F. ,PREVIOU$ OCCURRENCES:
j Thire was a previous occurance of an AF pump auto start during the performance of this procedure. -l LER No. DVR Number Title 50-457/88-006 20-2-88-018 Inadvertent Start of Unit 2 Auxiliary Feedwater Pump Due to personnel Error -j t
The corrective actions were implemented addressing both root and contributing causes. previous corrective ,
actions are not applicable to this event.
G. C0HP0tlENT FAltVRE DATA:
.}
This event was not the result of component failure, nor did any components fall as a result of this event. l I
3036m(062190)/4 n
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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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