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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Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr 05000456/LER-1988-012, Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits1989-04-21021 April 1989 Advises That LER 88-012-00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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Rout 3 c1, Box 84 kg; ("
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. _ Braceville, Illinois 60407 Telephone 815/458 2801 g/
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May 16,1990 BW/90-0525 - 1 l
U.' S, Nuclear Regulatory Commission ,
' Document Control Desk '
Washington; D.C. 20555
?
Dear Sir:
The enclosed Licensee Event Report from Braldwood Generating Station is being transmitted to you in accordance with the requirements of -
10CFR50.73(a)(2)(v) which requires a 30-day written report.
T This report is number 90-004-00; Docket No. 50-457. !
Very truly yours,
- f&s, a R. E.' Querto -
Station Manager ,
Braldwood Nuclear Station L ,
, REQ /JDW/jfe . y E
- (71261) j 4
Enclosure:
Licensee Event Report No. 90-004-00 .
I cc: NRC Region 111 Administrator ,
NRC Resident inspector INPO Record Center ;
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. LICENSEE EVENT REPORT (tER). g Ficility Nan.e (1) Docket Number (2) lage (3)
Jta[dwggd 2 015lOl_QJ0141517 1!ofl0l3_
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'2A DieselJeneLLt.9r Speed Oscillations due_in_alefective Resister. !
lytnLDAte_15) _ LELuumbeE_1fd _ leAnti late (7) 0theElacilitleLinyJ1vedl0) b Month Day Year Year /// Sequential //p/ Revision Month Day Year Facilliv_Namel._ JagletJudgris1 jf (fffLt.Judkr LLL lv&tr i Nont Ol'51 01 01 01 l i
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__Q I 4 11 6 91 0 91 0 0l014 Q_l 0 0l5 . Il 4 91 0- 01510101Ol l i THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10CFR OP N M I EI N 1 n2 W H0DE (9) 6 20.402(b) _ 20.405(c) _ 50.73(a)(2)(iv) _._. 73.7)(b)
POWER __ 20.405(a)(1)(1) ___ 50.36(c)(1) L 50.73(a)(2)(v) _._ 73.71(c)
LEVEL. , , ._ 20.405(a)(1)(li) _ 50.36(c)(2) __ 50.73(a)(2)(vil) ___ Other (Specify j (10) J_lj) 1 0- __ 20.405(a)(1)(iii) ._ 50.73(a)(2)(1) _. 50.73(a)(2)(viii)(A) in Abstract
////////////////////////// __ 20.405(a)(1)(iv) __ 50.73(a)(2)(li) _.__ 50.73(a)(2)(viii)(B) below and in
////////////////////////// __ 20.405(a)(1)(v) _. 50.73(a)(2)(iii) _ 50.73(a)(2)(x) Text)
LICENSEE CQHIACT FOR THIS LER (121 Name. TEf,Ef11QMEJV!101R AREA CODE jin GrtemLki . Tech Staf f Io.g. Ext. 2M2 8l115 415181 -l 2Le.llL1 COMPLETE ONE LINE FOR EA_CH_COM 0 FAILURE DESCRISID IN THlilEPORT (13)
CAUSE- SYSTEM COMPONENT MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT HANUFAC- REPORTABLE TUB 18__ TO NPRD$ TURER TO NPRDS j
.E l IL X l llLc J.LZl 91 0 Y l l l l i 1._j l l l l 1 l l l l l l 1 l l SUPPLEMENIALELEDRT EXPLCTED (14) Expected Month l Day _1_ygar Submission J.jJO Date (15) ll l1 i
._lY31 (If veb tQmplele_EKEECIED..SW_MISS104.DAJE.) 1 ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16)
At 0315 on April 16,1990 the 2A Diesel Generator (DG) was started to perform a four hour warm up run. The !
DG started normally and achieved rated speed of 600 RPM. Shortly af ter startup the DG speed began ;
escillating between 300 and 600 RPM. The 2A DG was immediately shut down. At 0913 it was identified that th3 cause of the speed oscillattuns was a failure of one of the dropping resistors in the Governor Unit. The rssistor was replaced. This resistor had f ailed on the IB DG severcl weeks earlier. Byron Station, which has four DGs that are identical to Braidwood DGs, had experienced a failure of this resistor also. At 1607 the 2A DG was started for a maintenance test, DG speed remained constant at 600 RPM. At 1653 the 2A DG was !
sttrted for its monthly operability run. The DG had successfully completed the test. DG speed had remained constant at 600 RPH. At 2118 the 2A DG was declared operable. The root cause of the event was component failure, fhe resistor in the governor power-dropping resistor board failed creating an open circuit. An evaluation of the failure mode of the resistor was conducted. It has been concluded that the cause was simple long term heat fatigue. The resistors have been replaced on all DGs at the station, and placed on a three year replacement frequency. The resistor is being evaluated for 10CFR part 21 applicability.
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LIEENSIE EVENT REPORT _.(1g) TEXT EONTINUATION form R M FACILITY,'NAME (1) DOCKET NUMBER (2) _111LtN@iR __f 6) Page (3) _
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_StAldM0.0d.2= 0 l 5 l Q_jJ_LQ_ljjJl 7 910 - 0 IJ,.}_fl - 0 IJ_J[J.JLJjj f TEXT- Energy Industry Identification System (E!!$) codes are identified in the text us (XX) -l t
' A. PLANT CONDITIONS PRIOR TO EVENT: [
' Unit: . Braidwood 2;
, Event Date: 04/16/90; Event Time: 0315;-
Mode: 6 - Refueling; Rx Power: 0%;
RCS (AB) Temperature / Pressure: Ambient / Atmospheric
- B.. DESCRIPTION ~0F EVENT
' Th;re were no systems or.cumponents inoperable at the beginning of the event which contributed to the severity of -
th) event.
At 0315 on April '16i 1990 the 2A Diesel Generator (DG) (EK) was started to perform a four hour warm up run in-pr paration for its scheduled 18 month maintenance inspection.- The 2A DG started normally and achieved rated speed of 600 RPH and nonnal voltage of about 4.16 KV. Shortly af ter startup the 2A DG speed began oscillating between 300 and 600 RPH, The 2A DG was immediately shut down.
At 0913 it was identified that the cause of the speed oscillations was a f ailure of one of the dropping resistors -
in the Governor Unit. The resistor was replaced. The equivalent resistor on the IB DG had failed several weeks earlier during maintenance. Byron Station, which has four DGs that are identical to Draldwood's DGs, had -
experienced a failure of this resistor also. This event was screened for reportability. Based on the failures sxperienced at Braidwood and Byron _ lt was determined that a four hour non-emergency report was' appropriate pursuant to 10CFR50'72(b)(2)(lii)(A). .
The appropriate NRC notification via the ENS phone system was made at 1220.
1 At 1607 the 2A DG was started for a maintenance test. The DG successfully completed the test. DG speed remained constant at 600 RPM.
At 1615 the 2A DG was shut down.
At 1653 the 2A DG was started for its monthly operability run.
- At 1819 the 2A DG was shut down. The DG had successfully completed the test. DG speed remained constant at 600 RPH.
At 2118, following the completion of the reviews of the test run data and the work package, the 2A DG was declared
=op;rable.
This event is being reported pursuant to 10CrR50.73(a)(2)(v)(A)-an) event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to shutdown the reactor and maintain it in a safe shutdown condition.
l I
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Ll(IN$LE_[yLNT RWLRJ__11ER) TEXT C0HILWA11QN Fore Rev 2.0
' FACI,LITY NAME (1) DOCKET NUMDER (2) ,_._L M _M M ER (6) 'Paoe (3 _
Year // Revision
/,/,/j/ Num_her j//
/ Number
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. TEXT- Energy Industry Identification System (EIIS) codes are identified in the text as (XX)
LC2CAUSEOFEVENT:
The root cause of the event was component failure. The resistor in the governor power-dropping resistor board failed open. The f ailed resistor is one of 2 resistors in parallel on the positive lead of the governor's DC power _ supply. With one of the resistors f ailed, creating an 'open circuit, the voltage drop across the remaining resistor increased resulting in insuf ficient power supply to the governor. An b =cvaluation of the failure mode of the resistor was conducted by Sargent and Lundy Engineers. Based on the results of this evaluation it has been concluded that the cause was simple long term heat fatigue.
D .' SAFETY ANALYSISI This event'had no effect on the safety of the plant or the public. The 2B DG was operable and available throughout the event. Only 1 DG is required in Mode 6.
Under the worst case conditions of this f ailure occurring af ter a valid initiating signal. following a Safety !
Injection there would still be no effect. The redundancy of the safety system design provides for full safe I shutdown capability from a single ESF bus. The diversity of the electrical distribution system provides for powering an EST bus f rom its System Auxiliary Transformer, its own Diesel Generator, or its corresponding ; !
opposite Unit ESF bus which is capable.of being powered from its Diesel Generator or System Auxiliary Transformer. This is enveloped in section.8 of the Updated Final Safety Analysis Report.
E. CORRECTIVE ACTIONS:
B:th power dropping resistors in the 2A, lA and IB DG were replaced. These resistors had been replaced on April 4, 1990 for the 2B DG.
> These resistors have been'placed on a replacement frequency of three years in accordance with the reconmiendations of the Engineering evaluation.
Thr resistor is being evaluated for 10CFR part 21 applicability. This' action is being tracked to completion *
- by action item 457-200-90-01001.
F. PREVIOUS OCCURRENCES:
Th2re have been no previous similar reported occurrences at Braidwood Station.
G. COMPONENT FAILURE DATA:
Manufacturer Nomenclature Model Number / MFG Part Number 'I i
Pacific Resistor 100 CH 300 ohm 70 watt resistor Note: This item supplied as part of the Woodward Governor Model 2301.
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'3011m(0$1090)/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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