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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Dropping Resistor in Governor Unit.Resistors replaced.W/900516 Ltr 05000456/LER-1988-012, Advises That LER 88-012-00 Withdrawn.Investigation Revealed That Operator Did Indicate That Room Temps Less than Tech Spec Limits1989-04-21021 April 1989 Advises That LER 88-012-00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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text
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3 Commonwealth Edison-- .
'- / V)- IValdwood Route #1, Box Nucleir Powtr St; tion .!
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84 -
h / ' Bracoville, Illinois 60407
\x j Telephone 815/458-2801:
.t w ,
i May 24,1990 ,
BW/90-0566
+
i
.t U. S. Nuclear Regulatory Commission Document Control Desk l 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)(1)(B) which requires a 30-day written report. j This report is number 90-005-00; Docket No. 50-457.
i Very truly yours, ic .t j
L R. E Querlo l Station Manager Braidwood Nuclear Station i REQ /JDW/jfe '
-(7126z) l
Enclosure:
Licensee Event Report No. 90-005-00 l cc: NRC Region Ill Administrator NRC Resident inspector INPO Record Center CECO Distribution List p .
i 9005300.163 900324 PDR g2.b 6 ADOCK 05000457 p' PDC g .d4 .
(l r
LICENSEE EVENT REPORT (LER) 7 Facility Name (1) ., Docket Number (2) fastl31
.ItteldEonL2 fjLojaLQlAJl_.L1_of! 0 ! 3 Title (4) Diesel Generator Crisscrossed Starting Air Distribution System Tubing due to Pre-service Manufacturing Deficiency c _IrtoLQittJ5) LER_NumhtI_(f) RtP2tLQaitJ1} Othatltillilles InvohtL18)
Month Day Year _ Year /// Sequential // Revision Month Day Year .ltiility Ngings._ aptit13gmitIls) ff
//j/ Number
/j/j f
// Number.
Nont O!510]Ojj l l al 4 21 6 RLL ala_ -o_Lo I 5 J J _ L _0_L L all 3 Lo _0J3!AlL01J__L OPERATING ifhetLgat_gr more of the followingLill) !
20.402(b) __ 20.405(c) _. 50.73(a)(2)(lv) 73.71(b) )
-_ POWER 20.405(a)(1)(1) _ 50.36(c)(1) 50.73(a)(2)(v) ._ 73.71(c) l LEVEL _ 20.405(a)(1)(ti) __ 50.36(c)(2) 50.73(a)(2)(vii) _ Other (Specif y !
(10) ,_Q_ Q ! 0_ ._. 20.405(a)(1)(iii) l 50.73(a)(2)(1) __ 50.73(a)(2)(viii)(A) in Abstract
/ j/ j j/ j j j j /j j j j j j j/ j j j/ j j j/j j j /j j/ //// ///// 20.405(a)(1)(iv)
// /// // / _._ 50.73(a)(2)(li)- _._ 50.73(a)(2)(viii)(B) below and in i
/
g g g g g g jff _._ 20.405(a)(1)(v) __ 50.73(a)(2)(ill) ._ 50.73(a)(2)(x) Text)
LICENSEE CONTACT FOR THIS_LER (12)
Name TELEPHONE NUti)ER AREA CODE
.11m Grrtinski . Tech _S14f.f F.Dgr. Ext. 2402 _8_ l 1_ IJ_ lilllL-JallLold C0tiPLETE bHE L1HL[0R_EACH CQti?ONEN FAILURLDESCRIDIQ_1R.Iti1LREEORT (131 )
CAUSE SYSTEH COMPONENT MANUFAC- REPORTABtE CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE y
._JDRER _10JERQL JURER 10JERDL I I _LJ l !I I - _
l i I I I I I '
I LJ ! I I I i 1I I L_L.L. f iVffLEMENTAL REPORT EXPECTED (14) Expected tivnth I Day l Yes.t I Submission
- (
lyes (If vis. complete EXPECTED SUBMISSION DATE) X l _ NO l ll j_
ABSTRACT (Limit tc 1400 spaces, i.e, approximately fifteen single-space typewritten lines) (16) i On April 26, 1990 during the performance of scheduled maintenance on the 2A Diesel Generator (DG) a crisscross of the starting airlines for 2 cylinders was discovered while time checking each individual cylinder. These time checks had been added to the inspection as a corrective action from a previous event involving the IB DG. In that event the starting airlines had been crisscrossed at couplings following exhaust manifold replacement. The error on the 2A DG occurred during the custom routing of the tubing into th) starting air distributor. This routing is performed during the original manufacturing process. With the !
existing custom tubing it was not possible to obtain a simple airline swap. A review of the starting -l histories for the 2A DG Indicated that the crisscross of the starting airlines did not significantly ef fect i thy performance of the 2A DG, The 2A DG had experienced only one " slow start" f ailure and had experienced 43 {
successful starts since the completion of pre-operational testing. The cause of the event was pre-service ranufacturing deficiency. The defective custom routed airlines were replaced. The inspection that identifled this deficiency was part of the corrective action for a previous event. This inspection has been l I
completed for 3 of the 4 DGs and will be completed for the remaining DG, This event has been submitted to engineering for 10 CFR part 21 consideration.
3017a(052390)/2
C..
m .
'i1EENSEE EVENT RENILT (LER) . TEXT EONTINUATION Form Rev 2.0
, FACILITY NAME (1)
- DOCKET NUMBER (2) I J.IR hut 9EIL[$1 PAgg._{3)'
. Year fj// Sequential
/
f
///
fff Revision HZJ mber... UL Number y _g.cgidsgod 2 0 1 5 1 0 1 0 1 0 l'41 51 7 910 - 01015 - 01 0 01 2 0F. 01 3
- TEXT Energy Industry Identification System (E!!S) codes are identified in the text.as (XX)
' A.
. PLANT CONDITIONS PRIOR TO EVENT:
'Ualt:' Braldwood 2; Event Date: April 26, 1990; Event Time: .0900; Mode: ' 6 - Refueling; Rx Power: 0%;
RCS (AB) Temperature / Pressure: Ambient / Atmospheric
'B. DESCRIPTION Of EVENT:
There were no systems or components.troperable at the beginning of the event which contributed to the severity of th) event.
- At 0900 on April 26, 1990 during the performance of the scheduled 18 month maintenance on the 2A Diesel Generatorf I (DG). (EK) a crisscross of the starting. air distribution system tubing to cylinders 6L and 9L was discovered. The 1 discovery occurred while time checking each individual cylinder. Individual cylinder time checks were 'not "
normally performed for scheduled 18 month maintenance but had been added to this inspection as a' corrective action from a previous event involving the IB DG (reference LER 50-456/90-006). In,that event the starting airlines to 4 cylinders had been crisscrossed at couplings in a tubing trough following exhaust manifold replacement.
Af ter the crisscross of the starting airlines on the 2A DG was discovered the tubing couplings.were inspected a'nd ]
found to'be correctly assembled per the vendor stamped numbers. The error occurred during the custom routing of. 1 the tubing into the starting air distributor._ The custom routing is performed during the original manufacturing L J pr cess at.the factory. With the existing custom tubing it was not possible to obtain a simple airline swap. d L A review-of 'the starting histories for the 2A DG was conducted. Based on the results of that review it has been-concluded that the crisscross of the 6L:and 9L starting airlines did not significantly effect the performance of , '
th) 2A DG. The 2A DG had experier.ced only one " slow start" failure. This was a start time of 10.7 seconds as 1
.rscorded by a. stopwatch. This was in excess of tbo 10 seconds required by Technical Specifications. The 2A DG
,his experienced approximately 43 scccessful starts since the completion of pre-operational testing.
This event is being reported pursuant to 10CFR50.73(a)(2)(1)(B)-any operation or condition prohibited by the s plants Technical Specifications. ]
i C. .CAUSE OF EVENT: q
-The root cause of this event was a pre-service manufacturing deficiency.
i
.[.
~ .
. D. SAFETY ANALYSIS:
{
l This' event.had no effect on the safety of the plant or the public. Based on .trformance histories, the crisscross !
-of the 2 starting air lines did not significantly ef fect the performance of the 2A DG and it is reasonable to assume that-it would have performed as designed had an actual initiation signal occurred.
-3017)(052290)/3 1
d i
(
p; y- '
, . LIIENSILIYENLRLi'OfLLiLER) TEXT CQNTINUATION Fot3L.Erv 2.0 FACILITY-NAME,(1)
DOCKET NUMBER (2) _ LER NUMBL!L(j) pa.ge (3)
- Year /// Sequential /jj fjj
// Revision f
LU- 826tt lH Humktt
_prajdgend 2 0 1 5 1 0 [1]_Q l 41 51 7 910 - . O Lo.l.1 - 01 0 03 1 at 01.3 TEXT; Energy. Industry Identification System (Ells) codes are identified in the text as (XX) ;
D. SAFElf ANALYSI$: (Continued)
Undir. the worst case conditions -of a DG f ailure occurring af ter a valid initiating signal following a Safety
' Injection there would still be no ef fect. The redundancy of the safety system design provides for full safe shutdown and accident mitigation capability f rom A single ESF bus. The diversity of the electrical . p distribution system provides for powering an ESF bus from its $ystem Auxiliary Transformer, its own Diesel . i"
' Gen:rator, or its corresponoing 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- l
- An31ysis Report.
~ *
'E.- CORRECTIVE ACTIONS: ,
.The defecti ve custom rou et d airlines were replaced.
The' inspection that identified this deficiency was part of the corrective action for LER 50-456/90-006. The inspection of 1 A, IB, and 2A DG's is complete. Action item 456-200-90-01901 continues to track this item to
~
- completion for the inspection of the 2B DG.
/ This item has been submitted to Nuclear Engineering Department for 10CFR part 21 consideration. This will be
"' tr cked to completion by action item 457-200-90 01301. .
4
.F. PREVIOUS OCCURRENCES:
Th;re was a previous occurrence of crisscrossed DG starting airlines.
LER Title 50-456/90iOO6 Diesel Generator Slow Start From Crisscrossed Starting Airlines due to progrannatic Deficiency
- The; inspection that identified this deficiency was the result of corrective actions taken for that event.
G. COMPONENT FAILURE DATA:
This event was not the result of. component f ailure, nor did any components f ail as a result of this event.
301h(if.;2% /4 s
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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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