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{{#Wiki_filter:~$REGULATLT(Y INFORMATION DISTRIBUTION SYSTEM (BIDS)ACCESSION NBR: 8711190362 DOC.DATE: 87/11/12 NOTARIZED:
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NO DOCKET F*CIL: 50-315 Donald C.Cook Nuclear Power Plant>Unit 1>Indiana 8c 05000315 AUTH.NAME*UTHOR*FF ILI ATION SAMPSON>J.R.Indiana Michigan Power Co.(formerly Indiana 5 Michigan Ele SMITH>G.W.Indiana Michigan Pacer Co.(formerly Indiana&Michigan Ele REC IP.NAME RECIPIENT AFFILIATION
 
==SUBJECT:==
LER 87-021-00:
on 871013>ESF actuation occurred due to feedeater floe/steam mismatch coincident w/low level on steam'generator 11.Caused bg failure of east main feedeater pump shaft driven oil pump.Bearings replaced.W/871112 ltr.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR i ENCL JSIZE: TITLE: 50.73 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: RECIP IENT ID CODE/NAME PD3-3 LA WIGGINQTON>
D COPIES LTTR ENCL 1 RECIPIENT ID CODE/NAME PD3-3 PD COPIES LTTR E'NCL 1 1 INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/RO*B ARM/DCTS/DAB NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SQB NRR/DLPG/GAB NRR/DREP/RAB N S/SIB~RG IL 02 E E FORD>J RQN3 FILE 01 1 1 1 2 2 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 ACRS MOELLER AEOD/DSP/N*S AEOD/DSP/TPAB DEDRO NRR/DEST/CEB NRR/DEST/ICSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY QI RES/DE/EIB 2~2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: EGD~G GROH>M LPDR NSIC HARRIS>J 5 5 1 1 H ST LOBBY WARD NRC PDR NSIC MAYS>Q 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44
~r.h'r hh r hh r r,r'~e~ht~haawe t<'v hah h si,.hrh~t~NRC Form 355 (54)3)LICENSEE EVENT REPORT (LER)UA.NUCLEAR REQULATORY COMMISSION APPROVED OMB NO.31600104 EXPIRES: SI31ISS FACILITY NAME (I)D.C.Cook Nuclear Plant-Unit 1 DOCKET NUMBER (2)PA E 3 0 5 0 0 031510F05 REPORT DATE (7I LER NUMBER IS)EVENT DATE IS)DOCKET NUMBER(S)0 5 0 0 0 OTHER FACILITIES INVOLVED IS)FACILITY NAMES@VMSER MON H BEQUENTIAL NUMBER DAY YEAR MONTH DAY YEAR YEAR ESF Actuation (Reactor Trip)Due to Feedwater Flow/Steam Flow Mismatch Coinicdent With Low Steam Generator Level Resulting From Component Failure 1 0 1 3 8 7 8 7 0 2 1 0 0 1 1 1 2 7 0 5 0 0 0 OPERATINO MODE (5)POWER 0 6 9'"" ht" h 20A020r)20.405(e)II)(B 20A05(~)(I)(5)20.405(el(1)(ill) 20,405(e l(1)(iv)20,405 (e I (1)(v I 20.405(e)SOW(eH I)50.35(cl(2) 50.73(e I l2)(I)50.73(el(2)(lil 50.73(el(2)(ill)LICENSEE CONTACT FOR THIS LER 02)50.734)(2) lb)50.734)(2)(v)50.73(e)(2)(rll)50.73(el(2)(rilll(A)50.73(e)(2)(rl5)(B)50.73(~)(2)(x)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTs oF 10 cFR (): fcneep one or more of tne folloylnpl (11 73.7)(tr)73.71(c)OTHER fSpeelfy In Apt trect trelovr end In TexL HIIC Form 388A)NAME J.R.Sampson-Safety and Assessment Superintendent TELEPHONE NUMBER AREA CODE 6 1 6 4 6 5-5 9 0 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC TURER REPORTABLE:
CAUSE SYSTEM COMPONENT MANUFAC TUBER TO NPRDS X J K J K N A G 0 8 0 GRG0 8 0~p.,gg X J K X J K NAG08 0 GRG 0 8 0 SUPPLEMENTAL REPORT EXPECTED (14)YES (if yer, complete EXPECTED SIISMISSIDN DATE)NO ABSTRACT f(,lmlt to f400 rpecer, I e., epproxlmetely fifteen rlnpfeepece typevrritren linerl (15)EXPECTED SUBMISSION DATE DS)MONTH DAY YEAR On October 13, 1987, at 0818 hours, an Engineered Safety Features actuation (Reactor Trip)occurred due to a feedwater flow/steam flow mismatch coincident with low level on steam generator number 11.At approximately 0817 hours, a licensed operator removed the east main feedwater pump alternating current auxiliary oil pump from service as directed by procedure.
The shaft driven oil pump failed to maintain control oil pressure as expected.This resulted in a main feedwater system transient which culminated in the reactor trip.Post-event evaluation identified no component failure, other than the shaft.-driven oil pump, which significantly affected the event.The east main feedwater pump shaft driven oil pump was found to be damaged.It was repaired and the feedwater pump was returned to service.S7>S>90SSg 87<caa PDR ADOCK 05000315 S PDR NRC Form 355 rn e*h NRC form 366A (943)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVE'D OMB NO.3(50-0104 EXPIRES: 6/31/BS FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)YEAR'.j'or(SEOVENTIAL)N NUMBER REVISION NUMBER PACE (3)D.C.Cook Nuclear Plant, Unit.1 0 s 0 0 0 3 1 5 8 7 TEXT Ii/more s/rsseis rer/rrr)ed.
Iree eddrrians/NRC Farm 36M's/((7)0 2 1 0 0 0 2 OF 0 5 Conditions Prior to Occurrence Unit 1 was in Mode 1 (Power Operation) and at 69 percent reactor thermal power (RTP).Descri tion of Event On October 13, 1987, at 0818 hours, an Engineered Safety Features actuation (Reactor Trip)occurred due to a feedwater flow/steam flow mismatch on steam generator (EIIS/AB-SG) number ll coincident with low level on steam generator number 11.At the time of the trip, the unit was experiencing a feedwater transient.
initiated by the failure of the east main feedwater pump shaft driven oil pump (EIIS/JK-P) to maintain adequate control oil pressure as expected, when the east main feedwater pump's (EIIS/SJ-P) alternating current (A.C.)auxiliary electric oil pump (EIIS/JK-P) was secured.At approximately 0817 hours, a licensed senior reactor operator removed the A.C.auxiliary oil pump associated with the in service East main feedwater pump from service, as directed by procedure.
The east main feedwater pump speed was approximately 4100 revolutions per minute (R.P.M.).At this speed, the shaft driven oil pump is expected to maintain lubricating and control oil pressure.Due to internal damage, the shaft driven oil pump was unable to maintain pressure.When lubricating and control oil pressure decreased, the operator promptly restarted the A.C.oil pump.To compensate for decreasing east main feedwater pump speed, the feedwater regulating valves (FRVs)(EIIS/JB-FCV) were manually placed in the fully opened position and the speed of the west main feedwater pump was manually increased.
Attempts were made to increase east main feedwater pump speed.At this point some progress had been made in restoring feedwater flow to the steam generators, however the east main feedwater pump isolation valve (EIIS/SJ-ISV), which had been running shut, reached the fully closed position aggravating the feedwater transient and resulting in the reactor trip signal from a low steam generator level coincident with feedwater flow/steam flow mismatch.Following the trip sequence[opening of the reactor trip breakers (EIIS/JE-BKR), turbine (EIIS/TA-TRB) trip, insertion of the reactor control rods (EIIS/AA-ROD), feedwater isolation (EIIS/JB), automatic starting of the motor-driven and turbine-driven auxiliary feedwater pumps (EIIS/BA-P)
]Operations personnel immediately implemented the Emergency Operating Procedure 1-OHP 4023.E-O to verify proper response of the automatic protection system (EIIS/JC)and to assess plant conditions for initiating appropriate recovery actions.There was no automatic or manual actuation of the safety injection system (EIIS/BQ).
NRC FORM SBBA (9 63)
 
4 NRC Form 366A (9-83)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVEO OMB NO.3150&104 EXPIRES: 8/31/85 FACILITY NAME ((I OOC K ET NUMB E R (3)YEAR LER NUMBER (6)$y&SEOVENTIAL wX~g NUMBER ,g~: RFVISION'.<RI NVMBBR PACE (3)D.C.Cook Nuclear Plant, Unit 1 0 5 0 0 0 3]5 8 7 TEXT llf more speae/4 rerlrr/red, ace eddit/one/
NRC Farm JM4'4/(IT)0 2 1 0 0 0 3>>0 The unit was stabilized in Mode 3 (Hot Standby)at approximately 0903 hours, October 13, 1987.The Nuclear Regulatory Commission was notified of the event via the Emergency Notification System at 0904 hours.With the exception of the east main feedwater pump shaft driven oil pump, there were no inoperative structures, components, or systems that contributed significantly to this event.Cause of Event The cause of this event was determined to be failure of the east main feedwater pump shaft driven oil pump.Internal damage to this pump resulted in its inability to maintain lubricating and control oil pressure when the associated A.C.auxiliary oil pump was secured.When the oil pressure decreased, the east main feedpump turbine stop valves (EIIS/JK-SHV) went closed, causing the east main feedpump governor (EIIS/JK-65) to run back and the feedpump discharge valve to close.The resulting decrease in feedwater flow, coincident, with a low level in number 11 steam generator, generated the reactor trip signal.Anal sis of Event This Engineered Safety Features actuation, which resulted in a reactor trip sequence, is reportable pursuant to 10 CFR 50.73 (a)(2)(iv).Following the trip, various components of the east main feedpump turbine oil system (EIIS/JK)were inspected in order to de-termine the cause of the failure to maintain oil.pressure.
The shaft oil pump, oil pump suction strainers (EIIS/JK-STR) and check valves (EIIS/JK-V), pressure regulating valve (EIIS/JK-PCV), and auxiliary oil pump check valve (EIIS/JK-V) were inspected.
It was found that the pump upper shaft low pressure bearing thrust plate (EIIS/JK)had foreign object damage and the middle journal bearings (EIIS/JK)(upper and lower shaft)were partially wiped.The pump upper shaft low pressure gear (EIIS/JK-GR) was also found damaged.Beyond the fact that the bearings had gotten hot, the specific cause of the damage could not be firmly established.
During the feedwater transien't, the behavior of the east main feedwater pump and its discharge valve was as expected under the circumstances.
Loss of control oil pressure caused the feedpump turbine stop valves to go closed, picking up limit switches (EIIS/JK-33).
These limit switches caused the governor/speed changer to run back.Because of this, east main feedwater pump speed continued to decrease, even though the pump had not tripped and control oil pressure had been restored.The same limit switches also caused the feedwater pump discharge valve to run closed, shutting off feedwater flow from the'affected pump.NRC FORM SddA LB 83)
NRC Focm 3$8A (843)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION AI'PROVED OMB NO.3150-0104 EXPIRES: 8/31/85 FACILITY NAME (I)OOCKET NUMBER (2)YEAR LER NUMBER (8)SEOUENTIAL NUMBER REVISION NUMBEA PACE (3)D.C.Cook Nuclear Plant, Unit 1 p 5 p p p 3 1 5 8 7 TEXT/lf more speoeis reeuired.use eddc)ione/
NRC Form 3654's/()7)0 2 1 0 0 0 4 OF 0 5 During the post-trip review, and based on licensed Operator comments and a computer printout, it appeared that the feedwater flow/steam flow mismatch coincident with low steam generator level trip signal may have actuated at.a value of steam generator level Nove (the'onservative direction) the expected trip value.Instrumentation and Control Section checkout of the bistable setpoints confirmed accurate and proper bistable operation and satisfactory control room meter (EIIS/JB-MTR) indication accuracy.The automatic protection system responses, including reactor trip and its associated actuations, were verified to have functioned properly as a result of the engineered safety features actuation.
Based on the above, it is concluded that the event did not constitute an unreviewed safety question as defined in 10 CFR 50.59 (a)(2)nor did it adversely impact the health and safety of the public.Corrective Actions Immediate corrective action involved Operations personnel implementing plant procedures to verify proper response of the automatic protection system and to assess plant conditions for initiation of appropriate recovery actions.To repair the damage observed on the east main feedpump shaft driven oil pump, the middle journal bearings (upper and lower shaft)were replaced with spares and a new set of low pressure pump gears was installed.
The east main'feedpump turbine was brought up to speed on the morning of October 18, 1987 and the shaft,-driven oil pump successfully held pressure.Failed Com onent Identification In order to repair damage observed in the east main feedpump shaft driven oil pump, the following components were replaced: Plant
 
== Description:==
 
Manufacturer:
Manufacturer's ID Number: EIIS Code: Number Replaced: Bearing-Shaft Drive Oil pp BFPT General Electric GE gl01 C286FD-1 EIIS/JK 2 Plant
 
== Description:==
 
Manufacturer:
Manufacturer's ID Number: EIIS Code: Number Replaced: Bearing-Shaft Drive Oil pp BFPT General Electric GE N101 C286 FC-1 EIIS/JK 2 NRC FORM SBBA 5 83 I
 
~'~~))A%V A I'ALAI Q 4E~')~k NRC Form 368A (943)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3150&104 EXPIRES: 8/31/85 FACILITY NAME (I)DOCKET NUMBER (2)YEAR LER NUMBER (6)'EOUENZIAL eo NUMBER REVISION NUMBER PAOE (3)D.C.Cook Nuclear Plant, Unit 1 0 6 0 0 0 3 1 5 8 7 TEXT/I/more space/s required, use addicena/P/RC Form 3884's/(17)0 2 1 0 0 0 5 oF 0 Plant
 
== Description:==
 
Manufacturer:
Manufacturer's ID Number: EIIS Code: Number Replaced: Gear-Shaft Drive Oil.pp BFPT General Electric GE$134 B 230 BF-1 EIIS/JK-GR 1 Plant
 
== Description:==
 
Manufacturer:
Manufacturer's ID Number: EIIS Code: Number Replaced: Gear-Shaft Drive oil pump General Electric GE 0134 B 230 BF-2 EIIS/JK-GR 1 Previous Similar Events None-No previous, similar events involving the malfunction of the main feedwater pump shaft driven oil pump were identified.
NRC FORM 366A (9 83)
 
Indiana Michigan~Power Company Cook Nuclear Plant P.O.Box 458 Bridgman.Ml 49106 616 465 5901 Z INDIANA NlCHIGAN POWER November 12, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.2055S Operating License DPR-58 Docket No.SO-315 Document Control Manager: In accordance with the criteria established by,10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:
87-021-0 Sincerely, W.G.Smith, Jr.Plant Manager WGS:afh Attachment CC'ohn E.Dolan A.B.Davis, Region III M.P.Alexich R.F.Kroeger H.B.Brugger R.W.Jurgensen NRC Resident Inspector R.C.Callen G.Charnoff, Esq.D.Hahn INPO D.Wigginton, NRC PNSRC A.A.Blind Dottie Sherman, ANI Library P.A.Barrett/P.
Lauzau
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Revision as of 15:42, 23 October 2019

LER 87-021-00:on 871013,ESF Actuation Occurred Due to Feedwater Flow/Steam Mismatch Coincident W/Low Level on Steam Generator 11.Caused by Failure of East Main Feedwater Pump Shaft Driven Oil Pump.Bearings replaced.W/871112 Ltr
ML17325A451
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/12/1987
From: Sampson J, Galen Smith
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-021, LER-87-21, NUDOCS 8711190362
Download: ML17325A451 (11)
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