ML17325A451

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
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)

Text

~$

REGULATLT(Y INFORMATION DISTRIBUTION SYSTEM (BIDS)

ACCESSION NBR: 8711190362 DOC. DATE: 87/11/12 NOTARIZED: NO DOCKET F*CIL: 50-315 Donald C. Cook Nuclear Power Plant> Unit 1> Indiana 8c 05000315 AUTH. NAME *UTHOR *FF ILIATION 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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR E'NCL PD3-3 LA PD3-3 PD 1 1 WIGGINQTON> D 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 ~

2 AEOD/DOA 1 1 AEOD/DSP/N*S 1 AEOD/DSP/RO*B 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SQB 1 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB N S/SIB 1 1 NRR/PMAS/ILRB 1

~ RG IL 02 1 1 RES DEPY QI 1 E E FORD> J 1 RES/DE/EIB 1 1 RQN3 FILE 01 1 1 EXTERNAL: EGD~G GROH> M 5 5 H ST LOBBY WARD 1 1 LPDR 1 NRC PDR 1 1 NSIC HARRIS> J 1 NSIC MAYS> Q 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 UA. NUCLEAR REQULATORY COMMISSION (54)3)

APPROVED OMB NO. 31600104 LICENSEE EVENT REPORT (LER) EXPIRES: SI31ISS FACILITY NAME (I) DOCKET NUMBER (2) PA E 3 Nuclear Plant Unit 1 0 5 0 0 031510F05 D. C. Cook ESF Actuation (Reactor Trip) Due to Feedwater Flow/Steam Flow Mismatch Coinicdent With Low Steam Generator Level Resulting From Component Failure EVENT DATE IS) LER NUMBER IS) REPORT DATE (7I OTHER FACILITIES INVOLVED IS)

MONTH DAY YEAR YEAR BEQUENTIAL DAY YEAR FACILITYNAMES DOCKET NUMBER(S)

NUMBER @ VMSER MON H 0 5 0 0 0 1 0 1 3 8 7 8 7 0 2 1 0 0 1 1 1 2 7 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTs oF 10 cFR (): fcneep one or more of tne folloylnpl (11 OPERATINO MODE (5) 20A020r) 20.405(e) 50.734)(2) lb) 73.7)(tr)

POWER 20.405(e)II)(B SOW(eH I ) 50.734) (2)(v) 73.71(c)

'"" ht" 0 6 9 20A05( ~ ) (I ) (5) 20.405(el(1)(ill) 50.35(cl(2) 50.73(e I l2)(I) 50.73(e) (2) (rll) 50.73(el(2) (rilll(A)

OTHER fSpeelfy In Apt trect trelovr end In TexL HIIC Form 388A) 20,405(e l(1) (iv) 50.73(el(2)(lil 50.73(e) (2) (rl5)(B) h 20,405 (e I (1)(v I 50.73(el(2) (ill) 50.73( ~ )(2)(x)

LICENSEE CONTACT FOR THIS LER 02)

NAME TELEPHONE NUMBER AREA CODE J. R. Sampson Safety and Assessment Superintendent 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 REPORTABLE: MANUFAC TURER CAUSE SYSTEM COMPONENT TUBER TO NPRDS J K N A G 0 8 0 X J K NAG08 0

~p X J K GRG0 8 0 . ,gg X J K GRG 0 8 0 SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE DS)

YES (if yer, complete EXPECTED SIISMISSIDN DATE) NO ABSTRACT f(,lmlt to f400 rpecer, I e., epproxlmetely fifteen rlnpfeepece typevrritren linerl (15)

On October 13, 1987, at 0818 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br />, 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 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br />, 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.

returned to service.

It was repaired and the feedwater pump was S7>S>90SSg 87<caa PDR ADOCK 05000315 S PDR NRC Form 355 rn e*h

NRC form 366A U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVE'D OMB NO. 3(50-0104 EXPIRES: 6/31/BS FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PACE (3)

'.j'or( SEOVENTIAL REVISION YEAR NUMBER )N NUMBER D. C. Cook Nuclear Plant, Unit. 1 0 s 0 0 0 3 1 5 8 7 0 2 1 0 0 0 2 OF 0 5 TEXT Ii/more s/rsseis rer/rrr)ed. Iree eddrrians/NRC Farm 36M's/ ((7)

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 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br />, an Engineered Safety Features actuation (Reactor Trip) occurred due to a feedwater flow/steam flow mismatch on steam generator (EIIS/AB-SG) number with low level on steam generator number 11. At the ll time coincident of the trip, the unit was experiencingfeedwater a feedwater transient. initiated by the failure of the east main 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 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br />, 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 promptlymain feedwater restarted the A.C.

oil pump. To compensate for decreasing east 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 U.S. NUCLEAR REOULATORY COMMISSION (9-83)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150&104 EXPIRES: 8/31/85 FACILITY NAME ((I OOC K ET NUMBE R (3) LER NUMBER (6) PACE (3)

YEAR $ y& SEOVENTIAL ,g~:

'.<RI RFVISION NVMBBR wX~g NUMBER D. C. Cook Nuclear Plant, Unit 1 0 5 0 0 0 3 ] 5 8 7 0 2 1 0 0 0 3>>0 TEXT llfmore speae /4 rerlrr/red, ace eddit/one/ NRC Farm JM4'4/ (IT)

The unit was stabilized in Mode 3 (Hot Standby) at approximately 0903 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.435915e-4 months <br />, October 13, 1987. The Nuclear Regulatory Commission was notified of the event via the Emergency Notification System at 0904 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.43972e-4 months <br />.

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 U.S. NUCLEAR REGULATORY COMMISSION (843)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AI'PROVED OMB NO. 3150-0104 EXPIRES: 8/31/85 FACILITY NAME (I) OOCKET NUMBER (2) LER NUMBER (8) PACE (3)

YEAR SEOUENTIAL REVISION NUMBER NUMBEA D. C. Cook Nuclear Plant, Unit 1 p 5 p p p 3 1 5 8 7 0 2 1 0 0 0 4 OF 0 5 TEXT /lfmore speoeis reeuired. use eddc)ione/ NRC Form 3654's/ ()7)

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 direction) the expected trip value. Instrumentation (the'onservative 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:

Bearing-Shaft Drive Oil pp BFPT Manufacturer: General Electric Manufacturer's ID Number: GE gl01 C286FD-1 EIIS Code: EIIS/JK Number Replaced: 2 Plant

Description:

Bearing-Shaft Drive Oil pp BFPT Manufacturer: General Electric Manufacturer's ID Number: GE N101 C286 FC-1 EIIS Code: EIIS/JK Number Replaced: 2 NRC FORM SBBA 5 83 I

~ ~ )) A %V A I 'ALAI Q 4E ~ ') ~ k

~

NRC Form 368A U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150&104 EXPIRES: 8/31/85 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PAOE (3)

'EOUENZIAL REVISION YEAR eo NUMBER NUMBER D. C. Cook Nuclear Plant, Unit 1 0 6 0 0 0 3 1 5 8 7 0 2 1 0 0 0 5 oF 0 TEXT /I/ more space /s required, use addicena/ P/RC Form 3884's/ (17)

Plant

Description:

Gear-Shaft Drive Oil.pp BFPT Manufacturer: General Electric Manufacturer's ID Number: GE $ 134 B 230 BF-1 EIIS Code: EIIS/JK-GR Number Replaced: 1 Plant

Description:

Gear-Shaft Drive oil pump Manufacturer: General Electric Manufacturer's ID Number: GE 0134 B 230 BF-2 EIIS Code: EIIS/JK-GR Number Replaced: 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 Z

Bridgman. Ml 49106 616 465 5901 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 M. P. Alexich III 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

~ V