ML17329A691

LER 92-012-00:on 921028,Turbine Trip/Reactor Trip Occurred During Power Increase to 30% to Perform Routine Calometric Test.Caused by Failure to Reset Thrust Bearing Wear Detector Setpoint.Procedures to Be drafted.W/921125 Ltr

ML17329A691
Person / Time
Site:	Cook
Issue date:	11/25/1992
From:	Blind A, Joel Wiebe INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-012, LER-92-12, NUDOCS 9212010294
Download: ML17329A691 (6)

Text

A.CCj.sj.'~~ j.'5;u Uie'j.'Zn O'I'rON DEMOSSTR~TION SYSTEM REGULRTC INFORMATION DISTRIBUTION Q3TEM (RIDE)

ACCESSION NBR:9212010294 DOC.DATE: 92/11/25 NOTARIZED: NO DOCKET I FAC'IL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION WIEBE,J.S. Indiana Michigan Power Co.'formerly Indiana & Michigan Ele BLIND,A.A Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 92-012-00:on 921028,Turbine Trip/Reactor Trip occurred due to Turbin Thrust bearing wear device not being set following maint.Tracking outage work performed on Cook Plant turbines & generators will be drafted.W/921125 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR t ENCL I SIZE: S TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 DEANFW 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRggj)ST SPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 ~E 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: EG&G BRYCEFJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POOREFW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM P!-S7 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 29

Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 INDIANA N!CHIGAbf POWM November 25, 1992 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort S stem the following report is being submitted:

92-012-00 Sincerely, A. A. Blind Plant Manager

/sb c'.

Attachment H. Williams, Jr.

A. B. Davis, Region E. E. Fitzpatrick III P. A. Barrett R. F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector

'W. M. Dean NRC J. G. Keppler M. R. Padgett G. Charnoff, Esq.

D. Hahn INPO S. J. Brewer B. A. Svensson

(~.!. U t.i 8 9212010294 921125 PDR ADOCK 05000315 p/~i 8 P llR I/

NRC FORM 355 U4. NUCLEAR RKGULATOAYCOMMISSION (54)9) APPROVED OMS NO. 31504)104 cXP IR ES'l30/02 ESTIMATED SURDEN PEll RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REDUFST( 50.0 HAS. FORWARD LICENSEE EVENT REPORT ILER) COMMENTS REGARDING SUADEN ESTIMATE TO THE RECORDS AND AFPORTS MANAGEMENTBRANCH IP030). U.S, NUCLEAR REGULA'TORY COMMISSION, WASHINGTON. DC 20555. AND TD THE PAPERWORK REDUCTION PROJECT (3)500104). OFFICE OF MANAGEMENTAND SUDGET. WASHINGTON. DC 20503.

FACILITY NAME lll DOCKET NUI4SER (21 PA D. C. Cook Nuclear Plant Unit 1 o 5 o o o 315 10F0 Turbine Trip/Reactor Trip Due to the Turbine Thrust Bearing Wear Device not Being Set Following Maintenance EVENT DATE (5) LER NUMSKR (5) AEPORT DATK (7) OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YKAR ~v'5OUCNTIAL MONTH DAY YEAR eACILITY NAM55 DOCKET NUMSEAISI NUMSKA o s o o o 1 0 2 8 92 92 012 0 011 25 9 2 0 5 0 0 0 OPKRATING THIS REPORT IS SUSMITTED PURSUANT TO THK RLOUIAEMENTS OF 10 CFR (J: (Check one ot inore or the rollowrnet (ill MODE (5) 20.402 0?) 20.405(cl X 50.7$ (c I (2) De) 7$ .7)(5) 20.4054)() l(il SOM(c) Ill 50.7$ 4) (2) le) 7$ .7)(c)

()0) 0 1 6 20.405 4) (I ) (5) SOM(cH2) 50.734 I1 2 I )eS I OTHER ISoeciry in Aptpoct heroic enp in Tee(. Ht(C Form 20A054lll l(WI 50.7$ 4) l2) I I) 50.73(cl(1)(eSII (A) $ 554) 20.4054) (I l(tel 50.7 34) (2) (ill 50.7 3(e ) (2) lyiiil (5 I 20.405 4) III (el 50.734) (2) IWI 50.7$ 4) 12) Ic I LICEICSKE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMSER Joel S. Wiebe Safety and Assessment Superintendent AAEA CODE 61 646 5- 590 COMPLETE ONE LINE FOR KACH COMPONENT FAILURE DESCRI ~ EO IN THIS REPORT (1$ )

bii CAU5 K SYSTFM COMPONENT MANU)'AC.

TUAKA irORT I@/+~ irPii

' r SYSTEM COMPONENT MANUFAC.

TUAER E PORTA TO NPRDS 5L N',

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QJPPLEMENTAL AEPORT EXPECTED (14) MONTH DAY YEAA EXPECTED SUSMISSION DATE (15)

YES ltl yet. cornprete EXPECTED SUEhtrSSIDht DATEI X o ASSTAACT Il.rrnrt to l 400 toecee, r.e., epproeirnetery rirteen trnerecpece typeerrrtten rinetl II5)

On October 28, 1992, at 0253 hours0.00293 days <br />0.0703 hours <br />4.183201e-4 weeks <br />9.62665e-5 months <br /> , with Unit One at 16 percent Reactor Thermal Power, a Turbine Trip/Reactor Trip occurred. The trip occurred during a power increase to 30 percent to perform a routine calometric test and was the result of a signal from an erroneously set main turbine thrust bearing wear device.

The erroneous signal was the result of the thrust bearing wear detector setpoint not being set, after maintenance, such that a turbine shaft displacement of approximately six mils would result in a Turbine Trip Signal.

Following the Reactor Trip, all automatic protection including reactor trip and its associated actuations were verified to responses, have functioned properly as a result of the reactor trip. The Unit was stabilized in Hot Standby tMode 3) at 0310 hrs on October 28, 1992.

Prior to restarting Unit One, the main turbine thrust bearing wear detector was adjusted to the proper setpoint. To prevent recurrence, administrative guidelines are being developed to provide positive control on work order activities related to major turbine inspections.

'RC Ferro 355 I54)SI

NRC FORM SSSA US. NUCLEAR REGULATORY COMMISSION APPROVEO OMS NO. 3150010i Id JIQI E X PIN ES: OI30I92 ESTIMATED SUROEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUEST: 500 HRS. FORWARD COMMENTS REGARDING SURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT SRANCH (P 530I. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150010OI. OFFICE Of MANAGEMENTAND SUDGET.WASHINGTON. DC 20503.

FACILITY NAME 11I DOCKET NUMSER 12) ' LER NUMSER ISI PAGE (31 YEAR r>>~I 5500drrTIAL

~ rvMOER " rrvrrroeo i odvldloN D. C. Cook Nuclear Plant Unit 1 5 o o o 315 9 2 012 0 0 02oF 04 TEXT illmore eoooe 0 merrrreo. ooe aoeOOOrool rYJIC Form 3FSA'll I Ill Conditions Prior to Occurrence:

Unit One in Mode 1 (Power Operation) at a power level of approximately 16 percent.

Descri tion of Event:

On October 28, 1992, , with Unit One at 16 percent Reactor Thermal Power, a Turbine Trip/Reactor Trip occurred. The trip occurred duringresult a power increase of a signal to 30 percent to perform a routine calometricbearing test and was the from an erroneously set main turbine thrust wear detector (EIZS:JJ/DET).

During the course of the July 1992 work on Unit 1 High Pressure Turbine (EIIS:TA) the Thrust Bearing Wear Detector (TBWD)(EIISEJJ/DET) was removed and reinstalled.

The job order (work order) directing the work on the High Pressure Turbine (EIZS: TA) did not contain a specif ic job order activity for the removal was or reinstallation of the TBWD (E1ZSEJJ/DET). Additionally, no action request generated by the Turbine Coordinator to request post-maintenance testing after the TBWD (EZZS:JJ/DET) was reinstalled.

On October 4, 1992 the Plant Engineering Department attempted to perform the Turbine Thrust Bearing Wear and Low Bearing Oil Pressure Trip Test (section 5.7 of 1-EHP 6040 PRE.099). The test was aborted because the wear detector switches were not functional. The IGC crew supervisor providing support for turbine instrument work was contacted to resolve the problem with the turbine wear detector switches. At this time both the ZGC crew supervisor and the system engineer became aware that the TBWD (EZIS:JJ/DET) may not be properly adjusted.

At this time the ZQC crew supervisor and the system engineer agreed would that no additional action request would be generated, and that the adjustments be made under an existing Job Order (work order) to perform a lineup of the main turbine Electrohydraulic Control (EHC) system (EIISETG). The work was to be performed without generating an additional action request.

On October 24, 1992 the Z&C Production Supervisor canceled the EHC lineup. The decision .to cancel the lineup was made based upon the fact that no Supervisor known EHC system (EZZS:TG) problems had been identified. The ZGC Production was not aware of the intention to make any needed adjustments to the TBWD (EZIS:JJ/DET) under the EHC lineup job order.

The turbine roll began'on October 27 at 2251 hours0.0261 days <br />0.625 hours <br />0.00372 weeks <br />8.565055e-4 months <br />. The unit was parallelled at 01:05 on October 28, 1992 and power was being increased to 30ItI to perform a calometric. At 0253 hours0.00293 days <br />0.0703 hours <br />4.183201e-4 weeks <br />9.62665e-5 months <br /> on October 28 the Unit One reactor tripped from 16%

power from a Turbine Trip caused by the Main Turbine Thrust Bearing Wear Trip.

This was the initial power ascension following refueling. Reactor Protection System (RPS)(EZIS:JE/RPS)'ccurred from the main turbine trip above 10% power.

All systems functioned as designedhours following the trip. The unit was stabilized in Hot Standby (Mode 3) at 0310 on October 28, 1992.

NRC Form 355A ISJ19I

NRC FORM ESSA US. NUCLEAR REGULA'TORY COMMISSION ISe9> APPROVED OMS NO. 0150d104 e XPIR ES: r/30/99 ESTIMATED SURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD COMMENTS REGARDING SURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT SRANCH IP.5$ 0I. US. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 90555. AND TO THE PAPERWORK REDUCTION PROJECT 15150dl041. OFFICE OF MANAGEMENTAND SUDGET,WASHINGTON. OC 20505 FACILITY NAME (1I DOCKET NUMSER (T) PAGE IS)

LER NUMSER ISI vEAR SEQUEHWAI, " AEV/SION 4VMPC/I I HUM D. C. Cook Nuclear Plant iJnit 1 0 5 o,oioi315 9 2 012 00 0 3 QF 0 4 TEXT /// move rpPrP rr rprvrpr. Vrr o Ar/a/mr/ HAC form J1EIA'r/ II7 I Cause of Event:

The erroneous signal was the result of the thrust bearing wear detector setpoint not being set, after maintenance, such that a turbine shaft displacement of approximately six mils would result in a Turbine Trip Signal.

The primary contributing factor related to this event was the failure to document the need for a setpoint adjustment job order (work order) activity Detector.

to perform post-maintenance testing of the Turbine Thrust Bearing Wear Anal sis of Event:

This event is reportable pursuant to 10CFR 50.73(a)(2)(iv), as an event that resulted in an unplanned automatic actuation of the Engineered Safety Features, including Reactor Protection System.

All automatic protection responses, including reactoras trip and its associated actuations were verified to have functioned properly a result of the reactor trip signal. As a question unreviewed safety result, it is concluded that the event did not constitute an as defined in 10CFR 50.59(a)(2) nor did it adversely impact the health and safety of the public.

Corrective Action:

Prior to restarting Unit One, the main turbine thrust bearing wear detectorPlant was adjusted to the proper setpoint. To prevent recurrence, the following preventive actions have been developed:

Procedures for documenting and tracking outage work performed on Cook Plant turbines and generators will be drafted. The procedure will contain instructions to initiate corrective action requests to ensure the operability/functionality of instruments which may have been affected during turbine or generator work. Completion of this action is scheduled for December 31, 1993, or prior to the next scheduled turbine generator outage.

2. Administrative guidance will be drafted and implemented on the use of the NPM system to ensure that plant components affected by work coordinated through the affected Plant Department(s) will be evaluated to confirm operability/functionality prior to being placed in service. Completion of this action is scheduled for June 1, 1993.

NRC Form SSSA 16eSI

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (669) APPROVED OMB NO. 3)500)OS EXPIRES: S/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REQUEST: 508) HRS. FORWARD COMMENTS REGARDINQ BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP 530), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504)OS). OFFICE Of MANAGEMENTAND BUDGET,WASHINGTON,OC 20503.

FACILITY NAME (II DOCKET NUMBER (2) LER NUMBER (6) PAGE I3)

YEAR >SN SEQUENTIAL j;O. REVISION ai>2 NUMBER y~ NUMSER D. C. Cook Nuclear Plant o s o o o 3 1 5 9 2 012 00 0 4 QF 0 4 TEXT /I/ mort sptct rs rtOItrtd, oss tddrn'ont/NRC Forrrr 3/JSA's/ ()7) 3 ~ Administrative guidance will be provided to the plant departments on the use of the NPM system to identify and track the work activities necessary to conf irm that instrumentation is operable/functional prior to being placed into service. Completion of this action is scheduled for December 18, 1992.

A review of all Unit and Unit 2 turbine preoperational/start up test 4 ~

requirements will be identified to ensure reliable system start 1

performed to determine ifup. adequate These measures reviews are are scheduled for completion by December 31, 1993 or prior to the next turbine generator outage. An action plan will be developed to address any deficiencies identified by the review.

5. A review will be performed on Turbine Start up activities for both Unit 1 and Unit 2 to determine if all of the appropriate preoperational/start, up actions (eg valve lineups and surveillance tests) are performed to ensure reliable turbine start up. An action plan will be developed to address any deficiencies identified by the review. Completion of this action is scheduled for December 31, 1993 or prior to the next turbine generator outage.

Failed Cpm onent Identification:

There were no failed components associated with this condition.

Previous Similar Events:

Similar LER's3 Ul-86-023 NR C FonII 366A (669)