ML17325A782

LER 87-009-01:on 870825,gland Seal Leakoff Condenser Effluent Radiation Monitor Found Inoperable.Caused by Failure to Perform Adequate Review of Monitor Status During Shift Surveillance.Procedures revised.W/880610 Ltr

ML17325A782
Person / Time
Site:	Cook
Issue date:	06/10/1988
From:	Baker K, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-009, LER-87-9, NUDOCS 8806220257
Download: ML17325A782 (6)

Text

REQUL Y INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR 8806220257 DQC. DATE: 88/06/10 NOTARIZED: NO DOCKET FAC I L: 50-.316 Donald C. Cook Nuclear Power Planti Unit 2i Indiana 0 05000316 AUTH. NAME AUTHOR *FF I L I AT I QN BAKERi K. R Indiana Michigan Power Co.

SMITHS'. G. Indiana Michigan Power Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-009-01: on 870825'land seal leakoff condenser ef fluent radiation monitor Found inoperable. Caused bg failure to perform adequate review of monitor status during shift surveillance. Procedures revised: W/880610 itr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR t ENCL l SIZE:

TITLE: 50. 73 Licensee Event RepoT t (LER)i Incident Rpti etc.

NOTES:

RECIPiENT CQP IES RECIPIENT COP I ES lD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGi J 1 1 INTERNAL: ACRS Mi CHELSON 1 1 ACRS MOELLER 2 ~c

• EOD/DO* AEOD/DSP INAS 1 AEOD/DSP /RQAB 2 2 AEOD/DSP /TPAB 1 1 ARM/DCTS/DAB 1 DEDRQ 1 1 NRR/DEST/ADS '7E 1 0 NRR IDEST/CEB BH 1 1 NRR/DEBT/ESB BD 1 NRR/DEST/ICSB 7 1 NRR/DEST/MEB 9H 1 1 NRR/DEBT/MTB 9H 1 NRR/DEST/PSB BD 1 NRR/DEST/RSB BE 1

'NRR /DEBT/SQB BD 1 1 NRR/DLPG/HFB 10 1 1 NRR/DLPG/GAB 10 1 NRR/DOEA/EAB 11 1 1 NRR 'B 02 NRR/DREP/PAB 10 9A 1 1

1 1

NRR/DREP/RPB NUDOCS-ABSTRACT RES TELFORDi J 10 2 1

2 1

1 RES/DE/EIB 1 RES/DRPS DEPY 1 1 RQN3 F I LE 01 ~

1 1 EXTERNAL: EG4G WILLIAMSrS 4 4 FORD BLDG HOYLE A 1 1 H ST LOBBY WARD 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS' 1 NSIC MAYST G 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 355 U.S. NUCLEAR REOULATORY COMMISSION (083)

APPROVED OMB NO. 31500104 LICENSEE EVENT REPORT (LER) EXPIRES: 5/31/SS FACILITYNAME (I) DOCKET NUMBER l2) PA E 3 D. C. Cook Nuclear Plant, Unit Two o s o o o3 16>QF04 Radiation Monitor Inoperable Without T.S. Required Compensatory Sample Due to Miscommunication (Personnel Error)

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (5)

SEOUBNTIAL RBvrsroN MONTH FACILITYNAMES DOCKET NUMBER(S)

MONTH OAY YEAR YEAR @ NUMBER PA ~UMBER O*Y YEAR D. C. Cook, Unit One o so o o 315 0 825 87 7 0 0 9 01 061 0 8 8 0 5 0 0 0 OPE RAT I NO THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR (): /Check one or more of the follorffnp) (11)

MODE (O) 1 20A02(B) 73.7 1(B) 20.405(c) 50.73(s) (2)Br)

POWER 20.405( ~ l(1)(i) 50.35(cl(1) lb.73(s)(2l(r) 73.71(c)

LEYEL 0 8 0 20A05( ~ ) (1) (Bl 50.35(cl(2) 50.73(s)(2)(rQ) OTHER (Specify In Abrtrect below end ln Text, NIIC Form 20.405(s)(I) IIIO 50.73( ~ l(2)(I) 50,73(s) (2)(rIIIIIAI 3BBA) 20AOS(s) O)(lr) 50.73(s) (2) (Ii) 50.73(s) (2)(rIS) (0) 20.405(s) H)(r) 50.73(sl(2) IIII) 50.73(s) (2)(x)

LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE K. R. Baker, 0 erations Su erintendent 6 16 465 -5 901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) r.' - ~

<or i,< .

CAUSE SYSTEM COMPONENT MANUFAC TVRER REPORTABLE TO NPRDS BSRR SYSTEM COMPONENT MANUFAC.

TVRER EPORTABLE TO NPRDS I

B IL K D E 070 N

'&A!

SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YES Ilfyer, complete EXPECTED SIIBMISSION DATEI NO ABSTRACT ILlmlt to f400 rpecer, l.e., epproxlmetely fifteen rlnple specs typewrlnen liner) (15)

This IER has been revised to reflect a change in the corrective action.

On August 25, 1987, at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />, during performance of shift surveillances, the. gland seal leakoff (GSLO) condenser effluent radiation monitor, SRA-2800, was found to be inoperable.

A review of SRA-2800 history file indicates that it failed at 0152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br /> on August 25, 1987. An administratively required shift surveillance performed at approximately 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> did not d'iscover the inoperability due to miscommunication between the two licensed operators performing the surveillances (personnel error). This misunderstanding resulted in the eight hour grab sample, required by T.S. 3.3.3.10, not being obtained until 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br />. SRA-2800 was restored to operable status at 1317 .hours.

Contributing to this event was an equipment failure on the Unit 2 Radiation Monitoring System (RMS) which required that.RMS data be obtained in the Unit 1 Control Room. This failure prevented a periodic observation of RMS status in the Unit 2 Control Room and disrupted the normal surveillance routine.

Surveillance procedures have been changed to establish periodic monitoring of local or opposite unit RMS indication whenever failure of an RMS control terminal, causes a loss of indication in the affected Control Room.

8806220257 8806l0 PDR ADOCK 05000316 NRC Form 355 8 PDR (04)3)

NRC Form 3ddA U.S. NUCLEAR REGULATORY COMMISSION (943(

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMB NO, 3150&(04 EXPIRES: 8/31/88 FACILITY NAME (Il OOCKET NUMBER (El LER NUMBER (dl PAOE (3I SEOUENTIAL REVISION NUMSER NUMSER D. C. Cook Nuclear Plant, Unit Two o s o o o 3 1 6 8 7 009 0 1 0 2 OF 0 4 TEXT /I/ moro u>>so /I rodu/sod, u>> oddru'or>>/h'RC %%dsm 388A's/ (IT)

Conditions Prior to Occurrence Unit 2 was operating at 80.5 percent'eactor thermal power at the time of this event. 1 Descri tion of Event This LER has been revised to reflect a change in the corrective action.

On August 25, 1987, at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />, during performance of shift surveillances, the gland seal leakoff (GSLO) (EIIS/TC) effluent radiation monitor (EIIS/

TC"MON) SRA-2800 was found to be inoperable. A review of the monitor history file indicated that the inoperability began at 0152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br /> on August 25, 1987.

The inoperability was initiated by a spurious isolation of turbine auxiliary cooling water (TACW) (EIIS/TJ) to the GSIO condensers (EIIS/TC-COND), which occurred at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> when the TACW pumps (EIIS/TJ-P) were switched. The Control Room. operators were unaware 'of the isolation because the associated alarm annunciated and cleared before The isolation of cooling water led to excess steam being exhausted which it could be recognized.

caused a condensation buildup in the SRA-2800 sample line and prevented adequate sample flow.

For the duration of this event, indication for the majority of the Unit 2 Radiation Monitoring System (RMS) (EIIS/IL), including SRA-2800, was unavailable in the Unit 2 Control Room due to a hardware problem with the control terminal (EIIS/IL-KBD). Indication for the Unit 2 monitors, however, was available in the Unit 1 Control Room and was being used for Technical Specification (T.S.) requirements.

An administatively required shift surveillance, performed at approximately 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, did not discover the inoperability due to miscommunication between the two utility licensed operators performing the surveillance (personnel error).

The Unit 2 dayshift operators noted the TACW isolated to the GSLO condensers during panel walkdowns for shift turnover; however', the potential effect on SRA-2800 was not recognized. TACW was restored at approximately 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

At 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br />, after the inoperablility: of SRA-2800 was discovered (1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br />), the compensatory grab sample required every eight hours by T.S.

3.3.3.10 was obtained. This was approximately ten hours after the SRA-2800 inoperability should have been identified. SRA-2800 was restored to operable status at 1317 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.011185e-4 months <br /> on August 25, 1987, by draining the condensate buildup from the sample line.

NRC FORM ESSA (983 I

NRC form SSSA 0 U.S. NUCLEAR REGULATORY COMMISSION IBS(3I LICENSEE EVENT REPORT (LERI TEXT.CONTINUATION APPROVED OMB NO. 3ISO&IOS EXPIRES: B/31/BB FACILITY NAME ((I DOCKET NUMBER (21 LER NUMBER IS) PACE (3>

YEAR SEOUENTIAL sos REVISION d'or< NVM ER NuMSER D. C. Cook Nuclear Plant, Unit Two 0 s o 0 03 16 8 7 0 0 9 010 3 OF 0 4 TEXT /// moro sosco /s rsrsrrirsd, Irss sddrs/srss/HRC Form 3////A'/ (17)

With the exception of the SRA-2800 and Unit 2 RMS control terminal inoperability, there were no inoperative structures, components or systems that contributed to this event.

Cause of Event The cause of this event was the failure to perform an adequate review of the RMS monitor status during the administratively imposed shift surveillances, which occurred due to the miscommunication (personnel error) between the operators performing the surveillances.

The spurious isolation of TACW to the GSLO condenser initiated the SRA-2800 inoperability. The lack of RMS indication in the Unit 2 Control Room, which prevented periodic observation of RMS status in the affected Unit and disrupted the normal surveillance routine, contributed to this event.

Anal sis of Event This event was determined to be reportable per 10 CFR 50.73(a)(2)(i), since the grap sample required by T.S. 3.3.3.10 every eight hours during SRA-2800 inoperability was not obtained until approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after the inoperability should have been discovered.

The purpose of the GSLO effluent radiation monitor is to give indication of a primary to secondary leak. The main condenser off gas effluent also has a radiation monitor for the same purpose. This monitor was operable during this event and there was no indication of a primary to secondary leak.

The grab sample of the GSLO effluent also indicated no primary to secondary leak.

Based on the above it is concluded that this event did not constitute a significant safety problem as defined in 10 CFR 50.59.

Corrective Actions

1) A grab sample as required by T.S. 3.3.3.10 was taken at 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br /> on August 25, 1987.

2) The SRA-2800 monitor was restored to operable status at 1317 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.011185e-4 months <br /> on August 25, 1987.

NRC FORM ESSA (983i

NRC Form 3ddA U.S. NUCLEAR REGULATCRY COMMISSION (9431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3(50-0104 EXPIRESPB/31/88 FACILITY NAME (11 COCKET NUMBER (31 LER NUMBER (SI PACE IS)

YEAR )i SEQUENTIAL NUMIIER (il REVISION

$:i>S NUMBER D. C. Cook Nuclear Plant, Unit Two o s o o o 31 687 0 0 9 0 1 04 QF 0 4 TEXT /// mors soscs/I rN/u/rsd. uss sddtu'orrs/ HRC Form 3SSA's/ (171

3) Surveillance procedures have been changed to establish periodic monitoring of local or opposite unit RMS indication whenever failure of an RMS control terminal causes' loss of indication in the affected Control Room.

4) The involved personnel have been counseled on the importance of clear, concise communications.

Failed Com onent Identification s Plant Designation: Radiation Monitoring System Control Terminal Manufacturer: Eberline Instrument Corporation Model: CT-1B EIIS Code: IL-KBD Previous Similar Events Three previous events were identified which involved failure to initiate compensatory sampling due to miscommunications.

LER 315/84-005 LER 315/84-026 LER 316/85-043 NRC FOAM SddA (9831

Indiana Michigan Power Company

~

Cook Nuclear Plant P.O. Box 458 Bridgman. Ml 49106 616 465 5901 INOIANA NICHIGiAN POWER June 10, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-316 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:

87-009-01 Sincerely, W. G. Smith, Jr.

Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr.

A. B. Davis, Region III M. P. Alexich P. A. Barrett H. B.- Brugger R. W. Jurgensen NRC Resident Inspector J. F. Stang, NRC R. C. Callen G. Charnoff, Esq.

Dottie Sherman, ANI Library D. Hahn INPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau