ML17328A993

LER 91-003-00:on 910308,liquid Release to Unrestricted Area in Violation of Tech Spec.Caused by Failure of Hi Fail Status of RRS-1000 to Produce Trip.Operations Procedure 12 Ohp revised.W/910408 Ltr

ML17328A993
Person / Time
Site:	Cook
Issue date:	04/08/1991
From:	Blind A, Wojcik J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-003, LER-91-3, NUDOCS 9104120346
Download: ML17328A993 (8)

Text

. ACCELERATED D+MBUTION DEMONS~TION SYSTEM 2

/i

~tS-

.* REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

.ACCESSION NBR:9104120346 DOC.DATE: 91/04/08 NOTARIZED: NO 'OCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315

'AUTH. NAME AUTHOR AFFILIATION WOJCIK,J.T. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 91-003-00:on 910308,licIuid release to unrestricted area in violation of tech spec. Caused by failure of Hi Fail D status of RRS-1000 to produce trip. Operations procedure 12 OHP revised.W/910408 ltr.

CODE: IE22T COPIES RECEIVED:LTR

"'ISTRIBUTION TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

j ENCL J SIZE: 5 NOTES RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D COLBURN,T. 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 - 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 '. 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 NRR/DREP/PRPB11'RR/DST/SICB 2 2 NRR/DST/SELB 8D 1 1 7E 1 1 NRR/D 1 1 NRR/DST/SRXB 8E 1 1 REG ~SPY 02-2LE 1 1 RES/DSIR/EIB 1 1 RGN3 TEE 01 1 1 EXTERNAL: EG&G BRYCE, J. H 3' L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1' NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 INDIANA NICHIGAN POWER April 8, 1991 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 ortin S stem the following report is being submitted:

91-003-00 Sincerely, A.A. Blind Plant Manager AAB:sb Attachment c: D.H. Williams, Jr.

A.B. Davis, Region M.P. Alexich III P.A. Barrett B.F. Henderson R.F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector T. Colburn NRC J.G. Keppler M.R. Padgett, G. Charnoff, Esq.

Dottie Sherman, ANI Library D. Hahn INPO S.J. Brewer/B.P. Lauzau B.A. Svensson 9<<4 "O~"'"

I PDR ADOCK 0'~OOO~XS S

e>>>>

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (689) APPROVED OMB NO. 31504)f04

• r>>>>

E XP IR Est 4I30I92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50D HAS. FOAWARD LICENSEE'EVENT REPORT ILER),. COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND RFPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (ll DOCKET NUMBER l2) PA E 3 D. C. 'OOK NUCLEAR;,'PLANT,UNIT 1 0 5 0 0 0 3 1 5 1 OF0 4 TITLE (4)

LIQUID REL'EASE TO UNRESTRICTED AREA IN-VIOLATION OF TECHNICAL SPECIFICATION 3/4.3.3 EVENT DATE l5) >>'ER NUMBER l6) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR  ;~~.SEQUete TtaL OAY YEAR FACILITYNAMES OOCKFT NUMBER(SI NUMBER tcUMBEA MONTH

>>>> D.C. -COOK PLANT UNIT 2 o 5 o o o 3 1 0 30 89 91 003 0 0 040.8 91. 0 5 0 0 0 THIS REPORT IS SUSMITTEO PUfISUANT TO THE RLQVIREMENTS OF 10 CPA (I: IChoch one or more or tho Iotiowinoi (11)

>>1 >> OPERATING ~ ~

MODE (SI 1>> 20A05(cl 50.73(e) (2)(irl 73.71AII 20AOS(el (1) I I) 50.36(c)(1), 50,73(e I (2) (v) 73.71(cl POWER 4Ã'0A02Bt) = ~

LEYEL 1 0 0 20.405(e)(II(6)>> >>>> .SOA(c)(21, ->>a EH>>~W S0.73(e I l2 I (r6 I OTHER ISoocliy in Ant trect i

~ P l2)(vlf(i(BI hetow onti In Toot, FIRC Form 20A05(e Illl(BI) X i+j(p~ j'j%':-," 50.73( ~ )(2)(I) 60.73lel(2)(vBI)(AI 36IFAI

10A05(e) (i)(tv) 10A05(e) (1)(v) 50.73 4 I (2) I II I 50.734) (2)((BI 50.73(el 50.Tie l(2) (el LICENSEE CONTACT FOR THIS LER (12)

NAME P TELEPHONE NUMBER J."T. WOJCIK TECHNICAL PHYSICAL SCIENCES AREA CODE DEPARTMENT SUPERINTENDENT 61 64 65 -5 901

• COMPLETE ONE. LINE FOA EACH COMPONENT O'AILVAE OESCRIBEO IN THIS REPORT (13)

'>> f'*

c>> CAUSE SYSTEM COMPO N E NT " ~ MANUFAC - j,>>

'>>TURER '>>y-MANUFAC.

TVRER EPOflTABLE NPRDS

@'O Ix 4 X'<<'I-'0 ,P IN 'tE'0-7 "'0 Wnt(~4 g)@%%i@%

SUPPLEMENTAL REPORT EXPECTED (14). MONTH OAY YEAR EXPECTED I >>

>> ~

Kw vrt>>: SUBMISSION

'O DATE (15I YES III yet, comotete EXPECTED $ (ISMISSIOItttDATEI ABSTRACT ILimit to 1400 g>>tet, ioonnrooimetoiy rirtoon tinotott>>co tyt>>written I>>nett IISI On'ar'cjit 81 1991't"'approximatelv 0745 hour0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />sPITE sampled but unmonitored liquid release occurred w'hen a.liquid waste release was restarted and completed while the,.3.iquid waste discharge. monitor (RRS-1000) was inoperable.

't, ~

'This is-a violation of Technical Speci'fication 3/4.3.3, Radiation Monitoring Instrumentation, 'LCO 3.3.3.-9, Radiation Liquid Effluent Instrumentation.

review of the radioanalytical results, of the monitor tank contents indicate that while the maximum permissible concentration (MPC) was at 3.58E+0 MPC (including Tritium)*,"the- actual concentration discharged to Lake Michigan was',.3.70E-4"MPC when"consider'ing monitor tank flow rate (1.24E+2 gpm) and dilution water flow rate (1.20E+6 gpm). Therefore, 10CFR20 limits were not challenged.

'The primarv factor of. this event is the failure of the monitor to actuate the

. discharge fsolation valve, RRV,285, while the radiation monitoring device (RRS-1001) was in a Hi,Fail status.'he root cause although not conclusive, i's attributed to a shorted interrupt logic line which kept the

'onitor +rom alarm checking while in the High Fail status. A secondary factor is 'attributed to the failure of the operator to recognize the significance of-a "Hi Fai3." status.

NRC Forth 366 (649) t o>> l>>t>>v+ o>> 4C) ' > er->>'>>-

t NRC FORM 366A U.S, NUCLEAR REGULATORY COMMISSION (64)9) APPROVED OMB NO. 31500104 EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPI.Y WTH THIS LICENSEE EVENT REPORT HLER) INFOAMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH IP4301, U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31604104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME u) DOCKET NUMBER (ll LER NUMBER (6) PAGE (3)

it) SEQUENTIAL NUMBEII 4~% RSV SION

's1r$ NUMBFII D. C. COOK NUCLEAR PLANT UNIT 1 TEXT ///mad 4/>>cu /4 nquked, u44 uddidouu//VRC FomI 35549/ ((7) osooo 9 1 0 0 3 0 0 02 QF 0 4 Conditions Prior to Occurrence Unit I and Unit 2 (EIIS/AB-RCT) at Mode 1 (Power Operations), 100K power.

Descri tion of Event On March 8, 1991, at approximatelv 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, Operations personnel began discharging liquid waste release number L91-035. The release was automatically terminated at 0131 hours0.00152 days <br />0.0364 hours <br />2.166005e-4 weeks <br />4.98455e-5 months <br /> on a sample flow trip (External Fail).

The sample flow through the off-line radiation monitor (EIIS/IL-MON) exceeded the high flow setpoint (approximately 14 gpm) when the operator was attempting to balance the release flow rate and sample flow rate in accordance with the procedure 12 OHP 4021.006.004. In accordance with step 10.8 of the procedure, the individual called the Unit Supervisor (US) to request restart of the release. This step allows restart of the release if the termination was due to a sample flow adjustment problem. The US agreed to the restart. At approximately 0157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br />, while, attempting to adjust sample flow, the release was once again automatically terminated due to sample flow out of. limits. It was at this ti'me the radiation monitor went not only into an External Fail status but also went into a Hi Fail status on channels 1 and 3. Channel 1 is the detector which views the effluent sample. Channel 3 is the local area detector which is not associated with the actual release. It should 'adiation also be recognized that the External Fail flow alarms are displayed using channel 1.

After the second trip, the US requested another operator to investigate the problems the shift was having with this release. The individual reviewed the Radiation Monitoring System (RMS) CRT and noted the Hi Fail status and the count rate exhibited by channel 1 which appeared normal. He deduced incorrectly that the Hi Fail was not valid since the detector response appeared normal and below the high alarm setpoint, therefore the problems existed in adjusting sample flow.

The release was restarted at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> and continued until completion at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />. During this time, the monitor was in a Hi Fail status with channel 1 ten-minute averages at negative count rates. A Hi Fail status provides a trip signal to the isolation valve and monitor tank pump and should nothave allowed restart of the release.

The condition was discovered by Operations personnel when obtaining a ten-minute average history printout from the control terminal (CT) for the Eberline Radiation Monitoring System at the end of the release as required by 12 OHP 4021.006.004.

NRC Form 366A (569(

NAC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (669) APPROVED 0MB NO. 31504104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT [LER) INFORMATION COLLECTION REQUEST: 60.0 HRS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P4)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3)

LER NUMBER (6)

SEOVENTIAL REVISION D. C. COOK NUCLEAR PLANT YEAR NVMSER NVMSER UNIT 1 o s o o o 315 0 3 0 0 0 3 oF0 4 TEXT /i/mare 4Pdce /4mEIdmd, VJ4 dddic)m4/HRC FdmI 36643/ (17)

Technical Specification 3/4.3.3 LCO 3.3.3.9.requires that with.,a required channel inoperable, releases may continue up to thirty days providing at least two independent samples are analyzed in accordance with Specification 4.11.1.1.1 and at least two qualified individuals verHy discharge valving prior to initiating the release otherwise, suspended releases, via this pathwav. This specification was not complied with from approximatelv 0245 to 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> for release L91-035.

Cause of Event The event was caused bv two factors. The primarv. factor .is the failure of the Hi Fail status of RRS-1000 to produce a trip. signal Co.;terminate Ithe release. The second factor is attributed to the failure of.. the operator,.to recognize the significance of a Hi Fail status; 'I Analysis of Fvent A review of the release flow rate, the dilution water flow rate and the radioanalvtical results of. the Monitor Tank being. release -indicates that,-the actual total NPC value for the release was 3.70E-4"when, accounting for the Monitor Tank release flow rate (1.24E+2 gpm) and the dilution water flow rate (1.20E+6 gpm). This event did not have an'mpact on the he'alth and safetv of the public.

Batch liquid releases were ceased pending initial investigation. They have since continued under the requirements of LCO 3.3.3.9, Action Statement'3.

Corrective Action Troubleshooting of the liquid discharge Monitor (RRS-1000) has verified trip signals and valve isolation due to a Hi Fail status. Operations procedure 12 OHP 4021.006.004 has been revised to require a channel check of the required channel before initiating the release and while the release is in progress.

The change will also include acceptance criteria for the channel check.

N R C F one 266A (609)

NRC FORM 366A US. NUCLEAR REGULATORY COMMISSION (669) APPROVED OMB NO 3)50010O E X P I R ES: I/30/92

'UCENSEE EVENT REPORT (LER) ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS. FORWARD TEXT CONTINUATION COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13)SOO)oi), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2)

LER NUMBER (6) PAGE (3)

YEAR )&1 SEOUBNTIAL NUMBER oak tr'< REYISION NUMBER D. C. COOK NUCLEAR PLANT UNIT 1 o 5 o o o 31 5 91 00 3 00 04 oF 0 4 TEXT /// mare <<ace/e rrquked, ace a//&arre/ NRC %%drm 36549/ (17)

Failed .Com onent Identification Liquid Waste Discharge Monitor Plant- Designation: RRS-1000 Manufacturer: Eberline Installed Design: American Electric Power Service Corporation (AEPSC)

.Previous Similar Events r

None.

~ ~

NRC Form 356A (689)