ML18005A935

LER 89-009-00:on 890501,discovered That Monitoring for Radioactivity in Turbine Bldg Floor Drain Effluent Not Performed from 890429-30.Caused by Isolation of Sample Collection Path for Calibr of detector.W/890530 Ltr

ML18005A935
Person / Time
Site:	Harris
Issue date:	05/30/1989
From:	Lew G, Richey R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-890059-(O), LER-89-009-01, LER-89-9-1, NUDOCS 8906060491
Download: ML18005A935 (6)

Text

gccEMRA.TED D1STRIBU73ON DE)dO~STRATION SYSTEM REGULATY YNFORNATYON DYSTRYSUTIOYSTE>l (RYDS)

ACCESSION NBR:8906060491 DOC.DATE: 89/05/30 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION LEW,G.T. Carolina Power & Light Co.

RICHEYiR.B. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-009-00:on 890501,failure to obtain grab sample from turbine bldg floor drain effluent w/inoperable monitor.

W/8 ltr.,

DISTRIBUT10N CODE: IE22T COPIES RECEIVED:LTR L ENCL /

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

SIZE:

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BECKER,D 1 1 iNTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 IRM/DCTS/DAB 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 , NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RPB 10 2 2 NUDOCS-ABSTRACT 1 1 RKG 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G WILLIAMSgS 4 4 FORD BLDG HOY,A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYSgG 1 1 NSIC MURPHYEG.A 1 1 NOXK 'IO ALL %IC6" RZCIPZEÃIS:

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 42

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Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 MAY 3 0 1989 File Number: SHF/10-13510C Letter Number: HO-890059 (0)

U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 89-009-00 Gentlemen'.

In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September 1983.

Very truly yours, R. B. Richey, Mana er Harris Nuclear Project RBR:tbb Enclosure cc'Mr. R. A. Becker (NRR)

Mr. W. H. Bradford (NRC - SHNPP)

Mr. S. D. Ebneter (NRC RII) 890boh049i 85'0530 PDR ADQCK 05000400 S PNU MEM/LER-89-009/1/OS1

NRC Form 355 US. NUCLEAR REQULATOAY COMMISSION 1943)

APPROVED OMB NO. 11500101 EXPIRES: 5/31/BS LICENSEE EVENT REPORT (LER)

FACILITY NAME (I) DOCKET NUMBER (2) PA E SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE 050004 1 OF 0 4 FAILURE TO OBTAIN GRAB SAMPLE FROM TURBINE BUILDING FLOOR DRAIN EFFLUENT WHILE D ON M NITOR WAS INOPERABLE EVEN'T DATE (5) LER NUMBEA (5) REPORT DATE 17) OTHER FACILITIES INVOLVED (5)

MONTH YEAR e+~.. SEOUE<<vrAL rl f vrsloN DAY YEAR FACILITYNAMES DOCKET NUMBER(SI OAY YEAR rCUMSER ycS NUMBER MONTH 0 5 0 0 0 0 0 9 0 0 053 089 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (I: IChectr one or more ol the lollowinPI (11) 0 5 0 0 0 OPERATINO MODE (9) 20A02(5) 73.71(II) 20.405(cl 50.73(c) 121()el POWER 20.405(s)111(0 50.35(c)(1) 50.73(s) (21(rl 73.71(cl LEYEL 1 0 20.COB( ~ I(1)(5) 50.35(cl(2) 50.73(s) (2)(vBI DTHEA ISpeclly ln Ahrtrect herowend ln Test, hrRC Penn 20.SOS( ~ I(1 I ((BI 50.73(sl(2) (I) 50.73(s) (1) (rIIII (Al Jdb'Al 20A05( ~ l(1)(lv) 50.71(sl(2)(BI 50.71( ~ l(2)(rIBI(B) 20.505(s) ill(v) 50.73(c) (2)(IIII 50.71(s) 12)(el LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE G. T. Lew, Project Engineer Regulatory Compliance COMPLE'TE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS AEPOAT (13)

MANUFAC. EPOATABLE MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TO NPADS SYSTEM COMPONENT TUREA TUAER TO NPADS ii)jgi')jsa3('((5)

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

YES IIIyn. complete EXPECTED SVSStlSSIOtt OA TEI NO ABSTRACT ILlmit to tetr() spec<<, I e.. epproslmetely ttttnn rlnple spree typewritten linnl llSI ABSTRACT On May 1, 1989, it was discovered that monitoring for radioactivity in the Turbine Building Floor Drain Effluent Line was not performed in accordance with Technical Specifications during the period of April 29 and April 30, 1989. Technical Specification Table 3.3-12, Action Statement 36, requires that a grab sample be analyzed for radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the monitor is inoperable. The required sample was not taken on April 29 and April 30, 1989. The plant operated at full power throughout the period of time considered by this event.

A sample was taken and analyzed on May 1, 1989, as soon as supervisory personnel realized the error. The sample results showed that effluent radioactivity levels had not changed throughout the period of time in question.

The failure to collect the required sample was the result of isolation of the sample collection path for calibration of the detector. Corrective action consisted of locating an alternate sample point and appropriate procedure changes.

NRC Form 355 (9 53)

NRC Form SSSA V.S. NUCLEAR REOULATORY COMMISSION (043 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION AFFROVED OMS NO, 3(SOW104 EX/rIRES: 8/31/88 FACILITY NAME ill DOCKET NVMEER (ll LER NUMSER (SI ~ AOE (3I soovSNT/AL ASVISION NVM S4 NVM Srl SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE 0 s 0 0 0 40 89 009 00 02 oF0 4 TEXT /IF moro <<roce /o eerrokerd rroe arRR/ono/HRC Form 3(E(4'o/ (PI DESCRIPTION The Turbine Building Drain Monitor (REM-01MD-3S28) provides an indication to plant operating personnel of the activity in the effluent from the Turbine Building industrial waste sumps to the cooling tower blowdown via the yard oil separator. The monitor was declared inoperable at 1410 on July 23, 1988, as a result of equipment problems and a work request was initiated to accomplish repairs. The repairs required design changes which required a significant amount of time to design and implement. Daily compensatory grab sampling was initiated as required by Technical Specification Table 3.3-12, Action Statement 36. The sample is normally taken from a grab -sample collection valve located on the radiation monitoring skid. Grab samples were drawn and analyzed as required until this event.

On April 27, 1989, repairs to the monitor were completed and a calibration of the 'monitor was initiated in accordance with procedure RST-011. As a part of this procedure, the flow path to the monitor is isolated and the detector assembly disconnected and removed for calibration. In this condition, a grab sample cannot be drawn from the normal grab sample connection. On April 27 and April 28, the technician performing the sampling was assisted in obtaining the sample by the Radiation Monitoring System Technicians on shift. To obtain sample flow, the sample lines to the detector were plugged, a valve bypassing the detector opened, and the isolation valve opened. The isolation valve was closed after the sample was obtained. This action isolated the grab sample connection from the process flow path.

Work on the monitor was suspended for the weekend of April 29 and April 30.

The technicians on duty during the preceding week did not make any log entries concerning the status of the sample path or the additional actions needed to obtain a grab sample. The chemistry technician coming on duty for the weekend was not aware of, or informed of, the fact that the grab sample path was not in service. On April 29 and April 30, the technician on duty attempted to obtain the sample and was not able to obtain sample flow because of the isolated flow path. He assumed that the lack of sample flow indicated that the effluent flow path was not in service and; therefore, a sample was not required. Log entries on April 29 and April 30 to the effect that the effluent path was not in service were made.

On the morning of May 1, 1989, a supervisor's review of the records disclosed that the required samples were not taken. A compensatory sample was obtained at 1140. The results of this sample indicated no increase in the activity levels of the floor drain effluent. There was no observed primary to secondary leakage during the time interval of this event.

NRC FORM SOS* 4 V.S.O/rO:1088 0824 d38/4dd (043(

NRC Ferro 3SSA U.S. NUCLEAR REOULAYORY COMMISSION 1840)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3150&IOO EXPIRES: 8/31/88 FACILISY NAME I'l DOCKET NUMSER Ill LER NUMSER IS) PACE 131 SHEARON HARRIS NUCLEAR POWER PLANT yEAR +~el sECUENTIAL NVMSSII pl

'~P osvrsroN NVM so UNIT ONE 400 8 9 09 00 0 3 QF 0 4 TEXT ///more 3/rece/e n//r/rerd Iree /AS/orro////IC Femr 3//IrA3/113>

CAUSE This event was caused by personnel error. The following elements should be considered as factors contributing to the cause of this event:

1. The sampling procedure assumed that a grab sample could be taken from the sample point on the skid at all times. This procedure and repair and calibration procedures did not allow for the possibility of isolating the sample path. The sampling procedure assumes that a lack of sample flow means that the system flow path is secured.

2. System status was not effectively communicated to personnel responsible for obtaining samples. Technicians aware of the abnormal conditions needed to draw a sample did not communicate this condition to personnel coming on duty.

3. The technician taking the sample incorrectly evaluated the significance of the absence of sample flow. He assumed that the lack of sample flow was due to no effluent system flow.

ANALYSIS There are no adverse safety consequences as a result of this event. The only potential source of radioactive material to the Turbine Building would be the result of primary to secondary leakage. There was no change in the activity levels of the secondary coolant and samples taken before and after the period of missed samples show that there was no change in the radioactivity levels of the effluent.

There have been other previous Licensee Event Reports that pertain to the failure to meet technical specification sampling requirements. These include LER 86-001, LER 86-010, LER 87-015, LER 87-016, LER 88-015, and LER 88-027.

These reports deal with sampling requirements that were missed. The current event is the only'ne that resulted from an incorrect assessment of system status.

CORRECTIVE ACTION

1. The sampling procedure was changed to provide for a sampling point that is not subject to isolation by radiation monitor calibration procedures'.

Procedures will be revised to account for the possibility of loosing sample flow.

3. The cause and implications of this event will be reviewed with the appropriate personnel.

NRC FORM SSSA o U.S.OPO,1088 0 824 d38/Sdd 18831

NRC Par>> SSSA U.S, NUCLEAR REOULATORY COMMISSION IBBS I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO 0MB NO, 3150WIOA EXPIRES: B13IIBS PACILI'TY NAME 111 DOCKET NUMBER (21 LER NUMBER IS) PACE 131 SHEARON HARRIS NUCLEAR POWER PLANT yEAR @'EQUENTIAL S'ji ASV>>K>N NVMS\R:",< NVM

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UNIT ONE s o o o 400 8 9 0 9 0 0 0 4 OF TEXT N ma>> g>>ce B>>outed, VPP 1VRC ANN 3BBAS I II' ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) CODES!

Com onent or S stem EIIS Code Cooling Tower Blowdown Radiation Monitor IL Radiation Monitoring System IL Yard Oil Separator WH NRC PORM SSSA P U.S.OPO: I EBB.0424.03B/Add IB 431