ML18005A967

LER 89-010-00:on 890529,Tech Specs Violation Occurred When Performing Incorrect Reactor Coolant Analysis.Caused by Personnel Error.Correct Analysis for Sample Completed. Technician Involved counseled.W/890629 Ltr

ML18005A967
Person / Time
Site:	Harris
Issue date:	06/29/1989
From:	Richey R, Schwabenbauer R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-890073-(O), LER-89-010-01, LER-89-10-1, NUDOCS 8907050440
Download: ML18005A967 (5)

Text

ACCELERATED %1.'i~BU'IION DEMON%RATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8907050440 DOC.DATE: 89/06/29 'OTARIZED: NO DOCKET N FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION SCHWABENBAUER,R Carolina Power & Light Co.

RICHEY,R.B. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-010-00:on 890529,Tech Specs violation due to performing incorrect reactor coolant analysis.

W/8 ltr.

DISTRZBUTZQN CODE: ZE22T COPIES RECEIVED:L TR i ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

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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 NRR/DOEA/EAB NUDOCS-ABSTRACT ll 1 1

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FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 42-

Carolina Power & Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562, JUN 2 9 1989 File Number: SHF/10-13510C Letter Number: HO-890073 (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 89-010-00 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, Ma ager Harris Nuclear Project RBR:tbb Enclosure cc'. Mr. R. A. Becker (NRR)

Mr. W. H. Bradford (NRC SHNPP)

Mr. S. D. Ebneter (NRC - RII)

~907050'Cg pDR ~0 890++9

+ 05000400 PNU MEM/LER-89-010/1/Osl

NRC Form 345 US. NVCLEAR REOULATOIIY COMMISSION (903)

APPROVED OMB NO. 3150410I LICENSEE EVENT REPORT {LER) EXPIRESl 5/31/SS FACILITYNAME I'l DOCKET NVMSER 12) ~ t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 05000400TOFU3 TECHNICAL SPECIFICATION VIOLATION DUE TO PERFORMING THE INCORRECT REACTOR COOLANT ANALYSIS CAUSED BY PERSONNEL ERROR EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (5)

MONTH DAY YEAR YEAR 4EQVENTIAL DAY YEAR FACILITY NAMES DOCKET NUMBER(3)

NVMSEIV NVM44R MONTH 0 5 0 0 0 0 010 0 0 6 2 9 8 9 THIS REPOAT IS SUBMITTED PURSUANT T0 THE REOUIREMENTS OF 10 CFA (): IChech one or morc 0 5 0 0 0 OPERATINO of the foilowlntf (11 MODE IS) 20.402(4) 20A05(c) 50.'73(e l(2) (iv) 73.7)(III POWER 20 405(e) II)B) 50.35(c) II) 50.73(e I 12((v) 73.71(cl LEYEL 0 7 0 20.405(e)(ll(4) 50.35(c) (2) 50.7341(2) (v4) OTHER ISpoclfy ln Aorcrect trerow enrf ln yceL HRc Form 20.405(e)(11(SI) X 50.73(e) (2)(l) 50.734) (2) (vN) (Al SSSAJ 20.405 (e) (I ) (Iv) 50 734) 12) (41 50.73(e) (2) (v14)(S) 20.405(e I (I) (v) 50.734)(2) OS) 50.73( ~ )(2)(c)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER R. SCHWABENBAUER AREA CODE REGULATORY COMPLIANCE TECHNICIAN 919 362- 2669 COMPLE'TE ONE LINE FOA EACH COMPONENT FAILVRE DESCRIBED IN THIS REPOR'T (13)

CAUSE SYSTEM COMPONENT MANUFAC EPOATABLE MANUFAC.

TURER TO NPRDS CAUSE SYSTEM COMtONENT TVRER SUttLEMENTAL AEPOA'2 EXtECTED IICI MONTH DAY YEAII EXPECTED SUBMISSION YES llfyer, complete fXtfCyfD SUF erISSIDff DA yfl X NO DATE (151 AssTA ACT ILimit ro t f00 rpetcL l. 4, epprovlme rely fi freen cinfie rpece rypcwrlrten lineD 115)

The plant was operating in Mo'de 1, Power Operation, at 100 percent reactor power on May 28, 1989. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, reactor power was being reduced by a rate of 15 percent an hour to 70 percent power in order to perform turbine valve testing.

'I Technical Specifications Table 4.4-'4 requires an isotopic analysis of reactor coolant for iodine be performed at power changes of 15 percent or greater per hour, within 2-6 hours fo>lowing the thermal power change. The sample was taken at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on May 29, 1989; however, instead of performing an isotopic analysis for iodine as required, a boron analysis was performed.

This incorrect analysis was discovered at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on May 30, 1989, during routine review of surveillance test records by a foreman. Upon discovering that the wrong analysis had been performed another sample was obtained and analyzed at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> and found to be within acceptable limits.

The cause of the event was personnel error as the Technician performing the test failed to perform the required analysis. Corrective actions for this event was to complete the . correct analysis for the sample, counsel the technician involved, and review the event with appropriate personnel. There were no safety consequences as a result of this event as isotopic analysis of reactor coolant prior to and subsequent to the event revealed no abnormal or unusual levels of any isotopes of iodine.

This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B'R a Technical S ecification violation.

NRC Form 344 191)31

NRC ffrM 344A UA. NUCLEAR RECULATORY COMM)34)ON (943)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. 3)SOCIO(

EXPIRES: 9/31/49 FACILITY NAME I) I OOCKET NUMSER (2) LER NUMSER (4) PACE (3)

HEARON HARRIS NUCLEAR POWER PLANT YEAR '3 SEQUENTIAL NVM 'Cll j:3 A(YAK)N

"+'VM EA IT 1 TEXT /r ~ a N ~~

DESCRIPTION:

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0 5 0 0 0 0 2 OF The plant was operating in Mode 1, .Power Operation, at 100 percent reactor power on May 28, 1989.

Technical Specification Table 4.4-4 Surveillance 4b requires an isotopic analysis of reactor coolant for iodine be performed between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a Thermal Power change exceeding 15 percent of the Rated Thermal Power within a one hour period. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on May 28, 1989, reactor power was being reduced at a rate exceeding 15 percent an hour to 70 percent power in order to perform turbine valve (EIIS:SB) testing. A reactor cooLant sample was taken at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on May 29, 1989; however, a boron analysis was performed instead of the required isotopic analysis for iodine.

The performance of an incorrect analysis was discovered at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> by while doing routine review of surveillance test records. A reactor a'oreman coolant sample was then taken and analyzed for iodine at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on May 30, 1989, and found to be within acceptable limits.

CAUSE:

The cause of the event was personnel error as the Technician performing the test failed to perform the required analysis within the required time frame.

ANALYSIS:

There were no safety consequences as a result of this event. Isotopic analysis for iodine of reactor. coolant are performed to determine if a reactor power change initiated on iodine spike in the reactor coolant. Subsequent analysis showed no abnormal or unusual levels of any isotopes of iodine.

This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) as a Technical Specification violation.

There have been no similar events reported.

NRC FORM 344A (943>

f U.S GPO.)9450.424 434/Edd

NRC form SSSA U.S. NUCLEAR REOUL*TORY COMMISSION

)940)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROYED OMS NO. 3)50&)8e EXPIRES: 8/31/88 fACILITYNAME I)I DOCKET NUMSER 111 LER NUMSER IS) ~ AOE Q)

ILP SEOVSNTIAI RIS +ey>>K/N SHEARON HARRIS NUCLEAR POIeIER PLANT yEAR No NUM eo >><'vv eo UNIT 1 o 5 o o o 400 89 010 00 03 oF.O 3 TEXT /t //>>/e a>>ce /e esv/k/ecE vee NRMke>>/ A//IC /ce/II 38SA'e/ I )T)

CORRECTIVE ACTION:

1. The reactor coolant was analyzed for iodine isotopes and found to be acceptable.

2. The t'echnician who performed the incorrect analysis'as been counselled on the importance of carefully reading and adhering to procedural instructions.

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

4. A human performance evaluation will be performed on this event.

NRc eo/IM seeo 1983) o U S OPO,)988 0 82e 538/e55