ML18010B144

LER 93-009-00:on 930622,TS Violation Occurred Due to Axial Flux Difference Logging Error.Caused by Personnel Error. Individuals Involved Counseled & Afd Operations Surveillance Test OST-1070 revised.W/930720 Ltr

ML18010B144
Person / Time
Site:	Harris
Issue date:	07/21/1993
From:	Robinson W, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-930126, LER-93-009-01, LER-93-9-1, NUDOCS 9307300104
Download: ML18010B144 (4)

Text

ACCEI ERATO DOCUMENT DIST UTION SYSTEM REGUL Y INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR:9307300104 DOC.DATE: 93/07/21 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.

ROBINSON,W.R. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 93-009-00:on 930622,TS occurred due to axial flux difference logging error. Counseled individuals & revised D operations surveillance test 1070.W/930720 ltr.

DISTRIBUTION CODE: IE22T S COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER),

! ENCL Incident J SIZE:

Rpt, etc.

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 LE,N 1 1 D INTERNAL: ACNW AEOD/DOA 2,2 1 1 ACRS AEOD/DSP/TPAB 2

1 2

1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 N J)SSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 EG FILE 02 1 1 RES/DSIR/EIB 1 1 FILE 01 1 1 EXTERNAL: EG&G BRYCEPJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (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 32 ENCL 32

+gal.L Carolina Power & Light Company HARRIS NUCLEAR PLANT P.O. Box 165 New Hill, North Carolina 27562

<JUL 2 o l995 Letter Number: HO-930126 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 93-009-00 Gentlemen:

In accordance with Title 10 to the Code of Federal Regulations, t:he 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, W. R. Robinson General Manager Harris Nuclear Plant MV:kls Enclosure cc: Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - PM/NRR)

Mr. J. E. Tedrow (NRC - SHNPP)

'-'900-> S MEM/LER93-009/1/OS1 9307300i04 93072i PDR S

ADOCN 05000400 PDR

NRC FORM 368 (5-92) t LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGUlATORY COMMISSION t APPROVED BY OMB HO. 3160 EXPIRES 6/3II86 0I04 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THiS INFORHATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COHHENTS REGARDIHG BURDEN ESTIHATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (See reverse for required number of digits/characters for each block) (MNBB 7714)g U ST NUCLEAR REGULATORY COMMISSIONg WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF HANAGEHENT AND BUDGET 'WASHINGTON DC 20503.

FACILITY NAME II) Shearon Harris Nuclear Plant-Unit Nl DOCKET NUMBER i2) PAGE i3) 05000 400 1 OF 2 TITLE (4) Technical Specification violation due to Axial Flux Difference logging error.

EVENT DATE LER NUMBER 8 REPORT DATE OTHER FACILITIES INVOI.VED SEQUENTIAL REVISION FACILITY NAME DOCKET NUHBER MONTH DAY YEAR YEAR NUMBER HUHBER MONTH DAY YEAR 05000 22 93 93 -- 009 00 '21 93 FACILITY NAME DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR  %: Check one or more 11 MODE (8) 20.402(b) 20.405(c) 50 '3(a)(2)(iv) 73.71(b)

POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71 (c) 100X LEVEL IIO) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50 '3(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50.73(a)(2)(i I) 50.73(a)(2)(viii)(B) Abstract and in Text, below 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) NRC Form 366A)

I.ICENSEE CONTACT FOR THIS LER 12 (Include Area NAME Michael Verrilli TELEPHONE HUMBER (919) 362-2303 Code)

COMPLETE ONE lINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE REPORTABLE CAUSE SYSTEH COHPONENT MANUFACTURER SYSTEH COMPONENT MANUFACTURER TO NPRDS ms';."'.":,."..'AUSE TO HPRDS SUPPI.EMENTAL REPORT EXPECTED 14 MONTH DAY YEAR EXPECTED YES (lf yes, complete EXPECTED SUBMISSION DATE) ~ X NO SUBMISSION DATE II6)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) IIB)

On June 21, 1993 at 0846, the plant process computer (Emergency Response Facility Information System - ERFIS) was declared inoperable to allow for a software upgrade modify'.cation. This rendered the Axz.al Flux Difference (AFD) Monitor inoperable. Technical Specifications (TS) require logging AFD hourly inoperable and for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after declaring the AFD monitor every 30 minutes thereafter. At 0900, Operators began hourly AFD logging per the AFD Operations Surveillance Test (OST-1070). At

'0930 on June 22, the logging frequency, was not changed to a 30 minute interval as required by the OST and TS. Instead, Operators continued to log AFD hourly until the error'as detected at 2300 on June 23,'993.

The cause of this event was personnel error on the part of the control room operators performing the manual AFD logginq. Corrective actions include counseling the involved individuals, revis3.ng OST-1070 to require logging AFD at 30 minute intervals immediately upon declaring the AFD monitor inoperable, and disseminating information related to this event to other operations personnel.

This condition constitutes a TS violation and is being reported per 10CFR50. 72 (a) (2) (i) (b)

NRC FORM 366

NRC FORH 388A'5-92),

LICENSEE EVENT REPORT (LER) t APPROVED BY OMB NO.

EXPIRES 5/31/95 EST IHATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORHAT ION COLLECTION REQUEST: 50.0 HRS ~

FORWARD COHHEHTS REGARDING BURDEN EST IHATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH 31600104 (HHBB 7714), U.S. NUCLEAR REGULATORY COMHISSIOH, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MAHAGEHENT AND BUDGET 'WASHINGTON DC 20503.

FACILITY NAME I DOCKET NUMBER 2 LER NUMBER (6) PAGE 13 Shearon Harris Nuclear Plant YEAR SEQUENTIAL REVISION Unit g1 05000/400 2 OF 2 93 009 00 TEXT If more s ce is r uired use additional co ies of NRC Form 366A {17)

EVENT DESCRIPTION:

On June 21, 1993 at 0846, the plant process computer (Emergency Response Facility Information System - ERFIS) was declared inoperable to allow for.a software upgrade modification (Plant Change Request PCR-6535). The ERFIS computer normally performs the Axial Flux Difference (AFD) Monitor function required by Technical Specifications (TS). With the AFD Monitor inoperable, TS surveillance requirement 4.2.1.1.b requires manual logging of AFD hourly for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and every 30 minutes thereafter. At 0900, June 21, 1993, operators initiated OST-1070 (AFD Operations Surveillance Test) and began taking hourly readings as required. Following 24 hourly readings the logging interval should have been changed to every 30 minutes starting with the 0930 reading on June 22, 1993. However, this increase in logging frequency did not occur and operators continued to manually log AFD hourly until the error was detected at 2300 on June 23, 1993.

CAUSE:

The cause of this event was personnel error on the part of the control room staff involved with performing the manual AFD logging. The change in surveillance frequency at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from hourly to every 30 minutes was a human factors issue that increased the potential for this error.

SAFETY SIGNIFICANCE:

There were no significant safety consequences as a result of this condition. Operators continuously monitored AFD throughout the period of time when the 30 minute interval should have been invoked and documented the readings hourly. These readings indicated, that 100~ power equilibrium conditions existed and that AFD was stable and within TS limits.

This condition constitutes a TS violation and is being reported per 10CFR50.72(a)(2)(i)(b). Previous AFD logging errors were reported in LER's87-044 and 87-048. However, the cause of these events were different in that single AFD log entries were missed in both cases, due to operators being distracted by other evolutions.

CORRECTIVE ACTIONS:

1. The Reactor Operators that made the AFD logging error were counseled.

This involved reemphasizing the need for attention to detail and strict procedural compliance and a review of the Tech Spec and procedural requirements related to this event.

2. OST-1070 was revised to require a thirty minute logging upon declaring the AFD monitor inoperable, rather than interval'mmediately switching from 60 to 30 minutes't the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> point.

ElIS INFORMATION:

N/A NRC FORH 366A (5-92)