ML18009A934

LER 91-013-00:on 910515,reactor Trip Occurred During Performance of Calibrs.Caused by Personnel Error.Need for Effective Communications Stressed to Applicable Operations personnel.W/910614 Ltr

ML18009A934
Person / Time
Site:	Harris
Issue date:	06/14/1991
From:	Barker D, Richey R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-910081-(O), LER-91-013-01, LER-91-13-1, NUDOCS 9106190146
Download: ML18009A934 (7)

Text

ACCELERATED DILUTION DEMONS'TION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RXDS)ACCESSION NBR: 9106190146 DOC.DATE: 91/06/14 NOTARIZED:

NO FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION BARKER,D.W.

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

Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATXON DOCKET g 05000400

SUBJECT:

LER 91-013-00:on 910515,reactor trip occurred during performance of calibrs.Caused by personnel error.Need for effective communications stressed to applicable operations personnel.W/910614 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR (ENCL (SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400~RECIPIENT ID CODE/NAME PD2-1 LA MOZAFARI,B.

INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL: EGGG BRYCE,J.H NRC PDR NSIC POORE,W.COPXES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRS AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D PLBBD1 REG FIL 02 FILE 01 L ST LOBBY WARD NSIC MURPHYiG A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WARM CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPXES REQUIRED: LTTR 33 ENCL 33 V+4 I FORM 22 Carolina Power&Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 JUN 1 4 1991 Letter Number: HO-910081 (0)U.S.Nuclear Regulatory Commission A'ZTN: 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 91-013-00 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 Or!ginal Sig'ned By R.8.R/CHEY R.B.Richey Vice President Harris Nuclear Project RBR:dmw Enclosure cc: Mr.S.D.Ebneter (NRC-RII)Ms.B.L.Mozafari (NRC-RII)Mr.J.E.Tedrow (NRC-SHNPP)MEM/LER91-013/1/OS1 9106190146 910614 PDR ADOCK 05000400 DAO

NAC FORM 366 (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILERI APPROVED OMB NO.31504104 EXPIRES: 4I30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTt 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P6301.U.S.NUCLEAR REGULATORY COMMISSION.

WASHINGTON.

OC 20555.AND TO THE PAPERWORK AEDUCTION PROJECT (3(500104).

OFFICE OF MANAGEMENT AND BUDGET.WASHINGTON, OC 20503.FACILITY NAME (I)DOCKET NUMBER (2)PA E 3 TITLE Iel s Nuclear Power Plant o 5 o o o 400~or0 3 EVENT DATE (5I LFR NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (6)MONTH OAY YEAR YEAR SEQUENTIAL

~NUMBER 4LVISK MONTH NUMSEII OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 5 1 5 919 1 013 0 006 14 91 0 5 0 0 0 OPERATING MODE (9I POWER LEVEL (10)20A02(b)20A06(e)0 I(l))0'(9)20.406(e)(1)(SII 20A05 I~)(I)(lv)20A06(el(1)(v)20.405(e)5036(cl (I)50.&(e)(2) 50.73(e)(2)(I)5073(eol)(N) 60.73(e)(2)(ill)LICENSEE CONTACT FOA THIS LFR (12)50.73(e)(1)

Av)60,73(e)(2)(v)EC.71(e)(1HvL'I 50.73(e)(1)(vill)(Al 50.73(~I(2)(vill)

(6)50.73(~)(21(el THIS REPORT IS SUBMITTED PURSUANT TO THE RLGVIREMENTS OF 10 CFR (Ir ICnect one or morr of trrr followinpl (11)73.7)(Ir)73.71(c)OTILE R fen-Jolty ln AtA.er telow rnrf ln Teer, ffRC Form 388AI NAME David W.Barker-Sr.Regulatory Compliance Specialist AREA CODE TELEPHONE NUMBER 2-2 0 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TVAEA EPORTABLE:

TO NPRDS yj CAUSE SYSTEM COMPONENT MANUFAC-TURER EPORTABL TO NPADS o'URN 4%R A SUPPLEMENTAL REPOAT EXPECTED (14)YES Ill yrr, complete EXPECTED$(f84tlSSIOff OATEl NO ABSTRACT fLlmlr to le00 rpecrt, f.r., rpproefmetrfy fiftern rlnplr.rpecr typewritten llnnl (ISI ABSTRACT: EXPECTED SUBMISSION DATE (15)4'MONTH DAY YEAR I In preparation for cooldown to repair a steam leak, Control Rod Shutdown Bank"C" was withdrawn fully and all other control rods were wiehdrawn six steps.Nuclear Instrument N-43 was-in the tripped c'o".edition fo'nstallation of monitoring instrumentation during post-refueling start-up testing.When surveillance test inseruments were disconnected following Reactor Coolant System resistance temperature detector testing, a spurious Overeemperature re)Temperature signal was generated causing a reactor trip.The potential for a reactor trip signal during restoration from the surveillance test had been previously discussed by Operations and Maintenance personnel, but the information was not communicated eo the shift operators.

The procedure governing ehe RTD surveillance test provided precautions during data acquisition, but failed eo identify the risk of generating a trip signal during restoration.

This event will be discussed with.maintenance and operations personnel and the surveillance tese procedure will be revised to include appropriate precautions during restoraeion.

NAC Form 365(669)

'\I eVRC FOAM 366 A (64)9)U.S.NUCI.EAA REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPAOVEO OMB NO.31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.

OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)SOD)04).

OFFIC'E OF MANAGEMENT AND BUDGET;WASHINGTON, DC 20503.FACILITY NAME (1)Shearon Harris Nuclear Power Plant DOCKET NUMBER (2)VEAA LER NUMBER (6)SEOVENl'IAL NUMBER;.1~1I REVISION NUMBER PAGE (3)TEXT///mdIP 4P444/4 swtv/Nd, Il)4 4ddidone/P/RC FPmI 3664'll (IT)EVENT DESCRIPTION:

0 5 0 0 0 4 0 0 9 0 1 3 0 0 02 O" 0 3 I On 5/15/91 the plant was in Mode 3 following a refueling outage, Nuclear Instrument N-43 had been placed in its tripped condition for installation of monitoring instrumentation (reactivity computer)during post-refueling startup testing.In order to repair a steam leak on Pressurizer Power Operated Relief Valve block valve 1RC-117, preparations were heing made for plant cooldown pe" procedure GP-007;The Reactor Trip Breakers were closed, Control Rod.Shutdown Bank"C" was fully withdrawn and all other rods were withdrawn 6 steps.Surveillance testing was also in progress for Reactor Coolant System (RCS)resistance temperature detector (RTD)cross-calibration in accordance with procedure MST-I0650.

MST-I0650 requires acquisition of data at several different RCS temperature plateaus with the precaution that a reactor trip signal may be generated when RTD leads are lifted for data acquisition.

MST-I0650 requires opening the reactor trip breakers at each data acquisition plateau, but not during restoration.

Although the restoration section of MST-I0650 does not require that the reactor trip breakers be opened, it does require that restoration be performed one RTD at a time.At the 5/15/91 morning outage meeting, maintenance personnel requested that the reactor trip breakers be.left open during the restoration section of MST-I0650.

This was to facilitate the timely performance by allowing restoration actions on more than one RTD at a time.The Shift Supervisor agreed to leave the Reactor Trip Breakers open, but failed to communicate this to the on-shift operators.

Data acquisition had been successfully completed and the test instrumentation was being removed (on more than one RTD)when a spurious Overtemperature temperature trip signal was generated resulting in a reactor trip.There has been one similar event involving a reactor trip during performance of instrument calibrations as reported in LER 89-005-00.

CAUSE: The cause of'his event was personnel error.This Reactor Protection System actuation was caused.by the simultaneous performance of plant cooldown, which required the Reactor Trip Breakers to be closed, and restoration from MST-I0650 concurrent with one channel of N-43 in the trip condition.

Maintenance personnel performing the surveillance testing failed to follow the procedural requirement for restoring one RTD at a time.The potential for a reactor trip signal during restoration was communicated to'the Shift Supervisor, but this information was not discussed with the on-shift operators.

ICRC FOAM 366A (689)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED 6MB NO.31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REGUESTI 500 HRS.FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS AND AEPOATS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATOR Y COMMISSION, WASHINGTON.

DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600104).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME 0)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)Shearon Harris Nuclear Power Plant TEXT/ll more 4/Mce/4 rer/Ir/red.

ore eddro'orN/I/IC Form 3664'4/(17)0 5 0 0 0 4 0 0 YEAR QVc'1 SEQUENTIAL A'6: NUMBER 0 1 3 REVISION NUMBER 00 03 OF 0 3 SAFETY SIGNIFICANCE:

There were no significant safety consequences as a result of this event..A11 safety systems responded as required.This event is reportable as an actuation of the reactor protection and engineered safeguards systems per 10CFR50.73(a)(2)(iv).

CORRECTIVE ACTIONS: MST-I0650 will be revised prior to next use to clarify restoration requirements.

2.The requirement that surveillance testing be performed only in strict accordance with approved written procedures will be re-emphasized to applicable maintenance personnel.

3.The need for effective communications will be stressed to applicable operations personnel.

4.An evaluation will be performed on possible alternatives to the reactivity computer which do not require N-43 to be placed in the tripped condition during post-refueling start-.up.

EIIS CODE INFORMATION:

N/A