ML18010A711

LER 92-008-00:on 920713,reactor Tripped Due to lo-lo SG Level.Caused by Operator error.Post-event Debriefing Conducted W/Involved Operations Personnel Re Need for Attention to detail.W/920811 Ltr

ML18010A711
Person / Time
Site:	Harris
Issue date:	08/11/1992
From:	Hinnant C, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-920115, LER-92-008-02, LER-92-8-2, NUDOCS 9208140020
Download: ML18010A711 (5)

Text

ACCELERATED DISTIGBUTION DEMONS'HWTION SYSTEM REGULAT ZNFORMATZON DZSTRZBUTZOEiiSTEM (RZDS)

ACCESSION NBR:9208140020 DOC.DATE: 92/08/11 NOTARIZED: NO DOCKET ¹ FACIL:50-.400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH .'NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.

HINNANT,-C.S. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 92-008-00:on 920713,reactor trip when SG level dropped to lo-lo setpoint of 38.5%.Caused by operator error. Post-event debriefing was conducted w/operations personnel & need for attention to detail was reemphasized.W/920811 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 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 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB NRR/DST/SELB 8D QPLB8D1 1

1 1

1 1

1 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E 1,

2 1

2 1

1 REG FILE 02 1 1 RES/DSIR/EIB 1 1 GN2 IDLE 01 1 1 EXTERNAL: EG&G BRYCEFJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A ,1 1 NSIC POOREFW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DIFHUBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED .

TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

CARL Carolina Power 8 Light Company P.O. Box 166 'aw Hill, N.C. 27602 C. S. HINNANT Ganarsl Msnsgar - Hsnls Plant AUG 3 1 1992 Letter Number: HO-920115 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 92-008-00 Gentlemen:

In accordance wit:h 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 C. S. Hinnant General Manager Harris Nuclear Project MV:dmw Enclosure cc: Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRC - RII)

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

Mr. G. E. Vaughn MEM/LER92-008/1/Osl 9208140020 9208ll PDR ADOCK 05000400 8 PDR

NRC Fh)RM 368 , US. NUCLEAR REGULATORY COMMISSION (8J)9) APPROVED OMB NO. 31504104 EXPIRES: e/30I92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST) 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENTBRANCH IP430), US. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(500(OCI. OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC 20503.

FAC(LITY NAME Hl DOCXET NUMBER l1) PA ShearonHarris Nuclear Plant Unit II)1 0 5 0 0 0 1 OF TITLE (el Reactor Trip due to Lo-Lo Steam Generator f.evel caused by operator error C

EVENT DATE (5) LER NUMBER (5) REPORT DATE 17) OTHER FACILITIES INVOLVED ( ~ )

MONTH DAY YEAR YEAR ~l

~<PA: SKOUENTIAL NUMBER MONTH DAY YEAR I'AC)LITY NAMES DOCKET NUMBER(S) 0 5 0 0 0 07 13 92 92 008 0 008 11 92 0 5 0 0 0 OPERATING THIB REPDRT Is BUBMITTED PURBUANT To THE RtoUIREMKNTB DF 10 ctR (I: (check onr ot mote oI the Iollowinfl l11)

MODE (Sl 20A02(bl 20A05(c) 50.7$ 4) (2)(Ie) 73.710t)

POWER 20A05(el(1) ll) 50M(c) Ill 50.73(el( 2) I el 73.71(c)

LEUK(.

(10) 0 20A054)(ll(VI 50M(cH2) 50.734) )2llr9) OTHER IEpectiy In Aptorct Oeiow rnd In Trit, IHIC Bonn 20A054)(1)(IB) 50.734) l2 I I I) 50 73(el(2)(eBI) IAI 3BBA) 20A054) () ) (le) 50.734) l2) I 9 I 50.734) (21 (e(9)(B) 20AOSIell1)(el 50.734) (21 (BI) 50.71(e I l2) I el LICENSEE CONTACT FOR THIS LER l12)

NAME TELEPHONE NUMBER AREA CODE Michael Verrilli Specialist Regulatory Compliance 91 3.6 2- 23 03 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REtORT 11$ ) ~ ~

e' el SYSTEM MANUFAC. )9; 'PORTABL'E MANUFAC. EPORTABL CAUSE COMPONENT TO NPRDS c~ CAUSE SYSTKM COMPONENT TURER TURER r(Ti) .. ~.n,...

TO NPRDS

.C ....vk MIM BUttLEMENTALRKPDRT ExtEcTED lie) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)

YES IlfTet, comPietr EXPECTED SUBMISSION DATE) NO ABBTRAcT (Limit to )coo tpecee, I r., epptoeimetrty Rtrren eintirrprcr trpeeetittrn linet) (15)

ABSTRACT:

On July 13, 1992 the plant was in Mode-3 making preparations -for start-up.

Shutdown Bank "C" control rods were fully withdrawn. Steam generator (S/G) water levels were being controlled manually using the Auxiliary Feedwater (AFW) Syst: em and Reactor Coolant System temperature was being controlled by'umping steam via the "B" S/G Power Operated Relief Valve, During secondary plant start-up, problems were encountered with starting the first condensate pump. Control room personnel focused their efforts on resolving the problem with the condensate pump and during this time, level in the "B" S/G dropped to the lo-lo setpoint of 38.5 percent by narrow range indication. At 2123 a reactor trip and automatic. AFV actuation signal was generated due to lo-lo S/G level. Shutdown bank "C" rods inserted and both motor driven AFW pumps started as required. Operations personnel verified the plant to be in a stable Mode-3 condition.

The cause of this event was operator error. Adequate attention to detail was not applied in maintaining S/G levels. Corrective actions included conducting a post-event debriefing with operations personnel involved. The cause of the event was discussed and the need for attention to detail was reemphasized. This event has also been reviewe'd by other applicable operations personnel to help prevent recurrence.

This event is being reported in accordance with 10CFR50.73 (a)(2)(iv) as an unplanned Engineered Safety Feature and Reactor Protection System actuation.

NRC Fotm 388 (889)

NAC FORM 366A Ug. NUCLEAR REOULATORY COMMISSION APPROVED OMS NO. 31504)0i (660)

EXPIRES: C)30)62 IMATED SUROEN PEA RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) NFOAMATION COLLECTION REOUESTI 500 HRS. FORWARD MMENTS REOARDINO BURDEN ESTIMATE-TO THE RECORDS TEXT CONTINUATION ND REPORTS MANAGEMENTBRANCH (P430l, U.S. NUCLEAR OULATORY COMMISSION. WASHINGTON, DC 20555, AND TO IE PAPERWOAK REDUCTION PROJECT (3150410CI. OFFICE 0( MANAOEMENTAND SUDOET, WASHINOTON, DC 20503.

FACILITYNAME 11) DOCKET NUMSER 12) LER NUMSER 16) PACE IS)

"?< SSOUSNTIAL IIEVISION YEAR ScN NUM ER /gal TEXT IlfII>>cP <<>>I>> is IpqIIlpd, I>>P EVENT DESCRIPTION'

~ Hi)C FccIn 35642) 117) 5 0 0 0 9 2 008 0 0 2 QF2 On July 13, 1992 the plant was in Mode-3 making preparat.'.ons for start-up.

Shutdown Bank HC" control rods were fully withdrawn. Steam generator (S/G) water levels were being controlled manually within a desired band of 45 to 75 percent by narrow range indication by using the Auxiliary Feedwater (AFW) System.

Reactor Coolant System temperature was being controlled by dumping steam via.the HB" S/G Power Operated Relief Valve.

At approximately 2110, an unsuccessful attempt was made to start the "A" Condensate Pump per. Start;up Procedure GP-004. The condensate pump failed to start due to the "clear-path" interlock permissives not being satisfied. This was caused by the Condensate Polisher/Demineralizer Bypass Valve (1CS-718) indicating dual position. The control room staff focused their efforts on resolving this condition to allow for successfully starting the "AH Condensate Pump. At 2123 a reactor trip and automatic AFV actuation signal was generated on "B" S/G lo-lo level at 38.5 percent by narrow range indication. Shutdown bank "C" rods inserted and both motor driven AFP pumps started as required. Upon obtaining the desired S/G levels, the AFW pumps were secured an'd the plant was restored to a"stable Mode-3 condition.

Two events involving reactor trips caused by low steam generator level were reported in LER's ¹89-003 and 89-005, but neither of these events were caused by operator error.

CAUSE:

The cause of this event was op'erator error. Adequate attention to detail was not applied in maintaining S/G levels. Operations personnel allowed their attention to be diverted to the problems encountered wi;th starting the condensate pump.

SAFETY SIGNIFICANCE There were no safety consequences as a result of this event. All safety systems functioned as required to place ~,r the plant in a safe condition.

CORRECTIVE ACTIONS:

A post-event debriefing was conducted with involved operations personnel.

2. This event has been reviewed by other applicable operations personnel and the need for attention to detail was reemphasized.

NRC FOIIII 366A )666)

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