ML18010A718

LER 92-009-00:on 920715,manual Reactor Trip/Afw Actuation Occurred Due to Low SG Level.Caused by Inadvertent Deenergization of MFP Recirculation Valve Power Supply. Supply Breaker replaced.W/920814 Ltr

ML18010A718
Person / Time
Site:	Harris
Issue date:	08/14/1992
From:	Hinnant C, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-920119, LER-92-009-02, LER-92-9-2, NUDOCS 9208170190
Download: ML18010A718 (5)

Text

A;CCELERATED DJ~ UTION DEMONST~RATION SYSTEM REGULA ..Y INFORMATION DISTR I BUT I . SYSTEM (P IDS)

ACCESSXQIQ NBR: 9208170190 DOC. DATE: 92/08/24 NOTAR IZED: NQ DOCKET FACXL: 50-400 Shearan Harris Nuclear Pacer PI ante Unit ic CaroI,ina 05000400 AUTH. NAME AUTHOR AFFILIATION VERR ILLI N.

c Carolina Pacer 8c Light Ca.

HENNANTc C. S. Carolina Pacer;c Light Ca.

REC IP. NAME RECXP EENT AFFXLXATIQN

SUBJECT:

LER 92-009-00: on 920715c manual 'reactor tri p/AFW actuation occurred due to loe SG level. Caused bg inadve. tent deenerg f zation of MFP recirculation valve pacer supply.

Supply breaker replaced. W/920824 ltr.

DISTRIBUTION CODE: XE22T COPIES RECEIVED: LTR ENCL , SIZE:

TITLE: 50. 73/50. 9 Licensee Event Report (LER)c Xncident Rpti etc.

NOTES: Application for permit reneeal f i led. 05000400 RECIPIENT COPIES REC XP XENT COPIES ID CODE/NAME LTTR ENCL lD CODE/NAME LTTR ENCL PD2-1 LA PD2-1 PD 1 1 LEc N 1 INTERNAL: ACNM 2 ACRS 2 2 AEOD/DOA *EQD/DSP/TPAB 1 1 AEOD/ROAB/DSP NRP/DET/EMEB 7E 1 NRR/DLPG/LHFB10 1 NRR/DLPG/LPEB20 1 NRR/DQEA/OE*B 1 NRR/DREP/PRPB21 2 2 NRR/DST/SELB SD 2 NRP /DST/S I CBSH3 1 SPLBSD2 NRR/DST/SRXB SE 2 IL RG ~F EG F I LE 02 01 2

2 RES/DSI R/EI 8 1 EXTERNAL: EGGG BRYCEi d. H L ST LOBBY WARD 2 2 NRC PDR NSXC MURPHY'. A 1 NSIC POQREc W. NUDOCS FULL TXT 1 NOTE TO ALL "RIDS" RECIPIENTS:

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

FULL TEXT CONVERSION REGUXRED TOTAL NUMBER OF CQP I ES REGUIRED: LTTR 31 ENC!,. 32

Carolina Power & Light Company P.O. Box 165 New Hill, N.C. 27562 C. S. HINNANT General Manager - Harris Plant AUG 1 4 1992 Letter Number: HO-920119 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 92-009-00 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 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/LER92-009/1/OS1 9208170190 920814 PDR ADOCK 05000400 8 PDR

NJIG FORM 3ri8 (64)9)

LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION t APPAOVED OMB NO. 3150r0104 EXPIRES) 4)30l92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEOUESTI 50.0 HAS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP4)30), U.S. NUCLEAR REGULATOAY COMMISSION, WASHINGTON, DC 20556, AND TO THE PAPERWORK REDUCTION PROJECT (31600104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) PA E 3 earon Harris Nuclear Power Plant Unit 81 0 5 0 0 0 400 1 OFO 3 Manual Reactor Trip/AFW Actuation due to Low S/G level caused by inadvertantly deener izin MFP recirc valve ower supply.

EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR '.SSXrl SEQVSNTIAL REVISION MONTH DAY YEAR FACILITYNAMED DOCKET NUMBER(SI PAr NUMBER 'r.PS NUMBER 0 0 0 0 0 0 7 1 5 92 92 0 0 9 0 0 0 8 149 2 0 S 0 0 0 THIS REPORT IS SUBMITTED PURSUANT 7 0 THE RLGUIREMENTB oF 10 cFR ((: (cbecA ont or mort ol tnt loiiowinpl l11)

OPERATING MODE (DI 20.402(bl 20.40S(cl 60,73( ~ l(2)(iv) 73.71(b)

POWER 20.405(el(1) 6) 50.38(c) Ill 50.73(e) (2)(v) 73.71(cl LEYEL 3 0 20.405(sill)(DI S0.38(cl(2) 50.73(e I (2 I (v9 I OTHER ISptcily in Abstrtct below end in Text, Ni)C Form g y. 20.405( ~ ) l1) (IIII 50.73( ~ I (2) Ill 60.73( ~ l(2) (viiil(AI 36640 iS 20AOS(el(1) (Ivl 50.73(e) l2) litl 50.73 I ~ ) (2)(viiil(B) 20,406(el(1)(vl 60 73(e) (2)(iii) 50,73( ~ I (2)(x I LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE Michael Verrilli Specialist Regulatory Compliance 9 193 62- 23 3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) r ow v CAUSE SYSTEM COMPONENT MANUFAG TURER EPORTABLE TO NPADS

. 9 CAUSE SYSTEM COMPONENT MANUFAC.

TURER EPOATABLE ~@

TO NPAOS

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.:. r . r... ~ .:: .:.. X SN MZN~., . 0 ~

B EB B KR B 4 5 5 NEW!(-N (F&M SUPPLEMENTAL REPORT EXPECTED (14) MONTH I~JR!

OAY YEAR EXPECTED SUBMISSION DATE HS)

YES illyes, complete EXPECTED S(ipsttSSIOH DATE) NO ABSTRACT (Limit to 1400 sprees, le.. epproximtrtly liltttn slnptetptce typewritten lintel ll6)

ABSTRACT:

On July 15, 1992 a supply breaker failure occurred while starting Exhaust Fan E-18 which resulted in the fan running with both the inlet and outlet dampers closed. This condition created a potential for fire in the fans charcoal filter unit. Remote and local efforts were made to trip open the breaker and secure the fan, but were unsuccessful. The control room staff determined that the supply bus for the E-18 fan (Bus ¹1D-2) would have to be deenergized to allow the fan breaker to be racked out and the fan secured. When 1D-2 was deenergized it caused the RBR Main Feed Pump and RBR Condensate Booster Pump Recirculation Valves to fail to the full-open position. This caused the running Main Feed Pump to trip on low suction pressure and resulted in rapidly decreasing Steam Generator water levels. A manual reactor trip was initiated by the control operator as required. All safety syst:ems functioned as required including an automatic Auxiliary Feedwater System actuat:ion. The cause of this event was a failure of the E-18 supply breaker. This breaker was replaced and satisfactorily tested on July 15, 1992.

NRC Form 388 (649)

NRC FORM SSSA U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 31600104 (6419)

E XP I R E3 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REQUEST: 604) HRS. FORWARD COMMENTS REQARDINQ BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (PCi30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PRO/ECT (31504)(04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME (II DOCKET NUMBER 12) LER NUMBER (5) PAGE (3)

Shearon Harris Nuclear Power Plant YEAR SEQUENTIAL NUMSER REVISION NUMBER Unit /El 0 6 0 0 0 Ir 00 0 9 000 2 OF 0 TEXT /llmore <<NIo /I neukrd, e>> edd/done/HRC ForrII 3654'4/ (17)

EVENT DESCRIPTION:

On July 15, 1992 at approximately 0230, an attempt was made from the main control room to start Reactor Auxiliary Building Exhaust Fan E-18. This start attempt resulted in no "run" indication or apparent control of the fan. Auxiliary operators were sent to the fan and fan supply breaker to investigate. They observed that the fan was running and that the inlet and outlet dampers were both closed. Attempts to secure the fan both locally and from the control room were unsuccessful. This situation created an immediate concern over the possibility of a fire in the fans charcoal filter unit. The control room staff decided to deenergize the supply bus (Bus ¹1D-2) for the E-18 fan to prevent this possibility. After completing a review to identify any loads that would be affected by deenergizing bus 1D-2, the bus supply feeder was opened and the supply breaker for E-18 was racked out. Shortly after 1D-2 was deenergized, control room operators observed "B" Main Feed Pump suction pressure decreasing.

Attempts were immediately made to increase condensate booster pump speed, but they did not prevent the feed pump from tripping on low suction pressure. A manual reactor trip and turbine trip was then initiated as required, due to rapidly decreasing steam generator levels. All safety systems operated as required including an automatic Auxiliary Feedwater actuation due to the loss of the running main feed pump. The plant was stabilized with the appropriate emergency operating procedures in Mode-3.

This event is being reported in accordance with 10CFR50.73(a)(2)(iv) as an Engineered Safety Feature and Reactor Protection System actuation. There have been no similar events reported.

CAUSE'he cause of this event was a failure of the E-18 supply breaker. This failure prevented the breaker from being tripped both manually and electrically and also blocked the open signal to the inlet and outlet dampers from the control switch.

A contributing factor was that the "B" Main Feed Pump and "B" Condensate Booster Pump Recirc Valves were not identified during the load review conducted prior to deenergizing 1D-2. During normal operating conditions, more time would have been available to fully research affected loads and take the needed precautions, but due to the potential fire threat, review time was limited and this component was not identified.

SAFETY SIGNIFICANCE:

There were no safety consequences as a result of this event. All safety systems functioned as required to place the plant in a safe condition and the possibility of a fire in the E-18 charcoal filter was averted by deenergizing bus 1D-2.

NRC Form 36SA (669)

NRC FORM 366A UA. NUCLEAR REGULATORY COlh(MISSION APPROVED 0MB NO. 31500104 (649)

EXPIRES: 6/30)92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F630). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504(OS). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER 12) LER NUMBER (6) PAGE (3)

SEOUENTIAL N$ 2 REVISION Shearon Harris Nuclear Power Plant YEAR NUMBER ~~ NUMBER Unit //1 o 5 o o o 400 92 0 0 9 0 0 03DF 0 3 TEXT (Ifmom EPEEP )s h)Ihh)PC Ihse PCChtionel NRC Fomh 36643) (17)

CORRECTIVE ACTIONS:

1. The supply breaker for the E-18 Fan was replaced on July 15, 1992.

2. Investigation into the breaker failure revealed mechanical binding in the breakers arcing contact. The apparent cause for this binding was pitting on the arcing contact spring retaining pin. As a result of this, Preventive Maintenance Procedure PM-E0012 was revised to include periodic inspections of this pin and buffing or pin replacement if needed.

3. Training will be performed for operations personnel to ensure their awareness of this event.

EIIS INFORMATION:

Medium Voltage Power System (Class-1E) EB NRC Form 366A (669)