ML18004B823

LER 87-026-00:on 870423 & 24,main Feedwater Pump Tripped & Actuated motor-driven Auxiliary Feedwater Pumps.Caused by Trip of Condensate Booster Pump.Main Feedwater Restored & Pumps Secured.Control Logic Under evaluation.W/870526 Ltr

ML18004B823
Person / Time
Site:	Harris
Issue date:	05/26/1987
From:	Hudson O, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870442-(O), LER-87-026, NUDOCS 8706040120
Download: ML18004B823 (7)

Text

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'ACCESSION NBR 8706040120 DOC. DATE.: 87/05/26 NOTARIZED: NO DOCKET FAC I L: 50-400 Shearon Harris Nuclear PoI"er Plant> Unit 1> Carolina

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05000400 AUTH. NAl 1E AUTHOR AFFILIATION HUDSON'. N. Carolina Power Zc Light Co.

WATSON> R. A. Carolina Power h Light Co.

REC IP. NAME RECIPIENT AFFILIATIQ'A

SUBJECT:

LER 87-026-00: on 870423 8c 24> main feed(eater pump tripped actuated motor-driven auxiliary f eedtuater pumps. Caused by trip of condensate booster pump. Main feeduater restored pumps secured. Contol log ic under evaluation. W/870526 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED; LTR 1 ENCL L SIZE:

TITLE: 50. 73 Licensee Event Report <LER) i Incident Rpt. etc.

NOTES: Application for permit rene'!al f iled. 05000400 REC IP I ENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 PD2-1 PD 1 1 BUCKLEY'S B INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 2 AEQD/DOA 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 DEDRQ 1 1 NRR/DEBT/ADE 0 NRR/DEBT/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 NRR/DEST/MEB 1 NRR/DEBT/MTB 1 NRR/DEST/PSB 1 1 NRR/DEBT/RBB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1

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NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 N~f .PMAS/I B 1 1 NRR/PMAB/PTSB R 02 1 1 RES DEPY GI RCN2 FILE 01 1 1 EXTERNAL: EGM GROH~ M 5 5 H ST LOBBY WARD 1 1 LP,DR 1 1 NRC PDR 1 1 NSIC HARRIS J 1 1 NSIC MAYBi G 1 TOTAL NUMBER OF COPIEB REQUIRED: LT I R 42 40 ENCL o

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NRC Form 388 U.S. NUCLEAR REOULATORY COMMISSION (54)3)

APPROVED OMB NO. 31504)OI LICENSEE EVENT REPORT tLER) EXPIRES: 5/31/88 FACILITY NAME (1 1 DOCKET NUMBER (2) PA 5 SHEARON HARRIS, UNIT 1 0 5 0 0 04 00 1'OFO 3 TITLE (41 AFW ACTUATION EVENT DATE (5) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR P+z+

SEOVSNTIAL .~RA MONTH OAY YEAR I'ACILITYNAMES DOCKET NUMBER(S)

N VMBS R 8N NUM85 A 0 5 0 0 0 0 4 2 387 87 0 2 6 0 005 26 87 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REOVIREMENTS OF 10 CFR f. (Check onr Or more Of thr follortfnrl (11)

MODE (0) 20.402(ir) 73.71(b) 20.405(cl 50.73(cl(2)(lc)

POWER 20.405( ~ ) ii )(il 50.38(cl(1) 50.73(c) (2) (c) 73.71(c)

LEYEL 0 0 20.405(el(1) (8) 50.38(cl(2) 50.73(c) (2) (r 8 l OTHER ISprclfy In Atrrtrrct helorrrend In Trxt, IYIIC Form 20.405(e) II)li'll 50.73(c)12 l(i) 50.73(c) (2)(xiii)(A) 366AI 20AOS(e)II)(ixl 50.73(el(2)(ii) 50.73(c)(2)blS)(B) 20.405( ~ 1 (1)(el 50.73(cl(2)(iiil 50.73(c) (2) I x I LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER

0. N. HUDSON AREA CODE SENIOR ENGINEER REGULATORY COMPLIANCE 9 1 936 2-2 363 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC EPORTABLE CAVSE SYSTEM COMPONENT MANUFAC. EPORTABLE @~

TURER TO NPRDS MPe%% TURER TO NPROS X

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SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)

YES Ilfyrr, complete EXPECTED SU64IISSIOII DA TEI NO ABSTRACT ILlmlt to 1400 rprcrr, lerpproxlmrtely flftrrn rlnO/r.corer typewritten liner) l18)

ABSTRACT'n April 23, 1987, while the Shearon Harris Nuclear Power Plant was operating in Mode 3, the Condensate Booster Pump tripped. This tripped the running Main Feedwater Pump. The trip of the Main Feedwater pump actuated the motor driven Auxiliary Feedwater (AFW) Pumps. On April 24, with the plant in Mode 2 at 3X power, the same Condensate Booster Pump tT4pped again, causing a loss of main feedwater, and AFW actuation. In both cases, AFW actuated as designed, Main Feedwater was subsequently restored and AFW was secured.

8706040120 87056 PDR ADOCIEI 05000400 PDR (04)3) a

NRC Form 366A U.S. NUCLEAR AEGULATORY COMMISSION (083)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVED OMB NO. 3150M(04 EXPIRES: 8/31/88 FACIUTY NAME ill DOCKET NUMBER (2) LER NUMBER (6) PACE (3)

SHEARON HARRIS YEAR SEQVENTIAL REVISION NVMSER NUMEER UNIT 1 o s o o o 4 008 7 0 2 6 0 0 0 2 oF0 3 TEXT (//nore 4(rece/4 ceo)eter( rrre IST/ono/HRC Forrn3554'4/ ()2)

DESCRIPTION OF EVENT:

April 23, 1987, the Shearon Harris Nuclear Power Plant was operating in On Mode 3 at normal temperature and pressure. Train 'A'f main feedwater (Main Feedwater, Condensate Booster, and Condensate Pumps) was in operation, At approximatel.y 1528, a lov lube oil pressure signal caused the trip of the Condensate Booster Pump. This, in turn, caused a trip of Main Feedwater Pump

'A'nd the consequent loss of all main feedwater. The trip of the Main Feedwater (MFW) Pump completed the logic for actuation of the motor driven Auxiliary Feedwater (AFW) Pumps. Both motor driven AFW pumps started to provide feed flow to the steam generators. Main feedwater flow was reestablished; auxiliary feedwater was secured at 1624.

On April 24, 1987, the plant was operating in Mode 2 at 3X reacto'r power at normal temperature and pressure. Main Feedvater Pump 'B'nd Condensate Booster Pump 'A'ere in operation. At 0228, a low lube oil pressure signal caused the trip of the Condensate Booster Pump. This caused the trip of the running MFW'ump and the loss of all main feedvater. The loss of all main feedwater resulted again in the actuation of the AFW system. Feedwater was restored through MFW Train 'B'; and AFW was secured.

CAUSE:

The cause of both of the AFW actuations was loss of main feedwater due to Condensate Booster Pump 'A'rip on low lube oil pressure. The cause of the low lube oil pressure trip was investigated ~ This investigation included:

1. The shell side (service water) of the lube oil cooler was disassembled and inspected. A small amount of debris was found.

However, no significant change in service water or lube oil temperatures were noted.

2. The oil filters were removed,.and inspected. No significant debris was found.

3. Lube oil pressure switches vere checked, with good results'trip pressure svitch, auxiliary pump start pressure switch, and low oil pressure alarm pressure switch.

4. The flow control valve was disassembled and inspected. No discrepancies were found.

5. The lube oil flow controller was adjusted to provide more flow.

In summary, no specific cause was identified. However, after this vork was done, the lube oil pressure observed was slightly higher. To date, the pump has run without a similar trip.

NRC FORM 366A *U.S.GPO.10884).824 538/455 (84)3)

NRC Form PNA U.S. NUCLEAR REGULATORY COMMISSION IS%31 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROV EO OMS NO. 3(50&104 EXPIRES: 8/31/88 FACILITY NAME ((l COCKET NUMBER (2) LER NUMBER LOl PAGE (3)

SHEARON HARRIS YEAR SEQUENTIAL NUM SEA ':?'.<r IIEVISIQN NUMOER UNIT 1 o s o o o4 00 8 7 0 2 60 0 0 3 OF 0 3 TEXT Ã/IKYOEOSOP lr IOOUPorf, UPS d/I/ooo////IC /omr 36549/(17(

ANALYSIS:

This event is reportable per 10CFR50.73 (a) (2) (iv) due to automatic actuation of the AFW system.

There are no safety consequences as a result of this event. The AFW system started as required upon loss of main feedwater. With the exception of the Condensate Booster Pump, systems and equipment responded as expected.

CORRECTIVE ACTIONS:

As mentioned above, no specific faults were found. However, an evaluation will be conducted to determine if improvements are possible in the control logic for the Condensate Booster Pump Auxiliary Oil Pump to reduce the possibility of spurious trips.

NRC'FORM SOOA o U.S.GPO:198SO.824.538/455 19831

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HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 MAY 26 1987 File Number: SHF/10-13510C Letter Number: HO-870442 (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 87-026-00 Gentlemen.'n 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,

/Z/ck~

R. A. Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc. 'Dr. J. Nelson Grace (NRC RII)

Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC - SHNPP)

MEM/HO"8704420/PAGE 1/OS1