ML18004B831

LER 87-028-00:on 870502,manual Turbine Trip Initiated During Performance of Power Ascension Test Procedure 9108-S-14. Caused by Tandem Trip of Both Heater Drain Pumps.Evaluation of Feedwater Response to Transients continues.W/870601 Ltr

ML18004B831
Person / Time
Site:	Harris
Issue date:	06/01/1987
From:	HOWE A, WATSON R A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870443-(O), LER-87-028, LER-87-28, NUDOCS 8706050347
Download: ML18004B831 (7)

Text

ACCESSI FAC IL<,'UTH.f REGULATORY INFORNATIOI'I DISTR IBUTI0>BYSTEN (R IDS)Oc!0503+DOC.DATE: 87/06/01 NO AR~cED: NO hl NBR: 87 3-400 Shearon Harris Nuclear Pouer Plant>Unit 1>Carolina ANE AUTHOR AFFILIATION DOCKET 0 05000400 HOWE>A.'ATSON>R.A.RECIP.NANE Carolina Power 5 Liah+Co.Carolina Power Zc Light Co.RECIPIENT AFFIL IATIV,'4 SUB JECT: LER 87-028-00:

on 870502>m-nual+urbine trip initiated du<ing performance of Power Ascension Test Procedure 9108-8-14.

Caused bg tandem trip of bo+h heater drain pumps.Evaluate on of feedulater response to tt ansients continues.

W/870601 l+r.1 DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SI ZE:TITLE: 50.73 Licensee Event Report (LEK)>Incident Rpt>etc.NOTES:Application for permit reneual filed.05000400 RECIPIENT ID CODE/NANE PD2-1 LA BUCKLEY, B INTERNAL: ACRS NICHELSON AEOD/DOA AEOD/DSP/TPAB NRR/DEBT/ADE NRR/DEBT/CEB NRR/DEBT/ICSB NRR/DEBT/NTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PNAB/PTBB RES DEPY QI EXTERNAL: KG8cG GROH>N LPDR NSIC HARRIS>S COP IES LTTR ENCL 1 1 1 1 1 1 1 1 1 1'0 1 1 1 1 1 1 1 1, 1 2 2 1 1 1 1 5 5 1 1 1 1 REC IP IENI ID CODE/MANE PD2-1 PD ACRS NOELLER AFOD/DBP/RQAB DEDRO rNR/DEBT/ADS NRR/DEBT/ELB I'~~RR/DEBT/I'IEO

'!RR/DEBT/PBB NRR/DEBT/SGB NRR/DLPG/GAB I'!RR/DREP/RAB

~t"'RNA LRB FRG FIL 02"42 F I LE Oi H BT LOBB Y WARD N~C PDR NBIC NAYS>G COP IEB LTTR E.4CL 1 2 2 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUNBER OF COPIES REQUIRED: LT I R 42 ENCL 40 NRC Form 355 (S43)LICENSEE EVENT REPORT ILER)Ug.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.319)0)0l EXPIRES: 5/31/SS FACILITY NAME (Il DOCKET NUMBER (2)PAGE 3 SHEARON HARRIS-UNIT 1 TITLE Ial AUXILIARY FEEDWATER ACTUATION 0 5 0 0 0 4 0 0 1 OF 0 3 EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (5)MONTH OAY YEAR YEAR iP~~E SEGUENTIAL NUMBER RE~O MONTH NUMBER OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 o 05 02 87 87 028 0 0 8 7 0 5 0 0 0 OPERATING MODE (0)POWER LEVEL 0;:ONv...k W K 20A02(B)20405(sl(1)(i) 20A05(s)(1) liil 20405(s)(I)(IS) 20405(s)(I)(lv)20A05(s)(I)(vl 20A05(c)50.35(c)(1)50.35(cl(2) 50.73(s)(2)(I)50.73(sl(2)

(5)60.73(a)(2)(iii)X 60.73(s)l2)(iv)60.73(s)(2Hvl 50.73(s)I 2)(vE)50.73(s)(2)(viii)(A)60.73(s)(2)(viE)I 5)50.73(s)l2)(el LICENSEE CONTACT FOR THIS LER (12)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR ()r (Check one or more of the follovyinPI (11)73.71(B)73.71(c)OTHER ISpecify In Ahrtrsct'Oerow end In Terrt, HI(C Form 3b'$4)NAME ANDREW HOWE-REGULATORY COMPLIANCE TELEPHONE NUMBER AREA CODE 919 362-27 19 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC-TURER REPORTABL'E TO NPRDS M NNN@%N@8K P.re:: CAUSE SYSTEM 4;-%%58 Tg+A[(I COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS~)5m&@MM SUPPLEMENTAL REPORT EXPECTED (IE)YES Ilf yer, complere EXPECTED SUBhtISSIOII DATE)NO ABSTRACT (Limit to IC00rpecet, Ie., spprorrfmerely fifteen cincleepece rypewrirten fined (15)ABSTRACT EXPECTED SUBMISSION DATE I)S)MONTH DAY YEAR On May 2, 1987, at 0206, a manual turbine trip was initiated during the performance of Power Ascension Test procedure 9108-S-14,"Turbine Trip From 100X".Following the trip, as feedwater demand was decreasing, both main feedwater pumps tripped.The cause was a tandem trip of both heater drain pumps (on low net positive suction head)followed by trip of both condensate booster pumps (on high discharge pressure).

Both motor-driven auxiliary feedwater pumps automatically started upon trip of both main feedwater pumps to maintain steam generator water levels.A normal plant shutdown to Mode 3 was then accomplished.

The plant remained shut down for a planned maintenance outage, and was subsequently returned to service on May 9.870b050347 870b0lPDR ADOCK 05000400 8 NRC Form 366 (903) j~ji'A'RC form 366A (94)3)~FACILITY NAME (1 I SHEARON HARRIS UNIT 1 U.S.NUCLEAR REOUL ATORY COMMISSION APPROVED OMS NO.3150-0104 EXPIRES: 8/31/SS DOCKET NUMBER (2)LER NUM8ER (6)YEAR MR 6EOVENT/AL rN REV+104 YEAR NÃ<4VM6ER 4./NVMBER PACE (3)o s o o o4 00 8 7 0 2 8-0 0 OF 0 3 LICEN E ENT REPORT (LER)TEXT CONTI U ION TEXT////nore 4/roon Jr/or)o6ed,/no////ono/NRC Form 36643)(IT)DESCRIPTION On May 2, 1987, Power Ascension Test procedure 9108-S-14,"Turbine Trip From 100K", was performed.

This test initiates a manual trip of the main turbine while operating at near full power.A reactor trip is, therefore, expected to occur', thus, the reactor trip is part of a pre-planned sequence during testing is not reportable (as per 10CFR50.72(b)(2)(ii) and 10CFR50.73(a)(2)(iv)).

The plant was at 97.5X reactor power and 840 Mwe net generator output, with normal temperatures and pressures.

The main feedwater system was in operation supplying 4.0 x 10E+06 ibm/hr to each steam generator.

The main feedwater pump discharge valves were throttled to maintain an appropriate differential pressure across the main feedwater regulating valves.The turbine trip was initiated at 0206.Immediately following the trip, heater drain pump 1B tripped, and approximately five seconds later, heater drain pump 1A tripped, along with both condensate booster pumps and both main feedwater pumps.Both motor-driven auxiliary feedwater pumps automatically started as required on a loss of both main feedwater pumps.The plant was stabilized in Mode 3 at normal temperatures and pressure following the turbine and reactor trips.The auxiliary feedwater system was being monitored as per the test procedure, and the operator manually throttled the flow to control steam generator levels.No other safeguards features actuated during or subsequent to the event.CAUSE The heater drain pump trips were caused by low net positive suction head (NPSH)which resulted directly from the turbine trip.The heater drain pumps have the number four feedwater heaters as the suction source.Extraction steam supply to the heaters is isolated upon a turbine trip, which reduced the pressure in the heaters such that the low NPSH trip setpoint of the heater drain pumps was reached.The condensate booster pump trips were caused by high discharge pressure.Upon the turbine and reactor trips, the feedwater flow demand is reduced and the main feedwater regulating valves throttle closed.The condensate booster.pumps are required to reduce speed and maintain the pressure at the main feedwater pump suction at 400 psig.The speed controller does not respond quickly enough for this transient, so the high discharge trip setpoint was reached.The main feedwater pumps trip automatically when the condensate booster pumps trip due to an interlock.

MEM/HO-8704430/PAGE 4/Osl NRC FORM 366A (94)3)o U S QPO 1986 0 624 638/455 NRC Form 366A (983)~LICEN NT REPORT (LER)TEXT CONT ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150&I04 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)SHEARON HARRIS UNIT 1 TEXT/g/RIVE EPBod (I Eqrrdor/, Iroor//rrro/HRC

%%d/rrr 35549)(lT)ANALYSIS YEAR o so oo400 7 EEOVENT/AL NVMBE/l 0 2 8 REYIBION NUMBER 0 0 0 3 OF 03 This event is reportable under 10CFR50.73(a)(2)(iv) as an unplanned actuation of an engineered safeguards feature.Prev'ious,events reported (see Licensee Event Re'ports'87-008-00, 87-013-00, 87-017-00, 87-018-00, 87-019-00) have discussed the response of the main feedwater system to transient conditions and the various corrective measures taken to improve system operations.

CORRECTIVE ACTIONS The condensate and feedwater system response to transients continues to be evaluated by CP&L.Long term actions to reduce the probability of pump trips include elimination of the condensate booster pump variable speed function which would permit elimination of the high discharge pressure trip.MEM/HO-8704430/PAGE 5/Osl NRC FORM SOdA (983)*U.S.GPO:1988 0.624 538/455 OO~0

~0 C~L Carolina Power&Light Company HARRIS NUCLEAR'PROJECT P.O.Box 165 New Hill, NC 27562 JUN 0<<<37 File Number'SHF/10-13510C Letter Number: HO-870443 (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 87-028"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, 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-8704430/PAGE 1 IOS1 OO