ML18005A825

LER 89-005-00:on 890222,reactor Trip on Low Steam Generator Level W/Steam/Feedwater Flow Mismatch Occurred During Calibr Test Procedure.Caused by Performance of Section of Procedure Intended to Be Conducted.Procedure revised.W/890321 Ltr

ML18005A825
Person / Time
Site:	Harris
Issue date:	03/22/1989
From:	Howe A, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-890037-(O), LER-89-005-01, LER-89-5-1, NUDOCS 8903280293
Download: ML18005A825 (6)

Text

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ACCESSION NBR:8903280293 DOC.DATE: 89/03/22 NOTARIZED: NO DOCKET FACXL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HOWE,A.J. Carolina Power & Light Co.

WATSON,R.A. Carolina Power & Light Co.

RECIP.NAME RECXPIENT AFFILIATION

SUBJECT:

LER 89-005-00:on 890222,reactor level w/steam/feed mismatch.

trip on low steam generator W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Application for permit renewal filed. 05000400/

RECXPIENT COPIES RECIPIENT COPIES ID'CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA I1 1 PD2-1 PD 1 1 BECKER,D 1 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 '2 ACRS WYLIE '1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO '.1 1 IRM/DCTS/GAB 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ES B 8D 1 1 NRR/DEST/ICSB 7 1' NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PS B 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR D XB 9A 1 1 NUDOCS-ABSTRACT 1 1 02 1 1 RES/DS IR/EIB 1 1 SR/PRAB 1 1 R RGN2 'XLE 01 1 1 EXTERNAL EG&G WILLIAMSI S 4 4 FORD BLDG HOY I A H ST LOBBY WARD 1 1 LPDR NRC PDR 1 1 NSIC MAYS,G NSIC MURPHY,G.A 1 1 h

D NCTE XO ALL "RIDS" RECXPXENIS:

PLEASE HELP US XO REDUCE WASTE! CXNZACT 'IHE DOCUMENTl'ONTROL DESK, ROOM P1-37 (EXT. 20079) KO EIZKQCQZ YOUR NAME FMH DISTfKBVZIOM LZSTS FOR DOCUMEMIS YOU DON'T NEED.'OTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 p,lo

NRC Form 355 U.S. NUCLEAR REOULATOAY COMMISSION (94)3) APPAOVED OMB NO, 31500(04 EXPIRES: SI31ldd LICENSEE EVENT REPORT ILER)

PACE 3 FACILITYNAME (ll DOCKET NUMBER (2)

SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE o so oo400>or.3 REACTOR TRI Sl EL E D ISMATCH DUE TO PERFORMANCE OF CALIBRATION TEST PROCEDURE EVENT DATE (5) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (dl MONTH YEAR M+X" SEQUENTIAL REVtCION MONTH OAY YEAR I'ACILITYNAMES DOCKET NUMBEA(SI OAY YEAR @j NUMSErl 0 5 0 0 0 0222 89 8 9 0 0 5 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PUASUANT TO THK REQUIREMENTS OF 10 CFR (); ICtrcctt one or morc of thc followlnpl (ll)

OPERATINQ MODE (1) 20.402(tr) 20.405(c) 50.73(c) (2) (N) 73.71(bl POWER 20.405 (c)(l ) I I) 50.36 (cl (1 I 50.73(c)(2) (rl 73.71(cl LEYEL 1 0 0 20.405 (4 ) (I ID)I 50.35(cl(2) 50.73(c)(2l(yE) OTHER ISpcclfy In Aprtrcct trcrow cnrf ln Text, HRC Form 20.405(c I (I l(BII 50.734) (2) (I) 50.73(x )(2)(rl)IHAI 366AI I)Ipj~"jjd>gj(rid(I 20A05(c) (1)(lr) 50.73(c) (2) (Bl 50.73(c) (2) (rl)I)(5) 20.405(c)(1 l(r) 50.73(c) (2)(IIII 50.73( ~ )(2)(x)

LICENSEE CONTACT FOR THIS LEA (12)

NAME TELEPHONE NVMSEA AREA CODE J. HOWE SENIOR SPECIALIST ANDREW 919 36 -27 19 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANVFAC. EPORTABLE c Ilyr MANUFAG EPORTABLE TVAEA TO NPADS SYSTEM COMPONENT TVAER TO NPRDS Ni'rN(mm mE42('g'g()r)

SUPPLEMENTAL REPORT EXPECTED (14I MONTH OAY YEAR FXPECTEO SV 5 M I SS ION DATE I'IS)

YES lllyct, comprctc EXPECTED SVSMISSIOH DA TEI X NO ABSTRACT It,lmlt to 1400 NNccd I 4, conrcxlmctrfy fllrcrn rinclo rPcCc tyPrwriucn lr'nerf (ld)

On February'2, 1989, at 1314, with the plant at 100K power and 878 net MWe, a reactor trip on low steam generator level coincident with steam/feedwater flow mismatch occurred during the performance of a calibration test procedure for steam generator level channel L-474. The section of the procedure being performed caused an isolation of feedwater to A steam generator, causing the steam/feed flow mismatch. A low level signal was already present when the channel was removed from service -for the test, so the trip signal occurred almost immediately after the isolation valves closed. The plant was stabilized in hot standby at,557'F after the trip, with all three auxiliary feedwater pumps automatically starting due to low steam generator levels.

The cause of the trip was performance of a section of the procedure intended to be conducted during shutdown. Cautions in the procedure, intended to alert personnel of the impact on plant operation, were reviewed by the technicians, and by the operators on shift including the shift foreman, but the cautions were not sufficiently explicit to be understood by these individuals'he plant was returned to service at 2255 of the same day. The procedures which test the feedwater control logic will be revised to ensure explicit instructions are provided as to the effect on performance of the test on the feedwater valve lineup. A review of other calibration procedures which could impact power operations will be conducted to ensure adequate precautions are provided.

NRC Form 3dd 890 '280293 8 J(- 2 (9.53) PDR AGGCK 0500(M(M 8 PDC

Pg NRC Poem 388A U.S. NUCLEAR REOULATORY COMMISSION (943)

LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO. 3)50MI04 EXPIRES: 8/31/88 FACILITY NAME (Il DOCKET NUMBER (2) I.ER NUMSER (5) PAOF. (3)

SEQUENTIAL 0 PEVOKIN

>4 NUMSSR SHEARON HARRIS NUCLEAR POWER PLANT- NUMSSN UNIT ONE o s o o o 400 89 0 5 00 0 20F 0 3 TEXt ////INvo opooo N need. um A//Oo'oo/ ///IC Ann 3(SAY/ ()T)

EVENT DESCRI PTION The plant was operating at full power producing 885 net MWe on February 22, 1989. Maintenance Surveillance Test procedure MST-I-0023, Steam Generator 1A Narrow Range Level Loop (L-474) - Protection Set I Calibration, was in progress.. This procedure is performed once per 18 months to calibrate level transmitter 474 (L-474) (EIIS:JB), and includes calibration of the nonsafety control interlocks which actuate an isolation of feedwater to steam generator A.

At approximately 1314, isolation and regulating valves for A steam generator closed, causing a steam/feedwater flow mismatch. With level instrument L-474 removed from service for the test, this completed the logic for a reactor trip on low~ steam generator level with steam/feed flow mismatch for A steam generator.

The plant response to the trip was as expected. All three auxiliary feedwater pumps ~(ALIIS:BA) eventually started on low steam generator water level. The main feedwater pumps (EIIS:SJ).tripped shortly after the reactor trip, due to low fl'ow occurring when the feedwater regul'ating valves closed on interlock at 564'F tReactor Coolant System average temperature. The pump's recirculation valve did I not open quickly enough to keep the pump flow rate above the trip setpoint.

CAUSE The feedwater isolation and regulating valves closed when a low level 'signal was initiated by the performance of Section 7.16 of the test procedure, wh)ch is a section to test the nonsafety feedwater valve control interlocks. A narrow range steam generator level of greater than 5X is required to open main feedwater isolation and regulating valves to permit main feedwater flow to the steam generators. This interlock is required to minimize the potential hammer events in the steam generator during start up of the main fox'ater feedwater system. This section of the test procedure is not intended to be performed while the plant is at power.

Prior to performance of Section 7.16, per the procedure, the technicians were required to obtain permission from the control operator to conduct that portion of the test procedure. Thh procedure provided cautions intended to alert personnel of the effect on feedwater valve position while performing that section. The operator discussed these cautions with the technicians, with the senior control operator and with the shift foreman. It was believed that the test would only actuate one channel of 2/3 logic needed to cause feedwater to isolate, and so permission was granted to conduct Section 7.16.

N/IC SO/IM SOOA P U.S.GPO'.1988 0 824 538/455 1943)

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NRC Form 855A V.S. NUCLEAR AEOVLATOAYCOMMISSION I0431 LICENSEE EVENT REPORT tLER) TEXT CONTINUATION APPAOVED OM8 NO, 3150MIOE EXPIAEE: 8/31/88 FACILITYNAME Ill DOCKET NVMREA Ill LER NVMEER (5) PAOE IS)

PLANT- YEAR',MI SEQUENTIAL @~</ REVISION

'N> NUMSER'K.

SHEARON HARRIS NUCLEAR POWER NUMSEA UNIT 'ONE 0 5 0 0 0 P'O OF O 0 0 TEXT /I/more sprNe ir eee/irer/. Poe er/orR/orM//YRC Forrrr NE'e/1171 CAUTION (continued)

The cautions in the test procedure were not sufficiently explicit so that personnel would understand that a feedwater isolation would occur. Other procedures which test this function contain identical cautions, but some procedures recently revised included more detailed descriptions, identifying specifically which valves would isolate.

The operators secured from the test and the plant was returned to service at 2255 that same day.

SAFETY SIGNIFICANCE There were no safety consequences as a result of this event. The reactor trip was normal and 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). There have been no previous similar events involving a reactor trip during performance of instrument calibrations.

CORRECTIVE ACTIONS

1. The level and pressure channel calibration procedures which test the feedwater isolation control logic will be revised to delete the feedwater bypass logic test. Separate procedures designated for use only during shutdown will be prepared to test the feedwater bypass logic.

2. A review is being conducted of other 18 month test calibration procedures to identi'fy those which cannot be performed in their entirety without having a .similar impact on the plant.

NRC FOIIM ESSA *V.S.OPO: 1 088.EP504 588/455 10451 P

HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 MAR 2 1 $ 989 File Number.'SHF/10-13510C Letter Number'HO-890037 (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

'ICENSE NO. NPF-63 LICENSEE EVENT REPORT 89-005-00 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~

R. A. Watson Vice President Harris Nuclear Project RAW:tbb Enclosure'c'.

Mr. R. A. Becker (NRR)

Mr. W. H. Bradford (NRC SHNPP)

Mr. S. D. Ebneter (NRC RII)

MEM/LER-89-005/1/Osl