ML17342B302

LER 88-004-00:on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of actions.W/880415 Ltr

ML17342B302
Person / Time
Site:	Turkey Point
Issue date:	04/15/1988
From:	Conway W, Salamon G FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-88-179, LER-88-004, LER-88-4, NUDOCS 8804260303
Download: ML17342B302 (5)

Text

'C CELERLTED DISSIBUTION DEMONSTRwi'ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8804260303 DOC.DATE: 88/04/15 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION SALAMON,G. Florida Power 6 Light Co.

CONWAY,W.F. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-004-00:on 880318,auxiliary feedwater initiation on low steam generator level.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR J TITLE: 50.73 Licensee Event Report (LER),

NOTES:

ENCL Incident Rpt, etc. j W/8 SIZE:

ltr.

ID RECIPIENT PD2-2 LA CODE/NAME COPIES LTTR ENCL 1 1.

ID RECIPIENT CODE/NAME PD2-2 PD COPIES LTTR ENCL 1 1 j

A EDISON,G 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 D AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DS P/ROAB 2 2 'EOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 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 SIB 9A 1 1 NRR/PMAS/ILRB12 1 1 R FILE 02 1 RES TELFORD,J 1 1 S DE/EIB 1 1 RES/DRPS DIR 1 1 RGN2 FILE . 01 1 1 EXTERNAL EGGG GROH i M 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 A

TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 355 UA. NUCLEAR REOULATORY COMMISSION (9e)3) APPROVED OM 5 NO. 3)504(BC EXPIRES: 5/31/SS LICENSEE EVENT REPORT (LER)

DOCKET NUMBER (2) PA E 3 FACILITY NAME (Il Turke Point Unit 3 0 5 0 0 0 2 5 0 1 OF 0 3 Auxiliary Feedwater Initiation on Low Steam Generator Level'ue to Inade uate Monitorin of Steam Generator Level EVENT DATE (5) LER NUMBER IS) REPORT DATE (7) O'THER FACILITIES INVOLVED IS) teovENTIAL;.~ neY~~ DAY YEAR FACILITYNAMES DOCKET NVMBERISI Nm NUMBER MDNTH MONTH OAY YEAR YEAR P<."3 NUMBER 0 5 0 0 0 3 18 88 8 004 00 It tUBMITTED PURSUANT TO THE THlt REPORT ill(B) REOVIREMENTS OF 10 CFR ()t ICnrck onr o( mo(r o/ thr Iollortlnp/ III) 0 5 0 0 0 OPERATINO MODE (1) 20A02(B) 20A05(c) 50.73(e) (2)(lrl 73.71(5)

POWER 20A05( ~ ) ill(III)

II )(I) BOW(cl(1) 50.73(c)12)(r) 73.71(cl LEVEL (10) 20A05( ~ ) 50.35(c) (2) 50.73(e) l2) (rt) OTHER ISprclty /n Acct(rct IN(or(rnd in Tret, HRC Form 20A05( ~ ) 50.73( ~ l(2)(I) 50,73(el(2) (rlII)(A) 366AI 20.e05(e l(11(lrl 50,73(e l(2) (5 l 50.73(e I (2) (rllI)(5 I 20.405(el(1)(rl 50.73(e)(2)(IBl 50,73(el(2)(e)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) g'w.

CAUSE SYSTEM COMPONENT MANUFAC TURER EPORTABLE TO NPRDS Xx J'

g '. CAUSE SYSTEM COMPONENT MANUFAC.

TURER EPORTABLE TO NPRDS:ggg

$ 8; NPMNÃP, I)ON~<

SUPPLEMENTAL REPORT EXPECTFD (Ie) MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)

YES Il/ yrt, comp(rte EXPECTED St/bet/St/OH DATE/ NO ABSTRACT /Limit tO IC00 tpccrt, I.r., rpp(oe/metr(y f(/tern dp(rroecr typrwttttrn liner/ IISI On March 18, 1988, Unit 3 was in mode 3, with the Reactor Coolant System being cooled using the Steam Generators (SG) . SG levels were being controlled manually using the Bypass Feedwater Control Valves (FCV).

The Reactor Control Operator (RCO) was attempting to maintain level within the approximate 50% to 70X range on the narrow range SG level indicator. At approximately 1050 the 3B SG level reached 68X and the RCO decreased the flow. By about 1120 the SG level had dropped to the Lo SG level setpoint of 35X, and at 1129 the SG level reached the Lo-Lo SG level setpoint,of 15X. Upon reaching the Lo"Lo setpoint on 2 out of 3 channels, the 3 Auxiliary Feedwater Pumps (AFW) received a start signal and delivered water to all 3 SG s. Upon the SG 3B water level returning to the operating range, the AFW pumps were secured'and SG level continued to be controlled manually using the Bypass FCVs. The cause of the AFW actuation was personnel error in that the RCO failed to adequately monitor the SG level. The RCO s .attention was focused on performing an operability test of a NIS channel, and because of this distraction, he failed to take corrective actions to return the SG level to the operating range upon the Lo level alarm annunciating at the 35X level, prior to the automatic AFW actuation. The operator was counseled concerning awareness of his actions and the seriousness of this error.

Pj(,

, 8802603,08."8804 i5 PDR 'ADOCIM 880015 S DCD NRC Form 385 (9 53)

U.S. NUCLEAR REOULATORY COMMISSION NRC Form 3EEA 943)

LICENSEE E ENT REPORT (LER) TEXT CONTINUA ON APPROVEO OMB NO. 3150-010O EXPIRES: 8/31/88

~ FACILITY NAME III OOCKET NUMBER I2) LER NUMBER Idl PACE IS)

SEQVENT/AI IIEVIEION YEAR NVMEE/I NVMEEII Turke Point Unit 3 o s o o o pgp OF TEXT ///moro o/Moo /o rodrrdod, o/o odd/I/orro//VRC Form 3//ErES/ IIT)

On March 18, 1988, Unit 3 was in mode 3, with the Reactor Coolant System (EIIS:AB) being cooled using the Steam Generators (SG) (EIIS:SB) and the atmospheric dump valves. SG levels were being controlled manually using the Bypass Feedwater Control Valves (FCV) (EIIS:SJ). Blowdown to control SG chemistry was in progress at the time . The Reactor Control Operator (RCO) was attempting to maintain level within the approximate 50% to 70% range on the narrow range SG level indicator. At approximately 0950, the SG 3B level was at 67%, and by about 1025, the level had fallen to about 48%. The RCO increased the flow to the SG such that by 1050, the level had increased to 68%. The RCO then decreased the flow and at about 1120 the SG level had dropped to the Lo SG level setpoint of 35%,

and by 1129 the SG level had dropped to the Lo-Lo SG level setpoint of 15%. Upon reaching the Lo-Lo setpoint on 2 out of 3 channels, the 3 Auxiliary Feedwater Pumps (AFW) (EIIS:BA) received a start signal, started, and delivered water to all 3 SG s. Upon the SG 3B water level returning to the normal range, the AFW pumps were secured and SG level continued to be controlled manually using the Bypass FCVs.

CAUSE OP EVENT The cause of the AFW actuation was personnel error in that the RCO failed to adequately monitor the SG level. The RCO was continuously involved in periodic testing starting at 1030. At the time of the event, the RCO s attention was focused on performing an operability test of a Nuclear Instrumentation System (NIS) (EIIS:IG) channel, and because of this distraction, he failed to take corrective actions to return the SG level to the normal range upon the Lo level alarm annunciating at the 35X level, prior to the automatic AFW actuation.

ANALYSIS OP EVENT At the time of the automatic AFW actuation, the main feedwater and standby feedpumps were operable . Upon the 3B SG water level reaching the 15X level on the narrow range SG water level indicator, all 3 AFW pumps started and delivered water to the Unit 3 SGs . Based on the above, the health and safety of the public were not affected.

NRC IEORM dddA I983)

NRC FOIIII 3EEA U.S. NUCLEAR REOULATORY COMMISSION (94(3(

LICENSEE EV(:NT REPORT (LER) TEXT CONTINUA1( N APPROVED OMB NO 3(SOW(84 EXPIRES: 8/31/88

~ FACILITY NAME (1I DOCKET NUMBER (3I LER NUMBER (SI PACE (3)

YEAR SEOVENTIAL .v?I?I REVISION

?'$5: NVM ER "(PS NVMEER Turkey Point Unit 3 p 5 p p p 2 5 0 8 8 0 0 4 00 03 OF 0 3 TEXT ///mao SPoco /4 hoqvhmd, voo Eddho'onV IVRC FomI 35MS/ (IT)

CORRECTIVE ACTIONS

1) The operator was counseled concerning awareness of his actions and the seriousness of this error.

2) An entry was made in the Short Term Instructions and Shift Information Book, to be discussed with the oncoming shifts, requiring increased operator awareness of the SG status whenever the SG s are fed manually, and stating that any testing on the unit should be performed by the third licensed operator, when possible .

3) This event will be reviewed by the Training Department to determine any additional training requirements.

ADDITIONAL DETAILS:

Similar occurrences: LER 251-86-17.

NRC FORM SESA (9 831

P. O. '4000, JUNO BEACH, FL 33408.0420 APRIL 1 5 1988 L-88-179 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Unit 3 Docket No. 50-250 Reportable Event: 88-04 Date of Event: March 18, 1988 Auxiliary Feedwater Initiation on Inade uate Monitorin 'f Low Steam Generator Level Due to Steam Generator Level The attached Licensee Event Report (LER) is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Very truly yours, W. F. Con y Acting Group Vice President Nuclear Energy WFC/SDF/gp Attachment cc: Dr. Z. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant SDF3. LER an FPL Group company