ML17326B573

LER 89-007-00:on 890310,reactor Trip Signal Received Due to lo-lo Steam Generator Level.Caused by Failure of Personnel to Adequately Anticipate Required Auxiliary Feedwater Flowrate.Personnel Involved counseled.W/890403 Ltr

ML17326B573
Person / Time
Site:	Cook
Issue date:	04/03/1989
From:	Runser H, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-007, LER-89-7, NUDOCS 8904140349
Download: ML17326B573 (5)

Text

'A.C CEM PAT,ED DlKBl'TlON DEMONISTl10% SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8904140349 DOC.DATE: 89/04/03 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATION RUNSER,H.F. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele SMITH,W.G. Indiana Michigan Power Co. (formerly Indiana S Michigan Ele RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-007-00:on 890310,steam generator lo-lo level reactor trip signal due to personnel error.

W/8 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 l. PD3-1 PD 1 1 STANG,J 1 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 2 ACRS WY LIE 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 AEOD/ROAB/DSP 2 2 DEDRO 1 IRM/DCTS/DAB 1 1 NRR/DEST/ADE 8H '1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 NRR/DEST/PSB 8D l. 1 NRR/DEST/RSB 8E 1 NRR/DEST/SGB 8D 1 1 10 NRR/DLPQ/HFB 10 NRR/DOEA/EAB NR~D ~ ll B 9A 1

1 1

NRR/DLPQ/QAB NRR/DREP/RPB NUDOCS-ABSTRACT 10 1

2 1

1 2

1 02 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 RGN3 FILE 01 1 1 EXTERNAL EG&G WILLIAMSg S FORD BLDG HOY,A 1 1 H ST LOBBY WARD LPDR 1 1 NRC PDR NSIC MAYS,G 1 1 NSIC MURPHYgG A ~

NOTE 'ZO ALL "RIDS" RECIPIENIS PLEASE HELP US K) REDUCE WM~i. CXWZACT 'lHE DOCUMENT CXWIROL DESKS RXYi Pl-37 (EXP. 20079) K) ELIMINATE YOUR NAME HKH DISHtZBVFIQN LISTS FOR DOCUMENZS YOU DGH'T NEED TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 43

NRC Form 358 US. NUCLEAR REOULATORY COMMISSION (84)3) APPROVED OMB NO. 3160-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT HLER)

DOCKET NUMBER 12) PAGE 3 FACILITY NAME (II D. C. Cook Nuclear Plant Unit 2 0 5 0 0 0 3 1 6 1 OFP 3 Steam Generator Low-Low Level Reactor Trip Signal Due to Personnel Error During Cooldown With Reactor Trip Breakers Open EVENT DATE (5) LER NUMBER (8) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

SEQUENTIAL >KOI Rr vseloN MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S)

MONTH DAY YEAR YEAR I@ NVMSER NUMBER 0 5 0 0 0 0 3 1 0 8 9 8 9 0 0 7 0 0 0 4 03 89 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CFR (Is (Check onr or more of thr follovflnpl (11 OP E RAT I N 0 MODE (8) 3 20A02(bl 20.405(cl X 50.73( ~ )(2)llvl 73.71(tr) 20A05( ~ ) (I) 0) 50.38 (I) 50,73( ~ l(2)(vl 73.71(c)

POWE R (c I LEVEL OTHER (Specify In Ahstrect p p p 20A05(e) (1((EI 50.38(c) (2) 50.73(e) (2) (rBI helper rnsf in Trxt, HIIC Form 20.405( ~ ) (1) (ill) 60.73( ~ ) (2) ill 60,73( ~ ) (2) (vill)(Al 36'SAJ 20A05(e) (1) (lv) 50.73(e) (2)(ll) 60.73(e)(2) (rilll(BI 20.40S(e) II I(vl 60.73(eH2)(ill) 50.73(el(2)(xl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE H. F. Runser, Operations Superintendent 61 6 46 5 59 01 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISEO IN THIS REPORT (13)

MANVFAC. REPORTABLE MANUFAC. EPORTABLE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TURER TO NPRDS Y~PWP V CAUSE TURER TO NPRDS gV reset. ~ w ..0 .. P.

fe%55 MONTH IINMIOAY YEAR SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SUBMISSION DATE (16)

YES Ilfyrs, complerr EXPECTED SUSMISSIOH DATE) NO ABSTRACT (Limit to f400 sprees, I.r., rpproxlmetrly fifrern slnplerpecr typrvrrlrrrn lintel l(SI On March 10, 1989, at 1738, a reactor trip signal was received due to a low-low steam generator (SG) level on number 21 SG during a cooldown using steam dumps to the condensers. Prior to the trip signal, a high SG blowdown rate was established for chemistry cleanup. The reactor operatoi controlling the SG levels did not adequately anticipate the amount of auxiliary feedwater which would be required to accommodate the cooldown and the blowdown. The auxiliary feedwater flow was increased significantly when level was close to the trip setpoint, but the increase in flow was not soon enough and the resultant shrink due to the cold water dropped the level to the trip setpoint.

The reactor trip breakers were open prior to the cooldown evolution. After the trip the opening of the motor operated auxiliary feedwater valves, the only anticipated automatic feature, performed as designed.

This event was caused by the failure of the Reactor Operator to adequately anticipate the required auxiliary feedwater flowrate and failure to take timely action to correct the situation or to notify other Control Room personnel of the situation. The involved Reactor Operator has been counseled on this event.

8904140349 890403 PDR ADOCK 05000316 PDC NRC Form 385 (8413)

NRC Form 366A ~ U.S. NUCLEAR REGULATORY COMMISSION (943) APPROVED OMB NO. 3150-0)04 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (3) LER NUMBER (6) PAGE (3)

SEQUE L v'. REVISION YEAR y@ NUM ER P

NUMSER D. C. Cook Nuclear Plant Unit 2 0 5 0 0 0 3 ] 89 00 7 0 0 02 "0 3 TEXT /// moro sosso I) rR)uirsd, u>> sddtu'orro/NRC Form 3654'sl (17)

Conditions Prior to Occurrence Unit Two in Mode 3 (Hot Standby).

Descri zion of Event On March 10, 1989, at 1738, a reactor trip signal was received due to a low-low steam generator (SG) (EIIS/AB-SG) level on number 21 SG during a cooldown using condenser steam dumps (EIIS/SB-FCV).

Prior to the cooldown, an extensive job briefing was given by the Unit Supervisor (senior licensed operator) to the three Reactor Operators (licensed operators) who were to perform the cooldown. Among other things, the briefing included instructions to use good communications, make all changes slowly and to ask for help if any problems were encountered.

A cooldown rate of 30 F/hour was established using the condenser steam dumps with SG levels at about 44%. Chemistry personnel then requested that the SG blowdown (EIIS/WI) rate be increased for cleanup. The SG blowdown lineup was then changed from the normal to startup alignment. The Reactor Operator (RO) controlling SG levels then initiated a high blowdown rate on all four steam generators. The auxiliary feedwater (AFW) (EIIS/BA) flow rate was then increased some, but the levels started to drop. The RO thought, that the level decrease would stop, so he observed the levels for a while without increasing AFW flow rate or reducing the SG blowdown rate.

The levels continued to decrease and the RO controlling the cooldown prompted the RO controlling the SG levels to increase the AFW flow, rate.

The blowdown from number 21 SG was stopped and the AFW flow rate was increased. The increased AFW flow rate was not initiated soon enough. The resultant shrink from the cold AFW dropped the number 21 SG level to the low-low level trip setpoint of 21X.

Prior to the cooldown evolution the reactor trip breakers (EIIS/JE-BKR) were open. Upon receipt of the reactor trip signal the AFW motor operated valves (EIIS/BA-ISV) traveled full open as designed and then throttled to the flow retention position. This was the only automatic actuation which should have occurred under the existing plant conditions. Operations personnel verified proper system response and plant conditions. There were no equipment or instrument malfunctions during this event.

NRC FORM 366A 19 83)

NRC Form 3884 U.S. NUCLEAR REQULATCRY COMMISSION 9431 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED OMS NO. 3150&)OS EXPIRES: 8/31/88 FACILITY NAME II) DOCKET NUMSER 13) LER NUMBER (Sl ~ AQE )3)

SEQUENTIAL ~r IIE Y IS IO N YEAR NUM ER NUMSER D. C. Cook Nuclear Plant Unit 2 0 5 0 o 0 3 1 6 8 9 0 0 7 0 0 0 3 OF 0 3 TEXT /// moss sosso is soqwiod. Uso oddd/ooo/P/RC Fosm 388A's) )IT)

Cause of Event This event was caused by personnel error. The RO controlling the SG levels did not adequately anticipate the required AFtII flow rate and failed to take timely action to correct the situation. The RO also failed to notify other Control Room personnel of the difficulty which was being encountered, Anal sis of Event This event is being reported in accordance with 10 CFR 50.73 (a)(2)(iv) as an event that resulted in an unplanned automatic actuation of an Engineered Safety Feature including the Reactor Protection System.

The automatic protection system responses were verified to have functioned properly as a result of the engineered safety features actuation.

the above, it is concluded that the event did not constitute an unreviewed Based on safety question as defined by 10 CFR 50.59(a)(2) nor did the health and safety of the public.

it adversely impact Corrective Action Immediate corrective action involved verifying proper system response and plant conditions. The SG levels were then restored to the proper levels.

The RO involved in this event has been counseled on the need to take actions and to communicate when difficulties are encountered. timely Failed Com onent Identification None Previous Similar Events No previous similar events involving failure to properly control SG levels during a cooldown evolution.

NRC FORM ESSA (983)

indiana Michigan Power Company Cook Nuclear Plant f'.0.'Box 458 Bridgman, Ml 49106 616 465 5901 Z

INDIANA MICHIGAN POWER April 3, 1989 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-74 Docket No. 50-316 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:

89-007-00 Sincerely,

. 'G. Smith, Jr.

Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr.

A. B.

M. P.

Davis, Region Alexich III P. A. Barrett J. E. Borggren R. F. Kroeger NRC Resident Inspector Wayne Scott, NRC R. C. Callen G. Charnoff, Esp.

Dottie Sherman, ANI Library D; Hahn INPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau