ML20006A871

LER 89-019-00:on 891227,discovered That Manual Reactor Trip Operating Surveillance Test Not Performed within Required Frequency Prior to Previous Reactor start-up on 891224. Caused by Inadequate start-up procedures.W/900123 Ltr

ML20006A871
Person / Time
Site:	Beaver Valley
Issue date:	01/23/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-019-01, LER-89-19-1, ND3MNO:2017, NUDOCS 9001300393
Download: ML20006A871 (5)

Text

, - - - - _

e

'A@

Telephone (4th 393-6000 Pti;?!

• Stuppingport. PA 16077 6 January 23, 1990 ND3MNO:2017 Beaver Valley Power Station, Unit No. 1 Docket No.-50-334, License No. DPR-66 LER 89-019-00 United States Nuclear Regulatory Commission  !

Document control Desk I Washington, DC 20555 l

Gentlemen:

In accordance with Appendix A Beaver Valley Technical Specifications, the following Lice,nsee Event Report is submitted:

LER 89-018-00, 10 CFR 50.73.a.2.i.B,." Start-up Prior to Trip Breaker Testing".

Very truly yours,

/

T. P. Noonan 3 General Manager Nuclear Operations Cj Attachment i

i 9001300393 900123 j FDR ADOCK 0500 4 l

'/ / .

Janu2ry 23, 1990 ,

• Np3MNOt2017 l Pago two >

cc: Mr. William T. Russell Regional Administrator

'; United States Nuclear Regulatory Commission l Region 1 475 Allendale Road

< King of Prussia, PA 19406 C. A. Roteck, Ohio Edison Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 J. Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Dave Amerine Centerior Energy.

6200 Oak Tree Blvd.

i Independence, Ohio 44101

, INPO Records Center Suite 1500 1100 Circle 75 Parkway i Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J. N. Steinmetz, Operating Plant Projects Manager l Mid Atlantic Area l Westinghouse Electric Corporation Energy Systems Service Division <

Box 355 Pittsburgh, PA 15230

, American Nuclear Insurers

c/o Dottie Sherman, ANI Library The Exchange Suite 245 l

270 Farmington Avenue Farmington, CT 06032 l Mr. Richard Janati Department of Environmental Resources

! P. O. Box 2063-

, 16th Floor, Fulton Building Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co. -

P.O. Box 26666 One James River Plaza Richmond, VA 23261

C Forni 3ee U S. NUCLt1R t.EIUL ATORY COMMISSION s # PPT.OvtD OM8 t'O 3156010e ,

LICENSEE EVENT REPORT (LER) ' m a ' * """

DOCKEY NUMSER 42) PAGE (3; F ACILITY NAME 01 Beaver Valley Power Station, Unit 1 0 l5 l 0 l0 l 0 l 3l 3 14 1 loFl0 13 (ITLE 447 Start-up Prior to Trip Breaker Testing IVINT DAf f (Si LER NUMalm its REPORT DAf t (71 OTHER F ACILITit$ INVOLvtD 18)

MONTH DAY YEAR F ACILIT v hAvt5 DOCAET NUMptRi$)

MONT H DAY YtAR Y t Aft ('>Q' '4, L ye['

N/A 0l510jojol l l

~ ~

1l 2 2l 4 8 9 8l 9 0l1l9 0l0 0l1 2l 3 9l0 N/A 0l5l0 toioi l l THis REPORT lt SUDMITTED PURSUANT TO THt Rt QUIREMENTS OF 10 CF R 5 ICher* one e, more of ,*e foue mpf 01)

OPE R ATING MODE m to 402It) to 4051st 60 ThsH2Hivl 73 71thi 3

POWER 20 406teH1Hil 40.34teHil SO 734sH21tet 73.714sl to D00 i 1 20 ost.inHo 30 misH2i no n eH2Hvsi OTHE R <s,.<,,r ,. um.<,

20 406'.eH1HW61 50.73(sH2HI) 60.73mH2Hou6HA) J6 A!

20 406(al0 Hewl 60.7Stel(2HHI 60.72(eH2MoulHB) 20 409teH1Hvi 60.73: elf 2Hui) 60.73te H2Hal LICEN5tt CONTACT FOR 1 AIS LER (121 NAME TELEPHONE NUMBER Thomas P. Noonan, General Manager of Nuclear Operations 4l 1 l2 6l 413 l -l1 l 215 l8 COMPLt15 ONE LINE FOR E ACH COMPONENT F AILURE DESCRISED IN THis REPOR f (131 M 'C' I "8' L CAUS$ Sv8 TEM COMPONENT g p RkPCRTA CAU$t Sv$7EM COMPONfNT TO N'R 5 D XI X XI Xi XI X X IX I X IX N l 1 1 I I l l l

l l I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 l MONTH DAY YEAR S'iBMIS$ TON YR$ terv.s core,.te EXPECTfD sv8 MIS $10N OA ffl NO l l l a:T R ACT a-, ,, ,m .,u., , .. .,,,. . .--,, u, oy. M.<. ,v me, o , 0. >

On 12/27/89, while recovering from a reactor-trip, it was discovered that the Manual Reactor Trip Operating Surveillance Test (OST 1.1.7) had not been performed within its required frequency (7 days) prior to the previous reactor start-up on 12/24 The test was immediately performed, verifying all trip /89. breakers to be operable. The failure to perform the test within the required frequency was due to inadequacies in the Start-up Procedures (Start-up Surveillance Checklist, Surveillance Schedule and Manual Reactor Trip Surveillance procedure) which did not reference the 7 day time limit. These procedures have been revised to clarify testing requirements.

There were no safety implications due to this event. The missed surveillance procedure is used to verify that the reactor trip breakers will open in response to a manual reactor trip signal from the control room. Although a formal surveillance was not performed within 7 days of the start-up on 12/24/89, station records document several instances on 12/21/89, 12/22/89 and 12/24/89 where the reactor trip breakers were opened via a manual signal from the control room.

i "$1

I NZCFym 3064 U S NUCLE AR r.EEULMORY COMMIS810N I- '"'"

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ' eeRovio ous No. r w-om 3 4

4 EXPtRES: 8731/2 -l P AcaLITY hAME HI DOCK L T NUMS E R (21 - LER NUMBER (4) ~ PA04 (3)

...- == =w j Beaver Valley Power Station Unit 1 o [5 l0 l 0 l 0 l 3l 3 l4 8l 9i - 0 l1 l9 -

O hl O l2 OF OI3 J

\ inn eu .m em a mwa m. .eu . nc re. nu u nn i l

l DescriDtion of Event j On 12/27/89 the station was recovering from a reactor trip. j While reviewing the Start-up checklist, it was discovered that the '

Manual Reactor Trip Operating Surveillance Test (OST 1.1.7) had j not been performed within its required frequency prior to the l previous reactor start-up on 12/24/89. Technical Specification _

1 j 3.3.1.1 require that this test be performed within 7 days prior to i

a plant start-up. Operators immediately performed this test and verified that all reactor trip and bypass breakers were operable.

l l_ Cause of Event l This event was caused by inadequacies in the Start-up procedures, j specifically the Start-up Surveillance Checklist, the Surveillance l Schedule and the Manual Reactor Trip Surveillance Test procedure. J Prior to the reactor start-up on 12/24/89, operations personnel used the Start-up Surveillance Checklist to verify that all 7 I

required surveillance tests had been performed within their required frequency. On 12/23/89, the Nuclear Shift Supervisor performing this checklist reached OST 1.1.7, the manual reactor

, trip test. He determined that it had last been performed on 1

12/11/89. As per the Start-up Checklist, its required frequency i

j was "SU". The frequency notation "SU" is defjned in the Technical Specifications as " prior to start-up". He then checked the I surveillance test procedure and the surveillance test schedule, both of which again listed the required frequency of OST 1.1.7 as "SU". Based on this review, he concluded that OST 1.1.7 had been ~

1 performed within its required frequency and initialed that it was not required to be re-performed prior to start-up.

l

Previous Similar Events l There have been no previous similar events at Unit 1. There was l one previous event trip breakers were c(LER losed87-004-00) while in Mode at Unit 2 where 5 (Cold the reactor Shutdown) prior to l

completion of all required surveillance testing.

Corrective Actions The' Start-up Surveillance Checklist, the Surveillance Schedule and the Manual Reactor Trip Surveillance Test procedure have all been revised to clarify the testing frequency requirements. A review of all Surveillance Test procedures and the. Start-up Surveillance ,

Checklist has been initiated. The pur l identify and clarify, when necessary, all pose of this review occurrences of the is to l frequency specification "SU".

l l

l 1

NR FOKM 3eea *U.F. GPGs 1968-520 469100070

=ac . A v.s =Uctein motAToRv commission j

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OM8 NO. 3160-0104

1. ' ,- , EXPIRES: t/31/OS F ACILITY NAME (1) DOCEET NUMSER (2) LER NUMGER 16) PAGE (31 -

ve^a " 20 l'. OTJ.O Beaver Valley Power Station, Unit 1 -

0 P l0 l010 3l 3 l4 8l9 0l1l9 -

0l 3 0F 0l3 0l'O TEXT 67 me,e space de severed use e#6past NAC Fams J8641/117)

Safety Analysis l

There were no safety implications due to this event. Although a l formal surveillance was not performed within seven days of the i plant start-up on 12/24/89, station records document several instances where the main reactor trip breakers were cycled from the control room during this seven day. time period.

and 12/22/89, the trip breakers were cycled repeatedlyOnduring/89 12/21 rod drop tests. On 12/24/89, prior to the start-up, the trip breakers were closed and opened to support Solid State Protection System-testing. Manually cycling the breakers in this manner meets all testing requirements of the Technical Specifications and OST 1.1.7 ~

for the main reactor trip breakers. -The main reactor trip breakers were the only breakers closed from 12/24/89 (plant start-up) until 12/27/89 (plant trip). The bypass reactor trip breakers normally only used for testing, were not used during this per1od. Although there.is no record of cycling the "B" bypass breaker, the "A" bypass breaker was cycled on 12/21/89 during Solid State Protection System testing. '

l

.gO- -.. .u... m,n..s s. mom

. . . - . . - - . - .- . -. . -- . .-- - _ - -. - - - _ - _ _ - -