05000259/LER-1984-011-01, :on 840209,during Routine Surveillance Testing, Automatic Scram Initiated.Caused by Failure of MSIV Dc Solenoid.Failure Considered Random Event.Solenoid Coils Checked Weekly for Operability

:on 840209,during Routine Surveillance Testing, Automatic Scram Initiated.Caused by Failure of MSIV Dc Solenoid.Failure Considered Random Event.Solenoid Coils Checked Weekly for Operability

ML20087B435
Person / Time
Site:	Browns Ferry
Issue date:	02/29/1984
From:	Jones G, Danni Smith TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-84-011-01, LER-84-11-1, NUDOCS 8403090085
Download: ML20087B435 (3)

LER-1984-011, on 840209,during Routine Surveillance Testing, Automatic Scram Initiated.Caused by Failure of MSIV Dc Solenoid.Failure Considered Random Event.Solenoid Coils Checked Weekly for Operability

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
2591984011R01 - NRC Website

text

-

l f

NRC P.,

ps U s. NUCtuu urWLATOav CO nies>ON l-12' u enovto OM. O m o_cio.

I LICENSEE EVENT REPORT (LER) l

)

, AC,u,,,,A.,E,,,

ooCRST U tR al PAoi a BrcNns Ferry - Unit 1 o g 5 l o g o ; o l21519 1lOFl012 TITLG 140 Automatic Scram Due to Failure of Main Steam Isolation Valve DC Solenoid 2VgarT DATE (96 Lan Nunette im REPOf*T DAff (7)

OTMSR F ACILITIts INVOLVED (8) esONTH DAY VE A,;

YEAR 88,O

• 8, E ~ y MONTM DAY YEAR P ACILeTy seawes DOCA tT NUMitRest g

0 151010101 l l 0l2 0l9 8 4

8l4 0l1 l1 0 l0 0l 2 2 l9 8!4 0 1 5 101 0 1 0l I I THIS RSPORT IS SUS $1TTED PUROUANT TO THE REQUIRitetNTS OF 10 CFM l- (Ceare sae er mers or r*e Peew asJ (11)

OPORAT M M

30.49ttbl 30.406tel

{

50 78teH2H=1 73.71165 4

304WieH1H4 90.384 H1) 90.73(eH2H.)

73.711el 0: 919 n ase=H1Hsi unwm gMgs,-g,e g oc.nieH3H I 30.4W4eH1Hilli 90.73deH2Hil 90.730sH2HedellAl Jis6A) 30.4ESteH1HM to.73teH2Hal go.73teH2HvinHet s

30.454eHilM 98.73eH2HMO go.731eH2Hal LICENHE CONTACT FOR TMis LER titt NAME 7tLtPHONE NVMstR AREA CODE 20 1 5 729l10 i 8 I 65 1

i 1 1 Nsr4 r4 f.

Rin4 & h COMPLETE ONE LING FOR RACH COnpOestNT PA3LURt OtsCRISED IN TMi$ IttPORT 113)

CAust SYSTEM COMPONENT

,,,T s' O

MA%AC Rt A E

~

CAust SYSTEM COMPONENT R

p X

JIM l IClt Al611 13 Y

l l I I I i I I I I I I i i

I I I I I I SUPPLktetNTAL REPORT EMPSCTED fiel MONTH CAY YEAR SUOMiSSION

~} vts or s,. e wwe exPacreo susarist on carts D NO l

l l

v AmeTR ACT a,.e ee.ue.. ee.,s.o e.e, ~.e., we.-e er,e.~,s

, no During routine surveillance testing, AC po'.:er to the "C" outboard main steam isolation valve control solenoid was properly removed and "B" channel of the reactor protection system was properly tripped, bringing in a half scram.

(

Previously the DC control solenoid coil had unknowingly failed and removal of the AC power caused the "C" outboard main steam isolation valve to close. When the "C" main steam line isolated, a reactor high pressure signal was received in "C" line causing the "A" reactor protection system channel to trip. This condition caused a full scram signal and the reactor scrammed. No unusual transients were observed.

The DC coil was replaced. The DC coil failure is considered to be a random failure cnd no further recurrence control is required.

8403090085 840229 PDR ADOCK 05000259 S

PDR

/

n,- -

l

aseC Pere 3BL5 L.6 er9 CLEAR KE2ULATOEY COMMISSIOrd

~*"

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Awaovto ove No vio-oio.

ERPIRES Sf3145 f ACitaf f fsAaBE tu DOCKEY Nue4SER 421 LER NtheER (Si PAGE (31

" R* F.P.

C,*.O ve*a Browns Ferry - Unit 1 o l5 jo lo lo l2 l5 l9 8] 4 l- 0 l 1l 1 0l0 0l 2 0F 0l2 TENT far mese ausse e seeseest oss entsenner Amec #erm Jm4'sJ t17)

Unit 1 was operating at 99 percent power; unit 2 was operating at 97 percent power; cnd unit 3 was in a refueling outage.

At 0928, during performance of routine surveillance testing, AC power was properly removed from main steam line "C" outboard isolation valve's (ISV) AC control c lenoid (SOL) and the "B" reactor protection system channel (JE) was also properly tripped. Plant personnel were unaware that the DC control solenoid (SOL) to the came valve had failed due to a burned-out coil (CL). The DC control solenoid failure, in combination with the AC solenoid power removal, completed the initiation logic fon full valve closure and caused the "C" outboard isolation valve to close. Since the reactor was at near full power, clouure of the "C" outboard isolation valve resulted in a high reactor pressure signal being received on the CC" main steam line (SB), causing the "A" reactor protection system channel to trip. Since both "A" and "B" channels of the reactor protection system were tripped, this resulted in an automatic reactor scram signal being received. This cvent is an analyzed situation and there was no safety significance.

The step in the surveillance test which removes the AC control solenoid power and trips "B" reactor protection system channel also trips the "B" channel of primary containment isolation system (JM). A high steam flow signal was received on main cteam line TA" causing the "A" channel of primary containmont isolation system to

' initiate; therefore, a reactor isolation occurred almost simultaneously with the reactor scram.

Failure of the DC control solenoid coil is considered to be a random event, and no recurrence control is required. These solenoid coils are checked weekly for cperability.

Resnonsible Plant Section - N/A

Previous Similar Events

- None gronw u l

i t,

,.[*A>

f' TENNESSEE VALLEY : AUTHORITY

. Browns Ferry Nuclear Plant 4 ',,

P. O. Box 2000 Decatur, Alabasa 35602

. e

, February.29, 1984

,y

U..S.'huolearRegulatoryCommission

+

Document Control Desk

'. Washington, D. C.

20555-n',

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 1 - DOCKET

.NO. 50-259.- FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE

. REPORT BFRO-50-259/84011 e

y

.The enclosed report providee details concerning autostaic scram due to failure'of a DC main steam isolation valve solenoid. This report is submitted in accordance with 10 CFR 50.73 (a)(2)(iv).

Very truly yours, TENNESSEE VALLEY AUTHORITY O. T. Jones Power ant Superintendent

. Browns Ferry Nuclear Plant Enclosure co. (Enclosure):

Regional Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcenient

_ Region II

.101 Marietta Street, Suite 2900 Atlanta, GA 30303

.NRC Inspector, Brc ns Ferry Nuclear Plant y

l

+ _

s g

e i '<

- 1 es\\

P Hs An Equal Opportunity Employer l

~

ii_=__________---____--___.____