05000260/LER-1984-003-04, :on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment

From kanterella
Jump to navigation Jump to search
:on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment
ML20087C815
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 03/06/1984
From: Jones G, Danni Smith
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-84-003-04, LER-84-3-4, NUDOCS 8403130181
Download: ML20087C815 (3)


LER-1984-003, on 840212,routine Surveillance Testing Stopped Because Operator Unable to Bring HPCI Turbine Speed Down to Required 2,400 Rpm.Caused by Erratic Ramp Generator/Signal Converter Box Adjustment
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function
2601984003R04 - NRC Website

text

_ _ _ _ _ _ _ _ _ _ _. _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _. _. _

NRC pera ate U S NUCLE AR Rt outaTOR Y COMMISSION APrROVED OMO NO 31to-4104 LICENSEE EVENT REPORT (LER)

F ACILITV NAME (1)

DOCitti NUMBER f 21 PAGE 4L Browns Ferry - Unit 2 o l5 I o Io l 0 l216 l0 l lorl012 TITLE (4)

HPCI Inoperable Due to Turbine Governor Control System Failure EV9NT DATI 891 ttR NUMetR lel REPORT DATE (71 OTHER F ActLITitt INVOLVED 10)

MONTH DAY ftAR YlAR "gO

'"k l

UONTH DAY VEAR F A Ci L

  • T '. Names DOCA ti NUM9t Rt51 015!0f0f01 l l 012 112 8

4 8 14 01011 0 10 01 3 Ol6 814 0 isto f o io; I l 1H18 REPORT 'S SUOMITTED PURSUANT TO THE REQUIREMENTS OF to CPR l- (Cano eae er more of sne reaserne litt s

OPE R AfileG 5

N 30 0 i.

! 30 0eiei so 73 eH2H 73 ?iini POWER 30 405teH1Hli 80 364e1115 00 73teH2Het 73.711el

'Eo!'

017l0

]

[ g,ng;s,-g,7lg,n,e,,

30 awHiHei neweim e0nwHmai 20 408tell1 Hein 30.73te n tst.:

60.73teH2HvielH A)

J66 A J 20 406(ell 1H6el to 73(eH211a, 50.73iel(2HestiHS) 20 400(el(1Hel 50 73(all211sul 80 73deH211ml LICENSEE CONTACT FOR TMis Lin (12)

NAME TELFPMONE NuM8tR ARE A CODE David L. Smith 21 015 7 12 19 l - 101816 ls COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRISED IN THIS REPORT (131

"'y

" 'y'g

^0 IASLE MA AC R E,POR T A E

CAUSE

SYlf tM COMPONE NT pg $

CAUlt SYSTt u COMPONENT ppd X

Bl3 ICIN ]V W121910 Y

I I I I I l l 1

l I l I I I I

I I i i l i SUPPLEMENTAL REPORT EXPECTED (148 MONTM DAY YEAR SU O MI SSION Yt1lif ven conwe*e EMPICTIO Sucut33!ON DA TE]

NO l

l l

AS TR ACT <t,-.,m -, e. e,,0.-,

,,- eye e - A e., n.i During routine surveillance testing (High Pressure Coolant Injection Turbine and Pump Flow Test), testing was stopped because the operator was unable to bring the high pressure coolant injection turbine speed down to the required 2400 rpm.

Maintenance was dispatched to troubleshoot. The ramp generator signal converter was found to be performing erratically.

The failure was determined to be random and the ramp generator / signal converter box was replaced.

Surveillance testing was successfully performed and no recurrence control required.

t 8403130181 840306 PDR ADOCK 05000260 S

PDR

".".V"* "*

\\

Nec Pere 3s44 U S NUCLEAR KtGULATOAV COMMIT $ SON LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPaovto ove No mo-oio4 ImPsatS 8/31 M P ACIL8 T Y hasti ill ducat T NUMetR 128 LER NUMGE R sel PAGE(31 7s 'a

" RO.

"li*,.O Browns Ferry - Unit 2 0 l5 l0 ]o l0 l 2l6 l 0 8l 4 0l 0l 3 0l0 0[2 oF 0l2 etxta--r m., u

- Nncr mr.mn Unit 1 was operating at 97 percent p:wer; unit 2 was operating at 70 percent power; and unit 3 was in refueling outage. Only unit 2 was affected by this event.

At 1030, the unit operator (licens-d reactor operator) was performing a normal plant surveillance instruction (High Pressure Coolant Injection Turbine and Pump Flow Test). During the test, the turbine (TRB) speed was 3000 rpm and the operator was unable to bring it down to the required 2400 rpm.

Therefore, the testing was stopped and the high pressure coolant injection system (BJ) declared inoperable.

No adverse effects resulted. The Technical Specification requirements were met.

(The high pressure coolant injection system is one of the emergency core coolant systems.)

Maintenance investigated the problem and found the ramp generator / signal converter box's (CNV) zero potentiometer adjustment (part of th s turbine governor control system) to be erratic. The converter box was replaced.

This is considered a random failure for the time this potentiometer was used.

Subsequent surveillance testing proved the system to be performing properly.

Therefore, no recurrence control is necessary.

ResDonsible Plant Section N/A l

i

Previous Similar Events

1 None l

l g.....

J

5 TENNESSEE VALLEY AUTHORITY 4

Browns Ferry Nuclear Plant P. O. Box 2000

~

Decatur, Alabama 35602 March 6,1984 U. S. Nuclear Regulatory Commission i

Document. Control Desk.

Washington, D. C.

20555'

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE

]

REPORT BFRO-50-260/84003 The enclosed report.provides details concerning high pressure coolant injection turbine inoperable due to turbine governor control system failure.

This report is submitted in accordance with 10 CFR 50.73 (a)(2)(v).

Very truly yours, TENNESSEE VALLEY AUTHORITY

$s

_h:_%

\\,

G. T. Jones Power Plant Superintendent Browns Ferry Nuclear Plant Enclosure cc (Enclosure):

Regional Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, Suite 2900 Atlanta, GA 30303 NRC Inspector, Browns Ferry Nuclear Plant i

l l

I An Equal Opportunity Employer 4

s---

4 e g

$n. -,,-

4 w

w w

, %m