05000338/LER-1980-046-03, /03L-0:on 800612,Mode 1 Level indicator,LI-1474, on a Steam Generator Read 5% Higher than Other Indicators. Caused by Steam Leak on Upper Transmitter Isolation Root Valve.Steam Leak Treated W/Furmanite

/03L-0:on 800612,Mode 1 Level indicator,LI-1474, on a Steam Generator Read 5% Higher than Other Indicators. Caused by Steam Leak on Upper Transmitter Isolation Root Valve.Steam Leak Treated W/Furmanite

ML19320B140
Person / Time
Site:	North Anna
Issue date:	07/02/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19320B135	List: 05000338/LER-1980-046, Forwards LER 80-046/03L-0 05000338/LER-1980-046-03, /03L-0:on 800612,Mode 1 Level indicator,LI-1474, on a Steam Generator Read 5% Higher than Other Indicators. Caused by Steam Leak on Upper Transmitter Isolation Root Valve.Steam Leak Treated W/Furmanite
References
LER-80-046-03L, LER-80-46-3L, NUDOCS 8007090353
Download: ML19320B140 (2)

LER-1980-046, /03L-0:on 800612,Mode 1 Level indicator,LI-1474, on a Steam Generator Read 5% Higher than Other Indicators. Caused by Steam Leak on Upper Transmitter Isolation Root Valve.Steam Leak Treated W/Furmanite

Event date:
Report date:
3381980046R03 - NRC Website

text

n()

U.S. NUCLEAR REGULATORY COMMISSION LICEFSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

/0/1/

/V/A/N/A/S/1/ (2)

/0/0/-/0/0/0/0/0/-/0/0/ (3)

/4/1/1/1/1 (4)

/ / / (5)

LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT

/0/1/

/L/ (6)

/0/5/0/0/0/3/3/8/ (7)

/0/6/1/2/8/0/

(8)

/ 0/ 7/ 0/ 2/ 8/ 0 (9)

DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)

/0/2/

/

On June 12, 1980 while operating at 100% power in Mode 1 the level indicator

/

/0/3/

/

LI-1474 on "A" steam generator read 5% higher than the other level indicators. /

/0/4/

/

Since the affected channel was placed in the tripped condition and redundant

/

/0/5/

/

indication was available, the health and safety of the general public were not /

/0/6/

/

affected. Reportable pursuant to T.S. 6.9.1.9.b.

/

/0/7/

/

/

/0/8/

/

/

SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

/_Bf_ (13) /V/A/L/V/E/X/ (14) g/ (15)

LD/ (16)

/0/9/

/I/A/ (11) /E/ (12)

B SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.

CODE TYPE NO.

(17) REPORT NUMBER

/8/0/

/-/ /0/4/6/

/\\/

/0/3/

/L/

/-/

B/

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

/B/ (18) /Z/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) LY/ (23) N (24) /A/ (25) /V/1/3/5/ (2C CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/

/

The level indication was showing a high level due to a steam leak on the

/

/1/1/

/

upper transmitter isolation root valve. The steam leak has been treated

/

/1/2/

/

with furmanite, and the level transmitter is providing normal indication.

/

/1/3/

/

_/

/1/4/

/

/

FACILITY METHOD OF STATUS

% POWER OTHER STATUS S

RY MSMRY MRMION 02)

/1/5/

/E/ (28)

/1/0/0/,(29) /

NA

/ (30)

/B/ (31)

/ Routine Channel Check /

ACTIVITY CONTENT RELEASED - 0" REIIASE AMOUNT OF ACTIVITY (35)

LOCATION OF RELEASE (36)

/1/6/

/Z/ (33)

/Z/ (34) /

NA

/

/

NA

/

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (39)

/1/7/ /0/0/0/ (37) /_ZZ (38) /

NA

/

Z PERSONNEL INJURIES NUMBER DESCRIPTION (41)

/1/8/ /0/0/0/ (40) /

NA

/

l LOSS OF OR DAMAGE TO FACILITY b3) l TYPE

DESCRIPTION

/1/9/

/Z/ (42) /

NA

/

l PUBLICITY ISSUED DESCRIPTION (45)

NRC USE ONLY L2/0/.

/N/ (44) /

NA

/////////////

800709o353 NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151

a

, y Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of 1 Docket No. 50-338 Attachment to LER 80-046

Description of Event

On June 12, 1980 while operating at 100% power in Mode 1 it was determined that LI-1474 was reading 5% higher than the redundant level channels. The channel was placed in the tripped condition and declared inoperable. The applicable Technical Specification is 3.3.1.1.

Probable Consequences of Occurrence Since LI-1474 was placed in the tripped condition and redundant channel 2 were available to provide level indication and initiate reactor trip if required, the health and safety of the public were not affected by this event.

Cause of Event

A steam leak on the upper transmitter isolation root valve was causing LI-1474 to read high.

Immediate Corrective Action

The valve was treated with furmanite to stop the steam leak. Level indication returned to normal.

Scheduled Corrective Action No scheduled corrective action is required.

Actions Taken to Prevent Recurrence No further actions are required.

i r

1