ML19340D596

LER 80-100/03L-0:on 801201,LI-1474 Steam Generator a Level Channel 1 Indicated Higher than Average of Three Channels. Caused by High Transmitter Output Due to Leaking Root Isolation Valve.Will Be Repaired in Next Refueling Outage

ML19340D596
Person / Time
Site:	North Anna
Issue date:	12/28/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340D577	List: ML19340D576 ML19340D596
References
LER-80-100-03L, LER-80-100-3L, NUDOCS 8012310333
Download: ML19340D596 (2)

Text

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U.S. NUCLEAR REGULATORY COMMISSION LICENSEE E\ TNT REPORT CONTROL BLOCK / / / / / / / (1) (PLEASE PRINT OR TYPE iLL 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 fE /L/ (6) /0/5/0/0/0/3/3/8i (7)

DOCKET NUMBER

/1/2/0/1/8/0/ (8) / L/ 2/ / 2/ s/ a/ (9)

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

/0/2/ / On December 1,1980 while operating at 77% power in mode 1, LI-1474 steam /

/0/3/ /_ generator A level cahnnel I indicated higher than the average of the three /

/0/4/ / channels. Since the affected channel was placed in the tripped condition and /

/0/5/ / redundant indication was available the health and safety of the public were not/

/0/6/ / affected. This event is reportable pursuant to T.S. 6.9.1.9.b. /

/0/7/ / /

/0/8/ / /

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBC0DE COMPONENT CODE SUBCODE SUBC0DE

/0/9/ /I/A/ (11) [E/ (12) /E/ (13) /I/N/S/T/R/U/ (14) /T/ (15) /Z/ (16)

SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO. CODE TYPE NO.

(17) REPORT NUMBER /8/0/ /-/ /1/0/0/ /\/ /0/3/ /L/ /-/ /0/

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

/X/ (18) /A/ (19) /Z/ (20) /Z/ (21) /0/0/0/0/ (22) /Y/ (23) /N/ (24) /A/ (25) /W/1/2/0/ (26)

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)

/1/0/ / The cause of this event is a high transmitter output due to a leaking root /

/1/1/ / isolation valve. Because the unit is nearing a refueling outage the channel /

/1/2/ / will be left in trip until the outage when the leaking valve will be repaired. /

/1/3/ / The next scheduled functional test on this channel is not scheduled to occur /

/1/4/ / prior to the unit I refueling outage. /

FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DESCRIPTION (32)

/1/5/ /E/ (28) /0/7/7/ (29) / NA / (30) DISCOVERY

/B/ (31) / OPERATOR OBSERVATION /

ACTIVITY CONTENT RELEASED OF RELEASE 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) /Z/ (38) / NA /

PERSONNEL INJURIES NUMBER DESCRIPTION (41)

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

LOSS TYPE OF OR DAMAGE TO FACILITY [43)

DESCRIPTION

/1/9/ [Z[ (42) / NA /

PUBLICITY ISSUED DESCRIPTION (45) NRC USE ONLY

/2/0/ [NL (44) / NA /////////////

NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-5151 8012310252523

9 Virginia Electric and Power Company North Anna Power Station, Unit #1

Attachment:

Page 1 of 1 Docket No. 50-338 Report No. LER 80-100/03L-0 Description of Event On December 1,1980 while operating at 77% power it was determined that LI-1474 steam generator A level channel I was indicating >5% higher than the average of the three channels. The channel was placed in trip and declared inoperable. This event is applicable to T.S. 3.3.1.1 and reportable pursuant to T.S. 6.9.1.9.b.

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

Cause of Event 1-Fb'-LT-1474, Steam Generator Level Channel I - Protection, indicated

>5% higher than the averages of the three channels due to a transmitter with excessive high output caused by a steam leak on the root isolation valve.

Immediate Corrective Action The valve was placed in trip and declared inoperable. Since the root valve had previously been Furmanited with no long term success the decision was made to leave the channel in trip until it can be replaced during the upcoming refueling.

Scheduled Corrective Action During the upcoming Unit I refueling the root valve will be cut out and replaced, the channel calibrated and placed back on service.

1 Actions Taken to Prevent Recurrence No further actions are required.

Generic Implications There are no generic implication.

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