05000315/LER-1980-023-03, /03L-0:on 800916,steam Generator 2 Channel 3 Level Indication Was Found to Be Indicating 6% Lower than Other Channels.Caused by Pinhole Leak in Impulse Line at Socket Weld.Repaired & Returned to Svc

/03L-0:on 800916,steam Generator 2 Channel 3 Level Indication Was Found to Be Indicating 6% Lower than Other Channels.Caused by Pinhole Leak in Impulse Line at Socket Weld.Repaired & Returned to Svc

ML17331A473
Person / Time
Site:	Cook
Issue date:	10/03/1980
From:	Delong S INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17331A471	List: 05000315/LER-1980-023, Forwards LER 80-023/03L-0 05000315/LER-1980-023-03, /03L-0:on 800916,steam Generator 2 Channel 3 Level Indication Was Found to Be Indicating 6% Lower than Other Channels.Caused by Pinhole Leak in Impulse Line at Socket Weld.Repaired & Returned to Svc
References
LER-80-023-03L-01, LER-80-23-3L-1, NUDOCS 8010090371
Download: ML17331A473 (2)

LER-1980-023, /03L-0:on 800916,steam Generator 2 Channel 3 Level Indication Was Found to Be Indicating 6% Lower than Other Channels.Caused by Pinhole Leak in Impulse Line at Socket Weld.Repaired & Returned to Svc

Event date:
Report date:
3151980023R03 - NRC Website

text

f'--I,

~

I NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BKOCKI t %,".

~

Qi (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

I 6

~i M

I D

C C

1 Qs 0

0 0

0 0

0 0

0 0.

0.

O.Qs 4I 1

1 1

1 Q4~Qs 7

8 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26'ICENSE TYPE 30 57 CAT 58 CON'T 070 9

1 6

8 OQs QB 7

8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~02 DURING NORMAL OPERATION THE STEAM GENERATOR 2 CHANNEL 3 LEVEL INDICATION WAS FOUND BE INDICATING 6 PERCENT LOWER THAN THE ASSOCIATED CHANNELS FOR THAT GENERATOR.

4 INITIAL INVESTIGATION REVEALED THA'T THE LEVEL TRANSMITTER BLP 122 OUTPUT WAS SL W Y

~06 DRIFTING DOWN.

THIS CONDITION WAS NON-CONSERVATIVE WITH RESPECT TO TECHNICAL SPECIFI-

~06 CATI'ON TABLE 3.3-4 ITEM 5a.

PREVIOUS OCCURANCES I C

~0 7

RO-050-316 80-009.

~os 7

8 9

80

~09 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~IB O44

~E O42 LXJ O44 3

R 0

O'"

L~J O>>

IZJ 0' 8

9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERiRO EVENT YEAR REPORT NO.

CODE TYPE NO.

Q17 REPQRT [JQ 0

Q

~02 3

QX

~03 QL

LOJ 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.

COMPONENT TAKEN ACTION ON PI.ANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER O4s ~~0>>

~~0m

~AQ>>

0 0 2

9

~~

0>>

~~O24

~~Oss B

0 0

D Qss 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o

THE CAUSE OF THE TRA S IP LSE LINE THE SOCKET WELD DOWNSTREAM OF THE ROOT VALVE FOR BLP-THE UNIT WAS SHUT DOWN REPAIRS ttADE AND THE G

3 THE ACTION REQUIREMENTS OF TECHNICAL SPECI FI CATION TABLE 3. 3-3 ITEM 5a WERE FULFILLED.

NO FURTHER ACTION IS PLANNED.

80 7

8 9

FACILITY STATUS

% POWER OTHER STATUS 1

5 E

2s 0

9 8

29 NA 80 80 45 80 80 gO /OOOO/ gg 80 NRC USE ONLY a

s 80 ss 0

7 8

9 10 PUBLICITY ISSUED DESCRIPTION~

~20

~Q44 7

8 9

10 68 69 METHOD OF DISCOVERY DISCOVERY DESCRIPTION O~O

~AQ31 OPERATOR OBSERVATION 7

8 9

10 12 13 44 45 48 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNTOF ACTIVITYQ35 LOCATION OF RELEASE Q [ii~]

Z Qss

~ZQ44 NA NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

~00 0

Qss ~ZQss 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 tiis] ~()

p p

Q44 N

7 8

9 11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

~19 Z

Q42 Nn NAME OF PREPARER S.

D.

DELONG PHONE:

W I