ML19209B263

LER 79-076/03L-0:on 790908,during Reactor Startup,Rod 26-07 Had No Position Indication at Notch 48.Rod Tested & No Problem Discerned.Work Request Issued to Investigate Problem

ML19209B263
Person / Time
Site:	Brunswick
Issue date:	10/01/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19209B258	List: ML19209B257 ML19209B263
References
LER-79-076-03L, LER-79-76-3L, NUDOCS 7910090397
Download: ML19209B263 (1)

Text

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. . LICENSEE EVENT REPORT CONTROL BLOCK: l 1

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7 LICENSEE CODE CON'T E 8 ERC l60L l@l610 l 5 l 0DOCKET 0 3 l 2 l 4 @[_0 l 9 0 l8 7 l 9 l@l 1 l 0 l 0 l 1 l 7 l 9 @

l - NUM8ER 68 69 74 75 REPORT DATE 80 7 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l During a normal reactor startup, the operator noticed that rod 26-07 had no position O 3 l indication at notch 48. All other indications were normal. l g l Technical Specification 3.1.3.7, 6.9.1.9b l 0 5 l 0 e l 1 0 7 l l 0 a I l 7 8 9 80 CE CODE S 8C DE COMPONENT CODE SU8 CODE SU E g

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,,. SEQUENTIAL OCCURRENCE REPORT REVislON LE R/ RO EVENT YEAR REPORT NO. CODE TYPE NO.

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]g 42 43 Nlg G 0 8 l0 [g 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l Rod 26-07 was operationally tested and no problem could be found with position indica-l FTTl I ting probe. The rod was notch in to notch 46 and back to notch 48 and normal indica- [

i 2 tion returned. An Engineering Work Request had been written to investigate the i 3 l position indicating system due to the number of position indicating failure we have i 4 l been experiencing.  ;

7 8 9 80 ST  % POWER OTH ER STATUS DISCO RY DISCOVERY '.3ESCRIPTION i s W@ l 0 l 3 l 0 lh! NA l Whl contenr surveilljnce A TIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE W LzJ

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l_i_j,aj l 0l 0 0lhl NA l 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY O TYPE DESCRIPTION h -) !

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