05000361/LER-1982-115, Forwards LER 82-115/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-115/03L-0.Detailed Event Analysis Submitted

ML20069J666
Person / Time
Site:	San Onofre
Issue date:	10/15/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20069J670	List: 05000361/LER-1982-115, Forwards LER 82-115/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-115-03, /03L-0:on 820916,during Mode 2 Operation,Control Element Assembly 47 Slipped & Dropped in Excess of 7 Inches. Caused by Defective Timing Card.Affected Solid State Chip Replaced
References
NUDOCS 8210250214
Download: ML20069J666 (2)

LER-1982-115, Forwards LER 82-115/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982115R00 - NRC Website

text

~

1

, *J

?

Southern California Edison Company SW

^

S AN ONOFRE NUCLE AR GENER ATING S T A TION P.O. B O R 12 8

'l

$ AN C LEMEN TE. C A LIFOR hl A 92672

$N N AUG,

October 15, 1982 g,,"j'[,",$

.p 7.-

Ej i

=

~a D

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Regican V 1450 Maria Lane, Suite 210 Walat Creek, California 94596-5368 Attention:

Mr. R. H. Engel ken, Regional Administrator

Dear Sir:

Subject: Docket No. 50-361 30-Day Report Licensee Event Report No.82-115 San Onofre Nuclear Generating Station, Unit 2 Pursuant to Section 6.9.1.13b of Appendix A, Technical Specifications to Operating License NPF-10, for San Onofre Unit 2, this submittal provides the required 30-day written report and copy of Licensee Event Report (LER) for an occurrence, involving the Control Element Assembly (CEA).

I Limiting Condition for Operation (LCO) 3.1.3.1 requires that while in Modes I and 2 all CEA's which are inserted in the core, shall be operable with each CEA of a given group positioned within 7 inches (indicated position) of all other CEA's in its group.

On September 16,1982, at 1631 with the plant in Mode 2, while attempting reactor startup CEA 47 (Group 5) slipped from approximately 50 inches to 20 inches violating LCO 3.1.3.1.

I Action Statement 3.1.3.1.C.1 allows operation to continue in Modes 1 and i

2 provided that within one hour the misaligner' CEA is restered to operable status within its specified alignment requirr

- is.

This was achieved

[

within 7 minutes by manually lowering the remaining rods in Group 5 to l

20 inches.

In addition, Group 4 rods were 8owered manually to 120 inches, and shutdown margin verified. This satisfactorily fulfilled the i

Action Statement and reactor startup was resumed at 1704.

f I

I 8210250214 821015 PDR ADOCK 05000361 b '~M '

_O PDR 82-357

9%*

R. H. Engel ken October 15, 1982 The cause for the f ailure was due to a defective timing card and the affected solid state chip was replaced. No additional corrective actions are necessary since this was the first and an isolated failure of this type.

LER 82-115 addresses this event. This event had no ef f ect on public health and safety since it did not affect the ability of the CEA to insert into the core whenever required.

If there are any questions, please contact me.

Sincerely,

/

[

Enclosure:

LER 82-115 cc:

A. E. Chaf fee (USNRC Resident inspector, San Onof re Unit 2)

U. S. fluclear Regulatory Commission Office of Inspection and Enforcement U. S. iluclear Regulatory Commission Of f ice of Management Information and Program Control institute of Nuclear Power Operations l