ML20010E118: Difference between revisions

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50.35(e) Report Docket Nos. 50-361/362 Southern California Edison Company                                 gE P O BOX 800 2244 W A LN UT GROVE A V E N U E ROSEMEAD C A Li F O SIN I A 917 7 0                 ~'j J. M. Curran                                                                           --      1. u . o ,
50.35(e) Report Docket Nos. 50-361/362 Southern California Edison Company gE P O BOX 800 2244 W A LN UT GROVE A V E N U E ROSEMEAD C A Li F O SIN I A 917 7 0
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August 17, 1981                                    -:    m''"*""
Curran
iia Mr. R. H. Engelken, Director                                           r     N             ,;fd
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                                                                                            ~
August 17, 1981 m''"*""
Office of Inspection and Enforcement                                                         .A U. S. Nuclear Regulatory Commission                                 ~
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3                 E Region V Suite 202, Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California               94506
iia Mr.
R.
H. Engelken, Director r
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U. S. Nuclear Regulatory Commission
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Region V Suite 202, Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94506


==Dear Mr. Engelken:==
==Dear Mr. Engelken:==
==Subject:==
==Subject:==
Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station, Units 2 and 3 This letter confirms verbal notification on August 17, 1981 of a condition discovered in construction which is considered potentially reportable in accordance with 10CFR50.55(e). The guide lug inserts (shims) for reactor internals exhibit cracks which are detectable by visual examination. The condition has been confirmed by dye penetrant examination.
Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station, Units 2 and 3 This letter confirms verbal notification on August 17, 1981 of a condition discovered in construction which is considered potentially reportable in accordance with 10CFR50.55(e).
We are performing an evaluation of this condition and will submit an appropriate report in accordance with 10CFR50.55(e)(3) if the condition is determined to be report-able.       If you have any questions or require additional infor-mation, please let me know.
The guide lug inserts (shims) for reactor internals exhibit cracks which are detectable by visual examination.
The condition has been confirmed by dye penetrant examination.
We are performing an evaluation of this condition and will submit an appropriate report in accordance with 10CFR50.55(e)(3) if the condition is determined to be report-able.
If you have any questions or require additional infor-mation, please let me know.
Very truly ycurs, k.
Very truly ycurs, k.
cc:     R. J. Pate (NRC, San Onofre Units 2 and 3)
cc:
R. J. Pate (NRC, San Onofre Units 2 and 3)
Dr. L. T. Papay m
Dr. L. T. Papay m
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Latest revision as of 06:36, 21 December 2024

Deficiency Rept Re Guide Lug Inserts (Shims) for Reactor Internals Which Exhibit Cracks That Are Detectable by Visual Exam.Condition Under Evaluation
ML20010E118
Person / Time
Site: San Onofre  
Issue date: 08/17/1981
From: Curran J
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8109030115
Download: ML20010E118 (1)


Text

_ _

50.35(e) Report Docket Nos. 50-361/362 Southern California Edison Company gE P O BOX 800 2244 W A LN UT GROVE A V E N U E ROSEMEAD C A Li F O SIN I A 917 7 0

~'j J. M.

Curran

1. u. o,

August 17, 1981 m"*""

s.. w. = a ' '* ass-~"

iia Mr.

R.

H. Engelken, Director r

N

,;fd Office of Inspection and Enforcement

.A

~

U. S. Nuclear Regulatory Commission

~

E 3

Region V Suite 202, Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94506

Dear Mr. Engelken:

Subject:

Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station, Units 2 and 3 This letter confirms verbal notification on August 17, 1981 of a condition discovered in construction which is considered potentially reportable in accordance with 10CFR50.55(e).

The guide lug inserts (shims) for reactor internals exhibit cracks which are detectable by visual examination.

The condition has been confirmed by dye penetrant examination.

We are performing an evaluation of this condition and will submit an appropriate report in accordance with 10CFR50.55(e)(3) if the condition is determined to be report-able.

If you have any questions or require additional infor-mation, please let me know.

Very truly ycurs, k.

cc:

R. J. Pate (NRC, San Onofre Units 2 and 3)

Dr. L. T. Papay m

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4 M, 7'

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S E P 0 21981

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