ML19308B086
| ML19308B086 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/31/1974 |
| From: | Thies A DUKE POWER CO. |
| To: | |
| References | |
| NUDOCS 7912120815 | |
| Download: ML19308B086 (3) | |
Text
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AEC DIS 7 E'TI C' FOR PART 50 DOCITT l'ATEE _.L (TDiPORARY TORM)
CONTROL NO:
945 TILE:
PRCti:
DATE OF DOC DATE REC'D LTR tric PET OTIER Duke Power Company Chsrlotte, N. C.
2S201 A. C. Thies 1-31-74 2-4-74 X
TO:
Mr. Giambusso 1 signed CLASS UNCLASS PROP I!iF0 INPUT NO CYS PIC'D DOCKET NO:
xxxx 1
50-269 DESCRIPTION:
ENCLOSUPIS:
Ltr reporting an abnormal occurrence in which it was noted that the level of radioactivity in the reactor coolant appeared to exceed
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T Mr. Angelo Giambusso Deputy Director for Reactor Projects t- ~
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Directorate of Licensing 4 j g [8/.4'^ I -
Office of Regulation
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U. S. Atomic Energy Com.ission k,m$ 4,f,.:
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Washington, D. C.
20545 Re: Oconee Nuclear Station I
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Docket No. 50-269
Dear Mr. Giambusso:
During initial startup and operation of Unit 1 of our Oconee Nuclear Station, it was noted that the level of radioactivity in the reactor coolant appeared to exceed a level attributable to corrosion products and tramp uranium. These indications have been monitored and evaluated during subsequent power operation.
The purpose of this letter is to provide you with information concerning this matter.
Gamma spectral analysis has shown that only a small portion of the Sross reactor coolant activity is a result of corrosion prodcct activation. The remainder of the observed activity appears to be due to various gaseous fission products. The observed fission product activities have been significantly less, however, than predicted reactor coolant activities based on one percent defective fuel.
pf Principal isotopic activities observed at 100 EFPD were as follows-Op 4
00cratD Oconee 1 g;gg Measured Values Isotope (uCi/cc)
FEB 4 1974
- m.aum I 131 0.38
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g me I 133 0.62 enrmrr naK J Xe 133 4.8 g, / % i \\ ", 't Xe 135 1.1 It should be noted, also, that reactor coolant alpha activity has been below minimum detectable limits, i.e., less than 10-6 ci/cc.
p On November 1, 19_73, in accordance with Technical Specification 4.1.2, reactor coolant E was determined to be 0.31 MeV. As per Technical
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i Mr. Angelo Giambusso Page 2 January 31, 1974 Specification 3.1.4, maximum allowabic reactor coolant activity was calculated to be approximately 720 pc/cc.
Current data indicate that i
the gross reactor coolant activity is less than three percent of this limit.
Also, the activity level has shown no discernible increasing trend from approximately 500 MWD /MIU burnup to the present burnup of approximately 3400 MWD /MIU.
We are continuing to monitor and evaluate reactor coolant activity.
Should any significant developments occur we will advise you further.
Very truly yours,
$P A. C. Thies
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Mr. N. C. Moseley j
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