ML19312C751
| ML19312C751 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/19/1969 |
| From: | Ross D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19312C752 | List: |
| References | |
| NUDOCS 7912190962 | |
| Download: ML19312C751 (2) | |
Text
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WASHINGTON. D.C. 20545 m.l; o *}
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August 19, 1969 Charles u.
eng, Chief, Reactor Projects Branch No. 3, Division of Reactor Lice.' sing 1
i REACTOR BUILDING LEAK-RATE SPECIFICATIONS FOR OCONEE (DOCKET NOS. 50-2693 50-270, and 50-287)
The proposed tech specs for reactor building leak-rate (Paragraph 15.4.3 of POL, Volume II) have been reviewed.
Several deficiencies have been noted; the details are the enclosure.
The deficiencies include:
1.
Leak rate is not well defined, as it is specified at one pressure only.
No mention is made of acceptance values at a reduced test pressure.
2.
Leak rate may be permitted to approach 3%/ day, provided it is through the penetration room.
However the analysis ignores the increased release of non-filterables (including organic iodine as well as noble gases).
In addition the charcoal heat load calculation is not presented, f
3.
No specific test criteria are presented for the 40 year life of the plant.
Instead it is propcsed to await the results of the first refueling-outage tests on each nuclear unit.
4.
It appears that Duke proposes that a re-test on one unit is applicable to the other two.
5.
No individual penetration leak-rate limits are presented.
No corrective action, such as plantshutdown, is offered.
We should explore these points with Duke at the next technical meeting.
4 CU p
D. F. Ross, Reactor Project Branch No. 3 Division of Reactor Licensing-Enclosure :
Reactor 31dg. Leak Rate Calculations for Oconee
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Charles G. Long August 19, 1969 8
cc:
Docket files (3)
A. Schwencer D. Ross (2)
A. Dromerick R. DeYoung R. Birkel R. Boyd B. Grices RPB-3 Reading 0
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