ML19209C574
| ML19209C574 | |
| Person / Time | |
|---|---|
| Issue date: | 07/10/1979 |
| From: | Zudans Z Advisory Committee on Reactor Safeguards |
| To: | Shewmon P Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19209C570 | List: |
| References | |
| ACRS-CT-1158, ACRS-CT-1159, NUDOCS 7910160166 | |
| Download: ML19209C574 (1) | |
Text
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- E y,..gi NUCLEAR REGULATORY COMMISSION 5
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Prof. P. Shewmon, Chairman, ACRS Subcommittee on Metal Comronents FROM:
Z. Zudans, ACRS Consultant In the following, I wish to make the following coments, together with scae negative impressions I wish to convey.
Program on piping break criteria proposes to identify distinction between the design loads and real loads.
I believe the only way real loads can be identified by actually instrumenting the systems in the plant.
Dynamic pipe whip analysis program (an improvement of A!SR) is not needed in my opinior.
Dissection of Surry Steam Generators - there has to be a better way
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of doing it'.
Suckling criteria development program, presented by David Jeng, is not well defined in terms of the objectives stated. There is a need for some such program, but not as definea under this item.
Consideration should be given to centralized, generally accessible data bank on physical properties of rnaterials (discussed by W, BMI).
David Ayres, CE., arguments on elimination of cold leg br eak are not adequately supported by his analysis and also are out of place in this meeting. Similarly, his discussion of irradiation effects correlation by CE vs. Reg. Guide 1.99 makes no impact on anything we discussed.
1147 067 79101001(6
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