ML19329D775
| ML19329D775 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/13/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Rodgers J FLORIDA POWER CORP. |
| Shared Package | |
| ML19329D772 | List: |
| References | |
| NUDOCS 8003170714 | |
| Download: ML19329D775 (1) | |
Text
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O N,_
s UNITED STATES Distribution:
,,i ATOMIC ENERGY COMMISSir N AEC PDR j-WASHINGTON. D.C. 2054S Docket File 6 DR Reading
_re; DRL Reading BWR Branch Ch. PWR-2 Reading
- w t Xc. 50-302 s/
March 13, 1970 PWR Branch Ch. C. K. Beck R0 Branch Ch.
M. M.' Mann L. Kornblith P. A. Morris llorida Pcwer Corporation F. W. Karas F. Schroeder 101 Fif th Street South D. F. Ross S. Levine St. Petersburg, Florida 33701 T. R. Wilson J. F. Newell
.it tenticn :
Mr. J. T. Rodgers R. C. DeYoung Xuclear Project Manager D. J. Skovholt R. S. Boyd Centlemen:
P. W. Howe
.e have reviewed your Amendment 8 to the Preliminary Safety Analysis laport for your Crystal River plant, containing the latest design
- nformation on the containment. One material criterion listed in four March 4,1970 letter of transmittal is that the NDTT would be
-15* F or that the material would meet acceptable impact tes t require-ments.
This criterion provides reasonable assurance that the anchor-age hardware can perform its function in an environment 30' F lower than the minimum expected site temperature. We conclude that your procurement criteria for the anchorage hardware components as described in your March 4,1970 letter of transmittal are acceptable. Appro-priate attention should be given to the fabrication processes for the components to prevent undesirable changes in properties. We understand
- hat you will provide us with a material description and fabrication process su= mary when that information is available.
We are continuing our review of Supplement 6 on the concrete anchorage zone s tress analysis. On the basis of our review thus far, we conclude that the design of the concrete anchorage zone reinforcement for the I
containmea; base mat is acceptable. When we have completed our review of Supplement 6, we will notify you of our further comments or concur-rence.
. Sincerely, Orl;inal Signed by htg6. Mort gi Peter A. Morris, Director Division of Reactor Licensing I
cc:
1 Mr. Roy B. Snapp 1
1725 K S treet, N.W.
Washington, D.C.
20006 PWR-2/DRL P
DRL' PWR/ 9 DRI DRI 0FR
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