ML19291C903
| ML19291C903 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/20/1969 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Minnick L YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011130403 | |
| Download: ML19291C903 (1) | |
Text
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DISTRIBUTION :
f k'. Dooly, DR R. Engelken, C3(2)
H. Shapar, CGC J. Euchanan, ORNL F. Schroeder, DP1 AUG 2 01959 A. Burger, DRL 3
D. Skovholt, DRL Docket No. 50-29 PDJ ytrocket File DR Reading 9h DRL Reading 44 Tenkaa Atomic riectric Company ORB-1 Reading 441 Stuart Street ACRS(3) p Boston, Massachusetts 02116 Attention:
Mr. L. E. Minnick Vice president Centlemen:
Tour letter of March 24, 1969, cummarised for our review and coissent your proposed performance criteria for a contemplated transition from stainlasa-steel clad fuel presently used in the Yankee-Rowe reactor to the future use of aircaloy c*ad fuel. We understand that, if the results of your visual inspection during August 1969 refueling confirm good appearanca of the aircaloy clad test fuel assemblies now being irradiated, you plan to use the first sirecloy clad fuel reload batch in the fall of 1970 or in the spring of 1971.
During a meeting on April 29, 1969, we discussed these utne criteria with you and comumented on the need for detailed analysis using appropriate conservative assumptions. We have also pointed out to you the need for providing satisfactory design margins.
You also acknowledged the need for additional safety injection system capacity and amergency power for operating this system in the event parzal power van lost ist order to meet your criteria (8) and (9) and subsequently provided a prelininary conceptual radasign dated June 18, 1969. We con-sider these improved safety features necessary to limit tha ralasse of fissiae products from the care and for pretseting and maintaining the containment integrity in the event of a major rupture of the priury systen pressure boundary. We understand that you are presently planning to have these additional capabilities designed, approved, installed end operational at the time you load the first batch of zircaloy fuel assemblies.
It is our opinion that your proposed criteria are an appropriate brais to use in design of a aircaloy clad core for the Yankee-Rove reactor.
Sincerely, s
g 4
Original signed by b
SEE ATTACHED SHEET FOR CONCURRENCES
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