ML19220A676
| ML19220A676 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/22/1973 |
| From: | Deyound R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Malloy J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML19220A675 | List: |
| References | |
| NUDOCS 7904240089 | |
| Download: ML19220A676 (1) | |
Text
J d,8. -h UNITED STATES
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ATOMIC ENERGY COMMISS!CN
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t J's y 5 t' JAM 2 3 '4d3 Mr. James F. Mallay Manager, Licensing Nuclear Power Cenerator Babcock & Wilec:c Cc=pany P. O. Box 1260 Lynchburg, Virginia 24505
Dear Mr. Mallay:
The Regulatory staff has cenpleted its review of Babecck & Wilc0x topical reports BAW-lCC07, Revisien 1 (Preprietary) and 3AW-10029 (Ncn-proprie:ary) entitled " Control Rod Drive Mechanism Tes: ? cgra=."
A su= nary of our review is enclosed for your infor ation.
As a result of cur review we have concluded that the non-proprietary report, BAW-lC029, is adequate and acceptable as a reference in lieu of the proprie:ary report, 3AW-lC007, in applica:icn for construction pernits and operating licanses provided that the applica:icn satisfico these conditions:
1.
The purpose of the reference to 3AW-10029 should be 11=1:ed to con :cl red drive rechanis: (CRDM) operating charac:cristics.
2.
The application should discuss the analytical nethods, criteria and stress li=its used in the design of the CRDM.
3.
The applica:1cn should address the difference between the 20-year design life of the CR M (as presented in 2AW-1CO29) and the 40-year design life of :he typical plant.
Sincerely, e
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'v: s J'e ' - e R. C. DeYoung, Assistant Director for Pressuriced Water Reactors Directora:e of Licensing
Enclosure:
Topical Repor Evaluation k'[3 k '1k
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