ML20235A240
ML20235A240 | |
Person / Time | |
---|---|
Issue date: | 08/24/1970 |
From: | Fraley R Advisory Committee on Reactor Safeguards |
To: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
Shared Package | |
ML20234A777 | List: |
References | |
FOIA-87-40 ACRS-GENERAL, NUDOCS 8707080368 | |
Download: ML20235A240 (1) | |
Text
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WY,5V 03 m .:
August 24, 1970 h*
E. G. Case, Director Division of Reactor Standards USE OF INDUSTRY CODES AND STANMEDS The ACRS would appreciate learning whether the adequacy of the current ASME code and code cases with respect to the secondary side of steam generators has been reviewed by the Division of Reactor Standards. The question arises in part from the use of electroslag welds and the "C" classification (under Section III of the ASME code) for the steam generator shells for the Davis-Desse station. However, it is more general in nature, since the relation between the of fset of potential steam generator failure end the type of design, fabrication and testing employed, enters as a general consideration for nuclear plants.
In addition, the Committee has requested a statement regarding the adequacy of USAS B31.7, Nuclear Power Piping and the proposed AttE Code for Pumps and valves for Nuclear Power Plants and the ADE Boiler and Pressure Vessel Code for Nuclear Vessels, particularly with respect ts stress analysis, piping strain and/or displacement calculations and checks, and the need for and requirements regarding independent calcu-1stions.
The constittee would also like to learn what procedures are being followed to determine the acceptability from the Regulatory point of view of all relevant industry codes.
t- OriSinal Signed by
,. E. E. Fraley R. F. Fraley
. O*-
g Executive Secretary l
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J. M. Hendrie @
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' hee: ACRS Members h' '
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