ML20107F946
| ML20107F946 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 10/27/1984 |
| From: | Drey L AFFILIATION NOT ASSIGNED |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8411070180 | |
| Download: ML20107F946 (1) | |
Text
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= Mrs. Leo Drey
' 515 West Point Avenue Universley City, Mo 63130 0ctober 27, 1984
- Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
E lt was_ nice having the opportunity finally to meet you in person in the elavator. descending (!) from the NRC's briefing on October 4, the day it was decided by the Commissioners that our Callaway plant here
-in Missouri is just in fine shape and in perfectly competent hands to be operated safely at full power.
I certainly wish I could agree with either conclusion.
I am writing to ask if I may please trouble you for information about the flow Indication (crack) discovered on August 6,1984 in the indian Point 2 reactor vessel during the 10 year in-service inspection?
Have you decided as yet whether the crack is one to two inches in depth, or no greater than a third of an inch; and do you still believe it is approximately two inches in length? Are you relying upon Consolidated Edison, Westinghouse (as Coned's In-service contractor),
Coned's independent consultant from Combustion Engineering, or NRC staff members to determine the actual measurements of the crack?
Because I believe our Callaway reactor vessel was also fabricated by Combustion Engineering, I find this " indication" to be particularly troublesome.
Sincerely,
/
\\
(JWR SEEBil
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