ML19256D241
| ML19256D241 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 06/26/1967 |
| From: | Check P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910170750 | |
| Download: ML19256D241 (2) | |
Text
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T Eg-UUPy, UNITED STATES GOVERNMENT s
Hamorandum q o 61967 TO
- Roger S. Boyd, Assistant Directcr, RP/DRL
/[ DATE:
THRU: Charles G. Long, Chief, RPB #3, DRL O.K
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pi, no:a : Paul S. Check, Reactor Proj u t Branch No. 3 Division of Reactor Licensig
< st:3 pct: STAFF /A??LICANT MEETING - THREE MILE ISLAND NUCLEAR STATION -
DOCKET NO. 50-289 Cn June 14, 1967, a meeting was held between the Division of Reactor Licensing and the Metropolitan Edison Cc=pany and its agents; Babcock &
Wilcox, Gilbert Associates, United Engineers and Constructors, and Pickard and Lowe Associates. This was the initial staff / applicant meeting in the matter of Metropolitan Edison's application to construct the Three Mile Island Nuclear Station.
In attendance were:
AEC MET. ED B&W R. S. Boyd R. E. Neidig F. R. Tho=asson C. G. Long G. F. Bierman R. F. Ryan B. Grimes J. S. Bartman W. B. Beisel J. Hard J. G. Miller R. E. Wascher M. Fairtile G. F. Trowbridge P. S. Check J. F. Gutzweiler Gilbert Assoc.
VEEC P&LA S. D. Gcodman A. E. Payne W. W. Lowe D. K. Craneberger W. H. Traffas W. B. Shields Babcock & Wilcox =ade a brief presentation co= paring this reactor with the Oconee (Dulle) reactors. The reactors are very similar, the only significant differences being in the fuel cycle.
Gilbert Associates outlined the principal design para:eters for the pre-stressed containment, citing differences in design and analysis among the Three Mile Island, Oconee and Brookwood containments.
Representative; of DRL then outlined for the applicant those items which would be most likely to receive special consideration during its review.
A=ong these are:
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i.~ith respect to contain ent a.
design approach b.
quality control provisions c.
grouted tendons d.
1:istruncatation to determina structural response and long tars sut millance e.
panatration design 2.
Control red drives 3.
Staa: generator tests 4.
Justification of sodium thiosulfate spray 5.
Sc ic acid interaction with =aterials 6.
Koility of reactor cavity to acco odate pressure pulses 7.
Turbine =issile analysis S.
Site hydrology and geolor/
The staff inquired about Metropolitan Zdison's nuclear qualifications and heard of their participation in Sa: ten.
The intaraction between organi-2ations was a13o disc *dsed.
Mr. Long (D'U.) concluded the uccting with an outline of the staff's tenta-tive schedule which was identical to the published esti=sted prcject ached-ule.
'dc pointed out that it was an aggressive schadule and that many isttors could cause a delay of at least ona month.
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Form AEC.318 (Rev. 9-53',
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