ML19312C766
| ML19312C766 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/13/1967 |
| From: | Long C US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912190979 | |
| Download: ML19312C766 (2) | |
Text
{{#Wiki_filter:_- \\ J JUN 131967 Roger S. Boyd, Assistant Director for Reactor Projects, DRL Charlas G. Long, Chief d by Reactor Project Branch No. 3 Dgnal S g DUKE POWER COMPANT - OCONRE NU R STATION UNITS 1, 2, AND 3 - DOCKET NOS. g 269/270/287 A meetjag was held at Bethesda on May 8,1967 with Duke Pcwer Company to discuss the rateorological accident considerations and to discuss the use of hydre plants as emergency power units for the three reactors. The following persons were in attendance: DUKE AEC W. Lee R. Ferguson, DRS F. Courtney D. Sullivan, DRL C. Wylie R. Waterfield, DRL J. Newell, DRL B&W C. G. Long, DRL H. E. Flora J. Vanderhoven, DRL Consultant The meeting van split into two groups: One to discuss;the site and the other to discuss emergency power. The major point of discussion of the site meeting was understanding the diffusion model used by Duke in eval-unting the NCA. Af ter presentst. ion it became apparent that Duke had not taken into account the possibility that the contnin=ent leakage cicud could be restricted to the river valley on and off-site. Severn1 models vers investigated to determine which was the most conservative to eval-uate the condition where the cloud would atay in the river valley until it reached the Hartwell reservior near Clemson, South Carolina. It was finally resolved that Duke vould provide an analysis based on the cloud moving down the valley taking credit only for the dilution in the volume represented by the cross-section of the valley from the elevation of the surrounding hills to the river basin. This assumption will be used for both the two hour dose calculation and for the duration of the accident cale.ulation for the low population zone. It was estimated that this model would show that the site is acceptable based on the contain= ant leakage rate of.25% and a.025% release from the penetration room system. Duke stated they would revise the Pre 14=4n=ry Safety Analysis Report voluntarily when they submit the answers to the list of questions that DEL has prepared. It was estimated they would file that information on May 7o 10A7 l OFFICE > .......J........ $URNAME> I DATE > Pbrm AEC.318 (Rev.1HL1) u.s. sevtmt%7 mmmG or nct : me-o-2144.'s 7912190 N f
o JUN 131967 Roser s. Boyd The meeting a amargency power for the facility has been reported in memorandums (1) 1. L. Ferguson to Files, dated May 18, 1967 and (2) D. F. Sullivan to C. G. Long, dated May 22, 1967. The pertinent points discussed are outlined in these memorandums. Based on the discussion, Duke will revise the PSAR to reflect the noted changes to t!:e emergency power system. Distribution: Suppl. (3 L, DRL Readini3 RPB #3 Reading B. Grimes 1 RPB #.3.;-DRL l....... omer > k-g., SURNAME > fUb _l 6-13-67 DATE > Form AEC-318 (Rev. sm e - a =}}