ML19322B270

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Forwards Comments by Environ Science Svc Administration on Fsar,Amends 15 & 16 in Response to AEC 700729 Request
ML19322B270
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/05/1970
From: Shaw M
US ATOMIC ENERGY COMMISSION (AEC)
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912020120
Download: ML19322B270 (4)


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4 Comenta on Oconee Nuclear Station Units 1, 2, and 3 Duke Power Company Final Safety Analysis Report Amerb=ent No.15 dated July 9,1970 and A=endment No'.16 Dated July 23, 1970 Prepared by Air Resources Environ = ental Laboratory Environmental Science Services Ad=inistration July 29, 1970 The fifteen gas tracer experiments conducted on the site under poor (inversion) conditions show that in all cases the centerline concentration was lower than that which would have been predicted by the use of the equivalent Pasquill Type diffusion rates. The closest agreement for a stability category of Type F was in test 1 b (see Table 2A-2) where gt a distance of 680 m a centerline concentraticn of 4 x 10-5 see m > was measured at a wind speed of 5.4 m/sec. The equivalent esti=a ed concentration for Pasquill Type F would be 2.4 x 10-4 see m, a factor of 6 higher than the measured value.

It must, however, be assumed that a building wake effect is pagt of the cause for this difference. Allcwing a p.A factor of 1270 m for this effect brings the estimated value to a factor of 2.2 higher than the measured value.

An examination of the joint frequency tabulation of wind at the top of the 150-ft tcwer und7. slightly stable and moderately to strongly stable conditions shows a e m h tive frequency of 9 percent for a diffusion rate equal to or worse than Pasquill Type F and 1.5 m/sec. Extrapolating the data to the 5 percent level of probability results in a diffusion rateequivalenttoTypeFand1m/sec.

Although a wind speed calibration check made in October 1969 indicated the speed to be reading 1cw by a factor of 1.4, there is no rigorous way to determine hcw long this situatien has persisted and to what extent the data in the joint frequency tables of speed ard temperature lapse rate were affected.

It was obvious from a site visit by AEC and ESSA personnel in February 1970 that the terrain within the site boundary is very ccmplicated and that it is difficult to make near-surface =easurements which would be representative of the general ficw of air in the area of the reactor 3 14

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g complex. Because of the wooded ne,.ture of the terrain it was felt that the measurement above tree-top level at the top of the 150-ft micro-wave tower would most nearly represent the ambient flow from the reactor complex, although speeds would be somewhat over-estimated with regard to near-surface conditions. However, it could well be that this overestimation is compensated for by the under-estimation due to calibration errors.

In surnag, for the short-term release (0-2 hours) it appears from the data presented that at the site boundary of 1.6 km, assuming an effective ground release, the use of Pasquill F diffusion, a 1 m/sec wind speed, a factor of 2.2 better diffusion because of site characteristics quantitatively shp by onsite diffusion experiments, and a AA facter of 12'70 m because of building wake effect is appropriately conservative. 3The resulting concentraticn 4 see m-would be approxi=ately 1 x 10

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'M Peter A. Morris, Director Division of Reactor Licensing SAFETY ANALYSIS REPORT Reference is made to the letter of July 29, 1970, from R. C. DeYoung, Assistant Director for Pressurized Water Reactors, DRL, to the Environmental Science Services Administration requesting comments on the following safety analysis report:

Oconee Nuclear Stations Units 1, 2, and 3 Duke Power Company Final Safety Analysis Report Amendment No.15 dated July 9,1970 and Amendment No.16 dated July 23, 1970 Review by the Air Resource Environmental Laboratory, ESSA, has now been completed and their coments are enclosed.

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,0 Cbw Milton Shaw, Director Division of Reactor Development and Technology

Enclosure:

Comments (Orig. & 1 cy.)

cc:

R. C. DeYoung, Assistant Director for Pressurized Water Reactors, DRL H. L. Price, Director, REG 2514

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