ML19319B274
| ML19319B274 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/14/1972 |
| From: | Gammill W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001140708 | |
| Download: ML19319B274 (1) | |
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sQA" MR I 41972 A. Schwencer, Chief, Pressurized Water Reactors Branch i 4, DRL SITE' QUESTIONS ON OCONEE UNITS 2 AND 3, DOCKET NOS. 50-270 and 50-287 2.
SITE AND D MIRONMENT Section 2.1-indicates that the population statistics are based on the 1960 census. This'section should be updated to include the 1970 census data.
Fiture 2-2, Plot Plan and Sito Boundary, shows the one-nile radius exclusion area boundary. Provide a revised figure which clearly lshows the boundaries which will be uced for establishing effluent release limits. [See 'the 'AEC's recently published "Shadard Format and content of Safety Analysis Reports for Nucicar Power Plants" dated February 1972,~ Section 2.1.2.2.]
The nearest location suitable for dairying should be identified. -
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Figure 2-2 shows a highway passing in a northerly direction through the one-mile radius exclusion area boundary. Provide an analysis of a truck transportation inciu.a. involving ' toxic chemicals, explosive _ raterials, and fla::z2able rnterii.s on the_ safe operation "of the Oconec Nuclear Power Station.
If there are any~ oil or gas pipelines which pass near the reactor facility, the effect of potential accidents on the cafe operation of a nuclear facility should be evaluated.
If gaseous chlorine is stored on-site, describe the consequences of accidental release of chlorine on the reactor control roo:s personnel. Describe any protective devices used to protect control roo:s personnel during such a postulated incident.
Describe, if any, all industrial ' activities within a 5-mile radius of the' site.
If industrial facilities are located within a 5-mile radius of the plant, provide a description of the products nanufactured, stored, or transported to indicate the maxinaus quantities of har.ardous material likely to be processed, stored, or transported.
Distribution:
DRL-Supple.
3 DRL-Rdg.
SRS-Rdg.
W. P. Carnaill,- Chief i;
Site Safety, Branch SSB-Rdg.
C.Ferrell
- Divisio'n of Reactor Licensing cc:. ~ Irving Felt:ler, RDT -
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