S1C PROTOTYPE REACTOR FACILITY. Environmental Monitoring Report, January- June 1962. Volume III, Number 2
Approximately 45.96 mC of beta radioactivity was released during the period January to June 1962 in liquid waste effluent and dilution water. The average concentration released was 8.7 x 10/sup -6/ mu C/cc. All liquid waste was released at less than 1/10 the permissible concentrations for continuous exposure as specified by the National Committee on Radiation Protection and Measurements for the radionuclides present. The Farmingion River was sampled monthly at various locations upstream, and downstream of the Industrial Waste Outlet and at the outlet. The average of the river results indicate values of 3.1 x 10/sup -8/ 1.3 x 10/sup -8/, and 2.3 x 10/sup -8/ mu C/cc beta atthe upstream, outlet and downstream locations, respectively. Radioactive fallout is collected on a weekly basis at six locations around the site (on-site) and analyzed for gross beta radioactivity. Radioactive fallout is also collected at eleven off-site locations in neighboring towns and analyzed for gross beta radioactivity. Comparison of the weekly averages of all on-site sampling stations indicated 19.71 mC/mi/sup 2//sample and 20.64 mC/mi/sup 2//sample for all off-site sampling stations. Airborne waste effluent monitored at the point of release for beta radioactivity indicated an average concentration of 4.0 x 10/ sup -11/ mu C/cc, for the period January to June 1962. This compares witu the recommendations of the National Committee on Radiation Protection Standards, 1 x 10/sup -10/ mu C/cc, for the radionuclides involved. Air samples taken downwind of the point of release during the period indicates an average of 7.1 x 10/sup -12/ mu C/cc beta. Measurements of radioactivity in the Farmington River, the industrial waste effluent from the plant, air and fallout, in the S1C Prototype vicinity, during the period January to June 1962 indicated no significant contribution of radioactivity from the S1C Prototype to the environment. Furthermore it can be stated that radioactivity discharged to the environment under controlled conditions from the S1C Prototype, during waste disposal operations, were in full compliance with the recommendations of the National Committee on Radiation Protection and the radiation protection standards established by the Federal Radiation Council. (auth)
- Research Organization:
- Combustion Engineering, Inc. Naval Reactors Div., Windsor, Conn.
- DOE Contract Number:
- AT(30-3)-519
- NSA Number:
- NSA-18-001282
- OSTI ID:
- 4159435
- Report Number(s):
- CENRD/HP/62/2
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-64
- Country of Publication:
- United States
- Language:
- English
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