ML20085J672

Proposed Tech Specs Re Addl Activity of Cs-137 & Kr-85 for Calibr of Newly Acquired Portable Radiation Instrumentation. Significant Hazards Considerations Analysis Encl

ML20085J672
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/28/1983
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20085J662	List: ML20085J660 ML20085J665 ML20085J672
References
NUDOCS 8310130279
Download: ML20085J672 (3)

Text

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Fort St. Vrain Technical Specifications License Information Amendment No.

Page 5 of 12 (2) Pursuant to the Act, 10 CFR Part 70, "Special Nuclear Material," and 10 CFR Part 73, " Physical Protection of Special Nuclear Material," to receive, possess, and use at any one time in connection with operation of the facility:

a.

Up to 1700 kilograms of contained uranium 235, b.

Up to 3

curies of plutonium contained in encapsulated plutonium-beryllium neutron sources, c.

Alpha calibration sources of plutonium and uranium, not to exceed 10 microcuries total per element; (3) Pursuant to the Act and 10 CFR Part 40, " Licensing of Source Material," to receive, possess, and use at any one time up to 25,000 kilograms of natural thorium in connection with operation of the facility; (4) Pursuant to the Act and to 10 CFR Part 30, " Rules of General Applicability to Licensing of Byproduct Material," to receive, possess, and use in connection with operation of the facility:

a.

The following without restriction as to chemical and/or physical form:

1.

Any byproduct material with Atomic numbers 1 through 83, inclusive, not to exceed 5 millicuries per radionuclide; 2.

Americium 241, not to exceed 2.01 curies; 3.

Americium 243, not to oxceed 5 millicuries; l

4.

Cesium 137, not to exceed 300 curies; 5.

Hydrogen 3, not to exceed 15 curies; l

6.

Krypton 85, not to exceed 200 millicuries; 7.

Neptunium 237, not to exceed 5 millicuries; 8.

Polonium 210, not to exceed 10 microcuries; 8310130279 830920 PDR ADOCK 05000267 P

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ATTACHMEtiT 3 SIGilIFICAllT HAZARDS CONSIDERATlotoS AllALYSIS

r-1 Significant Hazards Considerations Analysis Since the proposed changes to the Facility Operating License of the Fort St. Vrain Technical Specifications serves only to enhance the accuracy and efficiency of radiation protection instrumentation used at Fort St. Vrain, and since the changes are necessary to comply with Nuclear Regulatory Commission and ANSI N323 (Section 3.3.2) recommendations, it is apparent that no significant safety hazards considerations are involved.

Based on the above, operation of Fort St. Vrain in accordance with the proposed changes will not (i) involve a significant increase in the probability or consequencas of an accident previously evaluated,

_(2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.