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Title: ALARA and decommissioning: The Fort St. Vrain experience

Conference ·
OSTI ID:54678
;  [1];  [2]
  1. Public Service Co. of Colorado, Platteville, CO (United States)
  2. Scientific Ecology Group, Platteville, CO (United States)

The Fort St. Vrain Nuclear Generating Station, the first and only commercial High Temperature Gas Cooled Reactor to operate in the United States, completed initial fuel loading in late 1973 and initial startup in early 1974. Due to a series of non-nuclear technical problems, Fort St. Vrain never operated consistently, attaining a lifetime capacity factor of slightly less than 15%. In August of 1989, the decision was made to permanently shut down the plant due to control rod drive and steam generator ring header failures. Public Service Company of Colorado elected to proceed with early dismantlement (DECON) as opposed to SAFSTOR on the bases of perceived societal benefits, rad waste, and exposure considerations, regulatory uncertainties associated with SAFSTOR, and cost. The decommissioning of Fort St. Vrain began in August of 1992, and is scheduled to be completed in early 1996. Decommissioning is being conducted by a team consisting of Westinghouse, MK-Ferguson, and Scientific Ecology Group. Public Service Company of Colorado as the licensee provides contract management and oversight of contractor functions. An aggressive program to maintain project radiation exposures As Low As Reasonably Achievable (ALARA) has been established, with the following program elements: temporary and permanent shielding contamination control; mockup training; engineering controls; worker awareness; integrated work package reviews communication; special instrumentation; video camera usage; robotics application; and project committees. To date, worker exposures have been less than project estimates. from the start of the project through Februrary of 1994, total exposure has been 98.666 person-rem, compared to the project estimate of 433 person-rem and goal of 347 person-rem. The presentation will discuss the site characterization efforts, the radiological performance indicator program, and the final site release survey plans.

Research Organization:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Brookhaven National Lab. (BNL), Upton, NY (United States)
OSTI ID:
54678
Report Number(s):
NUREG/CP-0143; BNL-NUREG-52440; CONF-940505-; ON: TI95008770; TRN: 95:012712
Resource Relation:
Conference: 3. international workshop on implementation of ALARA at nuclear power plants, Long Island, NY (United States), 8-11 May 1994; Other Information: PBD: Mar 1995; Related Information: Is Part Of Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants; Khan, T.A. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; Roecklein, A.K. [Nuclear Regulatory Commission, Washington, DC (United States). Div of Regulatory Applications]; PB: 810 p.
Country of Publication:
United States
Language:
English

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