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Title: System 80+{trademark} standard design incorporates radiation protection lessons learned

Conference ·
OSTI ID:54635
;  [1];  [2]
  1. Duke Engineering & Services, Inc., Charlotte, NC (United States)
  2. ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)

Many lessons have been learned from the current generation of nuclear plants in the area of radiation protection. The following paper will outline how the lessons learned have been incorporated into the design and operational philosophy of the System 80+{trademark} Standard Design currently under development by ABB Combustion Engineering (ABB-CE) with support from Duke Engineering and Services, Inc. and Stone and Webster Engineering Corporation in the Balance-of-Plant design. The System 80+{trademark} Standard Design is a complete nuclear power plant for national and international markets, designed in direct response to utility needs for the 1990`s, and scheduled for Nuclear Regulatory Commission (NRC) Design Certification under the new standardization rule (10 CFR Part 52). System 80+{trademark} is a natural extension of System 80{sup R} technology, an evolutionary change based on proven Nuclear Steam Supply System (NSSS) in operation at Palo Verde in Arizona and under construction at Yonggwang in the Republic of Korea. The System 80+{trademark} Containment and much of the Balance of Plant design is based upon Duke Power Company`s Cherokee Plant, which was partially constructed in the late 1970`s, but, was later canceled (due to rapid declined in electrical load growth). The System 80+{trademark} Standard Design meets the requirements given in the Electric Power Research Institute (EPRI) Advanced Light Water Reactor (ALWR) Requirements Document. One of these requirements is to limit the occupational exposure to 100 person-rem/yr. This paper illustrates how this goal can be achieved through the incorporation of lessons learned, innovative design, and the implementation of a common sense approach to operation and maintenances practices.

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:
54635
Report Number(s):
NUREG/CP-0143; BNL-NUREG-52440; CONF-940505-; ON: TI95008770; TRN: 95:012669
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