New technologies for a postaccident control room habitability assessment

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6912367

Lahti, G P ^[1]; Perchiazzi, W T ^[2]

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1. Sargent Lundy, Chicago, IL (United States)
2. Commonwealth Edison Co., Downers Grove, IL (United States)

Older nuclear power plants typically considered only a nominal amount of unfiltered in-leakage (typically 10 ft[sup 3]/min) affecting their postaccident habitability. However, recent measurements of unfiltered in-leakage show leakages in excess of the nominal 10 ft[sup 3]/m in. The assessment of postaccident doses in control rooms is done in a number of well-defined steps: (1) Determine the initial release of radioactivity to the containment (the [open quotes]source term[close quotes]). (2) Determine the release of radioactivity to the environment. (3) Determine the atmospheric dispersion and the concentration at the control room air intake. (4) Determine within-building dilution (if any). (5) Determine unfiltered in-leakage. (6) Determine the concentration of radioactivity in the control room. (7) Determine the dose to control room occupants. The prescriptive methodology of the Murphy-Campe paper and Standard Review Plan (SRP) 6.4 has been used by the U.S. Nuclear Regulatory Commission (NRC) to assess control room designs. However, a number of new technologies have been employed to reevaluate an existing pressurized water reactor plant design.

• OSTI ID: 6912367
• Report Number(s): CONF-931160--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
• Country of Publication: United States
• Language: English

Related Subjects

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220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
ACCIDENTS
ATMOSPHERIC CIRCULATION
CONTROL ROOMS
DESIGN
DISPERSIONS
DOSE RATES
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS