Control room doses using new design-basis accident source terms

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:426499

Kamphouse, J L ^[1]

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1. Tennessee Valley Authority, Browns Ferry Nuclear Plant, Decatur, AL (United States)

Operating nuclear plants in this country are bound by the Code of Federal Regulations (CFR). One of the requirements is to maintain the postaccident doses to control room personnel below the 10 CFR 50, Appendix A, General Design Criteria 19 (GDC-19) limits. These limits are 30-rem thyroid dose and 5-rem whole-body dose. Inclusion of main steam isolation valve (MSIV) leakage, increased control bay habitability zone unfiltered inleakage, and the cost savings incentive of increased MSIV leakage have made it impossible for the plant under consideration to meet the GDC-19 limits without utilizing the NUREG-1465 source terms. The new source terms are used to calculate the control room doses. The calculation demonstrates the large reductions in thyroid dose, to the extent that charcoal filtration is not required to meet GDC-19 even with increased MSIV leakage.

• OSTI ID: 426499
• Report Number(s): CONF-961103--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
56 BIOLOGY AND MEDICINE
APPLIED STUDIES
COMPUTERIZED SIMULATION
CONTROL ROOMS
DESIGN BASIS ACCIDENTS
RADIATION DOSES
REACTOR OPERATORS
WATER COOLED REACTORS