Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry Plant

Technical Report · Tue Mar 01 04:00:00 EST 1994

DOI:https://doi.org/10.2172/142546· OSTI ID:142546

Kmetyk, L ^[1]; Smith, L ^[2]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Geo-Centers Inc., Albuquerque, NM (United States)

Activities involving regulatory implementation of updated source term information were pursued. These activities include the identification of the source term, the identification of the chemical form of iodine in the source term, and the timing of the source term`s entrance into containment. These activities are intended to support a more realistic source term for licensing nuclear power plants than the current TID-14844 source term and current licensing assumptions. MELCOR calculations were performed to support the technical basis for the updated source term. This report presents the results from three MELCOR calculations of nuclear power plant accident sequences and presents comparisons with Source Term code Package (STCP) calculations for the same sequences. The three low-pressure sequences were analyzed to identify the materials which enter containment (source terms) and are available for release to the environment, and to obtain timing of sequence events. The source terms include fission products and other materials such as those generated by core-concrete interactions. All three calculations, for both MELCOR and STCP, analyzed the Surry plant, a pressurized water reactor (PWR) with a subatmospheric containment design.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (United States); Geo-Centers, Inc., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 142546
• Report Number(s): NUREG/CR--6107; SAND--93-2042; ON: TI94008895
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
AVAILABILITY
BIOSPHERE
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CONTAINMENT SYSTEMS
FISSION PRODUCT RELEASE
LOSS OF COOLANT
M CODES
REACTOR PROTECTION SYSTEMS
S CODES
SOURCE TERMS
SURRY-1 REACTOR
THEORETICAL DATA