Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

Technical Report · Wed Jun 01 00:00:00 EDT 1994

DOI:https://doi.org/10.2172/10170668· OSTI ID:10170668

Yakle, J ^[1]; Darby, J ^[2]; Whitehead, D; Staple, B ^[3]

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1. Science Applications International Corp., Albuquerque, NM (United States)
2. Science and Engineering Associates, Inc., Albuquerque, NM (United States)
3. Sandia National Labs., Albuquerque, NM (United States)

This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 10170668
• Report Number(s): NUREG/CR-6143-Vol.2-Pt.3; SAND-93-2440-Vol.2-Pt.3; ON: TI94016048; BR: GB0103012; TRN: 94:016604
• Resource Relation: Other Information: PBD: Jun 1994
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GRAND GULF-1 REACTOR
RISK ASSESSMENT
FAULT TREE ANALYSIS
OUTAGES
REACTOR FUELING
REACTOR CORES
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
REACTOR ACCIDENTS
DAMAGE
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED