Analysis of risk reduction measures applied to shared essential service water systems at multi-unit sites

Technical Report · Sat Jun 01 00:00:00 EDT 1991

DOI:https://doi.org/10.2172/5746856· OSTI ID:5746856

Kohut, P; Musicki, Z; Fitzpatrick, R ^[1]

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1. Brookhaven National Lab., Upton, NY (USA)

This report summarizes a study performed by Brookhaven National Laboratory for the US Nuclear Regulatory Commission in support of the resolution of NRC Generic Issue 130. GI-130 is concerned with the potential core damage vulnerability resulting from failure of the emergency service water (ESW) system in selected multiplant units. These multiplant units are all twin pressurized water reactor designs that have only two ESW pumps per unit (one per train) backed up by a unit crosstie capability. This generic issue applies to seven US sites (14 plants). The study established and analyzed the core damage vulnerability and identified potential improvements for the ESW system. It obtained generic estimates of the risk reduction potential and cost effectiveness of each potential improvement. The analysis also investigated the cost/benefit aspects of selected combinations of potential improvements. 4 figs., 62 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5746856
• Report Number(s): NUREG/CR-5526; BNL-NUREG-52225; ON: TI91014441
• Country of Publication: United States
• Language: English

Related Subjects

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PWR TYPE REACTORS
AUXILIARY WATER SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR CORES
COST BENEFIT ANALYSIS
DAMAGE
ECCS
FAILURES
FEEDWATER
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
PROBABILISTIC ESTIMATION
PUMPS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
SEALS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
STATISTICAL MODELS
SURRY-1 REACTOR
SURRY-2 REACTOR
VULNERABILITY
ZION-1 REACTOR
ZION-2 REACTOR
ACCIDENTS
AUXILIARY SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MECHANICS
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled