Published 1996 | Version v1
Book

ECCS room temperature response due to loss of room cooler concurrent with a loss of coolant accident

  • 1. Commonwealth Edison Co., Chicago, IL (United States)

Description

The Emergency Core Cooling System (ECCS) in a nuclear power plant is designed to maintain adequate core cooling in a loss of coolant accident (LOCA). The system equipment is qualified (EQ) to operate under the thermal environment expected during a LOCA and is located in a compartment cooled by room coolers. Since it is important to maintain the compartment temperature below the EQ temperature in the event of a LOCA, the ECCS is declared inoperable whenever the room coolers are inoperable, such as when they are down for scheduled or unscheduled maintenance. This could lead to forced plant outages. An analysis is performed to determine if the room coolers are needed to maintain the room temperature below the EQ temperature during a LOCA event. The analysis uses a RELAP4 model. It conservatively calculates the temperature response and demonstrates that the EQ temperature is not exceeded during extended ECCS operation without room coolers. This eliminates the need to declare the ECCS system inoperable and contributes to improved plant performance

Additional details

Publishing Information

Publisher
American Power Conference.
Imprint Place
Chicago, IL (United States)
Imprint Title
Proceedings of the American Power Conference. Volume 58-II
Imprint Pagination
886 p.
Journal Page Range
p. 789-791.
ISSN
0097-2126

Conference

Title
58. annual meeting of the American power conference.
Dates
9-11 Apr 1996.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28008628
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AIR CONDITIONERS; ECCS; FAILURES; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; NUCLEAR POWER PLANTS; R CODES; RESPONSE FUNCTIONS; THERMAL ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; FUNCTIONS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-960426--.