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Feasibility study on the relaxation of the secondary side safety injection setpoint lead-lag ratio for Maanshan Nuclear Power Plant

  • 1. Taiwan Power Company, Taipei, Taiwan (China)

Description

Since 1979, Taipower has performed its own safety analysis to effectively support plant operation, reload applications, design changes, technical specification amendments and to build up our inhouse licensing capability. One of the activities is to acquire the RELAP5/MOD2 computer code from Idaho National Engineering Laboratory (INEL) for Pressurized Water Reactor (PWR) Application. The RELAP5/MOD2 is a computer program developed for analyzing the dynamic behavior of thermal-hydraulic systems. This program has been developed primarily for analyzing postulated accidents and transients in PWR system. Maanshan is a Westinghouse 3-loop-PWR plant. The design of the secondary side low pressure Safety Injection (SI) signal is to protect the plant from main steam line break. The normal operating pressure for the secondary side is about 1000 psia and the low steam pressure SI setpoint is 600 psia. During an abnormal transient, a sudden big load change would have a chance to drop the secondary side pressure up to 40 psi, and through the amplification of the current Lead-Lag ratio (10 times), this pressure drop would initiate the SI system. In order to avoid this inadvertent SI initiation, Taipower performs a feasibility study to search the best Lead-Lag ratio for the secondary side low pressure SI signal by using RELAP5/MOD2. It concludes that this Lead-Lag ratio can be relaxed or can be removed. (author)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1

Additional details

Publishing Information

Imprint Title
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1
Imprint Pagination
772 p.
Journal Page Range
p. 1C1-1C6
Report number
INIS-XA-N--080

Conference

Title
4. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
5-8 Apr 1994
Place
Taipei, Taiwan (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35095461
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANT LOOPS; FEASIBILITY STUDIES; MAANSHAN-1 REACTOR; R CODES; REACTOR KINETICS; SAFETY INJECTION; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; KINETICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 1 fig., 7 tabs