Published 1999 | Version v1
Miscellaneous

Operability enhancement for PWR by relaxation of safety design parameters

  • 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)

Description

The risk analysis was performed in order to extend the surveillance test interval (STI) of RPS/ESFAS from 1 month to 3 months. The results showed that core damage frequency (CDF) increase 1.47% for Kori units 3,4 and 1.19% for Yonggwang units 1,2 when the surveillance test interval is increased. The analysis report was submitted to regulatory body and the approval of relaxation of STI was obtained recently. 5 refs., 4 tabs

Part of:
The 21st KAIF-JAIF seminar on nuclear industry

Additional details

Publishing Information

Imprint Title
The 21st KAIF-JAIF seminar on nuclear industry
Imprint Pagination
444 p.
Journal Page Range
p. 71-78

Conference

Title
21. KAIF-JAIF seminar on nuclear industry
Dates
18-19 Oct 1999
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
31000728
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
PARAMETRIC ANALYSIS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REPUBLIC OF KOREA; RISK ASSESSMENT; SAFETY ANALYSIS; STEAM GENERATORS
Descriptors DEC
ASIA; BOILERS; DEVELOPING COUNTRIES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information