Published November 1992 | Version v1
Journal article Metadata-only

Application of statistical combination of uncertainties to the Three Mile Island unit 1 flux/flow reactor trip setpoint

Creators

  • 1. GPU Nuclear Corp., Parsippany, NJ (United States)
  • 2. S. Levy Inc., Campbell, CA (United States)
  • 3. Electric Power Research Inst., Palo Alto, CA (United States)

Description

This paper reports on typical reactor trip setpoints which established for the reactor protection system may be unduly restrictive, depending on how the uncertainties are handled in the plant safety analyses. The current deterministic approaches to establishing specific setpoints contain a substantial amount of conservatism, which can be reduced through the use of a statistical combination of uncertainties process. Using this approach for Three Mile Island Unit 1 indicates that the flux/flow trip setpoint can be relaxed to 1.1 from the existing technical specification value of 1.08. This provides an increased plant operating margin and reduction in the probability of spurious scrams

Additional details

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
100
Journal Page Range
p. 152-161.
ISSN
0029-5450
CODEN
NUTYBB

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24027271
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
FLUID FLOW; HEAT FLUX; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; SAFETY ANALYSIS; SCRAM; STATISTICAL MECHANICS; THREE MILE ISLAND-1 REACTOR
Descriptors DEC
ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS