Published December 1985 | Version v1
Report

The analysis and evaluation of recent operational experience from the Fort St. Vrain HTGR

  • 1. Oak Ridge National Lab., TN (USA)
  • 2. Nuclear Regulatory Commission, Washington, DC (USA). Office for Analysis and Evaluation of Operational Data

Description

The U.S. Nuclear Regulatory Commission's Office of Analysis and Evaluation of Operational Data has established an extensive program for screening, analyzing, and evaluating the operational experience data from all commercial nuclear power plants in the United States. This program is designed to provide feedback from field experience with actual operating events to the NRC's continuing efforts to assure the public's health and safety. Oak Ridge National Laboratory provides technical assistance to AEOD to evaluate the operating experience for Fort St. Vrain. Water ingress events continued to be a frequent problem caused most often by electrical/control system upsets. The most recent such event was in June 1983, when the circulator upset led to a moisture ingress large enough to cause icing of chillers in the helium purification train but apparently not large enough to be detected as a problem from available analytical monitors. As a result, the reactor was exposed to several hours of undiagnosed levels of ''high'' moisture, loss of purified helium flow to control rod mechanisms and finally a reactor scram in which 6 of 37 control rod pairs failed to insert automatically. Evidence has also been uncovered that high moisture has caused the transport of volatile chlorides throughout the reactor resulting in corrosion of stainless steel control rod cables and possibly hold down bolts used on a helium circulator closure. Moisture has also caused severe leaching of B2O3 contaminant from the reserve shutdown materials, precluding the complete dumping of material during a surveillance test

Part of:
Gas-cooled reactor safety and accident analysis

Additional details

Publishing Information

Imprint Title
Gas-cooled reactor safety and accident analysis
Imprint Pagination
349 p.
Journal Page Range
p. 35-45.
Report number
IAEA-TECDOC--358

Conference

Title
Specialists' meeting on safety and accident analysis for gas-cooled reactors.
Dates
13-15 May 1985.
Place
Oak Ridge, TN (USA).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
17036714
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUXILIARY SYSTEMS; CONTAINMENT BUILDINGS; ELECTRICAL EQUIPMENT; FAILURES; LEAKS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; VRAIN REACTOR
Descriptors DEC
ACCIDENTS; BUILDINGS; CONTAINMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HTGR TYPE REACTORS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY

Optional Information

Contract/Grant/Project number
Contract DE-AC05-84OR-21400
Notes
13 refs.