Safety significance of inadvertent operation of motor operated valves in nuclear power plants
Conference
·
OSTI ID:10151337
This report addresses concerns about the consequences of valve mispositioning which were brought to the forefront following an event at Davis Besse in 1985 (NRC, 1985a). The concern related to the ability to reposition ``position changeable`` motor operated valves (MOVs) in the event of their inadvertent operation from the control room and was documented in Nuclear Regulatory Commission (NRC) Bulletin 85-03 (NRC, 1985b) and Generic Letter (GL) 89-10 (NRC, 1989). The mispositioned MOVs may not be able to be returned to their required position due to high differential pressure (dP) or high flow conditions across the valves. The inability to reposition such valves may have significant safety consequences as in the Davis Besse event. However, full consideration of such mispositioning in safety analyses and in MOV test programs can be labor intensive and expensive. Industry raised concerns that consideration of position changeable valves under GL 89-10 would not decrease the probability of core damage to an extent which would justify licensee costs. As a response, Brookhaven National Laboratory (BNL) has conducted separate scoping studies for both Boiling Water Reactors (BWRS) and Pressurized Water Reactors (PWRs) using Probabilistic Risk Assessment (PRA) techniques to determine if such valve mispositioning by itself is significant to safety. The approach utilized internal events PRA models to survey the order of magnitude of the risk significance of valve mispositioning by considering the failure of selected position changeable MOVS. The change in core damage frequency (CDF) was determined for each valve considered and the results were presented as a risk increase ratio for each of four assumed MOV failure rates. The risk increase ratios resulting from this failure rate sensitivity study can be used as a basis for a judgement determination of the risk significance of the MOV mispositioning issue for BWRs and PWRS.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10151337
- Report Number(s):
- BNL-NUREG--60231; CONF-940774--1; ON: DE94011924
- Country of Publication:
- United States
- Language:
- English
Similar Records
Long-term performance of motor-operated valves
Motor-Operated Valve Importance Categorization Study Using Level 1 Internal Event PSA
Auxiliary feedwater system risk-based inspection guidance for the Davis-Besse nuclear power plant
Conference
·
Sat Nov 30 23:00:00 EST 1996
·
OSTI ID:402024
Motor-Operated Valve Importance Categorization Study Using Level 1 Internal Event PSA
Conference
·
Mon Jul 01 00:00:00 EDT 2002
·
OSTI ID:21070078
Auxiliary feedwater system risk-based inspection guidance for the Davis-Besse nuclear power plant
Technical Report
·
Wed Sep 01 00:00:00 EDT 1993
·
OSTI ID:10187159
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
FAILURES
OPERATION
POSITIONING
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY ANALYSIS
VALVES
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
FAILURES
OPERATION
POSITIONING
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY ANALYSIS
VALVES