NRC test results and operations experience provide insights for new gate valve thrust equation
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (United States)
Description
The Idaho National Engineering Laboratory (INEL) is performing motor-operated valve (MOV) research in support of the US Nuclear Regulatory Commission's (NRC's) efforts regarding Generic Issue 87, 'Failure of HPCI (High-Pressure Coolant Injection) Steam Line Without Isolation,' and Generic Letter 89-10 (GL 89-10), 'Safety-Related Motor-Operated Valve Testing and Surveillance.' This paper presents the results of testing to assess valve and motor operator performance under varying pressures and fluid conditions. This effort included an examination of the methods used by the industry for predicting required valve thrusts and research to provide guidelines for the extrapolation of in situ test results to design basis conditions. This research has identified several inconsistencies in the existing industry stem thrust equation and challenged the overly simplistic assumptions inherent in the use of the equation. This paper discusses development of a new equation whereby conservative stem thrust estimates can be calculated for some flexwedge gate valves, that is, those classes of valves whose operational characteristics have been shown to be predictable. The authors also present a method whereby the results of testing of such valves at low differential pressure can be used to estimate valve response at up to design basis conditions
Files
Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 7.11.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059450
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COOLANT CLEANUP SYSTEMS; FAILURES; HIGH PRESSURE COOLANT INJECTIO; IDAHO NATIONAL ENGINEERING LAB; MONITORING; PERFORMANCE; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RESEARCH PROGRAMS; STEAM; US NRC; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-911079--.