Reactor coolant pump seal failures
Creators
Description
Failures of reactor coolant pump (RCP) seals that could result in a loss-of-coolant accident (LOCA) are of current concern to the Nuclear Regulatory Commission (NRC). This could occur either where leakage through the seals exceeded the capacity of the normal makeup systems, as has occurred in operating plants, or under station blackout conditions where loss of seal cooling represents a common mode failure for all RCPs. The purpose of Generic Issue 23 Reactor Coolant Pump Seal Failures is to evaluate the adequacy of current licensing requirements relating to RCP seal integrity and to determine if further NRC action is necessary to assure that RCP failures and seal auxiliary system failures do not pose an unacceptable risk. The status of the resolution of the issue, the major sources of information for resolving Generic Issue 23, and the three alternative resolutions being evaluated are discussed in this paper
Additional details
Publishing Information
- Imprint Title
- Sixteenth water reactor safety information meeting. Volume 1: Plenary session, Decontamination and decommissioning, License renewal, Human factors, generic issues, Risk analysis/PRA applications, Innovative concepts for increased safety of advanced power reactors
- Imprint Pagination
- 561 p.
- Journal Page Range
- p. 293-298.
- Report number
- NUREG/CP--0097-Vol.1
Conference
- Title
- 16. water reactor safety information meeting.
- Dates
- 24-27 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22019069
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; BNL; BWR TYPE REACTORS; FAILURES; HYDRAULICS; IDAHO NATIONAL ENGINEERING LAB; LOSS OF COOLANT; MAINTENANCE; MANAGEMENT; OUTAGES; PIPES; PRIMARY COOLANT CIRCUITS; PROBABILITY; PUMPS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR MATERIALS; REACTOR SAFETY; RUPTURES; SAFETY ENGINEERING; SEALS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; MATERIALS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8810155--Vol.1.