Non-safety piping operability review case study -- Today and tomorrow
Creators
- 1. Cleveland Electric Illuminating Co., Perry, OH (United States)
- 2. Stevenson and Associates, Cleveland, OH (United States)
Description
During a 1993 Outage at the Perry Nuclear Power Station, a condition report was issued which identified potential intersystem loss of water between the Emergency Closed Cooling Water System and the Nuclear Closed Cooling Water System during a design basis event. The review of this condition report indicated that if a SSE (safe shutdown earthquake) event were to occur during a design basis event components important to plant safety could potentially be adversely affected if non-seismic/non-safety portions of the Nuclear Closed Cooling Water System could not maintain pressure boundary integrity as a result of the seismic loadings. Presented in this paper are steps, criteria, and methodology used to demonstrate the seismic acceptability of the affected portion of the Nuclear Closed Cooling Water System Piping. Also discussed are the potential benefits and applicability of a recently developed EPRI non-safety, non-seismic operability procedure. This discussion includes the potential cost savings which could have arisen from application of this recently developed procedure
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1344-4
- Imprint Title
- International pressure vessels and piping codes and standards. Volume 2: Current perspectives; PVP-Volume 313-2
- Imprint Pagination
- 505 p.
- Journal Page Range
- p. 325-330.
Conference
- Title
- Joint ASME/JSME pressure vessels and piping conference.
- Dates
- 23-27 Jul 1995.
- Place
- Honolulu, HI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27015489
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COST; EARTHQUAKES; ECCS; INSPECTION; LOSS OF FLOW; PERRY-1 REACTOR; PERRY-2 REACTOR; PIPES; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; RELIABILITY; SEISMIC EFFECTS; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SEISMIC EVENTS; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950740--.