Application of probabilistic safety assessment to the pipe rupture incident at hamaoka unit-1

Journal of Nuclear Science and Technology

Volumn 41, Issue 1, 2004, Pages 77-85

  Kishi, Toru ^a,c   Kikuchi, Hiromu ^a   Miura, Satoshi ^a   Fukuda, Mamoru ^a   Hirano, Mitsumasa ^a   Watanabe, Norio ^b  

^a Nuclear Power Engineering Corp   (Japan)

^b Ministry of International Trade and Industry   (Japan)

^c TOKYO ELECTRIC POWER COMPANY   (Japan)

Author keywords

Core damage frequencies (CDFs); Corrective actions; High pressure injection system (HPCI); Pipe rupture; Probabilistic safety assessment (PSA); Reactor core isolation cooling (RCIC); Residual heat removal system (RHR); Risk significance; Safe operation rules (SORs); Steam condensation mode (STCM)

Indexed keywords

BOILING WATER REACTORS; CONDENSATE TREATMENT; LOSS OF COOLANT ACCIDENTS; NUCLEAR REACTOR LICENSING; RADIOACTIVITY; REACTOR OPERATION; RISK ASSESSMENT; RUPTURE DISKS;

HIGH PRESSURE INJECTION SYSTEM; PIPE RUPTURE INCIDENT; PROBABILISTIC SAFETY ASSESSMENT; RESIDUAL HEAT REMOVAL SYSTEM;

CORE DISRUPTIVE ACCIDENTS;

EID: 1542365173     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9715461     Document Type: Article

References (8)

1. Nuclear Power Engineering Corporation, The Report of the Application of Risk Informed Regulation to Domestic Plants, INS/M00-30, (2001).
2. Nuclear and Industrial Safety Agency, Investigation Report on Pipe Rupture Incident at Hamaoka Nuclear Power Station Unit-1, (2002), [in Japanese].
3. Nuclear Safety Research Association; Study on Probabilistic Safety Assessment (PSA) Procedure—Level 1 PSA, Internal Events, (1995), [in Japanese].
4. Nuclear Power Engineering Corporation, Procedure of BWR level 1 PSA—Level1 PSA Considering Accident Management Measures (BWR-4,3 and ABWR plant), INS/M00-10, (2001), [in Japanese].
5. Nuclear Power Engineering Corporation, The Report of Providing the Procedure of BWR Level 1 PSA—Level1 PSA Considering Accident Management Measures (BWR-5plant), INS/M00-09, (2001), [in Japanese].
6. Annual Report of Nuclear Power Plants, 2001 version (Record of 2000), Thermal And Nuclear Power Engineering Society, (2002), [in Japanese].
7. AD. Swain and HE. Guttman, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278, (1983).
8. Nuclear Power Engineering Corporation, The Report of the Evaluation on the Result of Accident Management Implementation for Light Water Reactors, INS/M02-01, (2002), [in Japanese].