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Analysis of operating experience data in nuclear power plants. Loss of decay heat removal during reactor shutdown

Technical Report:

Abstract

This report analyzes pressurized water reactor (PWR) and boiling water reactor (BWR) experience involving loss of decay heat removal (DHR) during reactor shutdown. Referring to USNRC`s Licensee Event Reports (LERs), OECD/NEA-IRS reports, etc., we selected 206 loss of DHR events which have occurred in PWRs between 1976 and 1990 and 48 events in BWRs between 1985 and 1990. Analysis of 197 events which have occurred in U.S. PWRs indicates that the following direct causes are major contributions resulting in loss of DHR during reactor shutdown: 1) Inadvertent automatic closure of the suction/isolation valves in residual heat removal (RHR) system, 2) RHR pump cavitation due to air entrainment in reduced coolant inventory condition, and 3) Loss of power to RHR pumps. Human factors deficiencies involving procedural inadequacies and personnel errors were identified as the most significant underlying or root causes of the loss of DHR events. Most of the errors were committed during maintenance, testing and repair works. As for 48 events in U.S. BWRs, the leading category of loss DHR events was the inadvertent automatic closure of the suction/isolation valves in RHR system, most of which were caused by human errors. This report describes the above analysis results and presents  More>>
Authors:
Watanabe, Norio; Hirano, Masashi; Oikawa, Tetsukuni [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Sep 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-143
Reference Number:
SCA: 210200; 210100; 570100; PA: JPN-91:011155; SN: 92000630571
Resource Relation:
Other Information: PBD: Sep 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; BWR TYPE REACTORS; AFTER-HEAT REMOVAL; PWR TYPE REACTORS; FAILURES; PUMPS; REACTOR OPERATION; VALVES; SHUTDOWN; US NRC; NEA; HUMAN FACTORS; 210200; 210100; 570100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED; REAL ACCIDENTS
OSTI ID:
10110897
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92750964; TRN: JP9111155
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
184 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Watanabe, Norio, Hirano, Masashi, and Oikawa, Tetsukuni. Analysis of operating experience data in nuclear power plants. Loss of decay heat removal during reactor shutdown. Japan: N. p., 1991. Web.
Watanabe, Norio, Hirano, Masashi, & Oikawa, Tetsukuni. Analysis of operating experience data in nuclear power plants. Loss of decay heat removal during reactor shutdown. Japan.
Watanabe, Norio, Hirano, Masashi, and Oikawa, Tetsukuni. 1991. "Analysis of operating experience data in nuclear power plants. Loss of decay heat removal during reactor shutdown." Japan.
@misc{etde_10110897,
title = {Analysis of operating experience data in nuclear power plants. Loss of decay heat removal during reactor shutdown}
author = {Watanabe, Norio, Hirano, Masashi, and Oikawa, Tetsukuni}
abstractNote = {This report analyzes pressurized water reactor (PWR) and boiling water reactor (BWR) experience involving loss of decay heat removal (DHR) during reactor shutdown. Referring to USNRC`s Licensee Event Reports (LERs), OECD/NEA-IRS reports, etc., we selected 206 loss of DHR events which have occurred in PWRs between 1976 and 1990 and 48 events in BWRs between 1985 and 1990. Analysis of 197 events which have occurred in U.S. PWRs indicates that the following direct causes are major contributions resulting in loss of DHR during reactor shutdown: 1) Inadvertent automatic closure of the suction/isolation valves in residual heat removal (RHR) system, 2) RHR pump cavitation due to air entrainment in reduced coolant inventory condition, and 3) Loss of power to RHR pumps. Human factors deficiencies involving procedural inadequacies and personnel errors were identified as the most significant underlying or root causes of the loss of DHR events. Most of the errors were committed during maintenance, testing and repair works. As for 48 events in U.S. BWRs, the leading category of loss DHR events was the inadvertent automatic closure of the suction/isolation valves in RHR system, most of which were caused by human errors. This report describes the above analysis results and presents the events description for the selected significant events. As well, the brief descriptions of the 206 events in PWRs and 48 events in BWRs are provided in Appendix. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}