Nuclear Power Plant Operating Experiences from the IAEA/NEA Incident Reporting System 2015-2017

Nuclear Power Plant Operating Experiences from the IAEA/NEA Incident Reporting System 2015-2017
Foreword
Table of contents
	List of figures
	List of tables
Executive summary
Chapter 1. The International Reporting System  for Operating Experience
	1.1. What is the International Reporting System for Operating Experience?
	1.2. What are the benefits of the IRS?
	1.3. How can the IRS benefit decision makers?
	1.4. How does the IRS work?
		1.4.1. Event reports
		1.4.2. Sharing information
	1.5. How is the IRS used?
		1.5.1. Annual meetings
		1.5.2. Restricted access
		1.5.3. Other systems
		1.5.4. Other activities
	1.6. What has been achieved?
Chapter 2. Description of the three main categories  and of the related subcategories
	2.1. Human performance
	2.2. Equipment issues
	2.3. Management and oversight
Chapter 3. Experience and lessons learnt from  the IRS during the review period
	3.1. Human performance
		3.1.1. Operating practices
			Operating practices – lessons learnt
		3.1.2. Maintenance practices
			Maintenance practices – lessons learnt
			Maintenance practices that impact radiological controls – lessons learnt
		3.1.3. Procedure adherence
			Procedure adherence – lessons learnt
		3.1.4. Training and qualification
			Training and qualification – lessons learnt
	3.2. Equipment issues
		3.2.1. Design and modifications
			Design and modification – lessons learnt
			Design and modification issues related to installation and commissioning – lessons learnt
		3.2.2. Emergency diesel generators
			Emergency diesel generators – lessons learnt
	3.3. Management and oversight
		3.3.1. Maintenance programme
			Maintenance programme – lessons learnt
		3.3.2. Ageing management programme
			Ageing management programme – lessons learnt
		3.3.3. Procedure adequacy
			Procedure adequacy – lessons learnt
		3.3.4. Use of operating experience and implementation of corrective actions
			Use of operating experience and implementation of corrective actions – lessons learnt
		3.3.5. Management of external events
			Management of external events – lessons learnt
		3.3.6. Control of contractors
			Licensee control of contractors – lessons learnt
Chapter 4. Other safety issues
	4.1.  Reports related to management of external events and beyond-design-basis events
		Report #1
		Report #2
	4.2. Reports related to maintenance and ageing management programmes
		Report #1
		Report #2
		Report #3
	4.3. Report related to design and modification
Chapter 5. Conclusions
Glossary1F
	Barrier
	Causal factors
	Common cause failure
	Defence in depth
	Direct/observed cause
	Event
	Failure
	Human errors
	Human factors
	Human performance
	Normal operation
	Nuclear safety (or simply safety)
	Operation
	Operational limits and conditions
	Operating experience
	Precursor
	Prescribed limits (also called authorised limits)
	Protection system
	Quality assurance
	Recovery actions
	Regulatory body
	Residual heat
	Root cause
	Safety culture
	Safety functions
	Safety management system
	Safety systems
	Screening
Endnotes
NEA PUBLICATIONS AND INFORMATION