Key Reference Documents for Basic Knowledge
This section provides important documents for basic knowledge on long term operation of nuclear power plants.
For further information, please contact SKALTO.
Safety Aspects of Nuclear Power Plant Ageing
IAEA-TECDOC 540 on Safety Aspects of Nuclear Power Plant Ageing is a useful reference document, in particular for beginners. It includes a valuable discussion of ageing and NPP safety, equip qualification as a means of defence against common cause failures, and a review of material ageing mechanisms. The discussion deals with effects of ageing on the integrity of defense in depth, component failure rate and system performance. The review of ageing mechanisms includes metals, concrete structures, electronics, polymers and
other non-metals.
Key reference material
The following table shows the name and summary of other key reference documents which are indispensable for those engaged in ageing management activities
| Author, Year | Title | Summary |
| EPRI 1993 | Common Ageing Terminology | Glossary for understanding and managing the aging of nuclear power plant systems, structures and components |
| OECD/NEA 1999 | Glossary of Nuclear Power Plant Ageing | Five-language glossary of terminology to assist utility operators and regulators in OECD countries, and to help readers benefit from international experience |
| US NRC 2001 | Generic Aging Lessons Learned (GALL ) Report NUREG-1801 |
Technical basis document to the Standard Review Plan for License Renewal (SRP-LR); contains generic evaluation of existing nuclear plant programs |
| US NRC 1992 | Insights Gained from Aging Research NUREG-CR-5643 |
Hardware-oriented engineering research programs to identify and resolve technical issues related to the aging systems, structures, and components (SSCs) in operating nuclear power plants |
| European Commission 2001 | Safe Management of NPP Ageing in the European Union; a report of CE/DG XI |
Recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle obtained through a synthesis of the potential ageing mechanisms, their potential effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents |
| IEC 1984 | Qualification of Electrical Items of the Safety System for Nuclear Power Generating Stations IEC 780 |
Describes successively the general qualification process, qualification procedures and methods to be used and the associated documentation, and is applicable to electrical equipment of safety systems used in nuclear power plants. * recently revised “Nuclear power plants - Electrical equipment of the safety system – Qualification” IEC 60780 (Oct. 1998) |
| IEEE 1983 | Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations: IEEE-323-1983 | Basic requirements for qualifying Class 1E equipment with interfaces to be used in nuclear power generating stations, including principles, procedures, and methods of qualification |
| EPRI Holzman, P.M., Silter, G.E. 1992 |
Nuclear Power Plant Equipment Qualification Reference Manual EPRI Rep. TR-100516 |
Reference manual compiling technology, requirements, and experience in the specialized area of qualifying safety-related equipment in nuclear plants for function under both normal operating conditions and adverse environments such as those produced by steam line breaks and earthquakes |
