A new methodology to identify Structures, Systems, and Components needed to cope with Design Extended Conditions in the scope of a Nuclear Power Plant Long Term Operation

Autores/as

DOI:

https://doi.org/10.15392/2319-0612.2024.2636

Palabras clave:

Desing Extended Condition, Long Term Operation, NPP, Aging Management

Resumen

To obtain the License Renewal (LR) for the Long-Term Operation (LTO) of a Nuclear Power Plants (NPPs) is important ensuring the integrity of Structures, Systems, and Components (SSCs). Additionally, the SSCs must continue to perform their intended functions under Design Extended Conditions (DEC). DEC encompasses a wide range of conditions beyond the design basis, including both severe and non-severe scenarios. The ageing process can compromise the intended functions of SSCs in a NPP. NPPs must demonstrate their ability to cope with DEC without compromising safety. The objective of this paper is to describe one methodology have been developed to identify SSCs with scope of LR needed to cope with the DEC in LTO. The proposed methodology follows the recommendation of U.S. Nuclear Regulatory Commission (NRC) requirements and the International Atomic Energy Agency (IAEA) safety standards and demonstrating their commitment to safety and environmental protection. The main contributions of the new methodology is to identify the systems, components and subcomponents needed to cope with design extensions conditions  that not  have Maintenance Program (MP) or Aging Management Program (AMP) and address these components in the plant level AMP or recommend an Aging Managements Review (AMR) according to their characteristic and function. Accomplish the intended safety functions of SSCs throughout the plant's operational lifetime including during LTO is crucial to safety and reliable operation of the plant. An example of application of the proposed methodology is presented.

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Biografía del autor/a

  • Jorge Armando P. Junior, Eletronuclear

    Líder Técnico do Projeto de Extensão de Vida Útil da Usina de Angra 1

Referencias

[1] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Nuclear Power Plants: Design, International Atomic Energy Agency, IAEA Safety Standards Series No. SSR 2/1 (Rev.1), IAEA. Vienna, Austria, 2016.

[2] UNITED STATES NUCLEAR REGULATORY COMMISSION. Chapter 19. Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition - Severe Accidents, NUREG-0800, U.S. NRC, 2015.

[3] INTERNATIONAL ATOMIC ENERGY AGENCY, Design Extension Conditions and the Concept of Practical Elimination in the Design of Nuclear Power Plants, IAEA Safety Standards Series No. SSG-88, IAEA, Vienna, Austria, 2023.

[4] INTERNATIONAL ATOMIC ENERGY AGENCY, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants, IAEA Safety Standards Series No. SSG-48, IAEA, Vienna, Austria, 2018.

[5] NUCLEAR ENERGY INSTITUTE, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 4, U. S. NEI 12-06, Washington D.C., August, 2016.

[6] UNITED STATES NUCLEAR REGULATORY COMMISSION, Regulatory Guide 1.226 Rev.0, Flexible Mitigation Strategies for Beyond-Design-Basis Events, U.S. NRC, Washington, DC, 2019.

[7] 10 CFR 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, U.S. U.S. Code of Federal Regulations (CFR), Title 10, Part 54, January 1, 2016.

[8] 10 CFR 65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants, U.S. Code of Federal Regulations (CFR), Title 10, Part 65. January 1, 1999.

[9] UNITED STATES NUCLEAR REGULATORY COMMISSION. Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, NUREG-1800, Rev. 2, U.S. NRC, 2010.

[10] UNITED STATES NUCLEAR REGULATORY COMMISSION. Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, U.S. NRC, 2010.

[11] INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Standards Series No. SSG-30: Safety Classification of Structures, Systems and Components in Nuclear Power Plants, IAEA, Vienna, Austria, 2014.

[12] IAEA-TECDOC-1661, Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants, IAEA, Vienna, Austria, 2011.

[13] NEA/CSNI/R(2014)7, Status Report on Filtered Containment Venting, Nuclear Energy Agency, Committee on Safety of Nuclear Installations, July 2014.

[14] ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, The ASME Boiler and Pressure Vessel Code, 2004 edition as approved in 10 CFR 50.55a, The American Society of Mechanical Engineers, New York, NY 2004.

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Publicado

2025-06-23

Cómo citar

A new methodology to identify Structures, Systems, and Components needed to cope with Design Extended Conditions in the scope of a Nuclear Power Plant Long Term Operation. Brazilian Journal of Radiation Sciences (BJRS), Rio de Janeiro, Brazil, v. 12, n. 4B (Suppl.), p. e2636, 2025. DOI: 10.15392/2319-0612.2024.2636. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/2636. Acesso em: 17 jul. 2025.