Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental

Authors

  • Restu Maerani Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN)
  • Tulis Jojok Suryono Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN)
  • Muhammad Subekti Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia (BATAN)

DOI:

https://doi.org/10.17146/tdm.2019.21.1.5312

Keywords:

Computer-based system, I&C System, Requirements analysis, Licensing, RDE

Abstract

Developing and licensing of digital Instrumentation and control (I&C) system for nuclear power plant (NPP) are challenging especially for the new construction since digital technology are composite with a very high complexity of many integrated systems. National Nuclear Energy Agency of Indonesia (BATAN), who design Reaktor Daya Eksperimental (RDE), should prepare the documents to meet the licensing requirements of national regulator in this case Nuclear Energy Regulatory Agency of Indonesia (BAPETEN). BAPETEN’s chairman regulation No.6 year of 2012 is the first national requirement which state requirements related to design of computer-based system concerning on safety of power reactor that should be followed. Since BAPETEN only denotes requirements without state which code and standards to be used, therefore BATAN can add references from International Nuclear Energy Agency (IAEA) guidelines. In this paper, requirement document traceability is developed to determine which code and standards should be used to verify and validate the I&C computer-based system of RDE. The hierarchy of regulatory and utility requirements are developed to guide the design basis documentation. Developing requirements analysis of computer-based I&C system RDE are completed after determining the design requirements from the utility and regulatory requirements. This methodology will help the design engineers to follow the utility requirements by concerning to the production, and follow the regulatory requirements concerning the safety aspect.

References

Gou F., Chen F., Dong Y. Dynamic response of the HTR-10 under the control rod withdrawal test without scram. Energy Procedia. 2017. 127:247-54.

https://doi.org/10.1016/j.egypro.2017.08.126

IAEA IAEA Nuclear Energy Series No.NP-T1.13, Technical Challenges in the Application and Licensing of Digital Instrumentation and Control Systems in Nuclear Power Plants. Iaea Nuclear Energy Series Publications. 2015.

Andrashov A., Bezsalyi V., Siora A., Sklyar V., Kovalenko A. Implementation of Digital Instrumentation and Control Systems for Nuclear Power Plant using FPGA - Technology : Benefits and Solution. in: ReseLAS-ANS Symposium on Siting of new nuclear power and irradiated fuel facilities. 2013. pp. 24-8.

IAEA Harmonization of the licensing process for digital instrumentation and control systems in nuclear power plants, IAEA - TECDOC - 1327. 2002.

Maerani R., Mayaka J.K., Jung J.C. Software Verification Process and Methodology for the Development of FPGA-based Engineered Safety Features System. Nucl. Eng. Des. 2018. 330(April):325-31.

https://doi.org/10.1016/j.nucengdes.2018.02.009

Yih S., Fan C.-F. Analyzing the Decision Making Process of Certifying Digital Control Systems of Nuclear Power Plants. Nucl. Eng. Des. 2012. 242:379-88.

https://doi.org/10.1016/j.nucengdes.2011.10.010

US.NRC Guidance for Developing Principal Design Criteria for Non-Light Water Reactor, Regulatory Guice 1.232. Rev 0. 2018.

Mcdowell B., Mitchell M., Pugh R., Nickolaus J., Swearingen G. High Temperature Gas Reactors : Assessment of Applicable Codes and Standards. U.S. Nuclear Regulatory Commission Regulations Pacific Northwest National Laboratory. 2011.

https://doi.org/10.2172/1031438

Theron W., Matzner D., Erasmus L. The Pebble Bed Modular Reactor and the Usage of Systems Engineering to Establish New Standards for the Nuclear Revival. in: IFAC Proceedings Volumes (IFAC-PapersOnline). 2007. pp. 1-7.

https://doi.org/10.3182/20070822-3-ZA-2920.00002

Ball S.J., Cetiner M.S., Holcomb D.E. Task 1 - Instrumentation in Vhtrs for Process Heat Applications. 2010.

U.S.NRC Standard Review Plan Appendix 7.1- A, Acceptance Criteria and Guidelines for Instrumentation and Control Systems Important to Safety. NUREG-75/087. 2005.

Jung J.C. Fundamentals of Systems Engineering, Requirements Analysis. in: kepco International Nuclear Graduate School. 2017.

S.J.Ball, Holcomb D.E., Cetiner S.M. HTGR Measurements and Instrumentation Systems. 2012.

https://doi.org/10.2172/1040751

Tyobeka B., Reitsma F. Results of the IAEA CRP5 - Benchmark Analysis Related To the PBMR-400, PBMM, GT-MHR, HTR-10 and the Astra Critical. in: PHYSOR 2010 - Advances in Reactor Physics to Power the Nuclear Renaissance. 2010.

Xu Y. The HTR-10 Project and its Further Development. Inst. Nucl. energy Technol. Tsinghua Univ. Beijing, China 1. 2000.(1):1- 8.

Kumar L., Rajput H. Ensuring Safety in Design of Safety Critical Computer based Systems. Ann. Nucl. Energy. 2016. 92:289-94.

https://doi.org/10.1016/j.anucene.2016.02.002

IAEA Safety Standards, Specific Safety Guide No.SSG-39, Design of Instrumentation and Control Systems for Nuclear Power Plants. 2016.

Bapeten Peraturan Kepala Badan Pengawas Tenaga Nuklir Nomor 6 tahun 2012 tentang Desain Sistem yang Penting Untuk Keselamatan Berbasis Komputer pada Reaktor Daya.

Maerani R., Saharudin, Sudarno, Santoso S., Deswandri, Bakhri S., et al. Developing Digital Instrumentation and Control System for Experimental Power Reactor by Following IEEE Std 1012 TM - 2004 to be Verified and Validated . in: The 2nd International Conference on Energy Science ( to be published). 2018.

Santoso S., Maerani R., Situmorang J., Cahyono A. Software requirement analysis for digital based reactor protection system of RDE design. in: Symposium of Emerging Nuclear Technology and Engineering Novelty (to be published). 2018.

https://doi.org/10.1088/1742-6596/1198/2/022046

US. NRC Software Requirement Specification for Digital Computer Software and Complex Electronics Used in Safety System of Nuclear Power Plants. in: Regulatory Guide 1.172. 2013.

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Published

2019-02-22

How to Cite

Maerani, R., Suryono, T. J., & Subekti, M. (2019). Requirement Analysis of Computer-Based Instrumentation and Control System for Reaktor Daya Eksperimental. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 21(1), 39–46. https://doi.org/10.17146/tdm.2019.21.1.5312