Skip to main content

Quantitative Analysis of Safety Margin Reduction of Power Uprate in MBLOCA

  • Conference paper
  • First Online:
Proceedings of The 20th Pacific Basin Nuclear Conference (PBNC 2016)

Included in the following conference series:

  • 784 Accesses

Abstract

Nuclear Energy Agency of OECD has developed a methodology in the Safety Margin Action Plan (SMAP) to quantify the reduction of safety margin due to power uprate. The methodology combines the probabilistic and deterministic approaches of safety analyses. In the present study, the SMAP methodology is adopted to quantify the reduction of safety margin of a 5 % power uprate of Maanshan nuclear power plant (NPP) of Taiwan Power Company. The sequence selected to demonstrate the methodology is a medium break cold leg loss of coolant accident. An evaluation model code, RELAP5-3D/K is used in the LOCA analysis. Based on the plant specific PSA model, two dominant accident sequences of the medium LOCA are analyzed. Minimum success criterion of the PSA model is used. Phenomenon Identification and Ranking Table (PIRT) for parameters that are important for the medium break LOCA analyses and their distribution are identified. Two sets of calculations for each accident scenarios are performed to determine PCT at 102 and 105 % rated power. The data of the predicted PCTs are analyzed parametrically and nonparametrically (rank statistics) to determine PCT of the 95th percentile with 95 % of confidence. The results show that the nonparametric results always giving higher 95/95 PCT value and therefore, smaller safety margin. The change of safety margin after SPU is different for different accident scenarios. When the best estimated value is determined parametrically, the safety margin before power uprate is 12.3 and after power uprate is 11.8. There is 4.2 % reduction of safety margin when power is elevated from 102 to 105 % rated power. When the best estimated value is determined nonparametrically, the safety margin before SPU is 10.17 and after SPU is 10.42. The margin increases slightly after SPU. From these results, it can be concluded that the impact of SPU on the safety margin of PCT is very insignificant. The results also demonstrate that, among the parameters in PIRT, the parameter, PBOT, represents the axial power distribution has the largest impact on the predicted PCT. When the power distribution is bottom peaked, the predicted PCT is lower. It can be concluded that the steam cooling effect after core uncover plays a significant role in removing heat from the uncovered portion of the core.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 169.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 219.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. “Safety Margins Action Plan—Final Report”, NEA/CSNI/R(2007)9.

    Google Scholar 

  2. “Appendix K to Part 50—ECCS Evaluation Models”, U.S. NRC, March, 2013.

    Google Scholar 

  3. “Nuclear Plant Power Uprate Safety Analysis Preliminary Report”, Taiwan Power Company, June, 2009.

    Google Scholar 

  4. “Living Probabilistic Risk Assessment of Maanshan Nuclear Power Plant”, Institute of Nuclear Energy Research, Vol. 1, 3-1–3-18, Dec 1995.

    Google Scholar 

  5. “Emergency Operator Procedure 570.00: Reactor Scram or Safety Injection version 10”, Taiwan Power Company, July, 2011.

    Google Scholar 

  6. “Emergency Operator Procedure 570.04: Loss of Coolant at Reactor Vessel or Secondary Side version 5”, Taiwan Power Company, August, 2011.

    Google Scholar 

  7. “Emergency Operator Procedure 570.06: Cooldown and Depressurization version 5”, Taiwan Power Company, July, 2011.

    Google Scholar 

  8. “Living Probabilistic Risk Assessment of Maanshan Nuclear Power Plant”, Institute of Nuclear Energy Research, Vol. 4, C1-21, Dec 1995.

    Google Scholar 

  9. “Best-Estimate Analysis of the Large-Break Loss of Coolant Accident for Maanshan Unit 1 and 2 Nuclear Power Plant Using the ASTRM Methodology”, Westinghouse, June 22, 2009.

    Google Scholar 

  10. Joseph, L. Leva, “A Fast Normal Random Number Generator”, ACM Transactions on Mathematical Software, Vol. 18, No. 4, Dec. 1992, 449–453.

    Google Scholar 

  11. Sukho Lee and Hho-Jung Kim, “Prediction of Loop Seal Formation and Clearing During Small Break Loss of Coolant Accident”, Journal of the Korea Nuclear Society, Vol. 24, No. 3, Sep. 1992.

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Y. M. Chen .

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 2017 Springer Science+Business Media Singapore

About this paper

Cite this paper

Chen, Y.M., Lee, M., Lin, J.D. (2017). Quantitative Analysis of Safety Margin Reduction of Power Uprate in MBLOCA. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2311-8_43

Download citation

  • DOI: https://doi.org/10.1007/978-981-10-2311-8_43

  • Published:

  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-10-2310-1

  • Online ISBN: 978-981-10-2311-8

  • eBook Packages: EnergyEnergy (R0)

Publish with us

Policies and ethics