[논문]Determination of Performance Indicator Thresholds Based on Typical PSA Results

Kang, Dae-Il; Kim, Kil-Yoo; Hwang, Mee-Jung; Sung, Key-Yong

Determination of Performance Indicator Thresholds Based on Typical PSA Results 원문보기

Journal of the Korean Nuclear Society = 원자력학회지, v.36 no.6, 2004년, pp.485 - 496

Kang, Dae-Il (Korea Atomic Energy Research Institute) , Kim, Kil-Yoo (Korea Atomic Energy Research Institute) , Hwang, Mee-Jung (Korea Atomic Energy Research Institute) , Sung, Key-Yong (Korea Institute of Nuclear Safety)

Abstract ▼ AI-Helper

Typical probabilistic safety assessment (PSA) results were used to estimate the performance indicator (PI) thresholds of unplanned reactor scram (URS) and safety system unavailability (SSU) for Korean nuclear power plants (NPPs). The changes in core damage frequency (${\Delta}$CDFs) of $10^{-6}/yr$, $10^{-5}/yr$, and $10^{-4}/yr$ were adopted as the risk criteria in setting up the PI thresholds. The PI thresholds for the URS were estimated using information pertaining to the initiating event frequencies, the CDF, and the CDF contribution of each initiating event. The PI thresholds of the SSU were estimated using information on the unavailability, the Fussell-Vesely importance, and the CDF.

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문제 정의

On the other hand, the thresholds for the SSU PI were estimated using information on the component unavailability, the Fussell-Vesely (FV) importance, and the CDF. This study presents an assessment of PI thresholds for Korean NPPs and discusses related problems and proposed resolutions for improvement.

가설 설정

• The Cyan/Yellow and Yellow/Orange thresholds for the SSU PI of the two NPPs are slightly higher than the corresponding KINS thresholds. Thus, the current KINS SSU PI thresholds are set up somewhat conservatively.
• The high pressure safety injection system (HPSIS) PI thresholds of the KINS are very conservatively set up compared to those of the KI NPP. Meanwhile, the HPSIS Green/Cyan threshold of the KINS is optimistically determined compared to that of the K2 NPP.

제안 방법

In light of these circumstances, we carried out a pilot study to estimate the thresholds for the URS and SSU Pls for two representative Korean NPPs. In the previous studies presented in SECY 99-007[8] and NUREG-1753 [4], the thresholds for the URS Pls were determined based on conditional core damage probabilities, while those for the SSU PI were determined by changing the probabilities of the basic events for system fault trees in the PSA models.
In the previous studies presented in SECY 99-007[8] and NUREG-1753 [4], the thresholds for the URS Pls were determined based on conditional core damage probabilities, while those for the SSU PI were determined by changing the probabilities of the basic events for system fault trees in the PSA models. In this study, the thresholds for the URS and the SSU PI were determined based on typical PSA results without additional works for PSA models. The thresholds for the URS PI were estimated using information on the initiating event frequencies, the CDF, and the CDF contributions of each initiating event.
Several previous studies [4, 8] estimated the thresholds of the SSU PI by increasing the probabilities of the basic events modeled in the system fault trees. Iterative works were performed to estimate the unavailabilities of safety systems corresponding to the plant-specific (CDF of 10^-6/yr, 10^-5/yr, and 10^-4/yr. In this study, the component unavailability, the Fussell-Vesely (FV) importance measure, and the CDF were used to determine the SSU PI thresholds.
The thresholds for the SSU PI were established mainly in consideration of the plant's technical specifications. The Cyan/Yellow and the Yellow/Orange thresholds for the URS and SSU Pls were determined based on the corresponding values from the ROP program of the USNRC. Meanwhile, a recent state-of-the-art report of the KINS on Korean Pls [10] indicates that, in the future, PSA would be utilized to determine the PI thresholds for all Korean NPPs.
The ΔCDFs of 10^-6/yr, 10^-5/yr, and 10^-4/yr were adopted as the criteria for setting up the PI thresholds. The PI thresholds for the URS were estimated using information on the initiating event frequencies, the CDF contribution of each initiating event, and the CDF. The PI thresholds of the SSU were estimated using information on the unavailability, the Fussell-Vesely importance, and the CDF.
In this study, the thresholds for the URS and the SSU PI were determined based on typical PSA results without additional works for PSA models. The thresholds for the URS PI were estimated using information on the initiating event frequencies, the CDF, and the CDF contributions of each initiating event. On the other hand, the thresholds for the SSU PI were estimated using information on the component unavailability, the Fussell-Vesely (FV) importance, and the CDF.

대상 데이터

The methodology presented in Section 2 was applied to two representative Korean NPPs. The CDFs of the two selected Korean NPPs are similar.
NPPs. Two representative Korean NPPs were selected for this study. The ΔCDFs of 10^-6/yr, 10^-5/yr, and 10^-4/yr were adopted as the criteria for setting up the PI thresholds.

이론/모형

Iterative works were performed to estimate the unavailabilities of safety systems corresponding to the plant-specific (CDF of 10^-6/yr, 10^-5/yr, and 10^-4/yr. In this study, the component unavailability, the Fussell-Vesely (FV) importance measure, and the CDF were used to determine the SSU PI thresholds.

성능/효과

and 2) the Cyan/Yellow and Yellow/ Orange thresholds for the SSU PI based on typical PSA results are higher than the corresponding KINS thresholds. In order to establish the PI thresholds based on PSAs, it is recommended that the PSA models for all representative Korean reactor types be used.
The study results indicate that significantly different URS thresholds are obtained depending on the analysis method of the initiating events, even if the base CDF values for the two NPPs are similar. In order to resolve this problem, it appears that a unified method to analyze initiating events should be used in the PSAs for all Korean NPPs.

참고문헌 (19)

D.I Kang et aI., 'Development on the Application Technology of Risk-Based Performance Indicator for Korean NPPs (in Korean)', KINS/HR-584, KINS, (2004)
D. I Kang et aI., 'A Study of the State of the Art on the Determination of the Threshold Values of the Performance Indicators for Safety Systems and Initiating Events of Nuclear Power Plants (in Korean)', KAERI/AR-698/2004, KAERI, (2004)
USNRC, 'Rector Oversight Process', NUREG1649.Rev.3, (2000)
USNRC, 'Risk-Based Performance Indicators: Results of Phase I Development.' NUREG-1753, NRC, (2002)
USNRC, 'Reactor Oversight Process SelfAssessment for Calendar Year 2003', SECY04-0053, NRC, (2004)
Patrick W.Baranowsky and Donald A. Dube, 'Mitigating Systems Performance Index', seminar material (presentation to ACRS subcommittees on reliability and PRA, and plant operations), USNRC, (2003)
S. Chakraborty et a!', 'Risk-Based Safety Performance Indicators for Nuclear Power Plants', SMIRT17, Prague, Czech Republic, August 17-22, (2003)
USNRC, 'Recommendations for Reactor Oversight Process Improvements', SECY -99-007, Appendix H, NRC, (1999)
USNRC, 'Recommendations for Reactor Oversight Process Improvements(Follow-up to SECY 99-007)' , SECY-99-007A, NRC, (1999)
USNRC Website, http://www.nrc.gov/ NRR/OVERSIGHT / ASSESS/cornerstone.ht ml
O.H Keum et al. 'Assessment of Nuclear Safety Performance Indicators (in Korean)', KINS-AR/802, KINS, (2002)
KINS Website, http://opis.kins.re.kr/ spix/ spO 1_001_ 00 .jsp ?MENU _ CODESPIX WW03YYO1ZZ01
USNRC, 'An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis' , RG 1.174, (1998)
Michal C. Cheok et aI., 'Use of Importance Measures in Risk-Informed Regulatory Applications', Reliability Engineering and System Safety, Vol. 60, p 213-226, (1998)

상세보기
Wall, I.B and Worledge, D. H., 'Some Perspectives on Risk Importance Measures', In Proceedings of PSA '96, p 203-208, Park City Utah, September 29-0ctober 3, (1996)
Kil-You Kim et aI., 'A Study on Importance Measures for Risk-Informed Regulation & Applications (in Korean)', KAERI/TR- 2432/2003, KAERI, (2003)
. NRC, 'Draft Overview of the Development of Mitigating Systems Performance Indices (MSPls)' , ADMAS accession number ML031360121, NRC, (2003)
NEI, 'Regulatory Assessment Performance Indicator Guideline', NEI 99-02, Rev. 2, (2002)
Mee-Jung Hwang et al., 'A Study on Maintenance Rule Program and Its Application to Korean NPP(in Korean)' , Rev.1, KAERl/TR-1788/2001, KAERI, (2001)

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Determination of Performance Indicator Thresholds Based on Typical PSA Results 원문보기

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Determination of Performance Indicator Thresholds Based on Typical PSA Results 원문보기

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