Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Musicki, Z.

doi:10.2172/146733

Cited by 6 publications

(4 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Kim and Jung [2003] collected approximately 220 PSFs from existing taxonomies and other literature in order to form a new full-set PSF taxonomy. They reviewed seven detailed sets of PSFs (which they call fullset PIFs): CSNI taxonomy [Rasmussen et al 1981], THERP [Swain and Guttman 1983], HEART [Williams 1988], PHECA [Whalley 1987], PSF taxonomy [Bellamy 1991], Influencing factors [Gerdes 1997], K-HPES [KEPRI 1998] and eleven taxonomies used in HRA methods: SLIM [Embrey et al 1984] & PLG-SLIM [Chu et al 1994], INTENT [Gertman et al 1992], IDA [Phillips et al 1990], HRMS [Kirwan 1997], Macwan's [Macwan and Mosleh 1994], Julius' [Julius et al 1995], CREAM [Hollnagel 1998], INCORECT [Kontogiannis 1997], Taylor-Adams' [Taylor-Adams 1995], Rogers' [Gibson et al 1998], and ATHEANA [USNRC 2000]. They collated the PSFs into four main groups, which they defined as follows:…”

Section: Guidance On Psfsmentioning

confidence: 99%

Effects of digitalization of nuclear power plant control rooms on human reliability analysis – A review

Porthin

Liinasuo

Kling

2020

Reliability Engineering & System Safety

View full text Add to dashboard Cite

The changes in the operating conditions of the main control room of nuclear power plants due to new digitalized human-system interfaces (HSIs) pose challenges to traditional human reliability analysis (HRA) methods. This paper reviews current knowledge about the effect of digital HSI on human behaviour and reliability, relevant performance shaping factor (PSF) taxonomies as well as research on the effect of PSFs on human error probability estimates in advanced control rooms (ACRs). It cannot be generally concluded that either analogue or digitalized control rooms would be always better than the other. ACRs have the potential to offer error reducing and supportive features to the user, but may also introduce increased complexity and interface management tasks as well as potentially error-prone team working practices. Some effects seem universal, but most depend on the specific design. The main PSF categories presented in HRA methods and international guidelines seem still relevant in ACRs. Quantitative empirical studies show that especially training and experience, availability and quality of procedures as well as task type or complexity are important factors. However, digitalization changes the way in which the PSFs should be defined and measured, and the effects of PSFs on the error estimates may be different.

show abstract

Section: Guidance On Psfsmentioning

confidence: 99%

Effects of digitalization of nuclear power plant control rooms on human reliability analysis – A review

Porthin

Liinasuo

Kling

2020

Reliability Engineering & System Safety

View full text Add to dashboard Cite

show abstract

“…POS is a discrete NPP condition during low power and shutdown state; it is based on the reactor coolant system parameters (e.g., pressure and temperature) and other physical plant conditions. POS is characterized in terms of time after shutdown and the duration of the phases as estimated from plant experience [8]. Even if there is no standard format, POS can be separated into 15 states based on the reactor coolant system parameters and the physical plant conditions [9].…”

Section: Step 1: Define Posmentioning

confidence: 99%

“…This step may use a definition of POS from the literature, such as NUREG/CR-6144 [8] or IAEA-TECDOC-1144 [11]. For consistency of the PSA, this study uses the same definition as that in the PSA for the OPR1000, as shown in Table 2 [12].…”

mentioning

confidence: 99%

Identification of human-induced initiating events in the low power and shutdown operation using the Commission Error Search and Assessment method

Kim

2015

Nuclear Engineering and Technology

View full text Add to dashboard Cite

a b s t r a c tBackground: Human-induced initiating events, also called Category B actions in human reliability analysis, are operator actions that may lead directly to initiating events. Most conventional probabilistic safety analyses typically assume that the frequency of initiating events also includes the probability of human-induced initiating events. However, some regulatory documents require Category B actions to be specifically analyzed and quantified in probabilistic safety analysis. Methods: An explicit modeling of Category B actions could also potentially lead to important insights into human performance in terms of safety. However, there is no standard procedure to identify Category B actions. This paper describes a systematic procedure to identify Category B actions for low power and shutdown conditions. The procedure includes several steps to determine operator actions that may lead to initiating events in the low power and shutdown stages. Results: These steps are the selection of initiating events, the selection of systems or components, the screening of unlikely operating actions, and the quantification of initiating events. The procedure also provides the detailed instruction for each step, such as operator's action, information required, screening rules, and the outputs. Conclusion: Finally, the applicability of the suggested approach is also investigated by application to a plant example.

show abstract

“…Even with the comparable risks from low power and shutdown (LPSD) operations to those from full-power operations (NSAC, 1985;CEA/IPSN, 1990;EdF, 1991;Chu et al, 1994), LPSD probabilistic safety assessment (PSA) has widely used the methods developed for fullpower PSA due to the lack of the methods for LPSD PSA. Of them, the methods used for thermal-hydraulic 0029-5493/$ -see front matter © 2005 Elsevier B.V. All rights reserved.…”

Section: Introductionmentioning

confidence: 99%

Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR

Son

Shin

Lim

et al. 2005

Nuclear Engineering and Design

View full text Add to dashboard Cite

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Abstract: Portions of this doameat mag be illegible in electronic image products. h a g s are produced fmm the best available original document.

Cited by 6 publications

References 2 publications

Effects of digitalization of nuclear power plant control rooms on human reliability analysis – A review

Effects of digitalization of nuclear power plant control rooms on human reliability analysis – A review

Identification of human-induced initiating events in the low power and shutdown operation using the Commission Error Search and Assessment method

Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR

Contact Info

Product

Resources

About