The SPAR H human reliability analysis method

David I. Gertman; Harold S. Blackman; Julie L. Marble; Curtis Smith; Ronald L. Boring; Patrick O'Reilly

The SPAR H human reliability analysis method

David I. Gertman
, Harold S. Blackman
, Julie L. Marble
, Curtis Smith
, Ronald L. Boring
, Patrick O'Reilly

Nuclear Safety & Regulatory Research

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

29 Scopus citations

Abstract

This paper presents a simple HRA method for estimating the human error probabilities associated with operator and crew actions and decisions in response to initiating events at commercial U.S. nuclear power plants. The Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method was developed to support development of plant-specific PRA models for the U.S. NRC Office of Regulatory Research and recently has been used to help support the Reactor Oversight Process. SPAR-H addresses the need for the regulator to account for human errors when: (a) performing safety studies such as probabilistic risk analysis; (b) helping to risk-inform the inspection process; (c) reviewing special issues; and (d) helping to risk-inform regulation. The SPAR -H approach decomposes probability into contributions from diagnosis failures and action failures, accounts for the context associated with human failure events by using performance-shaping factors, and dependency assignment to adjust a base-case Human Error Probability, guidance on how to assign the appropriate value of the PSF and offers an adjustment factor to reduce double counting of influencing factors shared by PSFs. This paper discusses development of the method and reviews the application of SPAR-H to a sample problem. Strengths and limitations of the method will also be discussed.

Original language	English
Title of host publication	American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology
Pages	17-24
Number of pages	8
State	Published - 2004
Event	American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology - Columbus, OH, United States Duration: Sep 19 2004 → Sep 22 2004

Publication series

Name	American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology

Conference

Conference	American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology
Country/Territory	United States
City	Columbus, OH
Period	09/19/04 → 09/22/04

Keywords

HRA
Human error
Human reliability analysis
SPAR-H

Cite this

Gertman, D. I., Blackman, H. S., Marble, J. L., Smith, C., Boring, R. L., & O'Reilly, P. (2004). The SPAR H human reliability analysis method. In American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology (pp. 17-24). (American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology).

Gertman, David I. ; Blackman, Harold S. ; Marble, Julie L. et al. / The SPAR H human reliability analysis method. American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology. 2004. pp. 17-24 (American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology).

@inproceedings{da59b4dde2e345f29b29cbe29133cb22,

title = "The SPAR H human reliability analysis method",

abstract = "This paper presents a simple HRA method for estimating the human error probabilities associated with operator and crew actions and decisions in response to initiating events at commercial U.S. nuclear power plants. The Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method was developed to support development of plant-specific PRA models for the U.S. NRC Office of Regulatory Research and recently has been used to help support the Reactor Oversight Process. SPAR-H addresses the need for the regulator to account for human errors when: (a) performing safety studies such as probabilistic risk analysis; (b) helping to risk-inform the inspection process; (c) reviewing special issues; and (d) helping to risk-inform regulation. The SPAR -H approach decomposes probability into contributions from diagnosis failures and action failures, accounts for the context associated with human failure events by using performance-shaping factors, and dependency assignment to adjust a base-case Human Error Probability, guidance on how to assign the appropriate value of the PSF and offers an adjustment factor to reduce double counting of influencing factors shared by PSFs. This paper discusses development of the method and reviews the application of SPAR-H to a sample problem. Strengths and limitations of the method will also be discussed.",

keywords = "HRA, Human error, Human reliability analysis, SPAR-H",

author = "Gertman, \{David I.\} and Blackman, \{Harold S.\} and Marble, \{Julie L.\} and Curtis Smith and Boring, \{Ronald L.\} and Patrick O'Reilly",

year = "2004",

language = "English",

isbn = "0894486888",

series = "American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology",

pages = "17--24",

booktitle = "American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology",

note = "American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology ; Conference date: 19-09-2004 Through 22-09-2004",

}

Gertman, DI, Blackman, HS, Marble, JL, Smith, C, Boring, RL & O'Reilly, P 2004, The SPAR H human reliability analysis method. in American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology. American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology, pp. 17-24, American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology, Columbus, OH, United States, 09/19/04.

The SPAR H human reliability analysis method. / Gertman, David I.; Blackman, Harold S.; Marble, Julie L. et al.
American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology. 2004. p. 17-24 (American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - The SPAR H human reliability analysis method

AU - Gertman, David I.

AU - Blackman, Harold S.

AU - Marble, Julie L.

AU - Smith, Curtis

AU - Boring, Ronald L.

AU - O'Reilly, Patrick

PY - 2004

Y1 - 2004

N2 - This paper presents a simple HRA method for estimating the human error probabilities associated with operator and crew actions and decisions in response to initiating events at commercial U.S. nuclear power plants. The Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method was developed to support development of plant-specific PRA models for the U.S. NRC Office of Regulatory Research and recently has been used to help support the Reactor Oversight Process. SPAR-H addresses the need for the regulator to account for human errors when: (a) performing safety studies such as probabilistic risk analysis; (b) helping to risk-inform the inspection process; (c) reviewing special issues; and (d) helping to risk-inform regulation. The SPAR -H approach decomposes probability into contributions from diagnosis failures and action failures, accounts for the context associated with human failure events by using performance-shaping factors, and dependency assignment to adjust a base-case Human Error Probability, guidance on how to assign the appropriate value of the PSF and offers an adjustment factor to reduce double counting of influencing factors shared by PSFs. This paper discusses development of the method and reviews the application of SPAR-H to a sample problem. Strengths and limitations of the method will also be discussed.

AB - This paper presents a simple HRA method for estimating the human error probabilities associated with operator and crew actions and decisions in response to initiating events at commercial U.S. nuclear power plants. The Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method was developed to support development of plant-specific PRA models for the U.S. NRC Office of Regulatory Research and recently has been used to help support the Reactor Oversight Process. SPAR-H addresses the need for the regulator to account for human errors when: (a) performing safety studies such as probabilistic risk analysis; (b) helping to risk-inform the inspection process; (c) reviewing special issues; and (d) helping to risk-inform regulation. The SPAR -H approach decomposes probability into contributions from diagnosis failures and action failures, accounts for the context associated with human failure events by using performance-shaping factors, and dependency assignment to adjust a base-case Human Error Probability, guidance on how to assign the appropriate value of the PSF and offers an adjustment factor to reduce double counting of influencing factors shared by PSFs. This paper discusses development of the method and reviews the application of SPAR-H to a sample problem. Strengths and limitations of the method will also be discussed.

KW - HRA

KW - Human error

KW - Human reliability analysis

KW - SPAR-H

UR - https://www.scopus.com/pages/publications/32044458186

M3 - Conference contribution

AN - SCOPUS:32044458186

SN - 0894486888

SN - 9780894486883

T3 - American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology

SP - 17

EP - 24

BT - American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology

T2 - American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology

Y2 - 19 September 2004 through 22 September 2004

ER -

Gertman DI, Blackman HS, Marble JL, Smith C, Boring RL, O'Reilly P. The SPAR H human reliability analysis method. In American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology. 2004. p. 17-24. (American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology).

The SPAR H human reliability analysis method

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Keywords

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