Document: NUREG-0800
Document ID: eedf1a7c-578e-463a-9608-b06af6312cf1
Document Type: srp
Title: HUMAN FACTORS ENGINEERING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1310/ML13108A095.pdf
Revision Date: 2023-06
Chapter: 18
Section ID: 18.0
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Content:
Human-System Interface Design Review Guidelines,” NUREG-0700, Revision 2. 7. U.S. Nuclear Regulatory Commission, “Human Factors Engineering Program Review Model,” NUREG-0711, Revision 3. 8. U.S. Nuclear Regulatory Commission, “Training Review Criteria and Procedures.” NUREG-1220, Revision 1, 9. U.S. Nuclear Regulatory Commission, “Guidance for the Review of Changes to Human Actions,” NUREG-1764, Revision 1. 10. U.S. Nuclear Regulatory Commission, “Guidelines for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operating Staff Requirements Specified in 10 CFR 50.54(m) - Final Report,” NUREG-1791. 11. U.S. Nuclear Regulatory Commission, “Workload, Situation Awareness, and Teamwork,” NUREG/CR-7190. 12. U.S. Nuclear Regulatory Commission, “Technical Basis for Regulatory Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m),” NUREG/CR-6838. 13. U.S. Nuclear Regulatory Commission, “Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environmental Conditions During and Following an Accident,” Regulatory Guide 1.97. 14. U.S. Nuclear Regulatory Commission, “An Approach to Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Regulatory Guide 1.174. 15. U.S. Nuclear Regulatory Commission, “Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments,” Regulatory Guide 1.187. 16. U.S. Nuclear Regulatory Commission, “Combined License Application for Nuclear Power Plants” (LWR Edition), Regulatory Guide 1.206. 18.0-17 Draft Revision 3 – July 2015 Attachment A Guidance for Evaluating Credited Manual Operator Actions INTRODUCTION This attachment defines a methodology, applicable to both existing and new reactors, for evaluating manual operator actions. This attachment incorporates, with limited changes, the guidance in Section 3 of