Document: NRC Regulatory Guide
Document ID: f90c4bd2-d0e9-4015-81fc-f2cd85a8f58b
Document Type: regulatory_guide
Title: Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0802/ML080220459.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.114
CFR Part: 
CFR Title: 

Content:
U.S. NUCLEAR REGULATORY COMMISSION April 2008 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE Contact: M. Lintz (301) 415-4051 DRAFT REGULATORY GUIDE DG-1194 (Proposed Revision 3 of Regulatory Guide 1.114, dated May 1989) GUIDANCE TO OPERATORS AT THE CONTROLS AND TO SENIOR OPERATORS IN THE CONTROL ROOM OF A NUCLEAR POWER UNIT A. INTRODUCTION This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for complying with the Commission’s regulations that require the presence of an operator at the controls of a nuclear power unit and a senior operator in the control room from which the nuclear power unit is being operated. In addition, this guide clarifies and provides guidance on the acceptable boundaries of the control room. The “vital area,” as identified in Title 10 Section 73.2, “Definitions,” of the Code of Federal Regulation (10 CFR 73.2), and 10 CFR 73.55(c) serves as the basis for the “control room vital area” as used in this regulatory guide. The regulation at 10 CFR 50.54(k) requires that an operator or senior operator licensed pursuant to 10 CFR Part 55, “Operators’ Licenses,” be present at the controls at all times during the operation of a facility. General Design Criterion 19, “Control Room,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” requires, in part, that a control room be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain the nuclear power plant in a safe condition under accident conditions. As defined in 10 CFR 50.2, “Definitions,” and 10 CFR 55.4, “Definitions,” the term “controls,” when used with respect to nuclear reactors, means apparatus and mechanisms, the manipulation of which directly affects the reactivity or power level of the reactor. Under 10