DOE O 420.1C Chg 3 (LtdChg), Facility Safety - Change Chart

U.S. Department of Energy LIMITED CHANGE Washington, DC Chg 3 (LtdChg): 11-14-2019 SUBJECT: LIMITED CHANGE TO DOE O 420.1C, FACILITY SAFETY 1. EXPLANATION OF CHANGES. This change cancels DOE O 5480.30, Nuclear Reactor Safety Design Criteria, and adds a new section on this topic to Attachment 3. 2. LOCATIONS OF CHANGES: Page Paragraph Changed To 1 2 This Order (O) cancels: DOE O 420.1B, Chg. 1, Facility Safety; DOE Guide (G) 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and Nonnuclear Facilities; and DOE G 420.1-3, Implementation Guide for DOE Fire Protection and Emergency Services Programs for Use with DOE O 420.1B, Facility Safety. This Order (O) cancels: DOE O 420.1C Chg. 2, Facility Safety, dated 7-26-18; and DOE O 5480.30 Chg. 1, Nuclear Reactor Safety Design Criteria, dated 3- 14-01. Att. 3 Page 8 Section 3.c. Added. Nuclear Reactor Safety Design Criteria. Nuclear reactors are an important class of DOE facilities that require special attention to design criteria and standards to ensure safe design and operations. (1) The Code of Record for existing DOE nuclear reactors has been established by their designs. When a major modification is made to an existing reactor, the existing Code of Record is the starting point for the design of the major modification, and a design upgrade analysis is required in accordance with DOE-STD-1189-2016 to evaluate the application of nuclear safety design criteria and requirements. This design upgrade analysis may identify updated nuclear reactor safety design criteria and updated codes and standards to be applied to the major modification. (2) For any new DOE nuclear reactor, a set of reactor-specific safety DOE O 420.1C Page Paragraph Changed To design criteria and a set of reactor design codes and standards must be established in accordance with the Safety Design Strategy required by DOE-STD-1189-2016. Existing industry codes and standards should be used to the extent possible. LIMITED CHANGE TO DOE O 420.1C, FACILITY SAFETY 1. EXPLANATION OF CHANGES. 2. LOCATIONS OF CHANGES: FACILITY SAFETY 1. OBJECTIVE a. Nuclear safety design criteria; b. Fire protection; c. Criticality safety; d. Natural phenomena hazards (NPH) mitigation; and, e. Cognizant system engineer (CSE) program. 2. CANCELLATIONS. 3. APPLICABILITY. a. Departmental Applicability. b. DOE Contractors c. Equivalencies and Exemptions. d. Government-Owned, Government-Operated Facilities 4. REQUIREMENTS 5. RESPONSIBILITIES. a. Heads of Departmental Elements, and Administrator, National Nuclear Security Administration. b. Associate Under Secretary, Office of Environment, Health, Safety and Security. c. Director, Office of Enterprise Assessments. d. Heads of Field Elements. e. Contracting Officers. f. Central Technical Authorities. 6. INVOKED STANDARDS 7. APPLICABLE STANDARDS 8. REFERENCES AND ACRONYMS 9. CONTACT ATTACHMENT 1. CONTRACTOR REQUIREMENTS DOCUMENT DOE O 420.1C, FACILITY SAFETY 1. GENERAL REQUIREMENTS. 2. RELIEF FROM REQUIREMENTS, CODES AND STANDARDS. 3. REFERENCES AND ACRONYMS FACILITY SAFETY REQUIREMENTS CHAPTER I. NUCLEAR SAFETY DESIGN CRITERIA 1. OBJECTIVE. 2. APPLICABILITY. 3. REQUIREMENTS. a. Integration of Safety with Design. b. Nuclear Facility Design.

CHAPTER II. FIRE PROTECTION 1. OBJECTIVE a. Minimize the likelihood of occurrence of a fire-related event; b. Minimize the consequence of a fire-related event affecting the public, workers, environment, property and missions; and c. Provide a level of safety protection consistent with the “highly protected risk” class of industrial risks. 2. APPLICABILITY 3. REQUIREMENTS. a. General Fire Protection Program Requirements. b. Fire Protection Program Administration. c. Design. d. Operations. e. Emergency Response. Provide emergency response capabilities, as necessary, to meet site needs as established by the baseline needs assessment (BNA), safety basis requirements, and applicable regulations, codes and standards. f. Fire Hazard Analyses and Facility Assessments. g. Wildland Fire. An integrated site-wide wildland fire management plan, consistent with the Federal Wildland Fire Management Policy, must be developed, provided to DOE Head of Field Element for approval, and implemented in accordance with the relevan... CHAPTER III. NUCLEAR CRITICALITY SAFETY 1. OBJECTIVE 2. APPLICABILITY 3. REQUIREMENTS. CHAPTER IV. NATURAL PHENOMENA HAZARDS MITIGATION 1. OBJECTIVE 2. APPLICABILITY 3. REQUIREMENTS. a. General b. NPH Design Criteria c. NPH Accident Analysis d. Review and Upgrade Requirements for Existing DOE Nuclear Facilities (Hazard Category 1, 2 and 3). e. Seismic Detection f. Post-Natural Phenomena Procedures CHAPTER V. COGNIZANT SYSTEM ENGINEER PROGRAM 1. OBJECTIVE 2. APPLICABILITY 3. REQUIREMENTS. a. General b. CSE Program Coverage. c. Configuration Management. d. CSE Support for Operations and Maintenance. e. CSE Qualification Requirements. ATTACHMENT 3. DESIGN CRITERIA FOR SAFETY STRUCTURES, SYSTEMS, AND COMPONENTS 1. OBJECTIVE 2. APPLICABILITY. 3. REQUIREMENTS Table 1: Codes for Safety Significant and Safety Class Structures Table 2: Codes for Safety Significant and Safety Class Process Equipment Table 3: Codes for Safety Significant and Safety Class Ventilation System Components Table 4: Codes for Safety Significant and Safety Class Handling Equipment Table 5: Codes for Safety Significant and Safety Class Electrical Systems Table 6: IEEE Standards used for Both Safety Significant and Safety Class Electrical Systems, as appropriate ATTACHMENT 4. REFERENCES AND ACRONYMS