NFPA 806-2020 Performance-Based Standard for Fire Protection for Advanced Nuclear Reactor Electric Generating Plants Change Process. 2.1 General. The documents or portions thereof listed in this chapter are referenced within this standard and shall be considered part of the requirements of this document. 2.2 NFPA Publications. National Fire Protection Association, 1 Batterymarch Park, Quincy, MA 02169-7471. NFPA 259, Standard Test Method for Potential Heat of Building Materials, 2018 edition. NFPA 804, Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants, 2020 edition. 2.3 Other Publications. 2.3.1 ANS Publications. American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526. ANSI/ANS 58.23, Fire PRA Methodology, 2007. Δ 2.3.2 ASTM Publications. ASTM International, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA 19428-2959. ASTM E84, Standard Test Method for Surface Burning Character‐ istics of Building Materials, 2016. ASTM E136, Standard Test Method for Behavior of Materials in a Vertical Tube Furnace at 750°C, 2016. ASTM E1355, Standard Guide for Evaluating the Predictive Capa‐ bility of Deterministic Fire Models, 2012. ASTM E2652, Standard Test Method for Behavior of Materials in a Tube Furnace with a Cone-Shaped Airfow Stabilizer, at 750°C, 2016. ASTM E2965, Standard Test Method for Determination of Low Levels of Heat Release Rate for Materials and Products Using an Oxygen Consumption Calorimeter, 2016. 2.3.3 NEI Publications. Nuclear Energy Institute, 1201 F St., NW, Suite 1100, Washington, DC 20004-1218. NEI 00-01, Guidance for Post-Fire Safe Shutdown Analysis. Δ 2.3.4 UL Publications. Underwriters Laboratories Inc., 333 Pfngsten Road, Northbrook, IL 60062-2096. UL 723, Standard for Test for Surface Burning Characteristics of Building Materials, 2008, revised 2013. 2.3.5 US Government Publications. US Government Publish‐ ing Offce, 732 North Capitol Street, NW, Washington, DC 20401-0001. Title 10, Code of Federal Regulations, Part 20, “Standards for Protection Against Radiation.” 3.3 General Defnitions. 3.3.1 Action. 3.3.1.1 Compensatory Action. Actions taken if an impair‐ ment to a required system, feature, or component prevents that system, feature, or component from performing its intended function. These actions are a temporary alterna‐ tive means of providing reasonable assurance that the neces‐ sary function will be compensated for during the impairment, or an act to mitigate the consequence of a fre. Compensatory measures include but are not limited to actions such as frewatches, administrative controls, tempo‐ rary systems, and features of components. [805, 2020] 3.3.1.2 Recovery Action. Activities to achieve the nuclear safety performance criteria that take...
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