1、NFPA 806 Performance-Based Standard for Fire Protection for Advanced Nuclear Reactor Electric Generating Plants Change Process 2015 Edition NFPA, 1 Batterymarch Park, Quincy, MA 02169-7471, USA An International Codes and Standards Organization 1/14ISBN: 978-145591058-8 (Print)ISBN: 978-145591104-2 (
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29、t the NFPA website at www.nfpa.org. All NFPA codes and standards can be viewed at no cost at www.nfpa.org/freeaccess.Copyright 2014 National Fire Protection Association. All Rights Reserved.NFPA806Performance-Based Standard forFire Protection for Advanced Nuclear Reactor Electric GeneratingPlants Ch
30、ange Process2015 EditionThis edition of NFPA 806, Performance-Based Standard for Fire Protection for Advanced NuclearReactor Electric Generating Plants Change Process, was prepared by the Technical Committee onFire Protection for Nuclear Facilities. It was issued by the Standards Council on November
31、 11,2014, with an effective date of December 1, 2014, and supersedes all previous editions.This edition of NFPA 806 was approved as an American National Standard on December 1,2014.Origin and Development of NFPA 806The need for fire protection in nuclear power facilities has been demonstrated in a n
32、um-ber of incidents, including the Browns Ferry Fire in 1975 and other more recent incidents inthe United States and abroad. Probabilistic risk assessments of existing plants have shown thatfire is one of the largest single contributors to the possibility of reactor damage. This docu-ment represents
33、 a comprehensive consensus of baseline fire protection requirements for allaspects of change process for advanced nuclear reactor electric generating plants, includingtheir construction and all phases of operation, such as shutdown, degraded conditions, anddecommissioning.The first edition of NFPA 8
34、06 focused on risk-informed fire protection in advancednuclear plants where any change process is being performed and was based on current indus-try best practices and source materials.The 2015 edition has been edited for consistency with NFPA 805 and to remove referencesto NFPA 251, a withdrawn sta
35、ndard. Changes have been made to include the definitions andrequirements from NFPA 101 and NFPA 1144 on combustible, noncombustible, and limitedcombustible materials.8061NFPA and National Fire Protection Association are registered trademarks of the National Fire Protection Association, Quincy, Massa
36、chusetts 02169.Technical Committee on Fire Protection for Nuclear FacilitiesWilliam B. Till, Jr., ChairSavannah River Nuclear Solutions, LLC, SC UIvan Bolliger, Canadian Nuclear Safety Commission,Canada EJames Bouche, F. E. Moran, Inc., IL MRep. National Fire Sprinkler AssociationCraig P. Christenso
37、n, U.S. Department of Energy, WA EStanford E. Davis, PPL Susquehanna LLC, PA URichard L. Dible, AREVA NP, Inc., TX MEdgar G. Dressler, The Villages, FL IRep. American Nuclear InsurersDavid R. Estrela, Orr Protection Systems, Inc., MA IMNeal T. Hara, CH2M Hill Plateau Remediation Company,WA UDaniel J
38、. Hubert, Janus Fire Systems, IN IMSteven W. Joseph, Xtralis, Inc., OR MRobert Kalantari, EPM, Incorporated, MA SEElizabeth A. Kleinsorg, Kleinsorg Group Risk Services,LLC, NC SENeal W. Krantz, Sr., Krantz Systems (2) objec-tive criteria to assess performance are established based onrisk insights, d
39、eterministic analyses, and/or performance his-tory; (3) plant operators have the flexibility to determine howto meet established performance criteria in ways that will en-courage and reward improved outcomes; and (4) a frameworkexists in which the failure to meet a performance criterion,while undesi
40、rable, will not in and of itself constitute or resultin an immediate safety concern. 805, 20153.3.27 Performance Criteria. Specific measurable or calcu-lable parameters for systems and features that are quantifiedand described in engineering terms. 805, 20153.3.28 Plant Change Evaluation. An evaluat
41、ion performed inthe event of a change to a previously approved fire protectionprogram element or other plant changes that could impactthe fire protection program.3.3.29 PriorDistribution. Probability distribution quantifyingthe analysts state of knowledge regarding the parameter to beestimated prior
42、 to collection of new data. 805, 20153.3.30 Probabilistic Safety Assessment (PSA). A comprehen-sive evaluation of the risk of a facility or process; also referredto as a probabilistic risk assessment (PRA). 805, 20153.3.31* Reliability. The probability that the system, structure,or component of inte
43、rest will perform its specified functionunder given conditions upon demand or for a prescribedtime.3.3.32 Risk. The probability and consequences of an event,as expressed by the “risk triplet” that is the answer to the fol-lowing three questions: (1) What can go wrong? (2) How likelyis it? and (3) Wh
44、at are the consequences if it occurs?8066 FIRE PROTECTION FOR ADVANCED NUCLEAR REACTOR ELECTRIC GENERATING PLANTS CHANGE PROCESS2015 Edition3.3.33 RiskInformed. Consideration of risk insights togetherwith other factors to establish performance requirements thatbetter focus attention on design and op
45、erational issues com-mensurate with their importance to public health and safety.3.3.34 Safe and Stable Conditions. For fuel in the reactor ves-sel, head on and tensioned, safe and stable conditions are de-fined as the ability to maintain Keff 0.99, with a reactor cool-ant temperature at or below th
46、e requirements for hotshutdown for a boiling water reactor and hot standby for apressurized water reactor. For all other configurations, safeand stable conditions are defined as maintaining Keff 0.99and fuel coolant temperature below boiling. 805, 20153.3.35 Site. The contiguous property that makes
47、up anuclear power plant facility. This would include areas bothinside the protected area and the owner-controlled property.805, 20153.3.36 Source Term Limitation. Limiting the source of radia-tion available for release. 805, 20153.3.37* Spurious Operation. An unwanted change in state ofequipment due
48、 to fire-induced faults (e.g., hot shorts, opencircuits, or shorts to ground) on its power or control circuitry.804, 20153.3.38 Uncertainty.3.3.38.1 Completeness Uncertainty. Uncertainty in the pre-dictions of a model due to model scope limitations. Thisuncertainty reflects an unanalyzed contributio
49、n or reduc-tion of risk due to limitations of the available analyticalmethods. 805, 20153.3.38.2 Model Uncertainty. Uncertainty in the predictionsof a model related to the equations in the model beingcorrect, whether or not they are appropriate to the prob-lem being solved, and whether or not they are sufficientlycomplete. 805, 20153.3.38.3 Parameter Uncertainty. Uncertainty in the predic-tions of a model due to uncertainties in the numerical val-ues of the model parameters. 805, 20153.3.39 Uncertainty Analysis. An analysis inten