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1、80570 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS-V-VentilationBattery rooms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .E.2.12.1Control room . . .INDEX 80569PSA . . . . . . . . . . . . . . . . . . . .see Probabilistic safety assessment (PSA)Pump r。
2、ooms, nuclear-safety-related . . . . . . . . . . . . . . . . . . . . . . E.2.16PumpsFire . . . 80568 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSPerformance criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.5.3Shutdown facilities . . . . . . . INDEX 8。
3、0567Fire protection systems. . . . . . . . . . . . . . 2.4.1.4(d), A.3.1； see also Firesuppression systemsAcetylene-oxygen fuel gases . . . . . . . . . . . . . . . . . . . . . . . . . . . E.2.80566 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSDocumentation . . . . . . . . . . . 。
4、. . . . . . . . . . . . . . . . . .2.2(j), 2.2.11, 2.7.1Design basis document. . . . . . . INDEX 80565exAsn tdIn fire scenarios . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1.4(a)In-situ. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80564 FIRE 。
5、PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSAppendix F Referenced PublicationsF.1 The following documents or portions thereof are refer-enced within this standard for infoAPPENDIX E 80563E.2.19 Rad Waste and Decontamination Areas. Fire barriers,fire detection, and automatic fire sup。
6、pression should be pro-vided as determined by the fire hazards analysis. Manual ven-til80562 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS(c) Hydrogen in Safety-Related Areas. The requirements forhydrogen in safety related areas should comply with the fol-lowing.(1APPENDIX E 805。
7、61a direct fire exposure hazard to the fire barrier. Smoke andheat vents or sprinkler protection at the roof level can be nec-essary to protect the turbine building structure.E.2.13.2 B80560 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSbe designed for a density of 0.30 gpm/ft2(1。
8、2.2 L/min m2)over the most remote 2500 ft2(232.2 m2). Deluge and waterspray systemAPPENDIX E 80559E.2.3 Fire Detection. A general area fire detection capabilityshould be provided in the primary containment as a backupfor the hazard detection described above. To accomplish this,sui80558 FIRE PROTECTI。
9、ON FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSStaNon-inerted containmentReactor coolant pumpsPrimary and secondary containment refueling and maintenance:Transient combustiAPPENDIX D 80557can be used in this determination. In general, POSs at or nearthe risk level of full power operations are 。
10、considered high-riskevolutions. POSs at risk levels significantly below the f80556 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS(4) The analysis should explicitly account for the effect offire-induced environmental conditions (e.g., smoke) onthe effectiveAPPENDIX D 80555(f) Huma。
11、n error probabilities used in quantitative screen-ing should reflect the assumed conditions associated with thefire scenario, that is, fire and growth, resulting in direct and80554 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSA fire PSA is generally performed in stages. Each sta。
12、ge ofthe analysis represents an escalation of the level of detail con-sideAPPENDIX D 80553(6) Mowrer, F.W., and D.W. Stroup, “Features, Limitations, andUncertainties in Enclosure Fire Hazard Analyses Prelim-inary Review,” NISTIR 6152, National Institute of Standardsand T80552 FIRE PROTECTION FOR LIG。
13、HT WATER REACTOR ELECTRIC GENERATING PLANTSC.4.4 Threshold for Thermal Damage to Equipment. Failuresof equipment exposed to the harsh environment of a fire andthe subsequAPPENDIX C 80551Experimental data are widely used and provided as input to which is consistent with the reported data.Experimental。
14、 data used for verification or validation of firemodels as well as fo80550 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSC.3.5 Fire Event Tree and Other Analytical Tools. In thecontext of this standard, a fire scenario should not be con-fused withAPPENDIX C 80549Table C.3.4 Poten。
15、tial Fire ScenariosFuel Ignition Source Type Area Fuel Ignition Source Type AreaLube oil1Contact with hot piping surfaceContainment Core expansion materialHot work Se80548 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSperforming fire modeling calculations. The ventilation vari-ab。
16、le is a good example. Most NPPs rely on manual operatoractions ofAPPENDIX C 80547them from compartment to compartment. Most of the pro-grams listed on Table C.2.2(b) will perform that task.O2(Oxygen) Depletion. Refers to whether the programwill shut off or otherwi80546 FIRE PROTECTION FOR LIGHT WATE。
17、R REACTOR ELECTRIC GENERATING PLANTSM. A. Azarm Dey, R. Travis, G. Martinez-Guridi, andR. Levine reviewed and provided descriptions of some of thecurrent state-of-APPENDIX C 80545Plume/ceiling jet sublayer Yes Yes/plume only Yes From conservation lawsMechanical ventilation Yes Yes Yes YesTargets Yes。
18、 Yes Yes YesFire SourcesTypes 1. Gas 1. Gas2. Pool3. Solid1. G80544 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSIenemodel； therefore, the selection of representative heat releaserate characteristic (i.e., design fire) is critical in obtainAPPENDIX C 80543adequately satisfied. T。
19、his capability assessment should con-sist of a review of the plants technical specifications (TS)and administrative control practices, outage planning andasses80542 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSperformed, and the time constraints to perform the recoveryactions sh。
20、ould be obtained to assess the feasibility of the pro-poseAPPENDIX B 80541B.5.1 Methodology.Step 1: Identification of Affected Systems and Components. All unpro-tected cables and equipment within a fire area could be affectedby the fire. This does not imply80540 FIRE PROTECTION FOR LIGHT WATER REACT。
21、OR ELECTRIC GENERATING PLANTSFIGURE B.3.4(c) Common enclosure issues current transformer secondaries.B.3.4.1 Considerations When Evaluating Common PowerSuAPPENDIX B 80539FIGURE B.3.4(a) Common power supply issues. A type of common enclosure failure mode is that of second-ary ignition. As shown in Fi。
22、gure B.3.4(b), the fire at instru-ment Bus B induces 80538 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSFIGURE B.3.3(g) Ungrounded system multiple shorts to ground Part 1.FIGURE B.3.3(h) Underground system multiple shorts to APPENDIX B 80537FIGURE B.3.3(a) Instrumentation circui。
23、ts.FIGURE B.3.3(b) Open circuit.FIGURE B.3.3(c) Short to ground.IndicatorProtectionsystem/interlockPowersupply24 VdcCurrentsignalShortATransmitte80536 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS(b) During the process of identifying required nuclearsafety circuits, a hot short 。
24、circuit failure on the appropriateconductor(APPENDIX B 80535(b) To develop a nuclear safety equipment list (NSEL) in aconsistent and reproducible manner, the following should beconsidered.(1) Valves/dampers constituting system boundaries shoul80534 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GE。
25、NERATING PLANTSStep 2: System Interrelationships. The selection of systemsand the documentation of how these systems fulfill thenuclear safetyAPPENDIX B 80533A.5.2 Decommissioning sites should have their proceduresroutinely reviewed by representatives of the industrial fire bri-gade response forces 。
26、and cognizant fire protection engineer-in80532 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSThe ERFBS should meet other design-basis requirementsincluding seismic position retention and ampacity derating ofelectrical caAPPENDIX A 80531and use of equipment. Unannounced industrial。
27、 fire brigadedrills are to be used specifically to evaluate the fire-fightingreadiness of the industrial fire brigade, industrial fire brig80530 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSA.3.3.1.3.4 The administrative procedures should include amethod to control the use of el。
28、ectric heaters so that only thosethat APPENDIX A 80529local level could be responsible for life safety. The insurancecoverage provider or the owner/operator can be the AHJ forplant damage/business interruption aspects of the program.To e80528 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATI。
29、NG PLANTSThe following factors are helpful in determining theacceptability of the individual method or source:(1) Extent of general acceAPPENDIX A 80527www.bzfxw.comThe general understanding on the issue of smoke damageis described as follows.(a) Smoke, depending on what is in it such as HCl frombur。
30、ning polyvinyl chloride (PVC) insu80526 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.comFor nuclear safety, defense-in-depth is accomplished byachieving a balance of the following:(1) Preventing core daAPPENDIX A 80525www.bzfxw.com(l) Carefully review and describe the 。
31、control and operat-ing room areas and the protection and extinguishing systemsprovided thereto. Do not overlook the extra facilities80524 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.comFor fire protection, defense-in-depth is accomplished byachieving a balance of the 。
32、following:(1) Preventing fires APPENDIX A 80523www.bzfxw.comA.1.5.4 Determination of the acceptable levels of damage anddowntime for systems and structures that are not related tonuclear safety and that do not impact the plants a80522 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANT。
33、Swww.bzfxw.com5.3.5.4 Industrial fire brigade drills and training shall be per-formed commensurate with the hazard. The off-siteFIRE PROTECTION DURING DECOMMISSIONING AND PERMANENT SHUTDOWN 80521www.bzfxw.com4.3.1 Deterministic Approach. The protection specified in4.2.3.4 shall provide an acceptable。
34、 deterministic method forra80520 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.com4.2.3 Deterministic Approach. This section shall providedeterministic methods to meet the nuclear safety perfor-maDETERMINATION OF FIRE PROTECTION SYSTEMS AND FEATURES 80519Chapter 4 Deter。
35、mination of Fire Protection Systems and Features4.2 Nuclear Safety. 4.2.1 Free of Fire Damage. One success path necessary to80518 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.com3.10.5 Provisions for locally disarming automatic gaseous sup-pression systems shall be sec。
36、ured and under strict aFUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN ELEMENTS 80517www.bzfxw.com3.6.3 The proper type of hose nozzle to be supplied to eachpower block area shall be based on the area fire hazards. Theusual80516 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bz。
37、fxw.comaccordance with NFPA 13, Standard for the Installation of SprinklerSystems, or NFPA 15, Standard for Water Spray FFUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN ELEMENTS 80515www.bzfxw.comof five persons on duty and shall conform with the followingNFPA standards as applicable:(1) NFPA 600, St。
38、andard on Industrial80514 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.com3.3.1.3 Control of Ignition Sources.3.3.1.3.1* A hot work safety procedure shall be developed,implemented, and perFUNDAMENTAL FIRE PROTECTION PROGRAM AND DESIGN ELEMENTS 80513www.bzfxw.comChapter。
39、 3 Fundamental Fire Protection Program and Design Elements3.1* General. This chapter contains the fundamental ele-men80512 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.comThe impact of the proposed change shall be monitored (seeSection 2.6).2.4.4.1* Risk Acceptance Cri。
40、teria. The changMETHODOLOGY 80511www.bzfxw.com(b) Ignition Sources. The potential in situ and transient igni-tion sources shall be considered for the plant area. For firemodeling purposes, the combustibles shall be 80510 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSFIGURE 2.4 En。
41、gineering analysis.2001 Editionwww.bzfxw.comPerformance-Based ApproachEvaluate ability to satisfy performance requMETHODOLOGY 8059www.bzfxw.com2.2.1 Fundamental Fire Protection Program and Design Ele-ments. The fundamental fire protection program and designelements shall include the fire protection 。
42、features and 8058 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSFIGURE 2.2 Methodology.Establish fundamental fireprotection elements(Chapter 3)Identify fire hazards2001 Editionwww.bzfxw.comIdeMETHODOLOGY 8057www.bzfxw.com1.6.48 Probable Maximum Loss (PML). The loss due to asingle。
43、 fire scenario, which assumes an impairment to one sup-pression system and a possible delay in manual fire-figh8056 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.com1.6.26* Fire Zone. A subdivision of a fire area not necessarilybounded by fire-rated assemblies. Fire zon。
44、e can alsoINTRODUCTION 8055www.bzfxw.com1.5.3 Life Safety Criteria. The following performance crite-ria shall be met during all operational modes and plant con-figurations:(1) Provide safe egress and/or area o8054 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTSwww.bzfxw.comNFPA 80。
45、5Performance-Based Standard forFire Protection for Light Water ReactorElectric Generating Plants2001 Editiowww.bzfxw.comCONTENTS 80532001 EditionContentsChapter 1 Introduction. . . . . . . . . . . . . . . . . . . . . . . . . 80541.1 Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .。
46、 . 8052 FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS2001Technical Committee on Fire Protection for Nuclear FacilitiesWayne D. Holmes, Chair HSB Professional Loss Control, CT IRic8051www.bzfxw.comCopyright 2001 NFPA, All Rights ReservedNFPA 805Performance-Based Standard forFire 。
47、Protection for Light Water Reactor Electric Generating Plants2001 EditionThis edition of NFPA 805www.bzfxw.com8/00Licensing PolicyThis document is copyrighted by the National Fire Protection Association (NFPA). By making this documentavailable for use and adoption by public authorities and others8/0。
48、0Copyright NFPAOne Batterymarch ParkQuincy, Massachusetts 02269IMPORTANT NOTICE ABOUT THIS DOCUMENTNFPA codes, standards, recommended practices, and guides, of which the document contained herein NFPA 805Performance-BasedStandard forFire Protectionfor Light Water ReactorElectric Generating Plants2001 EditionNFPA, 1 Batterymarch Park, PO Box 9101, Quincy, MA 02269-9101An International Codes and。
