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{{#Wiki_filter:--U.S. NUCLEAR REGULATORY COMMISSIONJune 1976REGULATORY GUIDEOFFICE OF STANDARDS DEVELOPMENTREGULATORY GUIDE 1.120FIRE PROTECTION GUIDELINES FOR NUCLEAR POWER PLANTSI" INka)USNRC REGULATORY GUIDES Commenis should be sent to the Secretary ot the Commission. U S, Nurlea,Regulatory Guides are issued Io describe and make available to the public Regulatory Commission. Washington. 0 C 20M55. Attention Dfockeling andmethods acceptable to the NRC stall of implementing specific pan. ol the Service SectionCommission's regulations, to delineate techniques used by the staf in evoalu The guides atre Issued in the following ten broad divisionssaing specific problems or postulated accidanls, or to provide guidance to app!.cents. Regulatory Guides are niot substilutes torreggulallort, and compliance I. Powew Reaclors 6 Productswith them Is not required. Methods end solutions difflerenl from those set out in 2. Research and Test Reactors 7 Tranrporletionthe guides will be acceptable It they provid, a beei* for the findings requitel to 3. Fuels and Materials Facilities 8 Occupational Healththe Issuance or continuance olf permit or license by the Co nmmission 4 Environmental and Siting 9 Antitrust ReviewComments and suggestions for improvements in these guides are encouraged 6 Malteials and Plant Protection 10 Generalat all times. and guides will be revised. as appropriate, to accommodate comments and o reflect new information or eipeflenc. However. cuminonts nim Copies of published guides may be obtained by wrttien request indicatilig theIhis guide. I received within about two months alter its Issuance wilt hr par divisions desired 1o thi U S Nuclear Regulatory Commission Washinglton 0 Clicularly uselul in evaluating the need fo, an early revision 2 .Allention. Director. Office of Standards Oevalopment  
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U.S. NUCLEAR REGULATORY COMMISSION                                                                                      June 1976 REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
                                                    REGULATORY GUIDE 1.120
                    FIRE PROTECTION GUIDELINES FOR NUCLEAR POWER PLANTS
                                                              I"       IN
                                                            ka)
                      USNRC REGULATORY GUIDES                                     Commenis should be sent to       the Secretary ot the Commission. U S, Nurlea, Regulatory Guides are issued Io describe and make available to the public         Regulatory Commission. Washington. 0 C         20M55. Attention Dfockeling and methods acceptable to the NRC stall of implementing specific pan. ol the         Service Section Commission's regulations, to delineate techniques used by the staf in evoalu       The guides atre Issued in the following ten broad divisions saing specific problems or postulated accidanls, or to provide guidance to app!.
cents. Regulatory Guides are niot substilutes torreggulallort, and compliance     I. Powew Reaclors                       6 Products with them Is not required. Methods end solutions difflerenl from those set out in 2. Research and Test Reactors           7 Tranrporletion the guides will be acceptable It they provid, a beei* for the findings requitel to 3. Fuels and Materials Facilities       8 Occupational Health the Issuance or continuance olf permit or license by the Co nmmission             4 Environmental and Siting             9 Antitrust Review Comments and suggestions for improvements in these guides are encouraged           6 Malteials and Plant Protection       10 General at all times. and guides will be revised. as appropriate, to accommodate com ments and o reflect new information or eipeflenc. However. cuminonts nim           Copies of published guides may be obtained by wrttien request indicatilig the Ihis guide. I received within about two months alter its Issuance wilt hr par     divisions desired 1o thi U S Nuclear Regulatory Commission Washinglton 0 C
licularly uselul in evaluating the need fo, an early revision                     2     . Allention. Director. Office of Standards Oevalopment


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion 3, "Fire Protection" of Appendix A, "General Design Criteria forNluclear Power Planlts," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"requires that structures, systems, and components important to safety be designed and loc,3ted tominimize, consistent with other safety requirements, the probability and effect of fires andexplosions. Noncombustible and heat-resistant materials are required to be used wherever prac-tical throughout the unit, particularly in locations such as the containment and control room.Criterion 3 also requires that-fire detection and suppression systems of appropriate capacity andcapability be provided and designed to minimize the adverse effect of fires on structures, systems,and components important to safety and that firefighting systems be designed to ensure that theirfailure, rupture, or inadvertent operation does not significantly impair the safety capability ofthese structures, systems, anid components.This guide presents guidelines acceptable to the NRC staff for implementing this criterionin the development of a fire protection program for nuclear power plants. The purpose of thefire protection program is to ensure the capability to shut down the reactor and maintain it in asafe shutdown condition and to minimize radioactive releases to the environment in the event of afire. If designs or methods different from the guidelines presented herein are used, they mustprovide fire protection comparable to that recommended in the guidelines. -jitable bases andjustification should be provided for alternative approaches to establish aL.eptable implementa-tion of General Design Criterion 3.This guide addresses fire protection only for safety-related systems and equipment innuclear power plants. It does not give guidance on separation criteria for redundant cablesystems. Such guidance is included in Regulatory Guide 1.75, "Physical Independence of Elec-trical Systems." Economic and property loss considerations will probably dictate additionalrequirements for the fire protection program.
General Design Criterion 3, "Fire Protection" of Appendix A, "General Design Criteria for Nluclear Power Planlts," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"
requires that structures, systems, and components important to safety be designed and loc,3ted to minimize, consistent with other safety requirements, the probability and effect of fires and explosions. Noncombustible and heat-resistant materials are required to be used wherever prac- tical throughout the unit, particularly in locations such as the containment and control room.
 
Criterion 3 also requires that-fire detection and suppression systems of appropriate capacity and capability be provided and designed to minimize the adverse effect of fires on structures, systems, and components important to safety and that firefighting systems be designed to ensure that their failure, rupture, or inadvertent operation does not significantly impair the safety capability of these structures, systems, anid components.
 
This guide presents guidelines acceptable to the NRC staff for implementing this criterion in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines.     -jitable bases and justification should be provided for alternative approaches to establish aL.eptable implementa- tion of General Design Criterion 3.
 
This guide addresses fire protection only for safety-related systems and equipment in nuclear power plants.   It does not give guidance on separation criteria for redundant cable systems.   Such guidance is included in Regulatory Guide 1.75, "Physical Independence of Elec- trical Systems." Economic and property loss considerations will probably dictate additional requirements for the fire protection program.


==B. DISCUSSION==
==B. DISCUSSION==
The fire protection program for a nuclear power plant consist; of design features, personnel,equipment, and procedures. Management participation in the program should begin with earlydesign concepts and plant layout work and continue through plant operation. A qualified staffshould be responsible for engineering and design of fire protection systems for nuclear powerplants. This staff should also be responsible for fire prevention activities, maintenance offire protection systems, training, and manual firefighting activities. The equipment portion ofthe fire protection program comprises all equipment that provides fire detection, annunciation,control, containment, suppression, and extinguishment. It is the combination of all these thatprovides the needed defense-in-depth protection of the public health and safety.There have been 32 fires in operating U.S. nuclear power plants through December 1975. Ofthese, the fire on March 22, 1975, at Browns Ferry nuclear plant was the most severe. Withapproximately 250 operating reactor years of experience, one may infer a frequency on the orderof one fire per ten reactor years. Thus, on the average, a nuclear power plant may experienceone or wore fires of varying severity during its operating life. WASH-1400, "Reactor SafetyStudy -An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," dated October1975, concluded that the Browns Ferry fire did not affect the validity of the overall risk assess-ment. In any event, cost-effective fire protection measures should be instituted to significantlydecrease the frequency and severity of fires.A document entitled "The International Guidelines for the Fire Protection of Nuclear PowerPlants," (IGL) 1974 Edition, 2nd Reprint, published on behalf of the National Nuclear RisksInsurance Pools and Association, provides a step-by-step approach to assessing the fire risk in anuclear power plant and describes protective measures to be taken as a part of the fire protec-tion of these plants. It provides useful guidance in this important area. The fluclear EnergyLiability and Property Insurance Association (NIELPIA) hds prepared a document entitled "Soecifica-tions for Fire Protection of New Plants" which gives general conditions and valuable criteria. Aspecial review group organized by NRC under Dr. Stephen H. Hanauer, Technical Advisor to theExecutive Director for Operations, to study the Brcwns Ferry fire issued a report, NUREG-0050,"Reconviendatiot. Related to Drowns Ferry Fire," in February 1976, which contains recommendationsapplicable to all nuclear power plants. This guide uses the applicable information contained inthese documents.1.120-3 For the user's convenience, some of the terms related to fire protection are presented belowwith their definitions as used in this guide:Approved -signifies that devices or assemblie% have been tested and accepted for a specificpurpose or application by a nationally recognized testing laboratory.Automatic -self-acting, operating by its own mechanism when actuated by some impersonalinfluence such as a change in current, pressure, temperature, or mechanical configuration.Combustible Sources -any material that will burn or sustain the combustion process whetheror not it exhibits flame unoer exposure fire conditions that can exist at their point ofapplication.Concealed -if space containing combustible material is inaccessible to the extinguishingagent, the combustibles are ronsidered to be concealed.Design Basis Fires -fires that cause the most damage or the most severe exposure to thearea or systems being considered. They are fires-that may develop in local areas assumingno manual, automatic, or other firefighting action has been initiated, the fire has passedflashov!r (i.e., the temperature at which auto-ignition of other combustibles in the areawill occur), and the fire has reached its peak burning rate.Electrical Conduit -rigid or flexible tubing, usually either steel or aluminium, in whichelectrical cables are run.Enclosed -surrounded by a case that will prevent a person from accidentally contacting liveelectrical parts. Can also apply to flammable liquids that are contained or encased infire-resistive materials or buildings.Fire Area -that portion of a building or plant that is separated from other areas by bound-ary fire barriers (walls, floors, or roofs) with any openings or penetrations protected withseals or closures having a fire resistance rating equal to that of the barrier.Fire Barrier -those components of construction (walls, floors, or roofs) that are rated byapproving laboratories in hours of resistance to fire and are used to prevent the spread offire.Fire Break -a feature of construction that prevents fire propagation along the length ofcables or prevents spreading of fire to nearby combustibles within a given fire area or firezone.Fire Brigade -the team of plant personnel assigned to firefighting and who are trained inthe fighting of fires by ,n approved training program.Fire Detectors -a device designed to automatically detect the presence of fire and initiatean alarm system (see the National Fire Protection Association Standard NFPA 72E, "AutomaticFire Detectors"). Some typical fire detectors are classified as follows:Heat Detector -a device that detects abnormally high temperature or rate-of-temperaturerise..Smoke Detector -a device that detects the visible or invisible particles of combustion.Flame Detector -a device that detects the infrared, ultraviolet, or visible radiationproduced by a fire.Products of Combustion Detector -a detector whose actuation mechanism depends uponpyrolysis or combustion products.Fire Protection Program -the components, procedures, and personnel utilized in carrying outalTiactivities of fire protection. It includes such things as fire prevention, detection,annunciation, control, confinement, suppression, extinguishment, administrative procedures,fire brigade organization, inspection and maintenance, training, quality assurance, andtesting.Fire Rating -the endurance period of a fire barrier or structure; it defines the period ofresistance to a standard fire exposure before the first critical point in behavior isobserved. (See NFPA 251.)1.120-4 Fire Suppression -capability for control and extinguishing of fires (firefighting).ual fire suppression activities include the use of hoses or portable extinguishers.Automatic fire suppression includes the use of fixed systems such as water sprinklers,Halon, or carbon dioxide.Fire Zones -subdivisions of fire areas in which the fire suppression systems are designedto combat particular types of fires. The concept of fire zone aids in defining to thefirefighter the fire parameters and the actions that would be necessary.Noncombustible -materials, no part of which will ignite and burn when subjected to fire.Raceway -any channel that is designed expressly for holding wires, cables, or bus bars andis used solely for this purpose.Restricted Area -any area to which access is controlled by the licensee for purposes ofprotecting individuals fror exposure to radiation and radioactive materials.Safety-Related Systems and Components -systems and components required to shut down thereactor, mitigate the consequences of postulated accidents, or maintain the reactor in asafe shutdown condition.Srrinkler System -a system of overhead piping and components from the first supply valve tothe point where water discharges from the system to the fire area. The system is usuallyactivated by heat or smoke from a fire. The system sometimes includes a controlling and/ora sectionalizing valve that is activated by a fire detection system and a device for actuat-ing an alarm when the system is in operation. Sprinkler systems may be classified asfollows:Wet Pipe -a system employing automatic closed-head (fusible link operated) sprinklersattached to a piping system containing water and connected to a water supply so thatwater discharges immediately from sprinklers opened by a fire.DryPipe -a system employing automatic closed-head sprinklers attached to a pipingsystem containing air or nitrogen under pressure, the release of which, as from theopening of a sprinkler, permits the water pressure to open a valve known as a dry-pipevalve. The water then flows into the piping system and out the open sprinklers.Preaction System -a system employing automatic closed-head sprinklers attached to apiping system containing air that may or may not be under pressure, with a fire detec-tion system installed in the same areas as the sprinklers. Actuation of the firedetection system, as by a fire, opens a valve that permits water to flow into thesprinkler piping system and to be discharged from any sprinklers that have been openedby the fire.Deluuge_5ystem -a system employing open-head sprinklers and/or nozzles attached to apiping system connected to a water supply through a valve that is opened by the opera-tion of a fire detection system installed in the areas where the sprinklers or nozzlesare located. When this valve opens, water flows into the piping system and dischargesfrom all sprinklers or nozzles attached thereto.Standpipe and Hose Systems -a fixed piping system connected to a water supply to provideeffective fire hose streams in the shortest possible time to specific areas inside thebuilding.The Browns Ferry fire and subsequent events have shown potential inadequ.cie: in fire pro-tection. Some of the major conclusions that emerged from the Browns Ferry fire investigationswarrant emphasis and are discussed below.1. Defense in DepthNuclear power plants use the concept of defense in depth to achieve the required high degreeof safety by using echelons of safety systems. This concept is also applicable to fire safety innuclear power plants. With respect to the fire protection program, the defense-in-depth principleis aimed at achieving an adequate balance in:a. Preventing fires from starting;b. Detecting fires quickly, suppressing those fires that occur, putting them out quickly,and limiting their damage; and1.120-5 c. Designing plant safety systems so that a fire that starts in spite of the fire preven-tion program and burns for a considerable time in spite of fire protection activities will notprevent essential plant safety functions from being performed.Nio one of these echelons can be perfect or complete by itself. Strengthening any one cancompensate in some measure for weaknesses, known or unknown, in the others.The primary objective of the fire protection program is to minimize both the probability andconsequences of postulated fires. In spite of steps taken to reduce the probability of fire inthe design of the plant, it is expected that fires will occur. Therefore, leans should be nro-vided to detect, control, and extinguish fires. This can be done by providing fixed fire detec-tion and suppression systems of appropriate capability and adequate capacity in areas where thepotential fire damage may jeopardize safe plant shutdown. Backup manual firefighting capabilityshould be provided throughout the plant to limit the extent of a fire by providing portableequipment consisting of hoses, nozzles, portable extinguishers, and iir breathing equipment foruse by properly trained firefighting personnel.A nuclear power plant must maintain its capability to combat a fire under any operatingcondition with fuel on site. A single failure in the fire prot-cltion system or direct supportsystems should not impair both primary and backup plant fire pirotectioni capability. For example,to avoid such a consequence, the pumping portion of fire protection water supply systems shouldbe redundant and independent, including associated power supplie.s alnd controls. Also, failure orinadvertent operation of the fire suppression system should not result in failure of safety-related systems or components.Postulated fires or fire protection system failures need not be considered concurrent withother plant accidents or the most severe natural phenomena, e.g., fire and a LOCA or fire and theSafe Shutdown Earthquake (SSE). However, in the event of the SSE, the fire protection systemshould be capable of delivering water from manual hose stations located within hose reach ofareas containing equipment required for safe shutdown. The water supply for thi. condition maybe obtained by manual operator actuation of valves in a connection to the hose standpipe headerfrom a normal Seismic Category I water system such as the essential service water systemn. Thusat least manual hose and portable fire protection capability must be provided for all pottulateddesign basis events requiring plant shutdown. The fire protection systems should, however,because of the higher probability of occurrence, retain their original design capability for(1) natural phenomena of less severity and greater frequency (approximately once in 10 years)such as tornadoes, hurricanes, floods, ice storms, or small-intensity earthquakes that arecharacteristic of the site geographic region and (2) for potential man-created site-relatedevents such as oil barge collisions and aircraft crashes that have a reasonable probability ofoccurring at a specific plant site. The effects of lightning strikes should be included in theoverall plant fire protection system.Fire protection starts with design and must be carried through in all phases of constructionand operation. Furthermore, quality assurance (QA) programs are needed to identify and rectifyerrors in design, construction, and operation and are an essential part of defense in depth.This guide is intended to implement the pHlosophy of defense-in-depth protection against thehazards of fire and its associated effects on safety-related equipment.2. Use of Water on Electrical FiresExperience with major electrical fires shows that water should be used if initial attemptsto put out a cable fire with other agents are not immediately successful. Since prompt extin-guishing of the fire is paramount to reactor safety, damage would be reduced by discreet applica-tion of water from automatic sprinklers rather than manual application with fire hoses. Thewidespread opinion and practice that emphasize the reasons for not using water as contrasted tothose for its prompt and proper use are a concern. Firefighting procedures and fire trainingshould provide the techniques, equipment, and skills for the use of water in fighting electricalfires in nuclear plants, particularly in areas containing a high concentration of electric cableswith plastic insulation.Ie This is not to say that water systems should be installed everywhere. Equipment that maybe damaged by water should be shielded or relocated away from the fire hazard and the water.Drains should be provided to remove any water used for fire suppression and extinguishment.3. Establishment and Use of Fire AreasThe concept of separate fire areas for each division of safety equipment that requiresredundancy will facilitate the installation of automatic water extinguishing systems since itwill reduce the possibility of water damaging redundant safety-related equipment.1.120-6~1 Fire areas should be established based on the amount of combustible material present andconsidering suitably cljosen design basis fires so that adequate protection can be provided forsafety-related systems and equipment. Design basis fires are those fires that result in the mostduimage or most severe exposure to the area or systems being considered.Within each area, special attention should be given to limiting the amount of combustiblematerial ane to providing effective barriers and fire-resi3tive coatings to reduce the spread ofa fire in these areas. A design basis fire should be assumed, and provisions should be made tolimit the consequence of such a fire by providing fire barriers w.ith suitable separation betweenredundant systems and components that are provided to carry out required safety functions. Thisseparation is enhanced if the plant is divided into suitable fire areas since redundant safetyequipment can then be placed in separate fire areas.Particular design attention should be given to the use of separate isolated fire areas forredundant cables to avoid loss of redundant safety-related cables.Provisions should also be made to limit the consequences of a fire by suitable design ofthe ventilation systems so 'hat the spread of the products of combustion to other areas of the* plant is prevented. Means should be provided to ventilate, exhaust, or isolate the area asrequired. The power suppiy and controls for the area ventilation system should be from outsidethe area, and the power and control cables should not pass through the area.In the design, consideration should be given to providing personnel access to and escaperoutes from each fire area. The emergency plans for all plants should lay out access and escapeto cover the event of a fire in critical areas of the plant.
The fire protection program for a nuclear power plant consist; of design features, personnel, equipment, and procedures. Management participation in the program should begin with early design concepts and plant layout work and continue through plant operation. A qualified staff should be responsible for engineering and design of fire protection systems for nuclear power plants.   This staff should also be responsible for fire prevention activities, maintenance of fire protection systems, training, and manual firefighting activities.   The equipment portion of the fire protection program comprises all equipment that provides fire detection, annunciation, control, containment, suppression, and extinguishment.   It is the combination of all these that provides the needed defense-in-depth protection of the public health and safety.
 
There have been 32 fires in operating U.S. nuclear power plants through December 1975. Of these, the fire on March 22, 1975, at Browns Ferry nuclear plant was the most severe. With approximately 250 operating reactor years of experience, one may infer a frequency on the order of one fire per ten reactor years. Thus, on the average, a nuclear power plant may experience one or wore fires of varying severity during its operating life. WASH-1400, "Reactor Safety Study - An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," dated October
1975, concluded that the Browns Ferry fire did not affect the validity of the overall risk assess- ment. In any event, cost-effective fire protection measures should be instituted to significantly decrease the frequency and severity of fires.
 
A document entitled "The International Guidelines for the Fire Protection of Nuclear Power Plants," (IGL) 1974 Edition, 2nd Reprint, published on behalf of the National Nuclear Risks Insurance Pools and Association, provides a step-by-step approach to assessing the fire risk in a nuclear power plant and describes protective measures to be taken as a part of the fire protec- tion of these plants.   It provides useful guidance in this important area.   The fluclear Energy Liability and Property Insurance Association (NIELPIA) hds prepared a document entitled "Soecifica- tions for Fire Protection of New Plants" which gives general conditions and valuable criteri
 
====a.     A====
special review group organized by NRC under Dr. Stephen H. Hanauer, Technical Advisor to the Executive Director for Operations, to study the Brcwns Ferry fire issued a report, NUREG-0050,
"Reconviendatiot. Related to Drowns Ferry Fire," in February 1976, which contains recommendations applicable to all nuclear power plants. This guide uses the applicable information contained in these documents.
 
1.120-3
 
For the user's convenience, some of the terms related to fire protection are presented below with their definitions as used in this guide:
    Approved - signifies that devices or assemblie% have been tested and accepted for a specific purpose or application by a nationally recognized testing laboratory.
 
Automatic - self-acting, operating by its own mechanism when actuated by some impersonal influence such as a change in current, pressure, temperature, or mechanical configuration.
 
Combustible Sources - any material that will burn or sustain the combustion process whether or not it exhibits flame unoer exposure fire conditions that can exist at their point of application.
 
Concealed - if space containing combustible material is inaccessible to the extinguishing agent, the combustibles are ronsidered to be concealed.
 
Design Basis Fires - fires that cause the most damage or the most severe exposure to the area or systems being considered. They are fires-that may develop in local areas assuming no manual, automatic, or other firefighting action has been initiated, the fire has passed flashov!r (i.e., the temperature at which auto-ignition of other combustibles in the area will occur), and the fire has reached its peak burning rate.
 
Electrical Conduit - rigid or flexible tubing, usually either steel or aluminium, in which electrical cables are run.
 
Enclosed - surrounded by a case that will prevent a person from accidentally contacting live electrical parts.     Can also apply to flammable liquids that are contained or encased in fire-resistive materials or buildings.
 
Fire Area - that portion of a building or plant that is separated from other areas by bound- ary fire barriers (walls, floors, or roofs) with any openings or penetrations protected with seals or closures having a fire resistance rating equal to that of the barrier.
 
Fire Barrier - those components of construction (walls, floors, or roofs) that are rated by approving laboratories in hours of resistance to fire and are used to prevent the spread of fire.
 
Fire Break - a feature of construction that prevents fire propagation along the length of cables or prevents spreading of fire to nearby combustibles within a given fire area or fire zone.
 
Fire Brigade - the team of plant personne l assigned to firefighting and who are trained in the fighting of fires by ,n approved training program.
 
Fire Detectors - a device designed to automatically detect the presence of fire and initiate an alarm system (see the National Fire Protection Association Standard NFPA 72E, "Automatic Fire Detectors").   Some typical fire detectors are classified as follows:
          Heat Detector -   a device that detects abnormally high temperature or rate-of-temperature rise..
          Smoke Detector   - a device that detects the visible or invisible particles of combustion.
 
Flame Detector - a device that detects the infrared, ultraviolet, or visible radiation produced by a fire.
 
Products of Combustion Detector - a detector whose actuation mechanism depends upon pyrolysis or combustion products.
 
Fire Protection Program - the components, procedures, and personnel utilized in carrying out alTiactivities of fire protection. It includes such things as fire prevention, detection, annunciation, control, confinement, suppression, extinguishment, administrative procedures, fire brigade organization, inspection and maintenance, training, quality assurance, and testing.
 
Fire Rating - the endurance period of a fire barrier or structure; it defines the period of resistance to a standard fire exposure before the first critical point in behavior is observed.     (See NFPA 251.)
                                                1.120-4
 
Fire Suppression - capability for control and extinguishing of fires (firefighting).
          ual fire suppression activities include the use of hoses or portable extinguishers.
 
Automatic fire suppression includes the use of fixed systems such as water sprinklers, Halon, or carbon dioxide.
 
Fire Zones - subdivisions of fire areas in which the fire suppression systems are designed to combat particular types of fires. The concept of fire zone aids in defining to the firefighter the fire parameters and the actions that would be necessary.
 
Noncombustible - materials, no part of which will ignite and burn when subjected to fire.
 
Raceway - any channel that is designed expressly for holding wires, cables, or bus bars and is used solely for this purpose.
 
Restricted Area - any area to which access is controlled by the licensee for purposes of protecting individuals fror exposure to radiation and radioactive materials.
 
Safety-Related Systems and Components - systems and components required to shut down the reactor, mitigate the consequences of postulated accidents, or maintain the reactor in a safe shutdown condition.
 
Srrinkler System - a system of overhead piping and components from the first supply valve to the point where water discharges from the system to the fire area.     The system is usually activated by heat or smoke from a fire. The system sometimes includes a controlling and/or a sectionalizing valve that is activated by a fire detection system and a device for actuat- ing an alarm when the system is in operation. Sprinkler systems may be classified as follows:
            Wet Pipe - a system employing automatic closed-head (fusible link operated) sprinklers attached to a piping system containing water and connected to a water supply so that water discharges immediately from sprinklers opened by a fire.
 
DryPipe - a system employing automatic closed-head sprinklers attached to a piping system containing air or nitrogen under pressure, the release of which, as from the opening of a sprinkler, permits the water pressure to open a valve known as a dry-pipe valve. The water then flows into the piping system and out the open sprinklers.
 
Preaction System - a system employing automatic closed-head sprinklers attached to a piping system containing air that may or may not be under pressure, with a fire detec- tion system installed in the same areas as the sprinklers.   Actuation of the fire detection system, as by a fire, opens a valve that permits water to flow into the sprinkler piping system and to be discharged from any sprinklers that have been opened by the fire.
 
Deluuge_5ystem - a system employing open-head sprinklers and/or nozzles attached to a piping system connected to a water supply through a valve that is opened by the opera- tion of a fire detection system installed in the areas where the sprinklers or nozzles are located. When this valve opens, water flows into the piping system and discharges from all sprinklers or nozzles attached thereto.
 
Standpipe and Hose Systems - a fixed piping system connected to a water supply to provide effective fire hose streams in the shortest possible time to specific areas inside the building.
 
The Browns Ferry fire and subsequent events have shown potential inadequ.cie: in fire pro- tection. Some of the major conclusions that emerged from the Browns Ferry fire investigations warrant emphasis and are discussed below.
 
1.   Defense in Depth Nuclear power plants use the concept of defense in depth to achieve the required high degree of safety by using echelons of safety systems.       This concept is also applicable to fire safety in nuclear power plants. With respect to the fire protection program, the defense-in-depth principle is aimed at achieving an adequate balance in:
      a.     Preventing fires from starting;
      b.     Detecting fires quickly, suppressing those fires that occur, putting them out quickly, and limiting their damage; and
                                                1.120-5
 
c.   Designing plant safety systems so that a fire that starts in spite of the fire preven- tion program and burns for a considerable time in spite of fire protection activities will not prevent essential plant safety functions from being performed.
 
Nioone of these echelons can be perfect or complete by itself. Strengthening any one can compensate in some measure for weaknesses, known or unknown, in the others.
 
The primary objective of the fire protection program is to minimize both the probability and consequences of postulated fires. In spite of steps taken to reduce the probability of fire in the design of the plant, it is expected that fires will occur. Therefore, leans should be nro- vided to detect, control, and extinguish fires. This can be done by providing fixed fire detec- tion and suppression systems of appropriate capability and adequate capacity in areas where the potential fire damage may jeopardize safe plant shutdown.   Backup manual firefighting capability should be provided throughout the plant to limit the extent of a fire by providing portable equipment consisting of hoses, nozzles, portable extinguishers, and iir breathing equipment for use by properly trained firefighting personnel.
 
A nuclear power plant must maintain its capability to combat a fire under any operating condition with fuel on site. A single failure in the fire prot-cltion system or direct support systems should not impair both primary and backup plant fire pirotectioni capability. For example, to avoid such a consequence, the pumping portion of fire protection water supply systems should be redundant and independent, including associated power supplie.s alnd controls. Also, failure or inadvertent operation of the fire suppression system should not result in failure of safety- related systems or components.
 
Postulated fires or fire protection system failures need not be considered concurrent with other plant accidents or the most severe natural phenomena, e.g., fire and a LOCA or fire and the Safe Shutdown Earthquake (SSE).   However, in the event of the SSE, the fire protection system should be capable of delivering water from manual hose stations located within hose reach of areas containing equipment required for safe shutdown. The water supply for thi. condition may be obtained by manual operator actuation of valves in a connection to the hose standpipe header from a normal Seismic Category I water system such as the essential service water systemn. Thus at least manual hose and portable fire protection capability must be provided for all pottulated design basis events requiring plant shutdown. The fire protection systems should, however, because of the higher probability of occurrence, retain their original design capability for
(1) natural phenomena of less severity and greater frequency (approximately once in 10 years)
such as tornadoes, hurricanes, floods, ice storms, or small-intensity earthquakes that are characteristic of the site geographic region and (2) for potential man-created site-related events such as oil barge collisions and aircraft crashes that have a reasonable probability of occurring at a specific plant site. The effects of lightning strikes should be included in the overall plant fire protection system.
 
Fire protection starts with design and must be carried through in all phases of construction and operation. Furthermore, quality assurance (QA) programs are needed to identify and rectify errors in design, construction, and operation and are an essential part of defense in depth.
 
This guide is intended to implement the pHlosophy of defense-in-depth protection against the hazards of fire and its associated effects on safety-related equipment.
 
2.   Use of Water on Electrical Fires Experience with major electrical fires shows that water should be used if initial attempts to put out a cable fire with other agents are not immediately successful.   Since prompt extin- guishing of the fire is paramount to reactor safety, damage would be reduced by discreet applica- tion of water from automatic sprinklers rather than manual application with fire hoses. The widespread opinion and practice that emphasize the reasons for not using water as contrasted to those for its prompt and proper use are a concern. Firefighting procedures and fire training should provide the techniques, equipment, and skills for the use of water in fighting electrical fires in nuclear plants, particularly in areas containing a high concentration of electric cables with plastic insulation.
 
e This is not to say that water systems should be installed everywher
 
====e. Equipment that may I====
be damaged by water should be shielded or relocated away from the fire hazard and the water.
 
Drains should be provided to remove any water used for fire suppression and extinguishment.
 
3.   Establishment and Use of Fire Areas The concept of separate fire areas for each division of safety equipment that requires redundancy will facilitate the installation of automatic water extinguishing systems since it will reduce the possibility of water damaging redundant safety-related equipment.
 
1.120-6
                                                                                                  ~1
 
Fire areas should be established based on the amount of combustible material present and considering suitably cljosen design basis fires so that adequate protection can be provided for safety-related systems and equipment. Design basis fires are those fires that result in the most duimage or most severe exposure to the area or systems being considered.
 
Within each area, special attention should be given to limiting the amount of combustible material ane to providing effective barriers and fire-resi3tive coatings to reduce the spread of a fire in these areas. A design basis fire should be assumed, and provisions should be made to limit the consequence of such a fire by providing fire barriers w.ith suitable separation between redundant systems and components that are provided to carry out required safety functions.         This separation is enhanced if the plant is divided into suitable fire areas since redundant safety equipment can then be placed in separate fire areas.
 
Particular design attention should be given to the use of separate isolated fire areas for redundant cables to avoid loss of redundant safety-related cables.
 
Provisions should also be made to limit the consequences of a fire by suitable design of the ventilation systems so 'hat the spread of the products of combustion to other areas of the
* plant is prevented. Means should be provided to ventilate, exhaust, or isolate the area as required.     The power suppiy and controls for the area ventilation system should be from outside the area, and the power and control cables should not pass through the area.
 
In the design, consideration should be given to providing personnel access to and escape routes from each fire area. The emergency plans for all plants should lay out access and escape r*'o.tes to cover the event of a fire in critical areas of the plant.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
I. Overall
I.    Overall Reqcuirements of the Fire Protection Program a.    Personnel Responsibility for the overall fire protection program should be assigned to a desig- nated person in the upper level of management.        This person should retain ultimate responsibility even though formulation and assurance of program implementation is delegated. Such delegation of authority should be to staff personnel prepared by training and experience in fire protection and nuclear plant safety to provide a balanced approach in directing the fire protection program for the nuclear power plant.
 
The fire protection staff should be responsible for:
              (1) Coordination of building layout and systems design with fire area requirements, including consideration of potential hazards associated with postulated design basis fires.
 
(2)  Design and maintenance of fire detection,    suppression, and extinguishing systems.
 
(3)  Fire prevention activities.
 
(4)  Training and manual firefighting activities of plant personnel and the fire brigade.
 
( NOTE: NIFPA 6, "Recommendations for Organization of Industrial Fire Loss Prevention," contains useful guidance for organization and operation of the entire fire loss prevention program.)
        b.    Design Bases The overall fire protection program should be based on evaluation of potential fire hazards throughout the plant and the effect of postulated design basis fires relative to main- taining ability to perform safe shutdown functions and minimize radioactive releases to the environment.
 
c.    Backup Total reliance should not be placed on a single automatic fire suppression system.
 
Appropriate backup fire suppression capability should be provided.
 
d.  Single-Failure Criterion A single failure in the fire suppression system should not impair both the primary and backup fire suppression capability.      For example, redundant fire water pumps with independent
                                                    1.120-7
 
power supplies and controls should be provided.      Postulated fires or. fire protection system failures need not be considered concurrent with other plant accidents or the most severe natural phenomena.    However, in the event of the most severe earthquake, i.e., the Safe Shutdown Earth- quake (SSE), the fire suppression system should be capable of delivering water to manual hose stations located within


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose.of this section is to provide information to applicants regarding the NRC staff'splans for using this regulatory guide.Except in those cases in which the applicant proposes an acceptable alternative method forcomplying with specified portions of the Conmission's regulations, the method described hereinwill be used in the evaluation of submiittals in connection with construction permit applicationsdocketed after February 28, 1977.If an applicant wishes to use this regulatory guide in developing submittals for applica-tions docketed on or before February 28, 1977, the pertinent portions of the application will beevaluated on the basis of this guide.1.120-22 REFERENCESNational Fire Protection Association Codes and Standards1IFPA 4, "Organization of Fire Services."INFPA 4A, "Fire Department Organization."NFPA 6, "Industrial Fire Loss Prevention."NFPA 7, "Fire Emergencies flangement."rIFPA , "Effects of Fire on Operations, Management Responsiblity."NFPA IC, "Portable Fire Extinguishers, Installation."tJFPA IOA, "Port-able Fire Extinguishers, Maintenance and Use."NFPA 11, "Foaw Extinguishing Systems."IJFPA 12, "Carbon Dioxide Systems."IIFFA 12A, "Halon 1301 Systems.'NFPA 12U,, "Halon 1211 Systems."NiFPA 14, "Standpipe and Hose Systems."NFPA 15, "Water Spray Fixed Systems."NFFPA 20, "Centrifugal Fire Pumps."N;FPA 24, "Outside Protection."'IFPA 26, "Supervision of Valves."1jFPA 27, "Private Fire Brigade."NFPA 30, "Flamimable Combustible Liquids Code."IIFPA 49, "Hazardous Chemicals Data."NFPA 50A, "Gaseous Hydrogen Systems."NFPA 69, "Explosion Prevention System."NFPA 72D, "Proprietary Signaling Systems."IIFPA 60, "Fire Doors and Vindows."NFPA 9214, "Waterproofing and Draining of Floors,"r1FPA 194, "Fire Hose Connections."NFPA 196, "Fire Hose."IJFPA 197, "Initial Fire Attack, Training, Standard On."NIFPA 204, "Smoke and Heat Venting Guide."NiFPA 232 AM, "Archives and Record Centers."NFPA 251, "Fire Tests, Building Construction and Materials."1.120-23 NFPA 601, "Guard Service in Fire Loss Prevention."U.S. Nuclear Regulatory Commission DocumentsNUREG-O050, "Recommendations Related to Browns Ferry Fire," Report by Special Review Group,published Februdry 1976.WASH-1400 (NUREG-75/014), "Reactor Safety Study -An Assessment of Accident Risks in U.S.Commercial Nuclear Power Plants," published October 1975.Standard Review Plan 9.5.1, "Fire Protection System."Standard Review Plan 3.6.1, "Plant Design for Protection Against Postulated Piping Failuresin Fluid Systems Outside Containment."Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licens-ing of Production and Utilization Facilities," General Design Criterion 3, "FireProtection."Regulatory Guide 1.39, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants."Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for NuclearPower Plants," Revision 2, Section 9.5.1.Regulatory Guide 1.75, "Physical Independence of Electrical Systems."Regulatory Guide 1.88, "Collection, Storage, and Maintenance of Nuclear Power Plant QualityAssurance Records."Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants."Other DocumentsANSI Standard B31.1, "Power Piping."ANSI Standard N45.2.9, "Requirements for Collection, Storage, and Maintenance of QualityAssurance Records for Nuclear Power Plants."ASTM E-84, "Surface Burning Characteristics of Building Materials."ASTM E-119, "Fire Test of Building Construction and Materials."IEEE Std 383-1974, "IEEE Standard of Type Test of Class IE Electric Cables, Field Splicesand Connections for Nuclear Power Generating Stations," April 15, 1974.NELPIA, "Specifications for Fire Protection of New Plants."RP-0O-69, "Recommended Practical Control of External Corrosion on Underground or SubmergedMetallic Piping Systems," Material Association of Corrosion Engineers.Factory Mutual System Approval Guide -Equipment, Materials, Services for Conservation ofProperty.International Guidelines for the. rire Protection of Nuclear Power Plants, National NuclearRisks Insurance Poois, 2nd Report (IGL).Underwriters Laboratories Rating List.1.120-24}}
The purpose.of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.
 
Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Conmission's regulations, the method described herein will be used in the evaluation of submiittals in connection with construction permit applications docketed after February 28, 1977.
 
If an applicant wishes to use this regulatory guide in developing submittals for applica- tions docketed on or before February 28, 1977, the pertinent portions of the application will be evaluated on the basis of this guide.
 
1.120-22
 
REFERENCES
National Fire Protection Association Codes and Standards
    1IFPA 4, "Organization of Fire Services."
    INFPA 4A, "Fire Department Organization."
    NFPA 6, "Industrial   Fire Loss Prevention."
    NFPA 7, "Fire Emergencies flangement."
    rIFPA   , "Effects of Fire on Operations,   Management Responsiblity."
    NFPA IC, "Portable Fire Extinguishers,     Installation."
    tJFPA IOA, "Port-able Fire Extinguishers, Maintenance and Use."
    NFPA 11, "Foaw   Extinguishing Systems."
    IJFPA 12, "Carbon Dioxide Systems."
    IIFFA 12A, "Halon 1301 Systems.'
    NFPA 12U,, "Halon 1211 Systems."
    NiFPA 14, "Standpipe and Hose Systems."
    NFPA 15, "Water Spray Fixed Systems."
    NFFPA 20, "Centrifugal Fire Pumps."
    N;FPA 24, "Outside Protection."
    'IFPA 26, "Supervision of Valves."
    1jFPA 27, "Private Fire Brigade."
    NFPA 30, "Flamimable Combustible Liquids Code."
    IIFPA 49, "Hazardous Chemicals Data."
    NFPA 50A, "Gaseous Hydrogen Systems."
    NFPA 69, "Explosion Prevention System."
    NFPA 72D, "Proprietary Signaling Systems."
    IIFPA 60, "Fire Doors and Vindows."
    NFPA 9214, "Waterproofing and Draining of Floors,"
    r1FPA 194, "Fire Hose Connections."
    NFPA 196, "Fire Hose."
    IJFPA 197, "Initial Fire Attack, Training, Standard On."
    NIFPA 204, "Smoke and Heat Venting Guide."
    NiFPA 232 AM, "Archives and Record Centers."
    NFPA 251,   "Fire Tests, Building Construction and Materials."
                                                  1.120-23
 
NFPA 601,   "Guard Service in Fire Loss Prevention."
U.S. Nuclear Regulatory Commission Documents NUREG-O050, "Recommendations Related to Browns Ferry Fire," Report by Special Review Group, published Februdry 1976.
 
WASH-1400 (NUREG-75/014), "Reactor Safety Study - An Assessment of Accident Risks in U.S.
 
Commercial Nuclear Power Plants," published October 1975.
 
Standard Review Plan 9.5.1,   "Fire Protection System."
    Standard Review Plan 3.6.1, "Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment."
    Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licens- ing of Production and Utilization Facilities," General Design Criterion 3, "Fire Protection."
    Regulatory Guide 1.39, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants."
    Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants," Revision 2, Section 9.5.1.
 
Regulatory Guide 1.75, "Physical Independence of Electrical Systems."
    Regulatory Guide 1.88, "Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records."
    Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants."
Other Documents ANSI Standard B31.1,   "Power Piping."
    ANSI Standard N45.2.9, "Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants."
    ASTM E-84, "Surface Burning Characteristics of Building Materials."
    ASTM E-119, "Fire Test of Building Construction and Materials."
    IEEE Std 383-1974, "IEEE Standard of Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations," April 15, 1974.
 
NELPIA,   "Specifications for Fire Protection of New Plants."
    RP-0O-69, "Recommended Practical Control of External Corrosion on Underground or Submerged Metallic Piping Systems," Material Association of Corrosion Engineers.
 
Factory Mutual System Approval Guide - Equipment, Materials, Services for Conservation of Property.
 
International Guidelines for the. rire Protection of Nuclear Power Plants, National Nuclear Risks Insurance Poois, 2nd Report (IGL).
    Underwriters Laboratories Rating List.
 
1.120-24}}


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Fire Protection Guidelines for Nuclear Power Plants
ML13350A276
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Issue date: 06/30/1976
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- -

U.S. NUCLEAR REGULATORY COMMISSION June 1976 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.120

FIRE PROTECTION GUIDELINES FOR NUCLEAR POWER PLANTS

I" IN

ka)

USNRC REGULATORY GUIDES Commenis should be sent to the Secretary ot the Commission. U S, Nurlea, Regulatory Guides are issued Io describe and make available to the public Regulatory Commission. Washington. 0 C 20M55. Attention Dfockeling and methods acceptable to the NRC stall of implementing specific pan. ol the Service Section Commission's regulations, to delineate techniques used by the staf in evoalu The guides atre Issued in the following ten broad divisions saing specific problems or postulated accidanls, or to provide guidance to app!.

cents. Regulatory Guides are niot substilutes torreggulallort, and compliance I. Powew Reaclors 6 Products with them Is not required. Methods end solutions difflerenl from those set out in 2. Research and Test Reactors 7 Tranrporletion the guides will be acceptable It they provid, a beei* for the findings requitel to 3. Fuels and Materials Facilities 8 Occupational Health the Issuance or continuance olf permit or license by the Co nmmission 4 Environmental and Siting 9 Antitrust Review Comments and suggestions for improvements in these guides are encouraged 6 Malteials and Plant Protection 10 General at all times. and guides will be revised. as appropriate, to accommodate com ments and o reflect new information or eipeflenc. However. cuminonts nim Copies of published guides may be obtained by wrttien request indicatilig the Ihis guide. I received within about two months alter its Issuance wilt hr par divisions desired 1o thi U S Nuclear Regulatory Commission Washinglton 0 C

licularly uselul in evaluating the need fo, an early revision 2 . Allention. Director. Office of Standards Oevalopment

A. INTRODUCTION

General Design Criterion 3, "Fire Protection" of Appendix A, "General Design Criteria for Nluclear Power Planlts," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"

requires that structures, systems, and components important to safety be designed and loc,3ted to minimize, consistent with other safety requirements, the probability and effect of fires and explosions. Noncombustible and heat-resistant materials are required to be used wherever prac- tical throughout the unit, particularly in locations such as the containment and control room.

Criterion 3 also requires that-fire detection and suppression systems of appropriate capacity and capability be provided and designed to minimize the adverse effect of fires on structures, systems, and components important to safety and that firefighting systems be designed to ensure that their failure, rupture, or inadvertent operation does not significantly impair the safety capability of these structures, systems, anid components.

This guide presents guidelines acceptable to the NRC staff for implementing this criterion in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. -jitable bases and justification should be provided for alternative approaches to establish aL.eptable implementa- tion of General Design Criterion 3.

This guide addresses fire protection only for safety-related systems and equipment in nuclear power plants. It does not give guidance on separation criteria for redundant cable systems. Such guidance is included in Regulatory Guide 1.75, "Physical Independence of Elec- trical Systems." Economic and property loss considerations will probably dictate additional requirements for the fire protection program.

B. DISCUSSION

The fire protection program for a nuclear power plant consist; of design features, personnel, equipment, and procedures. Management participation in the program should begin with early design concepts and plant layout work and continue through plant operation. A qualified staff should be responsible for engineering and design of fire protection systems for nuclear power plants. This staff should also be responsible for fire prevention activities, maintenance of fire protection systems, training, and manual firefighting activities. The equipment portion of the fire protection program comprises all equipment that provides fire detection, annunciation, control, containment, suppression, and extinguishment. It is the combination of all these that provides the needed defense-in-depth protection of the public health and safety.

There have been 32 fires in operating U.S. nuclear power plants through December 1975. Of these, the fire on March 22, 1975, at Browns Ferry nuclear plant was the most severe. With approximately 250 operating reactor years of experience, one may infer a frequency on the order of one fire per ten reactor years. Thus, on the average, a nuclear power plant may experience one or wore fires of varying severity during its operating life. WASH-1400, "Reactor Safety Study - An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," dated October

1975, concluded that the Browns Ferry fire did not affect the validity of the overall risk assess- ment. In any event, cost-effective fire protection measures should be instituted to significantly decrease the frequency and severity of fires.

A document entitled "The International Guidelines for the Fire Protection of Nuclear Power Plants," (IGL) 1974 Edition, 2nd Reprint, published on behalf of the National Nuclear Risks Insurance Pools and Association, provides a step-by-step approach to assessing the fire risk in a nuclear power plant and describes protective measures to be taken as a part of the fire protec- tion of these plants. It provides useful guidance in this important area. The fluclear Energy Liability and Property Insurance Association (NIELPIA) hds prepared a document entitled "Soecifica- tions for Fire Protection of New Plants" which gives general conditions and valuable criteri

a. A

special review group organized by NRC under Dr. Stephen H. Hanauer, Technical Advisor to the Executive Director for Operations, to study the Brcwns Ferry fire issued a report, NUREG-0050,

"Reconviendatiot. Related to Drowns Ferry Fire," in February 1976, which contains recommendations applicable to all nuclear power plants. This guide uses the applicable information contained in these documents.

1.120-3

For the user's convenience, some of the terms related to fire protection are presented below with their definitions as used in this guide:

Approved - signifies that devices or assemblie% have been tested and accepted for a specific purpose or application by a nationally recognized testing laboratory.

Automatic - self-acting, operating by its own mechanism when actuated by some impersonal influence such as a change in current, pressure, temperature, or mechanical configuration.

Combustible Sources - any material that will burn or sustain the combustion process whether or not it exhibits flame unoer exposure fire conditions that can exist at their point of application.

Concealed - if space containing combustible material is inaccessible to the extinguishing agent, the combustibles are ronsidered to be concealed.

Design Basis Fires - fires that cause the most damage or the most severe exposure to the area or systems being considered. They are fires-that may develop in local areas assuming no manual, automatic, or other firefighting action has been initiated, the fire has passed flashov!r (i.e., the temperature at which auto-ignition of other combustibles in the area will occur), and the fire has reached its peak burning rate.

Electrical Conduit - rigid or flexible tubing, usually either steel or aluminium, in which electrical cables are run.

Enclosed - surrounded by a case that will prevent a person from accidentally contacting live electrical parts. Can also apply to flammable liquids that are contained or encased in fire-resistive materials or buildings.

Fire Area - that portion of a building or plant that is separated from other areas by bound- ary fire barriers (walls, floors, or roofs) with any openings or penetrations protected with seals or closures having a fire resistance rating equal to that of the barrier.

Fire Barrier - those components of construction (walls, floors, or roofs) that are rated by approving laboratories in hours of resistance to fire and are used to prevent the spread of fire.

Fire Break - a feature of construction that prevents fire propagation along the length of cables or prevents spreading of fire to nearby combustibles within a given fire area or fire zone.

Fire Brigade - the team of plant personne l assigned to firefighting and who are trained in the fighting of fires by ,n approved training program.

Fire Detectors - a device designed to automatically detect the presence of fire and initiate an alarm system (see the National Fire Protection Association Standard NFPA 72E, "Automatic Fire Detectors"). Some typical fire detectors are classified as follows:

Heat Detector - a device that detects abnormally high temperature or rate-of-temperature rise..

Smoke Detector - a device that detects the visible or invisible particles of combustion.

Flame Detector - a device that detects the infrared, ultraviolet, or visible radiation produced by a fire.

Products of Combustion Detector - a detector whose actuation mechanism depends upon pyrolysis or combustion products.

Fire Protection Program - the components, procedures, and personnel utilized in carrying out alTiactivities of fire protection. It includes such things as fire prevention, detection, annunciation, control, confinement, suppression, extinguishment, administrative procedures, fire brigade organization, inspection and maintenance, training, quality assurance, and testing.

Fire Rating - the endurance period of a fire barrier or structure; it defines the period of resistance to a standard fire exposure before the first critical point in behavior is observed. (See NFPA 251.)

1.120-4

Fire Suppression - capability for control and extinguishing of fires (firefighting).

ual fire suppression activities include the use of hoses or portable extinguishers.

Automatic fire suppression includes the use of fixed systems such as water sprinklers, Halon, or carbon dioxide.

Fire Zones - subdivisions of fire areas in which the fire suppression systems are designed to combat particular types of fires. The concept of fire zone aids in defining to the firefighter the fire parameters and the actions that would be necessary.

Noncombustible - materials, no part of which will ignite and burn when subjected to fire.

Raceway - any channel that is designed expressly for holding wires, cables, or bus bars and is used solely for this purpose.

Restricted Area - any area to which access is controlled by the licensee for purposes of protecting individuals fror exposure to radiation and radioactive materials.

Safety-Related Systems and Components - systems and components required to shut down the reactor, mitigate the consequences of postulated accidents, or maintain the reactor in a safe shutdown condition.

Srrinkler System - a system of overhead piping and components from the first supply valve to the point where water discharges from the system to the fire area. The system is usually activated by heat or smoke from a fire. The system sometimes includes a controlling and/or a sectionalizing valve that is activated by a fire detection system and a device for actuat- ing an alarm when the system is in operation. Sprinkler systems may be classified as follows:

Wet Pipe - a system employing automatic closed-head (fusible link operated) sprinklers attached to a piping system containing water and connected to a water supply so that water discharges immediately from sprinklers opened by a fire.

DryPipe - a system employing automatic closed-head sprinklers attached to a piping system containing air or nitrogen under pressure, the release of which, as from the opening of a sprinkler, permits the water pressure to open a valve known as a dry-pipe valve. The water then flows into the piping system and out the open sprinklers.

Preaction System - a system employing automatic closed-head sprinklers attached to a piping system containing air that may or may not be under pressure, with a fire detec- tion system installed in the same areas as the sprinklers. Actuation of the fire detection system, as by a fire, opens a valve that permits water to flow into the sprinkler piping system and to be discharged from any sprinklers that have been opened by the fire.

Deluuge_5ystem - a system employing open-head sprinklers and/or nozzles attached to a piping system connected to a water supply through a valve that is opened by the opera- tion of a fire detection system installed in the areas where the sprinklers or nozzles are located. When this valve opens, water flows into the piping system and discharges from all sprinklers or nozzles attached thereto.

Standpipe and Hose Systems - a fixed piping system connected to a water supply to provide effective fire hose streams in the shortest possible time to specific areas inside the building.

The Browns Ferry fire and subsequent events have shown potential inadequ.cie: in fire pro- tection. Some of the major conclusions that emerged from the Browns Ferry fire investigations warrant emphasis and are discussed below.

1. Defense in Depth Nuclear power plants use the concept of defense in depth to achieve the required high degree of safety by using echelons of safety systems. This concept is also applicable to fire safety in nuclear power plants. With respect to the fire protection program, the defense-in-depth principle is aimed at achieving an adequate balance in:

a. Preventing fires from starting;

b. Detecting fires quickly, suppressing those fires that occur, putting them out quickly, and limiting their damage; and

1.120-5

c. Designing plant safety systems so that a fire that starts in spite of the fire preven- tion program and burns for a considerable time in spite of fire protection activities will not prevent essential plant safety functions from being performed.

Nioone of these echelons can be perfect or complete by itself. Strengthening any one can compensate in some measure for weaknesses, known or unknown, in the others.

The primary objective of the fire protection program is to minimize both the probability and consequences of postulated fires. In spite of steps taken to reduce the probability of fire in the design of the plant, it is expected that fires will occur. Therefore, leans should be nro- vided to detect, control, and extinguish fires. This can be done by providing fixed fire detec- tion and suppression systems of appropriate capability and adequate capacity in areas where the potential fire damage may jeopardize safe plant shutdown. Backup manual firefighting capability should be provided throughout the plant to limit the extent of a fire by providing portable equipment consisting of hoses, nozzles, portable extinguishers, and iir breathing equipment for use by properly trained firefighting personnel.

A nuclear power plant must maintain its capability to combat a fire under any operating condition with fuel on site. A single failure in the fire prot-cltion system or direct support systems should not impair both primary and backup plant fire pirotectioni capability. For example, to avoid such a consequence, the pumping portion of fire protection water supply systems should be redundant and independent, including associated power supplie.s alnd controls. Also, failure or inadvertent operation of the fire suppression system should not result in failure of safety- related systems or components.

Postulated fires or fire protection system failures need not be considered concurrent with other plant accidents or the most severe natural phenomena, e.g., fire and a LOCA or fire and the Safe Shutdown Earthquake (SSE). However, in the event of the SSE, the fire protection system should be capable of delivering water from manual hose stations located within hose reach of areas containing equipment required for safe shutdown. The water supply for thi. condition may be obtained by manual operator actuation of valves in a connection to the hose standpipe header from a normal Seismic Category I water system such as the essential service water systemn. Thus at least manual hose and portable fire protection capability must be provided for all pottulated design basis events requiring plant shutdown. The fire protection systems should, however, because of the higher probability of occurrence, retain their original design capability for

(1) natural phenomena of less severity and greater frequency (approximately once in 10 years)

such as tornadoes, hurricanes, floods, ice storms, or small-intensity earthquakes that are characteristic of the site geographic region and (2) for potential man-created site-related events such as oil barge collisions and aircraft crashes that have a reasonable probability of occurring at a specific plant site. The effects of lightning strikes should be included in the overall plant fire protection system.

Fire protection starts with design and must be carried through in all phases of construction and operation. Furthermore, quality assurance (QA) programs are needed to identify and rectify errors in design, construction, and operation and are an essential part of defense in depth.

This guide is intended to implement the pHlosophy of defense-in-depth protection against the hazards of fire and its associated effects on safety-related equipment.

2. Use of Water on Electrical Fires Experience with major electrical fires shows that water should be used if initial attempts to put out a cable fire with other agents are not immediately successful. Since prompt extin- guishing of the fire is paramount to reactor safety, damage would be reduced by discreet applica- tion of water from automatic sprinklers rather than manual application with fire hoses. The widespread opinion and practice that emphasize the reasons for not using water as contrasted to those for its prompt and proper use are a concern. Firefighting procedures and fire training should provide the techniques, equipment, and skills for the use of water in fighting electrical fires in nuclear plants, particularly in areas containing a high concentration of electric cables with plastic insulation.

e This is not to say that water systems should be installed everywher

e. Equipment that may I

be damaged by water should be shielded or relocated away from the fire hazard and the water.

Drains should be provided to remove any water used for fire suppression and extinguishment.

3. Establishment and Use of Fire Areas The concept of separate fire areas for each division of safety equipment that requires redundancy will facilitate the installation of automatic water extinguishing systems since it will reduce the possibility of water damaging redundant safety-related equipment.

1.120-6

~1

Fire areas should be established based on the amount of combustible material present and considering suitably cljosen design basis fires so that adequate protection can be provided for safety-related systems and equipment. Design basis fires are those fires that result in the most duimage or most severe exposure to the area or systems being considered.

Within each area, special attention should be given to limiting the amount of combustible material ane to providing effective barriers and fire-resi3tive coatings to reduce the spread of a fire in these areas. A design basis fire should be assumed, and provisions should be made to limit the consequence of such a fire by providing fire barriers w.ith suitable separation between redundant systems and components that are provided to carry out required safety functions. This separation is enhanced if the plant is divided into suitable fire areas since redundant safety equipment can then be placed in separate fire areas.

Particular design attention should be given to the use of separate isolated fire areas for redundant cables to avoid loss of redundant safety-related cables.

Provisions should also be made to limit the consequences of a fire by suitable design of the ventilation systems so 'hat the spread of the products of combustion to other areas of the

  • plant is prevented. Means should be provided to ventilate, exhaust, or isolate the area as required. The power suppiy and controls for the area ventilation system should be from outside the area, and the power and control cables should not pass through the area.

In the design, consideration should be given to providing personnel access to and escape routes from each fire area. The emergency plans for all plants should lay out access and escape r*'o.tes to cover the event of a fire in critical areas of the plant.

C. REGULATORY POSITION

I. Overall Reqcuirements of the Fire Protection Program a. Personnel Responsibility for the overall fire protection program should be assigned to a desig- nated person in the upper level of management. This person should retain ultimate responsibility even though formulation and assurance of program implementation is delegated. Such delegation of authority should be to staff personnel prepared by training and experience in fire protection and nuclear plant safety to provide a balanced approach in directing the fire protection program for the nuclear power plant.

The fire protection staff should be responsible for:

(1) Coordination of building layout and systems design with fire area requirements, including consideration of potential hazards associated with postulated design basis fires.

(2) Design and maintenance of fire detection, suppression, and extinguishing systems.

(3) Fire prevention activities.

(4) Training and manual firefighting activities of plant personnel and the fire brigade.

( NOTE: NIFPA 6, "Recommendations for Organization of Industrial Fire Loss Prevention," contains useful guidance for organization and operation of the entire fire loss prevention program.)

b. Design Bases The overall fire protection program should be based on evaluation of potential fire hazards throughout the plant and the effect of postulated design basis fires relative to main- taining ability to perform safe shutdown functions and minimize radioactive releases to the environment.

c. Backup Total reliance should not be placed on a single automatic fire suppression system.

Appropriate backup fire suppression capability should be provided.

d. Single-Failure Criterion A single failure in the fire suppression system should not impair both the primary and backup fire suppression capability. For example, redundant fire water pumps with independent

1.120-7

power supplies and controls should be provided. Postulated fires or. fire protection system failures need not be considered concurrent with other plant accidents or the most severe natural phenomena. However, in the event of the most severe earthquake, i.e., the Safe Shutdown Earth- quake (SSE), the fire suppression system should be capable of delivering water to manual hose stations located within hose reach of areas containing equipment required for safe plant s;iut- down. The fire protection systems should, however, retain their original design capability for

(1) natural phenomena of less severity and greater frequency (appruximately once in 10 years)

such as tornadoes, hurricanes, floods, ice storms, or small-intensity earthquakes that are characteristic of the site geographic region and (2) for potential man-created site-related events such as oil barge collisions or aircraft crashes that have a reasonable probability of occurring at a specific plant site. The effects of lightning strikes should be included In the overall plant fire protection program.

e, Fire Suppression Systems Failure or inadvertent operation of the fire suppression system should not incapacitate safety-related systems or components. Fire suppression systems that are pressurized during normal plant operation should meet the guidelines specified for moderate energy systems outside containment in Section 3.6.1 of the Standard Review Plan, NUREG-75/087.

f. Fuel Storage Areas The fire protection program (plans. personnel, and equipment) for buildings stoting new reactor fuel and for adjacent fire zones tha: could affect the fuel storage zone should be fully operational before fuel is received at the site.

g. Fuel Loading The fire protection program for an entire reactor unit should be fully operational prior to initial fuel loading in that reactor unit.

h. Multiple-Reactor Sites On multiple-reactor sites where there are operating reactors and construction of remaining units is being completed, the fire protection program should provide continuing evalua- tion and include additional fire barriers, fire protection capability, and administrative controls necessary to protect the operating units from construction fire hazards. The superintendent of the operating plant should have the lead responsibility for site fire protection.

i. Simultaneous Fires Simultaneous fires in more than one reactor unit need not be considered. Because of separation requirements, a fire involving more than one reactor unit need not be considered except for facilities shared between units.

2. Administrative Procedures, Controls, and Fire Brigade a. Administrative procedures consistent with the need for'maintaining the performance of the fire protection system and personnel in nuclear power plants should be provided.

.Guidance is contained in the following publications:

NFPA 4 - Organization for Fire Services NFPA 4A - Organization of a Fire Department NFPA 6 - Industrial Fire Loss Prevention NFPA 7 - Management of Fire Emergencies NFPA 8 - Management Responsibility for Effects of Fire on Operations NFPA 27 - Private Fire Brigades b. Effective administrative measures should be implemented to prohibit bulk storage of combustible materials inside or adjacent to safety-related buildings or systems during operation or maintenance periods. Regulatory Guide 1.39, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants," provides guidance on housekeeping, including the disposal of combustible materials.

c. Normal and abnormal conditions or other anticipated operations such as modifications (e.g., breaking fire stops, impairment of fire detection and suppression systems) and refueling activities should be reviewed by appropriate levels of management and appropriate special action fire watches or temporary fire barriers implemented to ensure adequate and and as protection such fire procedures reactor safety. In particular:

1.120-8

(1) Work involving ignition sources such as welding and flame cutting should be done under closely controlled conditions. Procedures governing such work should be reviewed and approved by persons trained and experienced in fire protection. Persons performing and directly assisting in such work should be trained and equipped to prevent and combat fires. If this is not possible, a person qualified in fire protection should directly monitor the work and function as a fire watch.

(2) Leak testing and similar procedures such as airflow determination should use one of thc conmercially available aerosol techniques. Open flames or combustion-generated smoke should not be permitted.

(3) Use of combustible material, e.g., HEPA and charcoal filters, dry ion exchange resins, or othrr combustible supplies, in safety-related rreas should be controlled. Use of wood inside buildings containing safety-related systems or equipment should be permitted only when suitable noncombustible substitutes are not available. If wood must be used, only fire-retardant- treated wood (scaffolding, lay-down blocks) should be permitted. Such materials should be allowed into safety-related areas only when they are to be used immediately. Their possible and probable use should be considered in the fire hazard analysis to determine the adequacy of the installed fi:-e protection systems.

d. Nuclear power plants are frequently located in remote areas at '.ome distance from public fire dcpartments. Also, first response fire departments are often volunLeer. Public fire department response should be considered in the overall fire protection program. However, the plant should be designed to be self-sufficient with respect to firefighting activities and rely on tile public response only for supplemental or backup capability.

C. The need for good organization, training, and equipping of fire brigades at nuclear power plant sites requires that effective measures be implemented to ensure proper discharge of these functions. The g'..i.nce in Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants," should be followed as applicable.

(1) Successful flrefiqhting requires testing and maintenance of the fire protection equipment, and the emergency lighting and communication, as well as practice as brigades for the people who miust utilize the equipment. A test plan that lists the individuals and their respon- sibilities in connection with routine tests and inspections of the fire detection and protection systems should be developed. The test plan should contain the types, frequency, and detailed procedures for testing. Procedures should also contain instructions on maintaining fire protec- tion during those periods when the fire protection system is impaired or during periods of plant maiintenance, e.g., fire watches or temporary hose connections to water systems.

(2) Basic training is a necessary element in effective firefighting operation. In order for a fire brigade to operate effectiv.ely, it must operate as a team. All members must know what their individual duties are. They must be familiar with the layout of the plant and with equipment location and operation in order to permit effective firefighting operations during times when a particular area is filleq with smoke or is insufficiently lighted. Such training can only be accomplished by conducting drills several times a year (at least quarterly) so that all members of the fire brigade have had the opportunity to train as I team testing itself in the major areas of the plant. The drills should include the simulated use of equipment ii each area and should be preplanned and postcritiqued to establish the training objective of the drills and determine how well these objectives have been met. These drills should periodically (at least annually) include local fire department participation where possible. Such drills also permit supervising personnel to evaluate the effectiveness of communications within the fire brigade and with the on-scene fire team leader, the reactor operator in the control room, and the offsite commuand post.

(3) To have proper coverage during all phases of operation, members of each shift crew should be trained in fire protection. Training of the plant fire brigade should be coordinated with the local fire department so that responsibilities and duties are delineated in advance.

lhis coordination should be part of the training course and implemented into the training of the local fire department staff. Local fire departments should be educated in the operational pre- cautions when fighting fires on nuclear power plant sites. Local fire departments should be made aware of the need for radioactive protection of personnel and the special hazards associated with a nuclear power plant site.

(4) NFPA 27, "Private Fire Brigade," should be followed in organization, training, and fire drills. This standard also is applicable for the inspection and maintenance of firefighting equipment. Among the standards referenced in this document, the following should be utilized:

NFPA 194, "Standards for Screw Threads and Gaskets for Fire Hose Couplings," NFPA 196, "Standard for Fire Hose," NFPA 197, "Training Standard on Initial Fire Attacks," and NFPA 601, "Recommended

1.120-9 ENAMMMMOME"

Manual of Instructions and Duties for the Plant V~Atchman on Guard." UFPA booklts and pamphlets listed on page 27-11 of Volume 8, 1971-72, are also applicable for good training references. In addition, courses in fire prevention and fire suppression that are recognized and/or sponsored by the fire protection industry should be utilized.

3. Quality Assurance Program Quality assurance (QA) programs of applicants and contractors should be developed and implemented to ensure that the requirements for design, procurerr!nt, installation, and testing and administrative controls for the fire protection program for safety-related areas as defined in this guide are satisfied. The progra;:i should be under the management control of the QA

organization. The QA program criteria that apply to the fire protection program should include the following:

a. Design Controi and Procurement Document Control Measures should be established to ensure that all design-related guidelines of tUe regulatory position of this guide are included in design and procurement documents and that deviations therefrom are controlled.

b. Instructions, Procedures, and Drawings Inspections, tests, administrative controls, fire drills, and training that govern the fire protection program should be prescribed by documented instructions, procedures, or drawings and should be accomplished in accordance with these documents.

c. Control of Purchased Material, Equipment, and Services Measures should be established to ensure that purchased material, equipment, and services conform to the procurement documents.

d. Inspection A program for independent inspection of activities affecting fire protection should be established and executed by or for the organization performing the activity to verify conformance with documented installation drawings and test procedures for accomplishing the activities.

e. Test and Test Control A test program should be established and implemented to ensure that testing is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. 1ihe tests should be performed in accordance with written test procedures; test results should be properly evaluated and acted on.

f. Inspection, Test, and Operating Status Measures should be established to provide for the identification of itermis that have satisfactorily passed required tests and inspections.

9. Nonconforming Items Measures should be established to control items that do not conform to specified require- ments.to prevent inadvertent use or installation.

h. Corrective Action Measures should be established to ensure that conditions adverse to fire protection such as failures, malfunctions, deficiencies, deviations, defective components, uncontrolled combustible material, and nonconformances are promptly identified, reported, and corrected.

i. Records Records should be prepared and maintained to furnish evidence that the criteria enu- merated above are being met for activities affecting the fire protection program.

J. Audits Audits should be conducted and documented to verify compliance with the fire protection program, including design and procurement documents, instructions, procedures and drawings, and inspection and test activities.

1.120-10

- I

4. General Plant Guidelines a. Building Design (I) Plant layouts should be arranged to:

(a) Iso. 'e safety-related systems from unacceptable fire hazards and (b) Separate redundant safety-related systems from each other so that both are not subject to damage from a single Fire hazard.

(2) In order to atzomplish a.(l) above, safety-related systems and fire hazards should be identified throughout the plant. Therefore, a detailed fire hazard analysis should be niade during initial plant design.

(3) For multiple-reactor sites, cable spreading rooms should not be shared between reactors. Eaci coble spreading room should be separated from other areas of thp plant by barriers (walls and floors) having a minimum fire resistance of three hours. Cabling for redundant safety divisions should te separated by walls having three-hour fire barriers.

(4) Interior wall and structural components, thermal insulatinn materials, radiation shielding materials, and soundproofing should be noncombustible. Interior finishes should be noncomlbustible or listed by a nationally recognized testing laboratory such as Factory Mutual or Underwriters Laboratory, Inc. , for flame spread, s-roke, and fuel contribution of 25 or less in its use configuration (ASTM E-84 Test, "Surface Burning Characteristics of Building Materials").

(5) Metal deck roof construction should be noncombustible (see the building materials directory of the Underwriters Laboratory, Inc.) or listed as Class I by Factory Mutual System Approval Guide.

(6) Suspended ceilings and their supports should be of noncombustible construction.

Concealed spaces should be devoid of combustibles.

(7) Hign-voltage/high-amperage transformers installed inside buildings containing safety-related systems should be of the dry type or insulated and cooled with noncombustible liquid.

(8) Buildings containing safety-related systems should be protected from exposure or spill fires involving oil-filled transformers by:

C Locating such transformers at least 50 feet distant or a Ensu,'ing that such building walls within 50 feet of oil-filled transformers are without openings and have a fire resistance rating of at least three hours.

(9) Floor drains sized to remove expected firefighting waterflow should be provided in those areas where fixed water fire suppression systems are inst~lled. Drains should also be provided in other areas where hand hose lines may be used if such firefighting water could cause unacceptable damage to equipment in the area. Equipment should be installed on pedestals, or curbs should be provided, as required, to contain water and direct it to floor drains. (See NFPA 92, "Waterproofing and Draining of Floors.") Drains in areas containing combustible liquids should have provisions for preventing the spread of the fire throughout the drain system. Water drainage from areas that may contain radioactivity should be sampled and analyzed before discharge to the environment.

(10) Floors, walls, and ceilings enclosing separate fire areas should have a minimum fire rating of three hours. Penetrations in these fire barriers, including conduits and piping, should be sealed or closed to provide a fire resistance rating at least equal to that of the barrier itself. Door openings should be protected with equivalent rated doors, frames, and hardware that have been tested and approved by a nationally recognized laboratory. Such doors should be normally closed and locked or alarmed with alarm and annunciation in the control room.

Penetrations for ventilation systems should be protected by a standard "fire door damper" where required. (See IIFPA 80, "Fire Doors and Windows.")

b. Control of Combustibles

(1) Safety-related systems should be isolated or separated from combustible materials.

When this is not possible because of the nature of the safety system or the combustible material,

1.120-11

special protection should be provided to prevent a fire from defeating the safety system function.

Such protection may involve a combination of automatic fire suppression and construction capable of withstanding and containing a fire that consumes all combustibles present. Examples of such combustible materials that may not be separable from the remainder of its system are:

(a) Emergency diesel generator fuel oil day tanks.

(b) Turbine-generator oil and hydraulic control fluid systems.

(c) Reactor coolant pump lube oil system.

(2) Bulk gas storage (either compressed or cryogenic.) should not be permitted inside structures housing safety-related equipment. Storage of flanrnable gas such as hydrogen should be located outdoors or in separate detached buildings so that a fire or explosion will not adversely affect any safety-related systems or equipment. (See NFPA 50A, "Gaseous Hydrogen Systems.")

Care should be taken to locate high-pressure gas storage containers with the long axis parallel to building walls. This will minimize the possibility of wall penetration in the event of a container failure. Use of compressed gases (especially flammable and fuel gases)

inside buildings should be controlled. (See NFPA 6, "Industrial Fire Loss Prevention.")

(3) The use of plastic materials should be minimized. In particular, halogenated plastics such as polyvinyl chloride (PVC) and neoprene should be used only when substitute noncombustible materials are not available. All plastic materials, including flamie- and fire- retardant materials, will burn with an intensity and Btu production in a range similar to that of ordinary hydrocarbons. When b'irning, they produce heavy dense smoke that obscures visibility and can plug air filters, especially charcoal and HEPA. The haioqenated plastics also release free chlorine and hydrogen chloride, which are toxic to humans *.J corrosive to equipment.

(4) Storage of flammable liquids shoula, as a minimum, comply with the requirements of NFPA 30, "Flammable and Combustible Liquids Code."

c. Electrical Cable Construction, Cabe Trays, and Cable Penetrations

(1) Only noncombustible materials should be used for cable tray construction.

(2) See Regulatory Position C.6.c. for fire protection guidelines for cable spreading rooms.

(3) Automatic water sprinkler systems should be provided for cable trays outside the cable spreading room. Cables should be designed to allow wetting down with deluge water without electrical faulting. Manual hose stations and portable hand extinguishers should be provided as backup. Safety-related equipment in the vicinity of such cable trays that does not itself require water fire protection but is subject to unacceptable damage from sprinkler water dis- charge should be protected from sprinkler system operation or malfunction.

(4) Cable and cable tray penetration of fire barriers'(vertical and horizontal)

should be sealed to give protection at least equivalent to that provided by the fire barrier.

The design of fire barriers for horizontal and vertical cable trays should, as a minimum, meet the requirements of ASTM E-119, "Fire Test of Building Construction and Materials," including the hose stream test.

(5) Fire breaks should be installed every 10 feet along horizontal and vertical cable routings to prevent the propagation of a fire. Flame- or fire-retardant coatings may be used as a fire break for grouped electrical cables to limit spread of fire in cable routings. (Possible cable derating owing to use of such coating materials must be considered during design.)

(6) Electric cable constructions should as a minimum pass the current IEEE No. 383 flame test. (This does not imply that cables passing this test will not require additional fire protection.)

(7) To the extent practical, cable construction that does not give off corrosive gases while burning should be used.

(8) Cable trays, raceways, conduit, trenches, or culverts should be used only for cables. Miscellaneous storage should not be permitted nor should piping for flammable or com- bustible liquids or gases be installed in these areas.

1.120-12

(9) The design of cable tunnels, culverts, and spreading rooms should provide for automatic or manual smoke venting as required to facilitate manual firefighting capability.

(10) Cables in the control room should be kept to the minimum necessary for operation of the control room. All cables entering the control room should terminate there. Cables should not be installed in floor trenches or culverts in the control room.

d. Ventilation

(1) The products of combustion that need to be removed from a rpecific fire area should be evaluated to determine how they will be controlled. Smoke and corrosive gases should generally be automatically discharged directly outside to a safe location. Smoke and gases containing radioactive materials should be monitored in the fire area to determine if release to the environment is within tho permissible limits of the plant Technical Specifications.

(2) Any ventilation system designed to exhaust smoke or corrosive gases should be evaluated to ensure that inadvertent operation or single failures will not violate the controlled areas of the plant design. This requirement includes containment functions for protection of the public and maintaining habitability for operations personnel.

(3) The power supply and controls for mechanical ventilation systems should he run outside the fire area served by the system.

(4) Fire suppression systems should be installed to protect charcoal filters.

(C) The fresh-air supply intakes to areas containing safety-related equipment or systems shou;d be located remote from the exhaust air outlets and smoke vents of other fire areas to minir.-ize the possibility of contaminating the intake air with the products of combustion.

(6) Stairvells should be designed to minimize smoke infiltration during a fire.

Staircases should serve as escape routes and access routes for firefighting. Fire exit routes should be clearly marked. Stairwells, elevators, and chutes should be enclosed in masonry towers with a minimum fire rating of three hours and automatic fire doors at least equal to the enclosure construction at each opening into the building. Elevators should not be used during fire emergencies.

(7) Smoke and heat vents may be useful in specific areas such as cable spreading rooms, diesel fuel oil storage areas, and switchgear rooms. When natural-convection ventilation is used, a minimum ratio of 1 square foot of vent area per 200 square feet of floor area should be provided. If forced-convection ventilation is used, 300 cfm should be provided for every

200 square feet of floor area. See NFPA 204 for additional guidance on smoke control.

(8) Self-contained breathing apparatus using full-face positive-pressure masks approved by ?LIOSH (Nlational Institute for Occupational Safety and Health - approval formerly given by the U.S. Bureau of Mines) should be provided for fire brigade, damage control, and control room personnel. Control room personnel may be furnished breathing air by a manifold system piped from a storage reservoir if practical. Service or operating life should be a minimum of one-half hour for the self-contained units.

At least two extra air bottles should be located on site for each self-contained breathing unit. In addition, an onsite 6-hour supply of reserve air should be provided and arranged to permit quick and complete replenishment of exhausted supply air bottles as they are returned. If compressors are used as a source of breathing air, only units approved for breath- ing air should be used. Special care must be taken to locate the compressor in areas free of dust and contaminants.

(9) Where total flooding gas extinguishing systems are used, area intake and exhaust ventilation dampers should close upon initiation of gas flow to maintain necessary gas concentra- tion. (See NJFPA 12, "Carbon Dioxide Systems," and NFPA 12A, "Halon 1301 Systems.")

e. Lighting and Communication Lighting and two-way voice communication are vital to safe shutdown and emergency response in the event of fire. Suitable fixed and portable emr-gency lighting and communication devices should be provided to satisfy the following requirements:

(1) Fixed emergency lighting should consist of sealed beam units with individual

8-houw minimum battery power supplies.

1.120-13

  • (2) Suitable sealed-beam battery-powered portable hand lights should be provided for emergency use.

(3) Fixed emergency conrnunication should use voice-powered headsets at preselected stations.*

sodb(4) Fixed repeaters installed to permit use of portable radio communication units should be protected from exposure fire damage.

5. Fire Detection and Suporession

a. Fire Detection

  • (1) Fire detection systems should, as a minimum, comply with NFPA 72D, "Standard for the Installation, Maintenance and Use of Proprietary Protective Signaling Systems."

(2) Fire detection systems should give audible and visual alarm and annunciation in the control room. Local audible alarms should also sound at the location of the fire.

(3) Fire alarms should be distinctive and unique. They should not be capable of being confused with any other plant system alarms.

(4) Fire detection and actuation systems should be connected to the plant emergency power supply.

  • b. Fire Protection Water Supply Systems

(1) An underground yard fire main loop should be installed to furnish anticipated water requirements. NFPA 24, "Standard for Outside Protection," gives necessary guidance for such installation. It references other design codes and standards developed by such organiza- tions as the American National Standards Institute (ANSI) and the American Water Works Associa- tion (AWWA). Lined steel or cast iron pipn should be used to reduce internal tuberculation.

Such tuberculation deposits in an unlined pipe over a period of years can significantly reduce waterflow through the combination of increased friction and reduced pipe diameter. Means for treating and flushing the systems should be provided. Approved visually indicating sectional control valves, such as post indicator valves, should be provided to isolate portions of the main for maintenance or repair without shutting off the entire system.

The fire main system piping should be separate from service or sanitary water system piping.

  • (2) A conmon yard fire main loop may serve multi-unit nuclear power plant sites if cross-connected between units. Sectional control valves should permit maintaining independence
  • of the individual loop around each unit. For such installations, common water supplies may also be utilized. The water supply should be sized for the largest single expected flow. For multiple- reactor sites with-widely separated plants (approaching I mile or more), separate yard fire main loops should be used.

(3) If pumps are required to meet system pressure or flow requirements, a sufficient number of pumps should be provided so that lO1 capacity will be available with one pump inactive (e.g., three 50% pumps or two 100% pumps). The connection to the yard fire main loop from each fire pump should be widely separated, preferably located on opposite sides of the plant. Each pump should have its own driver with independent power supplies and control. At least one pump should be driven by nonelectrical means, preferably diesel engine. Pumps and drivers should be located in rooms separated from the remaining pumps and equipment by a minimum three-hour fire wall. Alarms indicating pump running, driver availability, or failure to start should be pro- vided in the control room.

Details of the fire pump installation should, as a minimum, conform to NFPA 20,

"Standard for the Installation of Centrifugal Fire Pumps."

(4) Two separate, reliable water supplies should be provided. If tanks are used, two

100% (minimum of 300,000 gallons each) system capacity tanks should be installed. They should be so interconnected that pumps can take suction from either or both. However, a leak. in one tank or its piping should not cause both tanks to drain. The main plant fire water supply capacity should be capable of refilling either tank in a minimum of eight hours.

Common tanks are permitted for fire and sanitary or service water storage. When this is done, however, minimum fire water storage requirements sheuld be dedicated by means of a vertical standpipe for other water services.

1.120-14

(5) The fire water supply (total capacity and flow rate) should be calculated on the basis of the largest expected flow rate for a period of two hours, but not less than 300,000 gal- lons. This flow rate should bn based (conservatively) on 1,000 gpm for manual hose streams plus the greater of:

(a) All sprinkler heads open and flowing in the largest designed fire area or (h) The largest open-head deluge system(s) operating.

,6) Lakes or freshwater ponds of sufficient size may qualify as sole source of water for fire protection but require at least two intakes to the pump supply. When a comminon water supply is permitted for fire protection and the ul:imate heat sink, the following conditions should also be satisfied:

(a) The additional fire protection water requirements are designed into the total storage capacity and (b) Failure of the fire protection system should not degrade the function of the ultir:ate heat sink.

(7) Outside ;anual hose installation should be sufficient to reach any location with

.an effective hose stream. To accomplish this, hydrants should be installed approximately every

250 feet on the yard main system. The lateral to each hydrant from the yard main should be controlled by a visually indicating or key-operated (curb) valve. A hose house equipped with hose and combination nozzle and other auxiliary equipwent recoiimended in TIFPA 24. "Outside Pro- tection." S;houJld be provided as needed but at least ever'y 1,000 feet.

Threads cowpatible with those used by local fire departments should he provided on all hydrants. hose couplings, and standpipe risers.

c*. 1 , neand _andpi pSytd.

(1) Each automatic sprinkler system and manual hose station standpipe should have ar independent connection to the plant underground water main. Headers fed from each end are per- mitted inside buildings to supply multiple sprinkler and standpipe systems. When provided, such headers are considered an extension of the yard main system. The header arrangement should be such that no sinmle failure can impair both the primary and backup fire protection systems. Each spriNkler and standpipe system should he equipped with 0S&Y (outside screw and yoke) gate valve or other approved shutoff valve and waterflow alar,. Safety-related equipment that does not itself require sprinkler water fire protection but is subject to unacceptable damage if wet by sprinkler water discharge should be protected by water shields or baffles.

(2) All valves in the fire water systems should be electrically supervised. The elec;trical super'visicn signal Should indicate in the control room and other appropriate command locatiuns in the plant. (See MIFPA 26, "Supervision of Valves.")

(3) Automatic sprinkler systems should, as a minimum, conform to requirements of appropriate standards such as nFPA 13, "Standard for the Installation of Sprinkler Systems." and N1FPA 15, "Standard for Water Spray Fixed Systems."

(4l) Interior manual hose installation should be able to reach any location with at least one effective hose stream. To accomplish this. standpipes with hose connections equipped with a maximum of 75 feet of 111/2-inch woven jacket-lined fire hose and suitable nozzles should he provided in all buildings, including containment, on all floors and should be spaced at not more than 100-foot intervals. Individual standpipes should be at least 4 inches in diameter for multiple hose connections and 2-1/2 inches in diameter for single hose connections. These systems should follow the requirements of NIFPA 14, "Standpipe andHose Systems," for sizing, spacing, and pipe support requirements.

Hose stations should be located outside entrances to normally unoccupied areas and inside normally occupied areas. Standpipes serving hose stations in areas housing safety-related equipment should have shutoff valves and pressure-reducing devices (if applicable) outside the area.

Provisions should be made to supply water at least to standpipes and hose connec- tionis for manual firefighting in areas within hose reach of equipment required for safe plant shutdown in the event of a Safe Shutdown Earthquake. The standpipe system serving such hose stations should be analyzed for SSE loading and should be provided with supports to ensure system

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pressure integrity. The piping and-valves for the portion of hose standpipe system affected by this functional requirement should at least satisfy ANSI Standard B31.1, "Power Piping." The water supply for this condition may be obtained by manual operator actuation of valves in a connection to the hose standpipe header from a normal Seismic Category I water system such as the essential service water system. The cross connection should be (a) capable of providing flow to at least two hose stations (approximately 75 gpm per hose station) and (b) designed to the same standards as the Seismic Category I water system; it should not degrade the performance of the Seismic Category I water system.

(5) The proper type of hose nozzle to be supplied to each area should be based on the fire hazard analysis. The usual combination spray/straight-stream nozzle may cause unacceptable mechanical damage (for example, to delicate electronic equipment in the control room) and be unsuitable. Electrically safe nozzles should be provided at locations where electrical equipment or cabling is located.

(6) Certain fires such as those involving flammable liquids respond well to foam suppression. Consideration should be given to use of any of the available foams for such special- ized protection application. These.include the more common chemical and mechanical low-expansion foams, high-expansion foam, and the relatively new aqueous film-forming foam (AFFF).

d. Halon Suppression Systems The use of Halon fire extinguishing agents should, as a minimum, comply with the requirements of NFPA 12A and 12B, "Halogenated Fire Extinguishing Agent Systems - Halon 1301 and Halon 1211." Only UL or FM approved agents should be used.

In addition to the guidelines of 11FPA 12A and 128, preventive maintenance and testinn of t0e systems, including check-weighing of Nie Halon cylinders, should be done at least quarterly.

Particular consideration should also be given to:

(1) Minimum required Halon concentration and soak time.

(2) Toxicity of Halon.

(3) Toxicity and corrosive characteristics of thermal decomposition products of HaIon.

e. Carbon Dioxide Suppression Systems- The use of carbon dioxide extinguishing systems should, as a minimum, coaiply with the requirements of NFPA 12, "Carbon Dioxide Extinguishing Systems."

Particular consideration should also be given to:

(1) Minimum required C02 concentration and soak time;-

(2) Toxicity of C02 ;

(3) Possibility of secondary thermal shock (cooling) damage;

(4) Offsetting requirements for venting during C02 injection to prevent overpressuriza- tion versus sealing to prevent loss of agent;

(5) Design requirements from overpressurization; and

(6) Possibility and probability of C02 systems being out of service because of per- sonnel safety consideration. C02 systems are disarmed whenever people are present in an area so protected. Areas entered frequently (even though duration time for any visit is short) have often been found with C02 systems shut off.

f. Portable Extinquils'rs Fire extinguishers should be provided in accordance with guidelines of NFPA 10, "Port- able Fire Extinguishers, Installation," and IDA, "Portable Fire Extinguishers, Maintenance and Use." Dry chemical extinguishers should be installed with due consideration given to cleanup problems after use and possible adverse effects on equipment installed in the area.

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6. Guidelines for Specific Plant Areas a. Primary and Secondary Containment

(1) Normal Operation - Fire protection requirements for the primary and secondary containment areas should be provided on the basis of specific identified hazards. For example:

° Lubricating oil or hydraulic fluid system for the primary coolant pumps Cable tray arrangements and cable penetrations Charcoal filters Because of the general inaccessibility of these areas during normal plant opera- tion, protection should be provided by automatic fixed systems. Automatic sprinklers should be installed for those hazards identified as requiring fixed suppression.

Operation of the fire protection systems should not compromise the integrity of the containment or other safety-related systems. Fire protection activities in the containment areas should function in conjunction with total containment requirements such as control of contaminated liquid and gaseous release and ventilation.

Fire detection systems should alarm and annunciate in the control room. The type of detection used and the location of the detectors should be most suitable to the particular type of fire that could be expected from the identified hazard. A primary containment general area fire detection capability should be provided as backup for the above-described hazard detec- tion. To accomplish this, suitable smoke detectors (e.g., visual obscuration, light scattering, and particle counting) should be installed in the air recirculation system ahead of any filters.

Automatic fire suppression capability need not be provided in the primary contain- ment atmospheres that are inerted during normal operation. However, special fire protection requirements during refueling and maintenance operations should be satisfied as provided below.

(2) Refueling and 1.laintenance - Refueling and maintenance operations in containment may introduce additional hazards such as contamination control materials, decontamination sup- plies, wood planking, temporary wiring, welding, and flame cutting (with portable compressed fuel

!:as supply). Possible fires would not necessarily be in the vicinity of fixed detection and suppression systems.

Management procedures and controls necessary to ensure adequate fire protection are discussed in Section C.I. In addition, manual firefighting capability should be permanently installed in containment. Standpipes with hose stations and portable fire extinguishers should be installed at strategic locations throughout containment for any required manual firefighting operations.

Adequate self-contained breathing apparatus should be provided near the contain- ment entrances for firefighting and damage control personnel. These units should be independent of any breathing apparatus or air supply systems provided for general plant activities.

b. Control Room The control room is essential to safe reactor operation. It must be protected against disablino fire damage and should be separated from other areas of the plant by floors, walls, and roof having minimum fire resistance ratings of three hours.

Control room cabinets and consoles are subject to damage from two distinct fire hazards:

(1) Fire originating within a cabinet or console and

(2) Exposure fires involving combustibles in the general room area.

Manual firefighting capability should be provided for both hazards. Hose stations and portable water and Ilalon extinguishers should be located in the control room to eliminate the need for operators to leave the control room. An additional hose piping shutoff valve and pressure-reducing device should be installed outside the control room.

NJozzles that are compatible with the hazards and equipment in the control room should be provided for the manual hose station. The nozzles chosen should satisfy actual firefighting needs, satisfy electrical safety, and minimize physical damage to electrical equipment from hose stream impingement.

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Fire detection in the control room, cabinets, and consoles should be provided by smoke and heat detectors in each fire area. Alarm and annunciation should be provided in the control room. Fire alarms in other parts of the plant should also be alarmed and annunciated in the control room.

Breathing apparatus for control room operators should be readily available. Control room floors, ceilings, supporting structures, and walls, including penetrations and doors, should be designed to a minimum fire rating of three hours. All penetration seals should be airtight.

The control room ventilation intake should be provided with smoke detection capability to automatically alarm locally and isolate the control room ventilation system to protect opera- tors by preventing smoke from entering the control room. Manually operated venting of the con- trol room should be available so that operatorshave the option of venting for visibility.

Cables should not be located in concealed floors and ceiling spaces. All cables that enter the control room should terminate in the control room. That is, no cabling should be simply routed through the control room from one area to another.

Safety-related equipment should be mounted on pedestals, or the control room should have curbs and drains to direct water away from such equipment. Such drains should be provided with means for closing to maintain integrity of the control room in the event of other accidents requiring control room isolation.

c. Cable Spreading Room The primary fire suppression in the cable spreading room should be an automatic water system such as closed-head sprinklers, open-head deluge, or open directional spray nozzles.

Deluge and open spray systems should have provisions for manual operation at a remote station;

however, there should be provisions to preclude inadvertent operation. Location of sprinkler heads or spray nozzles should consider cable tray sizing and arrangements to ensure adequate water coverage. Cables should be designed to allow wetting down with deluge water without electrical faulting.

Open-head deluge and open directional spray systems should be zoned so that a single failure will not deprive the entire area of automatic fire suppression capability.

The use of foam is acceptable, provided it is of a type capable of being delivered by a sprinkler or deluge system, such as an aqueous film-forming foam (AFFF).

An automatic water suppression system with manual hoses and portable extinguisher backup is acceptable, provided:

(1) At least two remote and separate entrances are provided to the room for access by fire brigade personnel and

(2) Aisle separation provided between tray stacks should be at least three feet wide and eight feet high.

Alternatively, gas systems (Halon or C02 ) may be used for primary fire suppression if they are backed up by an installed water spray system and hose stations and portable extinguishers immediately outside the room and if the access requirements stated above are met.

Electric cable construction should, as a minimum, pass the flame test in IEEE Std 383,

"IEEE Standard Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations."

Drains to remove firefighting water should be provided with adequate seals when gas extinguishing systems are also Installed.

Redundant safety-related cable divisions should be separated by walls with a three-hour fire rating, For multiple-reactor unit sites, cable spreading rooms should not be shared between reactors. Each cable spreading room of each unit should have divisional cable separation as stated above and be separated from the other and the rest of the plant by a wall with a minimum fire rating of three hours. (See NFPA 251, "Fire Tests, Building Construction and Miaterials," or ASTM E-119, "Fire Test of Building Construction and Materials," for fire test resistance rating.)

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The ventilation system to the cable spreading room should be designed to isolate the area upon actuation of any gas extinguishing system in the area. In addition, smoke venting of the cable spreading room may be desirable. Such smoke venting systems should ;,ccontrolled automatically by the fire detection or suppression system as appropriate. Capability for remote manual control should also be provided.

d. Plant Computer Room Computer rooms should be separated from other areas of the plant by barriers having a

.inini:um fire resistance rating 'of three hours. Automatic fire detection should be provided to alarm and annunciate in the control room and alarm locally. Manual hose stations and portable water and Halon fire extinguishers should be provided.

e. Switchgear Rooms Switchgear rooms should be separated from the remainder of the plant by barriers with a minimum fire rating of three hours. Redundant switchgear safety divisions should be separated by three-hour fire rated barriers. Automatic fire detectors should alarm and annunciate in the control room and alarm lotally. All cables that enter the switchgear room should terminate there. These rooms should not be used for any other purpose. Fire hose stations and portable fire extinguishers should be readily available.

Equipment should be located on pedestals or curbs, and drains should be provided to direct water away from safety-related equipment. (See NIFPA 92M, "Waterproofing and Draining of Floors.") Remote manually actuated ventilation should be provided for venting smoke when manual fire suppression effort is needed.

f. Remote Safety-Related Panels The general area housing remote safety-related panels should be provided with automatic fire detectors that alarm locally and alarm and annunciate in the control roo

m. Combustible

,aterials should be controlled and limited to those required for operation. Portable extinguishers and manual hose stations should be provided.

g. Station Battery Rooms Battery rooms should be protected against fire explosions. Battery rooms should be separated from each other and other areas of the plant by barriers having a minimum fire rating of three hours inclusive of all penetrations and openings. (See NIFPA 69, "Standard on Explosion Prevention Systems.") Battery rooms should be provided with hydrogen concentration detectors that alarm and annunciate in the control room and alarm locally. The detector alarm setpoint should be no greater than 2 vol-` hydrogen concentration. Ventilation systems in the battery roommms should be capable of maintaining the hydrogen concentration well below the detector alarm setpoint. Standpipe and hose and portable extinguishers should be provided.

h. Turbine Lubrication and Control Oil Storage and Use Areas A blank fire wall having a minimum resistance rating of three hours should separate all areas containing safety-related systems and equipment from the turbine oil systems.

i. Diesel Generator Areas Diesel generators should be separated from each other and other areas of the plant by fire barriers having a minimum fire resistance rating of three hours.

Automatic fire suppression such as AFFF, foam, or sprinklers should be installed to combat any diesel generator or lubricating oil fires. Automatic fire detection should be pro- vided to alarm and annunciate in the control room and alarm locally. Drainage for firefighting water and means for local manual venting of smoke should be provided.

Day tanks with total capacity up to 1100 gallons are permitted in the diesel generator area under the following conditions:

(1) The day tank is located in a separate enclosure with a minimum fire resistance rating of three hours, including doors or penetrations. These enclosures should be capable of containing the entire contents of the day tanks. The enclosure should be ventilated to avoid accumulation of oil fumes.

1.120-19

should be protected by an automatic fire suppression system such as

(2) AFFF enclosure The or sprinklers.

j. Diesel Fuel 0il Storage Areas Diesel fuel oil tanks with a capacity greater than 1100 gallons should not be located inside the buildings containing safety-related equipment. They should be located at least

50 feet from any building containing safety-related equipment or, if located within 50 feet, they should be housed in a separate building with construction having a minimum fire resistance rating of three hours. Buried tanks are considered as meeting the three-hour fire resistance require- ments. See ?lFPA 30, "Flammable and Combustible Liquids Code," for additional guidance.

When located in a separate building, the tank should be protected by an automatic fire suppression system such as AFFF or sprinklers.

Tanks should not be located directly above or below safety-related systems or equipment regardless of the fire rating of separating floors or ceilings.

k. Safety-Related Pumps Pump houses and rooms housing safety-related pumps or other safety-related equipment should be separated from other areas of the plant by fire barriers having at least three-hour ratings. These rooms should be protected by automatic sprinkler protection unless a fire hazards analysis can demonstrate that a fire will not endanger other safety-related equipment required for safe plant shutdown. Early warning fire detection should be installed with alarm and annunciation locally and in the control room. Local hose stations and portable extinguishers should also be provided.

Equipment pedestals or curbs and drains should be provided to remove and direct water away from safety-related equipment.

Provisions should be made for manual control of the ventilaticn system to facilitate smoke removal if required for manual firefighting operation.

1. New Fuel Area Hand portable extinguishers should be located within this area. Also, local hose stations should be located outside but within hose reach of this area. Automatic fire detection.

should alarm and annunciate in the control room and alarm locally. Combustibles should be limited to a minimum in the new fuel area. The storage area should be provided with a drainage system to preclude accumulation of water.

The storage configuration of new fuel should always be so maintained as to preclude criticality for any water density that might occur during fire water application.

m. Spent Fuel Pool Area Protection for the spent fuel pool area should be provided by local hose stations ind portable extinguishers. Automatic fire detection should be provided to alarm and annunciate in the control room and to alarm locally.

n. Radwaste Building The radwaste building should be separated from other areas of the plant by fire barriers having at least three-hour ratings. Automatic sprinklers should be used in all areas where combustible materials are located. Automatic fire detection should be provided to annunciate and alarm in the control room and alarm locally. During a fire, the ventilation systems in these areas should be capable of being isolated. Water should drain to liquid radwaste building sumps.

o. Decontamination Areas The decontamination areas should be separated from other areas of the plant by fire barriers having at least three-hour ratings. These areas should be protected by automatic sprinklers. Automatic fire detection should be provided to annunciate and alarm in the control room and alarm locally. The ventilation system should be capable of being isolated. Local hose stations and hand portable extinguishers should be provided as backup to the sprinkler system.

1.120-20

______________________________________________________________________________

I

p. Safety-Related Water Tanks Storage tanks that supply water for safe shutdown should be protected from the effects of fire. Local hose stations and portable extinguishers should be provided. Portable extin- guishers should be located in nearby hose houses. Combustible materials should not be stored next to outdoor tanks. A minimum of 50 feet of separation should be provided between outdoor tanks and combustible materials where feasible.

q. Records Storage Areas Records storage areas should be protected with automatic preaction sprinkler systems.

Early warning fire detectors should be provided to alarm and annunciate in the control room and to alarm locally. Local hose stations and portable extinguishers should serve as backup. (See rFPA 232AM, "Manual for Fire Protection for Archives and Records Centers," Regulatory Guide 1.88,

"Collection, Storage, and Maintenance of Nuclear Power Quality Assurance Records," and ANSI

N45.2.9, "Requirements for Collection, Storage, and Maintenance of Quality Assurance Recordc for Nuclear Power Plants.")

r. Cooling Towers Cooling towers should be of noncombustible construction or so located that a fire will not adversely affect any safety-related systems or equipment. Cooling towers should be of non- combustible construction when the basins are used for the ultimate heat sink or for the fire protection water supply.

s. Miscellaneous Areas Miscellaneous areas such as shops, warehouses, and auxiliary boiler rooms should be so located that a fire or effects of a fire, including smoke, will not adversely affect any safety- related systems or equipment. Fuel oil tanks for auxiliary boilers should be buried or provided with dikes to contain the entire tank contents.

7. Sýpecal Protection Guidelines a. Meldinq and Cutting Acetylene-Oxygen Fuel Gas Systems This equipment is used in various areas throughout the plant. Storage locations should be chosen to permit fire protection by automatic sprinkler systems. Local hose stations and portable equipment should be provided as backup. The requirements of NFPA 51 and 51B are applicable to these hazards. A permit system should be required to utilize this equipment.

(Also see C.2 herein.)

b. Storage Areas for Dry Ion Exchange Resins Dry ion exchange resins should not be stored near essential safety-related systems.

Dry unused resins should be protected by.automatlc wet pipe sprinkler installations. Detection by smoke and heat detectors should alarm and annunciate in the control room and alarm locally.

Local hose stations and portable extinguishers should provide backup for these areas. Storage areas of dry resin should have curbs and drains. (See NFPA 92M, "Waterproofing and Draining of Floors.")

c. Hazardous Chemicals Hazardous chemicals should be stored and protected in accordance with the recommenda- tions of NFPA 49, "Hazardous Chemicals Data." Chemical storage areas should be well ventilated and protected against flooding conditions since some chemicals may react with water to produce ignition.

d. Materials Containing Radioactivity Materials that collect and contain radioactivity such as spent ion exchange resins, charcoal filters, and HEPA filters should be stored in closed metal tanks or containers that are located in areas free from ignition sources or combustibles. These materials should be protected from exposure to fires in adjacent areas as well. Consideration should be given to requirements for removal of isotopic decay heat from entrained radioactive materials.

1.120-21

D. IMPLEMENTATION

The purpose.of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.

Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Conmission's regulations, the method described herein will be used in the evaluation of submiittals in connection with construction permit applications docketed after February 28, 1977.

If an applicant wishes to use this regulatory guide in developing submittals for applica- tions docketed on or before February 28, 1977, the pertinent portions of the application will be evaluated on the basis of this guide.

1.120-22

REFERENCES

National Fire Protection Association Codes and Standards

1IFPA 4, "Organization of Fire Services."

INFPA 4A, "Fire Department Organization."

NFPA 6, "Industrial Fire Loss Prevention."

NFPA 7, "Fire Emergencies flangement."

rIFPA , "Effects of Fire on Operations, Management Responsiblity."

NFPA IC, "Portable Fire Extinguishers, Installation."

tJFPA IOA, "Port-able Fire Extinguishers, Maintenance and Use."

NFPA 11, "Foaw Extinguishing Systems."

IJFPA 12, "Carbon Dioxide Systems."

IIFFA 12A, "Halon 1301 Systems.'

NFPA 12U,, "Halon 1211 Systems."

NiFPA 14, "Standpipe and Hose Systems."

NFPA 15, "Water Spray Fixed Systems."

NFFPA 20, "Centrifugal Fire Pumps."

N;FPA 24, "Outside Protection."

'IFPA 26, "Supervision of Valves."

1jFPA 27, "Private Fire Brigade."

NFPA 30, "Flamimable Combustible Liquids Code."

IIFPA 49, "Hazardous Chemicals Data."

NFPA 50A, "Gaseous Hydrogen Systems."

NFPA 69, "Explosion Prevention System."

NFPA 72D, "Proprietary Signaling Systems."

IIFPA 60, "Fire Doors and Vindows."

NFPA 9214, "Waterproofing and Draining of Floors,"

r1FPA 194, "Fire Hose Connections."

NFPA 196, "Fire Hose."

IJFPA 197, "Initial Fire Attack, Training, Standard On."

NIFPA 204, "Smoke and Heat Venting Guide."

NiFPA 232 AM, "Archives and Record Centers."

NFPA 251, "Fire Tests, Building Construction and Materials."

1.120-23

NFPA 601, "Guard Service in Fire Loss Prevention."

U.S. Nuclear Regulatory Commission Documents NUREG-O050, "Recommendations Related to Browns Ferry Fire," Report by Special Review Group, published Februdry 1976.

WASH-1400 (NUREG-75/014), "Reactor Safety Study - An Assessment of Accident Risks in U.S.

Commercial Nuclear Power Plants," published October 1975.

Standard Review Plan 9.5.1, "Fire Protection System."

Standard Review Plan 3.6.1, "Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment."

Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licens- ing of Production and Utilization Facilities," General Design Criterion 3, "Fire Protection."

Regulatory Guide 1.39, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants."

Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants," Revision 2, Section 9.5.1.

Regulatory Guide 1.75, "Physical Independence of Electrical Systems."

Regulatory Guide 1.88, "Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records."

Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants."

Other Documents ANSI Standard B31.1, "Power Piping."

ANSI Standard N45.2.9, "Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants."

ASTM E-84, "Surface Burning Characteristics of Building Materials."

ASTM E-119, "Fire Test of Building Construction and Materials."

IEEE Std 383-1974, "IEEE Standard of Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations," April 15, 1974.

NELPIA, "Specifications for Fire Protection of New Plants."

RP-0O-69, "Recommended Practical Control of External Corrosion on Underground or Submerged Metallic Piping Systems," Material Association of Corrosion Engineers.

Factory Mutual System Approval Guide - Equipment, Materials, Services for Conservation of Property.

International Guidelines for the. rire Protection of Nuclear Power Plants, National Nuclear Risks Insurance Poois, 2nd Report (IGL).

Underwriters Laboratories Rating List.

1.120-24