Report of the Committee on

Atomic Energy

Leonard R. Hathaway, Chair M&M Protection Consultants, GA, [I]

Wayne D. Holmes, Secretary HSB Professional Loss Control Inc., CT [I]

Mario A~ Antonetti, Gage-Babcock & Assn. Inc., NY [SE] Jack Balla, New York Power Authority, NY [U] William G. Boyce, U.S. Dept. of Energy, MD [U] Harry M. Corson, IV, Cerberus Pyrotronics, NJ [M]

Rep. Nat'l Electrical Mfrs. Assn. Donald A. DieM, Alison Control Inc., NJ [M] Paul H. Dobson, Factory Mutual Research Corp., MA [I] Stewart M. Fastman, American Ins Services Group Inc., NY [I] Paul Giaccaglia, American Nuclear Insurers, CT [I] Charles L. Girard, Sandia Nat'l Laboratories, NM [U]

Rep. NFPA Industrial Fire Protection Section, Arie T. P. Go, Bechtel Corp., CA [SE] LeRoyJ. Hill, McDermott Inc., VA [M] L. S. Homa, Underwriters Laboratories Inc., IL [RT] Thomas J. Kramer, Schirmer Engr Corp., IL [SE] Robert S. Levine, U.S. Nat'l Inst. of Standards and Technology, MD [RT] Patrick M. Madden, U.S. Nuclear Regulatory Commission, DC [E] Anthony J. Mascena, Stone & Webster End, Corp,, NJ [SE] David P. Notley, Science Applications Int I Corp. (SAIC), VA[SE] Robert J. O'Laughlln, Knoxville, TN [SE] Mark Henry Salley, Tennessee Valley Authority, TN [U] Jcack Siegel, Gerling America Insurance, NY [I]

llfford R. Sinopoli, II, Baltimore Gas & Electric, MD, Edison Electric Inst. [ U ] Wayne R. Sohlman, Nuclear Mutual Ltd, DE [I] Raymond N. Tell, Los Alamos Nat'l Laboratory, NM [U] Rupert M. H. "Mike" Terrier, Virginia Electric & Power Co., VA [U] Lynn K. Underwood, Wausau HPR Engr, WI [I]

Rep. The Alliance of American Insurers Steven F. Vieira, Grinnell Corp., RI [M]

Rep. Nat'l Fire Sprinkler Assn., Michael J. Vitacco, Jr., Westinghouse Savannah River Co., SC [U]

Alternates

Ingemar B. Asp, Gage Babcock & Assn. Inc., NY, [SE] (Alt. to M. A. Antonetti)

James B. Biggins, M&M Protection Consultants, IL, [I] (Alt. to L. R. Hathaway)

Edward A. Connell, U.S. Nuclear Regulatory Commission, DC [E] (Alt. to P. M. Madden)

Edgar G. Dressier, American Nuclear Insurers, CT, [I] (AlL to P. Giaccaglia)

L. Paul Herman, Professional Loss Control, Inc., IL, [I] (Alt. to W. D. Holmes)

Neal W. Krantz, Simplex, MI [M] (Alt. to H. M. Corson)

Jimmy J. Pierce, Tennessee Valley Authority, TN, [O] (Alt. to M. H: Salley)

Thomas A. Storey, Science Applications Int ' l Corp. VA, [SE] (Alt. to D. P. Nodey)

James R. Streit, Westinghouse Savannah River Co., SC, [U] (Alt. to M. J. vitacco)

Brian D. Tomes, Wausau HPR Engr, TX, [I] (Alt. to L. K. Underwood)

Robert W. Strong, General Electric, CA, [M] (Voting Alt. to GE Rep.)

Nonvoting

Donald J. Keigher, Los Alamos, NM (Member Emeritus)

Walter W. Mafoee, Bothell, WA (Member Emeritus)

Staff Liaison: Richard P. Bielen

This list represents the membership at the time the Committee was balloted on the text of this edition. Since that tira, changes in the membership may have occurred. A key to classifications is found at the front of the book.

Committee Scope: This Committee shall have primary responsibility for documents on the safeguarding of life and property from fires in which radiation or other effects of nuclear energy might be a factor.

The Report of the Technical Committee on Atomic Energy is presented for adoption in 3 parts.

Part I of this Report was prepared by the Technical Committee on Atomic Energy, and proposes for adoption a complete revision to NFPA 801-1995, Standard for Facilities Handling Radioactive Materials. NFPA 801-1995 is published in Volume 7 of the 1996 National Fire Codes and in separate pamphlet form.

This document when adopted will be retitled, Standard for Fire Protection for Facilities Handling Radioactive Materials, and is incorporating the subject matter presently included in NFPA 802, which is being withdrawn.

Part I this Report has been submitted to letter ballot of the Technical Committee on Atomic Energy, which consists of 30 voting members; of whom 25 voted affirmatively, 1 negatively after circulation of negative votes (Mr. Boyce), 2 abstained(Messrs. Homa and Vitacco), and 2 ballots were not returned (Messrs. Strong and Terrier.)

Mr. Boyce voted negatively stating: "In 1-5 the definition of "fire damper" from NFPA 90A precludes

the use of actuators other than beat detectors. Additionally, the term "smoke damper" is used in the NFPA 801 Proposal without being defined.

2-4(I) Although the second paragraph allows the use of noncombustible materials, the third paragraph requires use of fire- retardant lumber or coatings which are not necessary for noncombustible materials.

2-8.3 Guidance on drill critique, documentation and follow-up were deleted without substantiation.

3-8 The requirements restricting the classification of interior finish materials were deleted without substantiation except that the term "limited combustible" was being required. The term "limited combustible" seems to apply to the interior finish portion of floors, ceilings and walls rather than to the assembly. It is common to use stainless steel floor as wall coverings and such noncombustible materials should be clearly permitted.

3-9.6.2 HEPA filters are combustible. Unlike power plants where they may not be in continuous use, filters in facilities handling radioactive materials are routinely used. They collect radioactive material as well as combustible dust over time. Fire reaching the filter can free this accumulation. "Fire experience" is cited as the substantiation for deletin~ the requirements for detection and suppression systems but the "experience" is not further identified.

A-2-3.2 This section has been changed to say that a "fire risk analysis" should be required. A "fire risk analysis" is rarely needed. No substantiation has been offered for this change which is likely to lead to a great deal of expense with little benefit."

Mr. Homa abstained stating: "I haven' t had the opportunity to review this sufficiently to cast a

vote."

Mr. Vitacco abstained statinff. "It appears that the information on the spedfic changes to NFPA

801, that was sent out for review, was incomplete. For example, section 5-5 is missing and other information is in the appendices that are not cross-referenced in the body of the standard."

Part II of this Report was prepared by the Technical Committee on Atomic Energy, and proposes for adoption a withdrawal to NFPA 802-1993, Recommended Practice for Fire Protection for Nuclear Research and Production Reactors. NFPA 802-1993 is published in Volume 11 of the 1996 National Fire Codes and in separate pamphlet form.

Part II this Report has been submitted to letter ballot of the Technical Committee on Atomic Energy, which consists of $0 voting members; of whom 28 voted affirmatively, and 2 ballots were not returned (Messrs. Strong and Terrier.)

Part HI of this Report was prepared by the Technical Committee on Atomic Energy, and proposes for adoption amendments to NFPA 803-1993, Standard for Fire Protection for Light Water Nuclear Power Plant& NFPA 803-1993 is published in Volume 7 of the 1996 National Fire Codes and in separate pamphlet form.

460

N F P A 8 0 1 - - F 9 7 R O P

Part IH this Report has been submitted to letter ballot of the Technical C o m m i t t e e on Atomic Energy, which consists of ~0 voting members; of whom 28 voted affirmatively, and 2 ballots were not returned (Messrs. Strong and Terrier.)

PART I

(Log #1) 801- 1 - (3-2.1): Accept

i S U B M I T r I ~ Lynn K. Underwood, Wausan HPR Engineering R E C O M M E N D A T I O N : Revise text to read:

"Facilities having quantities of radioactlve, materials that might I become airborne in case of fire or explos,on shall ~ be I o~ segregated from other important buildings or operations."

SUBSTANTIATION: Clarification and correction. COMMITTEE ACTION: Accept.

(Log #CP1) 801- 2 - (Entire Document): Accept SUBMrrrER: Technical Committee on Atomic Energy R E C O M M E N D A T I O N : Combine NFPA 801, Standara for

I Facilities Handling Radioactive Materials and NFPA 802, [ Recommended Practice for Fire Protection for Nuclear Research I and Production Reactors into one standard as shown at the end of

this document. S U B S T A N T I A T I O N : NFPA 801, Standard for Facilities Handling Radioactive Materials and NFPA 802, Recommended Practice for Fire Protection for Nuclear Research and Production Reactors are being combined because many of the fire protection requirements for these facilities are the same. The combined document will be more user friendly as the user can refer to a single document for these facilities.

There were several specific changes made in the combined document and they are as follows:

1. Section 1-3.1, Alternative Methods. The wording was changed to coordinate with NFPA 804.

2. The definitions for Fire Damper and Fire Rated Seal was added because this terminology is used in the standard.

3. 2-40)* was added to coordinate with NFPA 804 in regards to temporary construction materials.

4. 2-8.3 was modified to delete the specific time intervals for conducting drills. Training and drill frequencies will vary according to the facility and mandating quarterly drills was too restrictive for small facilities.

5. 9-9 The committee feels this new material is important to the responding Fire Emergency Organization.

6. 3-1, the first sentence was deleted because it is redundant. 7. 3-6.3 This requirement was moved from the appendix as the

committee felt penetration seal listing shall be mandatory. 8. 3-7 The requirement for limited combustibles was struck

because it was too restrictive. 9. 3-8 The requirements for interior fit-fishings in processing or

storage of radioactive materials was modified to require limited combustible materials, not non-combustible. Non-combustible was too restrictive.

10. 3-9.3 The committee will allow plastic ducts to be used when the environment is corrosive•

11. 3-9.6.2* The committee removed the square footage requirement for HEPA filters. The hazard is independent of the filter size• Fire experience shows there should not be a mandatory requirement for detection and suppression.

12. 5-3.2.3 and 5-3.2.4 These sections were deleted/modified to emphasize the delivery system shall be periodically tested, not just the piping system. Also this requirement is redundant.

13. 5-3.2.5 was deleted because it is an impractical requirement. 14. 5-4.3.1 The materials specified in the paragraph were deleted

as a result of a research report called "Technical Report ". Fire Endurance Testing of Oil Filled Radiation Shielding Windows, by Jeff Gould and Peter Wu, prepared by Factory Mutual Research Corporation for the United States Department of Energy. Supporting material is located at the NFPA and will be provided u ~ n request.

• 5-4.3.4 and 5-4.3.5 were deleted as these requirements are already covered elsewhere in the standard.

16. 5-4.4.5 and 5-4.4.6 were deleted to be consistent with other changes made in the document.

17. Section 5-4.5, 5-4.6, 5-4.7, and 5-4.8 The recommendations are presently in NFPA 802. They were modified to make the material more user friendly and convert the language to mandatory language.

18. A-3-6, A-3-9.1, and A-3-9.6.2 were moved into the body of the standard. COMMrFrEE ACTION: Accept.

461

N F P A 801 - - F97 R O P

NFPA 801

Standard for Fire Protection for

Facilities Handling Radioactive Materials

44~i-1998 Edition

NOTICE: An asterisk (*) followingthe number or letter designating a paragraph indicates that explanatory material on theparagraph can be found in Appendix A.

Information on referenced publications can be found in Chapter 6 and Appendix C.

Chapter 1 Introduction

1-1 Scope.

1-1.1" This standard addresses fire protection requirements intended to reduce the risk of fires and explosions at facilities handling radioactive materials. These requirements are applicable to all locations where radioactive materials are stored, handled, or used in quantities and conditions requit ing a-government oversiCht (e.¢.. U.S. Nuclear Regulatory Commission or U.S. Devar~tment of Energy. etc~ license to possess or use these materials and to all other locations with equal quantities or conditions.

1-1.2 This standard shall not apply to rczczrch cr power reactors that are covered by NFPA °02, P.cc~.mmcnSc~ .~rc Protection

803, Standard for Fire Protection for Light Water Nuclear Power Plants, and NFPA 804. Standard for Fire Protection for Advanced Lieht Water Reactor Electric Generatine Plants.

1-2" Purpose. This standard provides requirements for personnel responsible for the design or operation of facilities that involve the storage, handling, or use of radioactive materials.

1-3 Alternative Methods.

1-3.1 Nothing in this standard is intended to prevent the use of systems, methods, or devices of equivalent or superior quality, strength, fire resistance, effectiveness, durability, and safety as altematives to those prescribed by' this standard,.provid.ed - ~ca;~.cal documentation is submitted to the authority hawngjun: demonstrate equivalency, and the system, method, o r ~ " . approved for the intended purpose. ~# ~ _ ~ . ~

1-3.2 The specific requirements of this standard shal be l ~ to be modified by the authority having juris " "~x'" " O ~ ? ~ . ~ :

shall the modification afford less fire prO.~i th~h..th ~ ~¢hich, in the judgment of the authority havingjuns(~', ~.ld ~. ~, provided by compliance with the c o r r e s p o n , ~ l ~ as~gCis contained in this standard. ~l i~::

1-3.3 Alternative fire protection methods accepted I~ the authority having jurisdiction shall be considered as conforming with this standard.

. . . . 1~. . . . . . +I-.^ , ~1^~ : . . . . k ^ l l K . . . . . . . . : k l ^ g ^ . . 3 . . . . . * ~ * : ~ . 1 . ^

1-4 Retroactivity.

1-4.1 The provisions of this standard shall be considered necessary to provide a reasonable level of protection from loss of life and property fi'om fire or explosion. They reflect situations and the state of the art at the time the standard was issued.

1-4.2 Unless otherwise noted, the provisions of this standard shall not be applied retroactively, except in those cases where it is determined by the authority havingjutisdiction that the existing situation involves a distinct hazard to life or adjacent property.

1-5 Definitions.

Alpha Particle. A positively charged particle emitted by certain radioactive materials, identical to the nucleus of a helium atom. It is the least penetrating of the three common types of radiation (alpha, beta, gamma) emi~ed by radioactive material, as it is stopped by a sheet of paper. It is not dangerous to plants, animals, or people unless the alpha-emitting substance has entered the body.

Approved.* Acceptable to the authority having jurisdiction.

Authority Having Jurisdiction.* The organization, office, or individual responsible for approving equipment, an installation, or a procedure.

Beta Particle. An elementary particle, emitted from a nucleus during radioactive decay, with a single electrical charge and a mass equal to 1/'1837 that of a proton. A negatively charged beta particle is identical to an electron, and a positively charged beta particle is called a positron. Beta radiation can cause skin bums, and beta- emitters are harmful if they enter the body. However, beta particles are easily stopped ~bz~a thin sheet of metal.

Canyon. ~ s ' u ~ ¢ ~ s i d e or above a series of hot cells for the purpose of s ~ the hot cells.

Cave. A ~ I h ~ x . ~ . intended for a specific purpose and limited

af~Ihl that, in the form in which it is used 3 ~ f ~ anticipated, will ignite and burn. A meet the definition of noncombustible or

A liquid having a flash point at or above

The state of sustaining a chain reaction, as in a nuclear

~ . t i c a l i t y Incident. An accidental, self-sustained nuclear fission F a i n reaction.

Decontamination. The removal of unwanted radioactive substances from personnel, rooms, building surfaces, equipment, and so on, to render the affected area safe.

Fire Area. That portion of a building or facility that is separated from other areas by fire barriers.

k"we Barrier. A continuous membrane, either vertical or horizontal, such as a wall or floor assembly, that is designed and constructed with a specified fire-resistance rating to limit the spread of fire and that will also restrict the movement of smoke. Such barriers shall be nermitted to might- have protected openings.

F'tre Brigade. As used in this standard, refers to those facility personnel trained in plant fire-fighting operations.

Fire Damper.* A device, installed in an air-distributlon system. desimned to close automatically unon_ detection of heat. tointerr~pg migratory airflow, and to restrict the n a . ~ e of flame. A combination fire and smoke damner meets the reouirements of both.

Fire Door. A door assembly rated in accordance with NFPA 252, Standard Methods office Tests of Door Assemblies, and installed in accordance with NFPA 80, Standard for Fire Doors and Fire Windows.

Fire Emergency Organization. As used in this standard, refers to those facility personnel trained in plant fire-fighting operations. For more information refer to NFPA fi00, Standard on Industrial Fire Brigades, and NFPA 1500, Standard on Fire Department Occupational Safe 0 and Health Program.

462

N F P A 8 0 1 ~ F 9 7 R O P

Fire Hazards Analysis. A comprehens ive assessment of the PnjOtential for a fire at any location to ensure that the possibility of

ury to people or damage to buildings, equ ipmen t , or the e n v i r o n m e n t is within acceptable ' l imits .

Fire Prevent ion. Measures d i rected toward avoiding the incept ion of fire.

Fire Protect ion. Methods of providing for fire control or fire ext inguishment .

Fire-Rated Penetra t ion Seal. An assembly nrovided in an onen in~ in a fire barrier for the oassatrewav of nines• cables, trays, and so on. to main ta in the fire resistance ratin~ of the fire barrier.

Fire Resis tance Rating. The t ime, in minu te s or hours , tha t materials or assemblies have withstood a fire exposure as establ ished in accordance with the test p rocedures of NFPA 251, Standard Methods of Tests of Fire Endurance of Building Construction and Materials.

1 / 8 in. (3.2 m m ) tha t has a f lame spread rat ing no t greater t h an 50, or o ther material having ne i ther a f lame spread rat ing greater than 25 nor evidence of con t inued progressive combust ion , even on surfaces exposed by cut t ing t h r o u g h the material on any plane.

Listed.* Equ ipment , materials, or services inc luded in a list

~ ubUshed by an organizat ion that is acceptable to the author i ty av ingjur i sd ic t ion and conce rned with evaluat ion of products or

services, tha t main ta ins periodic inspect ion o f p roduc t ion of listed e q u i p m e n t or materials or periodic evaluation o f services, a n d whose listing states tha t ei ther the equ ipmen t , material, or service mee ts identif ied s tandards or has been tested and f o u n d suitable for a specified purpose

Noncombus t ib le .* A material that, in the form in which it is u sed a n d u n d e r the condi t ions anticipated, will no t ignite, burn, suppor t combust ion , or release f lammable vapors when subjected to fire or heat. Materials tha t are repor ted as pass ing ASTM E136, Standard Test Method for Behavior of Materials in a Vertical Tube Furnace at 750°~ shall be cons idered noncombus t ib l e materials.

Radiation. The emiss ion and propaga t ion of energy t h roug h Fire Risk Analysis An analysis to quant i fy the fire risk by • . • " . mat te r or space by means of electromag~netic dis turbances tha t

cteterminin the robability of a fire and to evaluate the robabili • " . . . . . g . . p . . p . ty display bot~ wave-like and narucle-like~oehaxaor. T h e te rm includes of resul tant in ury to eo le or d a m a e to bui ldin s or e ui m e n t Lj P P g g q P • s t reams of f a s t - m o ~ g particles, such as a lpha and beta particles,

free neu t rons ar~..~, c radiat ion Nuclear radia t ion is tha t Fire Zone. Subdivisions of fire areas in which fire de tec t ion or 1 . ' .-.--:. ~ , " " " , " ° ' , , . . . . . . . emi t teu f rom a "" ic ~ i e i in various nuc lea r react ions inc iuu ing suppress ion systems provade a la rm re format ion indicat ing the . . . . } ~ . . . .

alplaa beta, . . ~ m m a radiat ion a n d neu t rons location of fire at a central fire control center• , ..~.-. ~..~...:~ " • . .<.",-~ "::~:... . . . .

Fissionable Materials. Materials which are canable of bein ~ Radtatio.,a "~ea . ~ g , e a accessible to pe r sonne l in which there i nduced to u n d e r g o nuclear fission by slow n e u t r o n s (e.g., ~ exists ~ ; o r i g ~ g , . . x ~ n whole or in par~t w i ~ i n radioactive U r a n i u m 233 and 235 mad ~ lu ton ium mat e~./il, at"ga~n leve l s" :~ : '~ major por t ion ot m e buoy c o m a

" " I " " . 4 9 " .. . x : : ~ " . 5 re, C,~ye a~'~..ose in exces~::~ 5 mil l i rems (5 x I0- se ive r t )dur in~ any

Fire-Resistant Fluid. A hs ted hvdrauhc f luid or l ubncan t that is .-_-¢.-..--2,.~-:~ ..:.:.: . . . . . . . . . . . . . . . . . . . . . . . , . - . . . . smg~.::'.~o~.-.~.., a cruse In excess o t too ml lu rems (tJ.uul selvert) difficult to ignite due to ~t s h igh fire po in t and au to - lgnmon d u ~ ; fiv~ consecutive days " ~ -g. t empera tu re tha t does no t sustain combus t ion due to its low hea t ~.~:~. " of combus t ion . %~!..~. Radioac~.~ .~¢~he spon t aneous decay or d i s in tegrauon of an

~ . . . . . . . . . . . . ~- .@.. t~s. table a t ' ~ t : nuc leus accompan ied by the emission of l~lame an reao Katmff A reiauve m e a s u r e m e n t o t m e surface ~":~2:.~.~x~..-. .x-

• - . .~" . . . . ~ : T ~ . . . o . n . . ¢ -~ bu rn ing characteristics of bui ld ing materials when tested in ::~:. ~ . ~ : 2 accordance with NFPA 255, Standard Method of Test of Surfa~... ..... '%.-::#?~hall')~':'~S]ndicates a manda to ry requ i rement . Burning Characteristics of Building Materials. . . ~ ! ~ ' ~ ~!~ ":'~"

" .::.-.6 ":~" ":~i~ ~'..~ ...S..~ould. Indicates a r e c o m m e n d a t i o n or that which is advised Flammable Liquid. Any liquid having a flash po in t b . ~ 100°~( ,:. : i ~ t no t reouired. .

(37.8°C) a n d having a vapor pressure no t exceeding,'~'~::.(2.~.. ':: '~::::.. ~!k.* -~ kPa) absolute oressure at 100°F (37 8°C~ ~ # " : % . ' ~ Standard. A documen t , the main text of which contains only

.~.....~:.,~:.~. "~.-'.,-:. "" manda to ry provisions us ing the word "shall" to indicate G a m m a Rays. High-energy, short-wavelengtl~. ~ : ~ l z n e / ~ ' . - % . , : . ' . . : . ~ r equ i r emen t s a n d which is in a fo rm ~enera l ly suitable for

radiation. G a m m a radia t ion f requent ly a c ~ p a ~ ang[~!~.@:" m a n d a t o r y re ference by ano the r stanffard or code or for a d o p t i o n beta emiss ions and always accompan ies ~ n . G a m m ~ i ~ ate" into law. N o n m a n d a t o r y provisions shall be located in an very pene t ra t ing and are best s topped o~h'}~.~..cd a g a i n s r : ~ dense appendix , footnote , or f ine-print no te and are no t to be considered material , such as deple ted u ran ium, lead, wa~:.~.qoncret~:*or iron. a oart of the r equ i rements of a s tandard.

i ~ : . ~ v ~ box are ie.i~l:6ves sealed to pl~ces hands and

Glove Box. A sealed enclosure in which i tems hand l ed exclusively us ing long rubber or neoprene ports in the walls of the enclosure. T h e operator fo rea rms into the gloves f rom the room outside of the box in order to main ta in physical separa t ion f rom the glove box env i ronmen t while re ta in ing the ability to manipu la te i tems inside the box with relative f r e edom while viewing the operat ion th rough a window.

H o t Cell. A heavily sh ie lded enclosure in which radioactive material can be hand l ed safely by persons working f rom outside the shield us ing r emote tools a n d manipu la to rs while viewing the work t h r o u g h special leaded-glass or liquid-filled windows or t h r o u g h optical devices.

Isotope. Any of two or more forms of an e l emen t having the same a tomic n u m b e r and similar chemical propert ies but differing in mass n u m b e r a n d radioactive behavior.

Labeled. E q u i p m e n t or materials to which has been a t tached a label, symbol, o r o ther identifying mark of an organizat ion tha t is acceptable to the author i ty having jur isdic t ion a n d conce rned with p roduc t evaluation, tha t ma in ta ins periodic inspect ion of p roduc t ion of labeled e q u i p m e n t or materials, and by whose labeling the manu fac tu r e r indicates compl iance with appropr ia te s tandards or pe r fo rmance in a specified manne r .

Limited-Combust ible .* A bui lding const ruct ion material that, in the form in which it is used, has a potential hea t value no t exceeding 3500 B t u / l b (8141 kJ/kg) a n d has ei ther a structural base of noncombus t ib l e mater ia l with a surfacing no t exceed ing

1-6 Uni t~* Metric uni ts in this d o c u m e n t are in accordance with the Internat ional System of Units, which is abbreviated officially as ASI ® in all languages.

C h a p t e r 2 Administrat ive Controls

2-1 General.

2-1.1" The in ten t of this chapter shall be me t by incorpora t ing the provisions of this chap te r in facility opera t ing procedures or as otherwise d e t e r m i n e d b y m a n a g e m e n t .

2-1.2 Administrat ive controls for changes in processes, equ ipment , o r ~ shall be developed to inc lude fire protec t ion concerns .

2-1.3 The administrat ive controls for facilities shall be reviewed and upda t ed periodically.

2-2* M a n a g e m e n t P o l i c y a n d Direction. Corpora te m a n a g e m e n t shall establish policies and insti tute a p r o g r a m to p romote life safety, the conservat ion of property, a n d the cont inui ty of opera t ions t h rough provisions of fire prevent ion and fire protect ion measures at each facility.

2-3* Fire Hazards Analysis.

2-3.1 A d o c u m e n t e d fire hazards analysis shall be initiated early in the des ign process or when conf igura t ion changes are made to ensure that the fire prevent ion a n d fire protect ion requ i rements of this s t andard have been evaluated. This evaluation shall consider the facility's specific design, layout, and ant ic ipated opera t ing needs . The evaluation shall cons ider acceptable m e a n s for

4 6 3

N F P A 8 0 1 ~ F 9 7 R O P

separation or control of hazards, the control or elimination of ignition sources, and the suppression of fires. (See Chapter 3.)

2-3.2" For existing facilities, a documented fire hazards analysis shall be performed for all areas of the facility.

24 Fire Prevention Program. A written fire prevention program shall be established and shall include the following:

(a) Fire safety information for all employees and contractors, including familiarization with procedur¢~ for fire prevention, . . . . . ~ . . . . . yal d F v . . . . . . . . . , emergenc arm ~ an r~.cc~urc:, .~.¢ - reporting o f f i r ~ a-gr~

(b) Documented facility inspections conducted at least monthly, including provisions for remedial action to correct conditions that increase fire hazards

(c) A description of the general housekeeping practices and the control of transient combustibles

(d) Control of flammable and combustible liquids and gases and in accordance with the applicable documents referenced

in Chapter 5

(e)* Control of ignition sources including, but not limited to, grinding, welding, and cutting

(f)* Fire reports, including an investigation and a statement on the corrective action to be taken

(g)* Fire prevention surveillance

(h) The restriction of smoking to properly designated and supervised areas of the facility

(i~* Temoorarv construction, demolition, and renovating ~¢tivities shall conform to the reouirements of NFPA 241. Standard for Saf~uardin~ Construction. Alteration. and Demolition O~erations

1. Noncombustible or fire-retardant scaffolds, formwork. ~lecking. and nartitions shall be used both inside and outside of

or delav constructioil schedules.

9r listed fire-retardant coatings shall be orovided.

t~¢sistant Textiles and Films. <:-'~"~:~.'.::.:~::.. :$..':k'.: x:::.'::::~:, :.-.'g • -.~:~:~$:. ?:-:,

2-5 Testing, Inspection, and Maintenance. -';~!~ . . . . ....:~!t "~"

2-5.1 Upc.n ."=:zmll:.:iom, all Fire protection systems.:~l features shall be inspected and tested in accordance with t G , ] e applicable documents referenced in Chapter 4.

2-5.2 ~l--Fire protection systems and equipment shall be periodically inspected, tested, and maintained in accordance with NFPA 25, Standard for the Inspection, Testin D and Maintenance of Water-Based Fire Protection Systems, and the applicable documents referenced in Chapter 4.

2-5.3 Testing, inspection, and maintenance shall be documented by means of written procedures, with results and follow-up actions recorded. Specific acceptance criteria shall be provided for each operation.

2-6 Impairments.

2-6.1 A written procedure shall be established to address impairments to fire protection systems and shall include the following:

(a) Identification and tracking of impaired equipment

(b) Identification of personnel to be notified

(c) Determination of needed fire protection and fire prevention measures

2-6.2 Impairments to fire protection systems shall be as short in duration as practicable. If the impairment is planned, all necessary parts and personnel shall be assembled prior to removing the

protection system(s) from service. When an unplanned impairment occurs, or when a system has discharged, the repair work or fire protection system restoration shall be expedited.

2-6.3 Once repairs are completed, tests shall be conducted to ensure proper operation and restoration of full fire protection equipment capabilities. Following restoration to service, those parties previously notified of the impa i rment shall be advised.

2-7~ Fire Emergency Plan. A written fire emergency plan shall be developed and shall include the following:

(a) Response to fire alarms and fire systems supervisory

(b) Notification of personnel identified in the plan

(c) Evacuation from the fire area of personnel not directly involved in fire-fighting activities

(d)* Coordination with security forces, radiation protection personnel, and other designated personnel for the admission of public fire department and other emergency response agencies

(e)* Fire extinguishment activities, particularly those that are unique to the facili~ handling radioactive materials (see Appendix

. . 4 : '" " ~ q " . . . . . . (f). Reqmrem: .~ . fo r ~ periodic drills, .and exyrmses to verify the ~ i ~ f the fire emergency plan, mcludlng practice sessions .q .o~ . '~ l ]na~ .gund previously developed valid emergency

Organization.

~ i ~ i l i t y fire emergency organization shall be provided.

i'~" 2-8.2 "-~e size of the facility and its staff, the complexity of fire- ~gKh. tlng problems, and the availability and response time of a ~ ' b l l c fire department shall determine the composition of the 4ffacility fire emergency organization.

2-8.$ Facility fire emergency organizations-training requirements and drill freouencies necessary to demonstrate nrofiencv shall be imolemente(i in accordance with the fire emergency nlan in Section 2-7. cc.:~uzt dr'llz :-t l z ~ t qua.~cr!7, m=~ "~k.c)':ha1! 5c e r~d - ] a l l ad - , 1 I.,. . . . . . . . * ^~ * ; ~A I : . , I ~A . ,~ I~ " 1 "1~ . 3 . . I l l - - :& ,~ . . . . . I - , ~11 I . . ~

2-9 Prefire Plans.

2-9.1_* Detailed prefire plans for all site fire areas shall be developed for assisting the facility fire emergency or wanization.

2-9.2 Prefire plans shall be reviewed and, if necessary, updated periodically.

2-9.3 Prefire plans shall be made available to the facility fire emerffencv orffanization.

Chapter 3 General Facility Design 3-1" Special Considerations. Pr~-~=:.e='~ tc !:..~..'t c2=z*2_-'z..:.--=~e:-. :h"q ~c ~:zca~ ~:= "..kc .fir: P.=.z~-d.= a:m!)~':. The design of facilities handling radioactive materials shall incorporate the following:

(a) Limits on areas and equipment subject to contamination

(b) Design of facilities, equipment, and utilities to facilitate decontamination

$-2 Location with Respect to Other Buildings and within Buildiag~

$-2.1 Facilities having quantities of radioactive materials that might become airborne in case of fire or explosion shall no~ be

segregated from other important buildings or operations.

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N F P A 8 0 1 - - F 9 7 R O P

3-2.2 Particular a t tent ion shall be given to the location of intakes a n d outlets of air-cleaning systems to reduce con tamina t ion potential .

3-8* Planning for Contamination Control. T he facility shall be des igned to provide const ruct ion tha t conf ines a potential radiat ion con tamina t ion inc iden t a n d shall inc lude surface f inishes tha t are easy to clean.

3-4* Fire Area Determina t ion . T he facility shall be subdivided into separate fire areas as d e t e r m i n e d by the fire hazards analysis for the

~i urposes of l imiting the spread of fire, p ro t ec t i ngpe r sonne l , and mir ing the c o n s e q u e n t i a l d a m a g e to the facility. Fire areas shall be

separa ted f rom each o ther by barriers with fire resistance c o m m e n s u r a t e with the potential fire severity.

841 Construct ion. Buildings in which radioactive materials are to be used, hand led , or s tored shall be fire resistive or noncombus t ib l e (Type I or Type II in accordance with NFPA 220, Standard on Types of Building Construction).

$-6 Open ings in Fire Barriers.

3 . 6 . 1 " ~ Open ings in fire barriers shall be pro tec ted consis tent with the des ignated fire-resistance ra t ing of the barrier. This shall include but no t be l imited to mechanica l and electrical penet ra t ions , bui ld ing cons t ruc t ion joints , and HVAC penetra t ions .

3-6.2 Fire doors a n d fire windows used in fire barriers shall be installed a n d ma in t a ined in accordance with NFPA 80, Standard for Fire Doors and Fire Windows.

3-6.3 Penet ra t ion seals nrovided for electrical a n d mechanica l o n e n i n ~ shall be listed to ~ mee t the r eou i rements of ASTM E814. Fire Tests of Throu~,h-Penetration Fire -StoCks. or UL 1479. Fire Tests of Throu~h-Pe~etration Fire StoOs.

8-7 Shielding. Any p e r m a n e n t or t empora ry shie lding materials shall be noncombus t ib le .

Exception: Where noncombustible materials cannot be u s e d , ~ ~ ::..--t:.:'.'Sl: ..~:L."-ial: : . ~ ~c. :;.=:2 :,-.d appropriate fire pro~

hazar.d~ m~ures shaU ~e t,~oviaed as a,t~,,,,ined 0 t~./ire . ~ n a O r ~

3-8 Inter ior Finish. "* ' ~ o . . . . 6 " ~ ' ~

A ~ ^ . ~ ' ~ 1

$-8.1 Inter ior f inish in areas process ing or s tor ing radioactive materials shall be l imi ted-combus t ib le ~.~.~z~.m~u~'..i~.z and, where practicable, shall be n o n p o r o u s for ease of decon tamina t ion .

- - ~ , - l : - - ~ : . . . . . ~ . . , . = ^ | . . I . ^11 L , . ^ c ' 11~ . ^ A ^ - - t " l l ~ - - 1~ : . . . . . . . 3 . . . . . . .~'~1.~

!~ .T 'L "zDA T tq l T . ' l ' . ~_~ '~ . t " ~ . J .

3-9* Heating, VentUating, and Air Conditioning.

3-9.1" The design of the venti lat ion shall be in accordance with NFPA 90A, Standard for the Installation of Air Conditioning and Ventilating Systems; NFPA 90B, Standard for the Installation of Warm Air Heating and Air Conditioning Systems; and NFPA 91, Standard for Exhaust Systems for Air Conveying of Materials. Exception: Where shutdown of the ventilation system is not permitted, fire dampers shall not be required for ventilation duct penetrations. Alternative means of prorating against fire propagation shall be provided.

3-9.2 The venti lat ion system shall be a r ranged such tha t the area conta in ing dispersible radioactive materials r emains at a lower pressure than tha t of adjoining areas of the facility before and du r ing any fire incident , inc luding du r ing and following any ac tuat ion of fire protec t ion systems.

3-9.3 Duct work f rom areas conta in ing radioactive materials passing t h r o u g h nonradioact ive areas shall be of noncombus t ib le const ruct ion a n d shall be pro tec ted f rom possible exposure fires by

materials having an appropr ia te fire-resistance rat ing as de t e rm in ed by the fire hazards analysis.

ExceOtion: Where the corrosive nature of the eftluents conveyed brecludes the use of metallic ducts. ~lastic ducts sl~all be'~ermitted.

If olastic duc ts are used. they shall be listed f i re-retardant tvoes and be evaluated in the fire hazards analysis.

3-9.4* Air entry filters shall have annroved filter med ia tha t n roduces a m i n i m u m a m o u n t o f smoke (UL Class I~ when subiected to heat.

3-9.5 Rough ing filters, where necessary, shall be cons t ruc ted of noncombus t ib l e materials.

Exception*: Where combustible filters or particulates are present in the ventilation system, additional fire protection features shall be provided as determined b 3 the fire hazards analysis.

3-9.6 HEPA Filtration Systems. 3-9.6.1 All HEPA filtration systems shall be analyzed in the fire hazards analysis.

$-9.6.2 HEPA filtration . . . . . . . . . ~"~- ~ '~ '~ : . . . . . "-~ . . . . . . . . . . . .

~ i ~ - ~ ' ~ + t - A 0 - ~ ~L~ shall be provided with thermal fire detect ion and . . . . - " suppress ion s y s t e m ~

3-9.7 Stool

3-9.7a*~., r a d i o ~

ere it is mos t

be located to reduce the possibility of ag in t roduced . Such inlets shall be :ely for radioactive con taminan t s to be

3-9.7 ~" ~' " : ' ~'~ ~ ? o 1 ~ , corrosive gases, a n d the nonradioact ive substances tha t rr tr~.¢~e f reed by a fire shall be ven ted f rom their place of

tii~ location. Radioactive materials tha t are origin i ~ , ~ a safe ~.~.J.eased I ~ shall be conf ined, removed f rom the exhaus t

"~" " ~..o~. ~tream, or re leased u n d e r control led condit ions. ~~ nti lat ion systems des igned to exhaus t smoke or corrosive all be evaluated to ensure that inadver tent operat ion or

~ res shall no t violate the control led areas of the facility design.

:9.7.4" Smoke control systems shall be provided for fire areas based u p o n the fire hazards analysis.

$-9.7.5 Smoke exhaus t f rom areas tha t at any t ime contain radioactive substances shall no t be venti lated outside the building. Smoke control systems for such areas shall be connec t ed to t r e a tmen t systems to prec lude release of radioactive substances.

$-9.7.6* Enclosed stairwells shall be des igned to minimize smoke infiltration du r ing a fire.

3-9.7.7* Where natural-convect ion venti lat ion is used, the smoke and hea t venti lat ion shall be provided in accordance with the fire hazards analysis.

, 3-9.7.8 The venti lat ion system shall be designed, located, an d pro tec ted such tha t a i rborne corrosive products or con tamina t ion shall no t be circulated.

3-9.7.9 The power supply a n d controls for mechanica l venti lat ion systems s h a l l b e located outs ide the fire area served by the system or protected f rom fire damage .

3-9.7.10 Fire suppress ion systems shall be installed to protect filters tha t collect combust ible material , unless the e l iminat ion of such protec t ion is just i f ied by the fire hazards analysis.

3.10 Drainage.

CAUTION: For facilities h a n d l i n g fissionable materials, areas where water can accumula te shall be analyzed for criticality potential .

3-10.1" Provisions shall be m a d e in all fire areas of the facility for removal of all l iquids directly to safe areas or for c o n t a i n m e n t within the fire area in order to reduce the potential for f looding of e q u i p m e n t and adverse impact on o ther areas. Drainage a n d the prevent ion of e q u i p m e n t f looding shall be accompl i shed by one or more o f the following:

(a) Floor dra ins

(b) Floor t r enches

(c) O p e n doorways or o ther wall open ings

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N F P A 8 0 1 - - F 9 7 R O P

(d) Curbs for containing or directing drainage

(e) Equipment pedestals

(f) Pits, sumps, and sump pumps

3-10.2 Drainage Design.

3-10.2.1 The provisions for drainage design in areas handling radioactive materials and in any associated drainage facilities (pits, sumps, and sump pumps) shall be sized to accommodate all o f the following:

(a) The spill of the largest single container of any flammable or combustible liquids in the area

(b) The credible volume of discharge (as determined by the fire hazards analysis) for the suppression system operating for a period of 30 minutes where automatic suppression is provided throughout

(c) The volume based on a manual fire-fighting flow rate of 500 g.p.m. (1892.5 L/min) for a duration of 30 minutes where automatic suppression is not provided throughout, unless the fire hazards analysis demonstrates a different flow rate and duration

(d) The contents of piping systems and containers that are subject to failure in a fire where automatic suppression is not provided throughout

(e) Credible environmental factors such as rain and snow where the installation is outside

3-10.2.2 Radioactive or potentially radioactive drainage piping shall not be routed through clean areas.

3-10.3 Floor drainage from areas containing flammable or combustible liquids shall be trapped to prevent the spread of burning liquids beyond the fire area.

3-10.4 Where gaseous fire suppression systems are installed, floor drains shall be provided with adequate seals, or the fire suppression system shall be sized to compensate for the loss of fire • .*~-..~ suppression agents through the drains. . . , g . ' ~

3-11 Emergency Lighting.

3-11.1 Emergency lighting shall be provided for means accordance with NF~PA 101, Life SafeO Code. ~-~:~'..~

3-11.2 Emergency lighting shall be provide~.~J~r critii~ areas; i.e., areas where personnel might .~ .~qui red t, valves, dampers, and other controls in a ~ e n c y .

3-12 Lightning Protection. Lightning protectio shall be provided in accordance with NFPA 7~ Installation of Lightning Protection Systems. .:~i}

3-13 Light and Power.

t for the

3-13.1" An auxiliary power system shall be available to supply power for temporary lighting, ventilation, and radiation-monitoring equipment in those facilities where the radioactive materials being handled are potentially dangerous to personnel.

3-13.2" Electrical conduits leading to or from radioactively "hot" areas shall be sealed internally to prevent the spread of radioactive materials. Only utilities required for operation within radioactively "hot" areas shall enter t h e h o t area.

3-13.3 Less hazardous dielectric fluids shall be used inplace of hydrocarbon-based insulating oils for transformers a n d capacitors located inside buildings or where they are an exposure hazard to important facilities•

3-13.4" ~ All electrical systems shall be installed in accordance with NFPA 70, National Electrical Code.

3-14 Storage.

$-14.1 General. Chemicals, materials, and supplies shall be in separate storerooms located in areas where no work with radioactive materials is conducted. Exception: Those quantities of chemicals, materials, and supplies needed for immediate or continuous use.

3-14.2 Storage of Radioactive Materials.

3-14.2.1 Radioactive materials shall not be stored in the same area as combustible materials. Separate or remotely located noncombustible storage facilities shall be used to store radioactive materials safely.

3-14.2.2" Special consideration shall be given to the storage of radioactive compressed gases, as their release under fire or explosion conditions can result in a severe life safety threat and loss by contamination. Storage fadlities for suchgases shall be designed with special consideration given to the specific characteristics of the gases.

3-14.2.3" Care shall be exercised in selecting the locations for the storage of radioactive waste material. Such material shall not be located near the fresh-air intakes to the heating, ventilation, and air conditioning systems nor the air intakes for air compressors.

3-15 Plant Control, Computer, and Telecommunications Rooms. control, computer, and telecommunications rooms shall meet the a P/ecplicable requirements of NFPA 75, Standard for the Protection of

tronic Computer~Data Processing Equipment.

3-16 Life Safety.

3-16.1 NFPA 101, ~ Safe~y Code, shall be the standard for life safety from fire irl,~lt~.design and operation of facilities handling radioactive ma.~'laJs,~*'~kcept where modified by this standard.

Systems and Equipment

4 - 1 . 1 " ~ h~ards analysis shall be conducted to determine the fire PJ'2~'~gn requirements for the facility.

~,~...-~:. 4-1.2 A u t o ~ e " sprinkler protection provides the best means for ~ g ~ V t l V e s and shall be provided unless the hazards analysis ~MYs~.~i~." P i a l ' ' ~ ' ' ~ ' ~ ~ " .,~_ec3dictates otherwise. As determined by the fire hazards

• hazards shall be provided with additional fixed ion systems. prote~J

~ 3 " For locations where fissile materials be and might present mould create a potential criticality hazard, combustible materials shall he excluded. If combustible materials are unavoidably present in a quantity sufficient to constitute a fire hazard, water or another suitable extinguishing agent shall be provided for fire-fighting purposes. Fissile materials shall be arranged such that neutron moderation and reflection by water shall not present a criticality hazard. A criticality calculation shall be performed for all areas with fissile material~,

4-2 Water Supply.

4-2.1" General.

4-2.1.1 The water supply for the permanent fireprotection installation shall be based on the largest fixed fire-suppression system(s) demand, including the hose-stream allowance, in accordance with NFPA 13, Standard for the Installation of Sprinkler S)$tertls. 4-2.1.2 For common service water/fire protection systems, the maximum anticipated service water demand shall be added to the fire protection demand.

4-2.1.3 The fire protection water supply system shall be arranged in conformance with NFPA 20, Standard for the Installation of Centrifugal Fire Pumps;, NFPA 22, Standard for Water Tanks for Private Fire Protection; and NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances, as applicable.

4-2.2* Where an auxiliary supply is required by the fire hazards analysis, each supply shall be capable of meeting the requirements of 4-2.1.

4-2.2.1 Where multiple fire pumps are required, the pumps shall not be subject to a common failure, electrical or mechanical, and shall be of sufficient capacity to meet the fire flow requirements determined by 4-2.1 with the largest pump out of servace.

4-2.2.2 Fire pumps shall be automatic-starting with manual shutdown. The manual shutdown shall ~ be at the pump control lers .-o~. .

466

N F P A 8 0 1 - - F 9 7 R O P

4-2.2.3* If tanks are for dual-purpose use, they shall be arranged to provide the water supply requirements as determined by 4-2.1 for fire protection use only.

4-2.2.4* Where water tanks are used, they shall be filled from a source capable of replenishing the supply for the fire protection needs in of-an 8-hour period.

4-2.3 If multiple water supplies are used, each water supply shall be connected to the fire main by a separate connections that arranged and valve controlled to minimize the possibility of multiple supplies being impaired simultaneously.

4-3* Valve Supervision. All fire protection water system control valves shall be monitored under a periodic inspection program (see Chapter 2) and shall be supervised by one of the following methods:

(a) Electrical supervision with audible and visual signals on the main fire control panel or at another constantly attended location in accordance with NFPA 72, National Fire Alarm Code," or

(b) Valves locked in the open position with keys available only to authorized personnel.

4-4 Supply Mains a n d Hydrants .

4-4.1 Supply mains and fire hydrants as required by the fire hazards analysis shall be installed on the facility site in accordance with NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances.

4-4.1.1 Where required by the fire hazards analysis, the supply mains shall be looped and of sufficient size to supply the flow requirements as determined by 4-2.1.

4-4.1.2 Indicator control valves shall be installed to provide adequate sectional control of the fire main loop to minimize protection impairments. :~

4-4.2 Each hydrant shall be equipped with a separate shutoff valve located on the branch connection to the supply main.

4-5 S t a n d p i p e a n d Hose Systems . . . . .~:~.<.~ . . ~ . - .

. . .~i~" ""~.-:~ 4-5.1 Standpipe and hose systems shall be installed m . ~ o r d a n ~ with NFPA 14, Standard for the Installation of S t a n d p ~ ~ ~ s~sten~. ' ' ~ % . . . . . "~, 4-5.2 Hose station location shall take into a c c o ~ , . e g r ~ .~%..,.,:_ personnel operating hose " ~ : : ' : " : " : " : " ~ - - hnes. "~'~:" "~<~';"':" ii e i ~,%...:.....~

:.$.'~ -~ .:.-'.'~?..::. '~::-'::" 4-5.$ Spray nozzles having shutoff capab~.~a. , d listed tf~.'.g ~ " electrical equipment shall be provided d:h ~ : l o c a t e d i ~ r e a s • . ~:~¢~::. .:.:-,: near energazed electrical %-:'~:~.-.:::.. ":!?.. equipment. "o~.~:::.. ~"

4-6 Portable Fire Extinguishers. Suitable fire e x t i i ~ s shall be installed in accordance with NFPA 10, Standard fi~ri'..~.~t~ble Fire Extinguishers.

4-7 Fire S u p p r e s s i o n Sys t e ms a n d E q u i p m e n t .

4-7.1" Fire suppression systems and equipment shall be provided in all areas of a facility as determined by the fire hazards analysis. Where required, the design of the fire suppression systems shall be in accordance with the following NFPA standards:

NFPA 11, Standard for Low-Expansion Foam NFPA l lA, Standard for Medium- and High-Expansion Foam Systems NFPA 12A, Standard on Halon 1301 Fire Extinguishing Systems NFPA 12B, Standard on Halon 1211 Fire Extinguishing Systems NFPA 13, Standard for the Installation of sprinkler Systems NFPA 14, Standard for the Installation of Standpipe and Hose Systems NFPA 15, Standard for Water Spray Fixed Systems for Fire Protection NFPA 16, Standard for the Installation of Deluge Foam-Water

Sprinkler and Foam-Water Spray Systems NFPA 16A, Standard for the Installation of Closed-Head Foam-Water

Sprinkler Systems NFPA 17, Standard for Dry Chemical Extinguishing Systems NFPA 17A, Standard for Wet Chemical Extinguishing Systems. NFPA 750• Standard on Water Mist Fire Protection Sy~Ccm~

NFPA 2001. Standard on Clean A~ent Fire Extintruishintr S~stems

4-7.2 The selection of the extinguishing agent system shall be based upon the following:

(a) Type of hazard

(b) Effect of agent discharge on equipment

(c) Health hazards

(d) Cleanup after agent discharge

(e) Effectiveness of agent in suppressing fire

(f) Cost of agent, including life cycle costs

(g) Availability of agent

(h) Criticality safety

(i) Environmental impact

4-Sgwegiffna-l~Algl~1_S~tems.

4-8.1 Fire detection and automatic Fixed fire-suppression systems shall be equipped with local audible and visual notification appliances with annunciation on the main fire control panel or at another constantly at tended location in accordance with NFPA 72, National Fire Alarm Code.

4-8.2 Automatic 1 NFPA 72, Nat i~ hazards a n a l x ~

fire

tectors shall be installed in accordance with ~larm Code, and as required by the fire

alarm system for the facility ~.ha~J. provide the following:

a ' ~ t e m by which employees can report fires

alarm system by which personnel can be alerted

T w o - ~ communications for the facility emergency ~ f i ~ ' f f determined to be required by the fire hazards ~ee..5.. s~tio~ z3 and z7) ~Ieans to notify the public fire department

U n a t t e n d e d Facilities.

4-9.1 Additional fire protection measures shall be provided if the fire hazards analysis identifies that a delayed response or lack of communications in an unat tended facility can result in a major fire spread prior to the arrival of fire-fighting personnel.

4-9.2 Remote annunciation of the fire-signaling panels shall be transmitted to one or more constantly attended locations.

Chapter 5 Spec ia l H a z a r d s in N u c l e a r Facilities

5-1" General.

g4 ,gs - l . l Flammable and combustible liquids shall be stored and handled in accordance with NFPA 30, Flammable and Combustible Liquids Code.

g- l~ 5-1.2 Flammable and combustible gases shall be stored and handled in accordance with NFPA 50, Standard for Bulk Oxygen ~5~5stems at Consumer Sites;, NFPA 50A, Standard for Gaseous Hydrogen

stems at Consumer Sites;, NFPA 54, National Fuel Gas Code; NFPA , Standard for the Storage, Use, and Handling of Compressed and

Liquefied Gases in Portable Cylinders; and NFPA 58, Standard for the Storage and Handling of Liquefied Petroleum Gases.

g4~45-1~ Solid and liquid oxidizing agents shall be stored and handled in accordance with NFPA 430, Code for the Storage of Liquid and Solid Oxidizers.

~1-~5-1.4 Combustible metals shall be stored and handled in accordance with NFPA 480, Standard for the Storage, Handling, and Processing of Magnceium Solids and Powder~, NFPA 481, Standard for the Production, Processing, Handling, and Storage of Titanium; a n d NFPA 482, Standard for the Production, Processing, Handling, and Storage of Zirconium.

~1-,65-1~ Fire protection for laboratories involved with radioactive materials shall be in accordance with NFPA 45, Standard on Fire Protection for Laboratories Using Chemical

467

NFPA 801 - - F97 ROP

~t-,-~ 5-1.6 Ovens, furnaces, and incinerators involved with radioactive mater ia ls shall be in accordance with the r equ i r emen t s of NFPA 82, Standard on Incinerators and Waste and Linen Handling Systems and Equipment; NFPA 86, Standard for Ovens and Furnaces; NFPA 86C, Standard for lndwtrial Furnaces Using a Special Processing Atmosphere; and NFPA 86D, Standard for Industrial Furnaces Using Vacuum as an Atmosphere.

5-1.7 Combus t ion mid safety controls and interlocks shall be tested periodically and after major m a i n t e n a n c e activities in accordance with the e q u i p m e n t manu fac t u r e r ' s r e commenda t ions .

5-1.8 Accident Involving Fissionable Materials. (From NFPA 802, Recommended Fire Protection Practice for Nuclear Research and Production Reactors, 2-5.1 to 2.5.3)

5-1.8.1 T h e fissionable materials, uranium-~33 a n d -935 a n d n lu ton ium, s ~ o a ~ s h a l l be used with orovisions to n reven t the accidental assemblv of f issionable material into critical masses.

5-1.8.2 Since water is a reflector a n d mode ra to r of neu t rons , it is theoretically nossible tha t an a r r a n c e m e n t of subcrltical fissionable material coulcl be m a d e critical bv t h e in t roduct ion of water. Storage containers , shelving, and s to re rooms are reoui red to be des igned to o reven t the accidental assembly of a critical ma,~s, [n many cases, the areas a re desimaed to be criticallv safe even when comnlete lv s u b m e r g e d in water. Emergency p l ann i ng ~,,o~qd- shall include the effects of fire filthtimt water on such areas, a ssumin~ d is runt ion of the conten ts I~v t h e a c c i d e n t or by fire hoses. If - manua l fire f lght in~ noses a notential hazard u n d e r the worst condi t ions, t hen it i sessen t iM that any r eau i r ed fire-extin~ruishin~t caoabilitv be self-contained a n d au tomat ic in onerat ion. - v

if, . ~ , , ~ : ~ - ~ ~ ~.-: ~2.~e..n..b!), cf f i~fcn~b!e m ~ t e ~ could t. . . . . . . . . . . . . . . . . . . . . :,:_~,, it zcu!~ nc~ cxplc~c !'kc m~ = tcm'c b o m b ~ n z e . . . . . . ' . . . . . . . . . . . . . . . . . . . . . . F! ~,glLgr.igg~ t o d a t e h a s s h o w n t h a t s u c h r e a c t i o n s h a v e b e e n s e l f - l i m i t i n c : b u t

do resul t in m ino r dis t r ibut ion of radioactive products over-the

nuclear radiat ion tha t could be lethal.

5-~' Hospi ta l s . G - " "

Care Facilities.

The appropr ia te f o rm of fire protect ion for . .~ radioactive materials exist in hospitals shall.J#~"l: hazards analysis. Addit ional precaut ions ~ . . b ~ if the radioactive materials are s tored o r~ .~"~ to cause t h e m to be m o r e susceptible to releas

5-3 Uran ium E n r i c h m e n t . Fuel Fabricat ion, a n d Facil it ies .

~1 1 , . . ¢ . I 5-3.1 Special hazards related to fire p rob lems ~ c z ' = t c ~ ; ; ' ~ . . uz . ._~-c~' .2cn ._c ' . ' f ic ; shall be control led by at least one of the following:

(a) Locat ion

(b) Safe opera t ing p rocedures

(c) Fixed protec t ion systems

(d) Iner t ing

(e) Any o ther m e t h o d s acceptable to the author i ty having ju r i sd ic t ion

5-3.2* F l a m m a b l e a n d Combust ib le Liquids and Gases.

5-3.2.1 In enclosed spaces in which combust ib le gas could accumula te outs ide of the s torage vessels, piping, a n d utilization equ.ipment, combust ible-gas analyzers tha t are appropr ia te to the specific gas shall be installed. T he analyzer shall be set to alarm at a concent ra t ion no h i ghe r than 25 pe rcen t of the lower explosive limit.

5-3.2.2 F lammable and combust ib le liquids in enclosed spaces in which vapors could accumula te outside of the s torage vessels, piping, a n d utilization e q u i p m e n t shall be installed with combnst ible-vapor analyzers appropr ia te for the vapors gene ra ted T h e analyzer shall be set to a la rm at a concent ra t ion no h ighe r than 25 pe rcen t o f the lower explosive limit.

. . . . . . . . . . . . . ~ . . . . . . ~ . . . . . . . . . . . . . ~ . . . . . . . j . . . . . . . . . . . . . . . .

c . ~ . ~ ' ~ c r t .~c ~cc~- . f~ : " ~x : t~ :~ . .~ f i~ ~ u t c ~ , c x c c ~ ~ - ; " . ' a l v e s , o r

g & ~ l - 5 - 3 . ~ Safety controls and interlocks for t . . .~ . . . . . . . . . . . . . . . . . ~_, ~,ajor-' c o m b u s t i b l e , ~ f l ammable l iquids and f lammable trases a n d their associated d e l i v e r y g a ~ l ~ a ~ systems shall be testecI periodically and tested- after ma in t enance operat ions.

!~|.: tcz:c~ at l c ~ : ann'.:^~!7 cr .~ rcq 'd ' rcd b 7 the cq 'd 'pmcnt -r ~,%.'~ L: f ~ , , Z t l l 7 C 7 .

g - g ~ 6 ~3.~.4 Hydraulic fluids used in presses or o ther hydraulic e q u i p m e n t shall be the fire-resistant fluid ~)~t.~.cSc, firc rc;~3tant I I . . . . h . . . . , 4 \ t y p e . x . . . . . . . . . . . t

5-g~ ~ . ~ . 5 Solvents.

5-g,g,4- ~3.~.~.1 * Where a f lammable or combust ible solvent is used, it shall be h a n d l e d in a system that does no t allow uncon t ro l l ed release, of vapors. Approved op erat ing controls an d limits shall be estab.[!shed. An approved f ixed system for fire ex t inguish ing sh~g~: . . ins ta l led or its absence jus t i f ied to the satisfaction of tl~"~u~t~:~g-ity having jur isdict ion. ..~.x.'~: ' '

~ ~ . L v e n t distillation a n d recovery e q u i p m e n t for f lammable ' - ' . ' ]~-x~"~ _ . ~ , c o r ~ b l e liquids shall be isolated f rom areas of u s e

gggtj

In ordd%-~%nsurd the safe operat ion of process : ~ , such as Ph,fiSnium U r a n i u m Reduct ion an d Extraction ~ ) , ~ n s shall be provided to p reven t entry of excess ~ ' o f igCater-soluble solvents into the evaporators.

pera t ing controls and limits for the hand l ing of r i P , rials shall be establ ished to the satisfaction of the ¢ .h~n' ~" g jur isdict ion. A supply of an appropr ia te ~ ] n g m e d i u m shall be available in all areas where fines rags of such materials are present . (See Section 5-I .)

Cells, Glove Boxes, Hoods , and Caves.

5-4.1 All glove boxes, hoods, cells, and caves shall be provided with a m e a n s of fire de tec t ion if used in the hand l ing of pyrophoric materials, oxidizers, or organic liquids.

g 4 . 2 " Fire suppress ion shall be provided in all glove boxes, cells, hoods , a n d caves that m igh t conta in combust ib le metals or organic liquids in quant i t ies that could cause a b reach of integrity.

g 4 . 3 Hot Cells.

5-4.3.1 Hot cells shall be of noncombus t ib l e construct ion.

~i-4.$.2 Where hydraulic fluids are used in mas te r slave manipula tors , ~ r e - r e s i s t a n t tl~ . . . . . . . . . . . . . g . . . . .4x, k)~."-_'_'!'c fluids shall be used.

~b4.$.$ Combust ib le concent ra t ions inside the cells shall be kept to a m i n i m u m . Where combust ibles are present , a f ixed ex t inguish ing system shall be installed in the cell. If explosive concent ra t ions of gases or vapors are present , an iner t a tmosphe re shall be provided, or the cell a n d venti lat ion system shall be des igned to withstand pressure excursions.

~ . ~ Nenccmb"~f ib!e f i! te~ : ~ ! be .2:e~ er ~ fire :u~reo~: .c~

! ~ A ~cc'.:: ' ..zntz~ ~,.~:.!'" .L.~'-=z~.~zc-~n- : . . . . . . : ^ _ . t . _ , , k ^ - - -~^

5-4.4* G l o v e B o x e s .

5-4.4.1 The glove box a n d window shall be of noncombus t ib l e cons t ruc t ion .

5-4.4.2 The n u m b e r of gloves shall be l imited to the m i n i m u m necessary to pe r fo rm the operations, w h e n theg loves are no t being used, they shall be t ied outside the box. W h e n the gloves are no longer n e e d e d for operat ions, the gloves shall be r emoved an d glove-port covers installed.

5-4.4.3 The concent ra t ion o f combust ibles shall be kep t to a m i n i m u m . W h e r e combust ibles a re present , a fire suppress ion system or f ixed iner t ing system shall be provided. If f ixed

468

NFPA 801 - - F97 ROP

ext inguish ing systems are utilized, the internal pressurizat ion shall be ca lcula ted in order to prevent gloves f rom failing or be ing blown off.

54 .4 .4 Fire damper s shall be provided between glove boxes tha t are opera ted in series.

. . + + + - - . I ~ ^ I I I ~ . . . . . . ' . ~ + . , 4

0 3 , 0 + . * . . . . . . . . . i ,~ . . . . . . . .

d dzSl;, p" : . . . . . . :^~ -,-~,, ~.+ --~a+ ~.~.~ A docur'...cntc • houzckcc n g .. . . r . . . . . . . . . . . . . . . . . . . for cach glovc 5o'x.

5-4.5 Research and Product ion ReaetolW

5 ~.5.! ~ "h Centre! Syztcmz.

5-4.5.1 General. This sect ion establishes the addit ional fir~ orotec t ion criteria anolicable to nuc lear research a n d n roduc t ion

5-4.6 Control Systems and Eouioment .

5-4.6.1 Reactor control s ~ t e m s shall be des igned to be fail-safe. such tha t loss of the control svstems will no{ result in a hazardous condi t ion . [802 3-8.5]

ExceOtion: Where fail-safe desiom is not tmssible or control is necessam und-er adverse conditior[s, du~icate control circuitm shall be .Oro~idcd, i802 3-8.51 5-4.6.2* Reactor control circuits a n d e o u i n m e n t requi red for pr imary reactor safety shall be electric,'tlly supervised. T he circuits shall be a r ranged to n r o d u c e audible or visual a larm simaals i~ the circuit conductors are ~ r o u n d e d or accidenta/lv broken. [802 3- 8.6]

Exc~tion: Reactor control circuits and eaui~ment intended to monitor sOeclal seroices, such as air su~ah_, tank" liauid levels, etc.. rn4r3 ~¢ arraneed to ~oduce audible or visual trouble signals rather than alarm signals if a conductor on the circuit is zround~ or broken. [802 3-8.6]

. . . . U " I . . . . . l ~" . . . . . .

shu tdown of the reactor ;h~.'.:'~ ..'n-.~t

hazards analvsis (see 2-3), [802 3-8.3]

5-4 .7* I n c o m o a t ~ l e Mater ia l s . T he fire hazards analysis shall consider the i n h e r e n t hazardous a ~ o d a t e d with the use 9f incomuat ib le reactor materials in fire situations. [802 2-8]

5-4.8 Life Safew Code. Research and produc t ion reactors shall be cons idered sneciallv hazard occuoanc ies in accordance with NFPA

"..~.!.2 E!c~a'~".w.! ce.=',.rv.! mcc~=.n'=--.z "n':c":c :cm~'.:z '-b!e

. . . . . . . . . . . ~ . . . . . . . . . . . . . . . . 1 " . . . . . . . . . l . . . . [ " . . . . . . . . . . .~ . . . . . : e * . . . . . . 4 . . . . . . . . . a - ,^,~ . . . . . : . . . . . . . "" - ~ t. ~.;,.. n _

A ~ ! A~k t O • . . . . . . * . ' L I - - l u , l - . ^ . . . = ' - I - / " . . ^ c . . I A ^ . : ~ T ~ - - . : _ ~

U / L 1

L-" . . . . . . . . * . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L" . . . . . . . .

C h a p t e r 6 R e f e r e n c e d P u b l i c a t i o n s

6-1 The following d o c u m e n t s or por t ions t he reo f are re fe renced within this code as manda to ry r equ i r emen t s and shall be cons idered par t o f the r equ i r emen t s of this code. The edi t ion indicated for each re fe renced manda to ry d o c u m e n t is the cur ren t edit ion as of the da te of the NFPA issuance of this code. Some of these manda to ry d o c u m e n t s m igh t also be re fe renced in this code for specific informat ional purposes and, therefore, are also listed in Append ix C.

6-1.1 NFPA Publ i ca t io ns . National Fire Protect ion Association, 1 Bat terymarch Park, P.O. Box 9101, Quincy, MA 02269-9101.

NFPA 10, Standard for Portable Fire Extinguishers, 1994 edition.

NFPA 11, Standard for Low-Expansion Foam, 1994 edition.

NFPA l lA , Standard for Medium- and High-Expansion Foam Systems, 1994 edition.

NFPA 12, Standard on Carbon Dioxide Extinguishing Systems, 1993 edit ion.

NFPA 12A, Standard on Halon 1301 Fire Extinguishing Systems, 1999 edit ion.

NFPA 13, Standar.~.~. the Installation of Sprinkler Systems, 1906 edit ion. , '4:~'~:,

NFPA 14, ~ for the Installation of Standpipe and Hose Systems, 1996 e d i tio ~i~.." "~?.':.,-'~:, ":~@. @:..

N ~ . . : ~ ~ . ~ . W . at.er Spray Fixed Systems for Fire Protection, 1 9 9 6 < . _ ~ . " ~ . . . ~ . . . . ~.-.x~..~.~. -*

"'~A 1 ff**.~ Standard f o ~ Installation of Deluge Foam-Water er ~.~oam-Wate:r Spray Systems, 1995 edition.

A, ".~'tandard for the Installation of Closed-Head Foam-Water Spray " "~, 1.~95 edition. ~ NFPA 17¢ ~ ' ' ' dard for Dry Chemical Extinguishing Systems, 1994

}C Standard for Wet Chemical Extinguishing Systems, 1994

. .lhl~A 20, Standard for the Installation of C_,entrift~gal Fire Pumps, ~ 6 edition.

NFPA 92, Standard for Water Tanks for Private Fire Protection, 1996 edit ion.

NFPA 24, Standard for the Installation of Private Fire Service Mains and Their Appurtenances, 1995 edition.

NFPA 25, Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems, 1996 edition.

NFPA 30, Flammable and Combustibl~ Liquids Code, 1996 edition.

NFPA 45, Standard on Fire Protection for Laboratories Using Chemicals, 1996 edition.

NFPA 50, Standard for Bulk Oxygen Systems at Consumer Sites, 1996 edit ion.

NFPA 50A, Standard for Gaseous Hydrogen Systems at Consumer Sites, 1994 edition.

NFPA 54, NationalFuel Gas Cod& 1996 edition.

NFPA 55, Standard for the Storage, Use, and Handling of Compressed and Liquefied Gases in Portable Cylinders, 1993 edition.

NFPA 58, Standard for the Storage and Handling of Liquefied Petroleum Gases, 1995 edition.

NFPA 70, National Electrical Code, 1996 edition.

NFPA 72, National Fire Alarm Code, 1996 edition.

NFPA 75, Standard for the Protection of Electronic Computer~Data Processing Equipment, 1995 edition.

NFPA 80, Standard for Fire boors and Fire Windows, 1995 edition.

NFPA 82, Standard on Incinerators and Waste and Linen Handling Systems and Equipment, 1994 edition.

NFPA 86, Standard for Ovens and Furnaces, 1995 edition.

NFPA 86C, Standard for Industrial Furnaces Using a Special Processing Atmosphere, 1995 edition.

NFPA 86D, Standard for Industrial Furnaces Using Vacuum as an Atmosphere, 1995 edition.

NFPA 90A, Standard for the lnstaUation of Air Conditioning and Ventilating Systems, 1996 edition.

469

N F P A 8 0 1 - - F 9 7 R O P

NFPA 90B, Standard for the Installation of Warm Air Heating and Air Conditioning Systems, 1996 edition.

NFPA 91, Standard for Exhaust Systems for Air Conveying of Materials, 1995 edition.

NFPA 99, Standard for Health Care Facilities, 1996 edition. NFPA 101, Life SafeO Cod~ 1997 edition. NFPA 220, Standard on Types of Building Construction, 1995 edition. NFPA 241, Standard for Safe-Guarding Construction, Alteration, and

Demolition Operations, 1996 edition.

NFPA 251, Standard Methods of Tests of Fire Endurance of Building Construction and Materials, 1995 edition.

NFPA 252, Standard Methods of Fire Tests of Door Assemblies, 1995 edition.

NFPA 255, Standard Method of Test of Surface Burning Characteristics of Building Materials, 1996 edition.

NFPA 430, Code for the Storage of Liquid and Solid Oxidizers, 1995 edition.

NFPA 480, Standard for the Storage, Handling, and Processing of Magnesium Solids and Powders, 1993 edition.

NFPA 481, Standard for the Production, Processin~ Handling, and Storage of Titanium, 1995 edition.

NFPA 482, Standard for the Production, Processing, Handlin~ and Storage of Zirconium, 1996 edition.

NFPA 600, Standard on Industrial Fire Brigades, 1996 edition. NFPA 701, Standard Methods of Fire Tests for Flame-Resistant Textiles

and Films, 1996 edition. NFPA 750, Standard on Water Mist Fire Protection Systems, 1996

edition. NFPA 780, Standard for the Installation of Lightning Protection

Systems, 1995 edition. NFPA 803, Standard for Fire Protection for Light Water Nuclear Power

Plants, 1993 edition.

t~¢actor Electric GeneraCin~ Plants. 1995 edition. . "

NFPA15OO, StandardonFireDepartmentOccupationa~ 2n~f~.~ Health Program, 1992 edition. ":~ ":~.:~ ~

NFPA 2001, Standard on Clean Agent Fire Extin~# !ing ~ ~ 1996 edition. ~ ! t n ~ '%i~N.,~";"

: Te. 6-1,2 ASTM Publications. American S o c , ~ f o , d Materials, 1916 Race Street, P h i l a d e l p h i ~ 1 0 3

Beha~-, a ~ s ~ ~1~6, Sta,.~rd Test Mnhod /or ~ ,teriai ~n Vertical Tube Furnace at 750°C, 1982. A

ASTM E814, Fire Tests of Through-Penetration Fire~ ~ i ~¢' 1994.

6-1.3 UL Publication. Underwriters Laboratories I:~ :., 333 Pfingsten Road, Northbrook, IL 60062.

UL 1479, Fire Tests of Through-Penetration Fire Stops, 1983 edition.

Appendix A Explanatory Material

This appendix is not a part of the requirements of this NFPA document but is included for informational purposes only.

A-I-I.1 The objectives of this standard are to reduce personal hazards, provide protection from property damage, and minimize process interruption resulting from fire and explosion. Radioactive contamination might or might no t be a factor in these risks.

A-l-2 The nature of radioactive materials is such that their involvement in fires or explosions can impede the efficiency of fire- fighting personnel, thus causing increased potential for damage by radioactive contamination. Various types of emitted radiation are capable of causing damage

to living tissue. In particular, fire conditions can cause the formation of vapors and smoke that contaminate the building of origin or neighboring buildings and outdoor areas. The fire protection engineer 's main concern is to prevent the release or loss of control of these materials by fire or during fire extinguishment. This is especially important because radioactivity is not detectable by any of the human senses.

For additional requirements for light water nuclear power reactors, see NFPA 803, Standard for Fire Protection for Light Water Nuclear Power Plants, ~...~.~ thz rzz~mr'...c~d.z~"2~z for rczcarzh

r__ ~r.._,.__ o . . . . . . r __J ,~__~...,:__ D . . . . . . and fo r the reauirements for advanced light water nuclear reactors see NFPA 804. Standard (or Fire Protection for Advanced Lieht Water Reactor Electric Generating Plants.

A-l-5 Definitions. A-l-5 Approved. The National Fire Protection Association does not approve, inspect, or certify any installations, procedures, equipment, or materials; nor does it approve or evaluate testing laboratories. In determining the acceptability of installations, procedures, equipment, or materials, the authority having jurisdiction may base acceptance on compliance with NFPA or other appropriate standards. In the absence of such standards, said authority may require evidence of proper installation, procedure, or use. The authority having jurisdiction may also refer to the lisdngs or labeling practices of an organization that is concerned with product evaluations and is thus in a position to determine compnm~liance with appropriate standards for the current production of liste~: items.

A-l-5 Authority ~ J u r i s d i c t i o n . The phrase "authority having jurisdiction" i ~ . ~ d in'BIFPA documents in a broad manner, since jurisdiction~{.~.~l~.t~roval agencies vary, as do their responsibi]!~s. ~ e public safety is primary, the authority having, ks~ t lon ~ b e a federal, state, local, or other regional d e p a g . ~ l n d i v i ~ h as a fire chief; fire marshal; cYaief of ~.~'~re~v.ention buread.~.~bor department, or health department; ,.~,~'.~g ¢~cial; electri~ J inspector; or others having statutory

insurance purposes, an insu nce inspect ion dep~ ~t, ~ t i ng bureau, or other insurance company

~ having jurisdiction. In many or his or her designated agent

represe Lye ..~. a)~ be t he authority circumst~ ~ e property owner,

~ r g . es t h ~ l e of the authority having jurisdiction; at government 1 ~ " ~ ~ ' ~ , the commandin~ officer or departmental official may

t t i ' ~ t h o r i t y having jurisdiction.

>A-l-5 "Combustible. The three terms used to describe the i l ~ b n s t i b i l i t y of materials ~ noncombustible, limited- ~ m b n s t i b l e , and combustible ~ have specific definitions. When :~ attempting to classify the combustibility of a material, ensure that the definitions of all three terms are thoroughly understood.

A-I-5 Combustible Liquid. See NFPA 30, Flammable and Combustible Liquids Code.

A-I-5 Fire Damper. Some such devices are listed in the Underwriters Laboratories Inc., Buildin~ Materials Director 3 under the category of "Fire Dampers (ALBR).

A-I-5 Limited-Combustible. The three terms used to describe the combustibility of materials - - noncombustible, limited- combustible, and combustible - - have specific definitions. Wheta attempting to classify the combustibility of a material, ensure that the definitions of all three terms are thoroughly understood. See NFPA 220, Standard on Types of Building Construction.

A-l-5 Listed. The means for identifying listed equipment may vary for each organization concerned with product evaluation; some organizations do not recognize equipment as listed unless it is also labeled. The authority having jurisdiction should utilize the system employed by the listing organization to identify a listed product.

A-I-5 Noncombust~ie. The three terms used to describe the combustibility of materials - - noncombustible, limited- combustible, and combustible - - have specific definitions. When attempting to classify the combustibility of a material, ensure that the definitions of all three terms are thoroughly understood.

A-I-6 For a full explanation, see ASTM E380, Standard Practice for Use of the International System of Unit~

A-2-1.1 Chapter 2 provides criteria for the development of administrative procedures and controls necessary for the execution of fire prevention and fire protection activities and practices for facilities handling radioactive materials.

A-2-2 Proper preventive maintenance of operating equipment as well as adequate facility personnel training are important aspects of a viable fire prevention program.

A-2-$ Fire Hazards Analysis. A thorough analysis of the fire potential is necessary to incorporate adequate fire protection into the facility design. Integrated design of systems is necessary to

470

N F P A 8 0 1 - - F 9 7 R O P

ensure the safety of the facility and the operators from the hazards of fire and to protect property and continuity of production.

The following steps are recommended as part of the analysis procedure:

(1) Prepare a general description of the physical characteristics of the facilities that outlines the fire prevention and fire protection systems to be provided. Define the fire hazards that can exist, and state the loss-hmiting criteria to be used in the design of the facility.

(2) List the codes and standards to be used for the design of the fire protection systems. Include the published standards of the National Fire Protection Association. Indicate specific sections and paragraphs.

(3) Define and describe the characteristics associated with potential fire for all areas that contain combustible materials, such as maximum fire loading, hazards of flame spread, smoke generation, toxic contaminants, and contributing fuels. Consider the use and effect of noncombustible and heat-resistant materials.

(4) List the f ireprotect ion system criteria and the criteria to be used in the basic design for such items as water supply, water distribution systems, and fire pump safety.

(5) Describe the performance criteria for the detection systems, alarm systems, automatic suppression systems, manual systems, chemical systems, and gas systems for fire detection, confinement, control, and extinguishment.

(6) Develop the design considerations for suppression systems and for smoke, heat, and flame control; combustible and explosive gas control; and toxic and contaminant control. Select the operating functions of the ventilating and exhaust systems to be used during the period of fire extinguishment and control. List the performance criteria for the fire- and trouble-annunciator warning systems and the auditing and reporting systems.

(7) Consider the qualifications necessary for personnel performing insi~ection checks and the frequency of testing needed to maintain rehable alarm, detection, and suppression systems.

(8) Use the features of building and facility arrangements and the structural design features to generally define the methods for fire prevention, fire extinguishing, fire control, and control of hazards created by fire. Fire barriers, egress, fire walls, and the isolation and containment features that should be provided for flame, heat, hot gases, smoke, and other contaminants should be caret ~ . . ~ . planned. Outline the drawings and list of equipment an~ [hat are needed to define the principal and auxiliary ~ i n systems. *~'~ ~ ~ i

(9) Identify the dangerous and hazardous combustibl~ maximum quantities estimated to be present i n , ~ ~cilit ~ - Consider wfaere these materials can be apprqg~'~t..:.4.,,., ~ ~ "~"" facility.

(10) Review the types of potential f i r e ~ ~" ~g...d on h e ' ~ .ecte quantities of combustible materials, thef'~ " e ~ $ ~ t e d geve~ ~, intensity, duration, and the potential hazards ~ ! " " te t. Fo~ tach of the types reviewed, indicate the total time invo ¢~:/~ ~d .~ time for each step from the first alert of the fire hazard i ~ u n ~2~:" ~ c'ontrol and extinguishment is accomplished. Describe in d ~ i l the facility systems, functions, and controls that will be provic[:i ~[ and maintained during the fire emergency.

(11) Define the essential electric circuit integrity needed during fire. Evaluate the electrical and cable fire protection, the fire confinement control, and the extinguishing systems that will be needed to maintain their integrity.

(12) Carefully review and describe the control and operating room areas and the protection and extinguishing systems provided for these areas. Do not overlook the additional facilities provided for maintenance and operating personnel, such as kitchens, maintenance storage, and supply cabinets.

(13) Analyze the available forms of back-up or public fire

~ rotection that can be considered for the installation. Review the ack-up fire department, equipment, number of personnel, special

skills, and training needed. (14) List and describe the installation, testing, and inspection

necessary during construction of the fire protection systems that demonstrate the integrity, of the systems as installed. Evaluate the operational checks, inspection, and servicing needed to maintain such integrity.

(15) Evaluate the program for training, updating, and maintaining competence of the facility fire-fighting and operating crew. Provisions should be required to maintain and upgrade the fire-fighting equipment and apparatus during facility operation.

(16) Review the qualifications for the fire protection engineer or consultant who will assist in the design and selection of equipment. This individual will also inspect and test the physical features of the completed system and develop the total fire protection program for the operating facility.

A-2-7 It is fighting fc systems, e~ control..~

(17) Evaluate life safety, protection of critical process/safety equipment, provisions to limit contamination, potential for radioactive release, and restoration of the facility after a fire.

A-2-3.2 A fire risk analysis migt~- should aiso be required to be performed.

A-2al(e) See NFPA 51B, Standard for Fire Prevention in Use of Cutting and Welding Processes.

A-2-4(f) Refer to Figure A-2-4(f). See figure shown on page 460.

A-2-4(f) See N'FPA 901, Uniform Coding for Fire Protection.

A-2-4(g) See NFPA 601, Standard on Guard Service in Fire Loss Prevention.

A-2-4fi) The use of noncombustible or fire-retardant concrete formwork is especially imnortant for large structures (e.~.. reactor buildin~ and turb ine~enera tor nedestal~ where large at~mtities of forms are used.

Pressure-imprel~nated fire-retardant lumber should be used in accordance with its listing and the manufacturer 's instructions. Where exposed to the weather or moisture (e.g., concrete forms), the fire retardant used should be suitable for this exposure. Fire- retardant coatings are not acceptable on walking surfaces or surfaces subject t hani damage.

i m ~ t ~ t - v ~ _ the responding fire brigade or public fire- f o r c ~ ' ~ . ~ iliar with access, facility fire protection

~, e ~ . ~ - ~ e t ~ ' ~ h t i n g , specific hazards, and methods of fire

A-2-7~

m i ' ~ ' ~ o r o v i d e d by a healthphysicist, the level ~e .a~/fimed should be dec idedby the officer in [htifig operation and based on the knowledge he operation to be accomplished.

Standard on Industrial Fire Brigade. NFPA 1500.

10.156, Fire Brigades, should be consulted for

e prefire plans should include, but not be limited to. the )ertinent issues:

g (a ) Fire hazards in area

(b) Chemical hazards in area

(c) Radiation hazards

(d) Egress access

(e) Emergency lighting

(f) Fire protection systems/equipment in area

(g) Special fire-fighting instructions

(h) Ventilation systems/air flow path

(i) Utilities

(j) Special considerations on adjoining areas

A-3-1 Special Considerations. The design and installation of service facilities - - such as light and power, h e a t l n g , . . c , p ~ ventilation, storage, and waste disposal materials - - might not present any unusual problems at facilities not handling radioactive materials: however. :-...'igOr nc.t p=c~cnt any "-nu~'-^~ pr~Sl=n-..~, the introduction of radioactive materials into a facility poses additional hazards to both personnel and property that warrants special consideration of these services. Inadequate attention to the design

¢ ! features of such service facilities u:'..-c.rtunz.tc.y has contributed to the need for extensive ~ decontamination f~-~'nd t* ~e ta~c-essm~ following fires and explosions. It "i; zc.r~.:.dcrcd Good practice ~ demands detailed analysis of the design of each service for the purpose of determining it's hhe-effect tS.c ;c';'Acc • ,;~'.:!~ .h.~d.': upon the spread of contamination following a fire or criticality accident. An appraisal of the severity of contamination spread then can be used to determine the necessity for modifying the design of the service facility under consideration.

471

N F P A 801 - - F 9 7 R O P

Name of company:.

Date of fire: Time of fire: Operating facili~

Under construction:

Location where fire occurred:

Description of facility, fire area, or equipment (include nameplate rating) involved:

Cause of fire, such as probable ignition source, initial contributing fuel, equipment failure causing ignition, etc:

Story of fire, events, and conditions preceding, during, and after the fire:

Types and approximate quantities of portable extinguishing equipment used:

Was fire extinguished with portable equipment only?

Employee fire brigade at this location?

For interior structural fires?

Was fixed fire-extinguishing equipment installed?

Specify type of fixed extinguishing system:

Automatic operation

Specify type of detection devices:

Did fixed extinguishing system control

Did detection devices and extinguishing system function pl

If no, why?

ic fire department called?

~ked for incipient fires?

Estimated direct damage due to fire: $

Estimated additional (consequential) loss: $

, manually' actuated "w&~'!:,. 0 or both

or both?

and $

Nature of additional loss:

Estimated time to complete r e p a i r s / r e p l a c e m ~

Number of persons injured: ~ q

What corrective or preventive suggestions would i

Number of fatalities:

others who may have similar equipment, structures, or extinguishing systems? _ _

Submitted by:

Planning for Decontamination. The extent to which decontamination might be necessary depends upon the amount of radioactive material being released, its half-life, its chemical and

hysical form, and the type of radiation emitted. Taking all of these ctors into account, a realistic assumption should be made as to

the extent of a possible contamination incident. When decontamination is necessary, it can be costly and time consuming. These factors tend to raise costs and, therefore, justify capital expenditures to reduce them to a minimum through good emergency planning procedures.

A-$-4 Determination of fire area boundaries should be based on consideration of the following:

(a) Types, quantifies, density, and locations of combustible material and radioactive materials

(b) Location and configuration of equipment

(c) Consequences of Iosit~g-inoperab[¢ equipment

(d) Location of fire detection and suppression systems

(e) Personnel safety/exit requirements

Tide:

Figure A-2-4(f) Sample fire report.

It is recommended that most fire barriers separating fire areas be of 3-hour fire-resistance rating unless a fire hazards analysis indicates otherwise. If a fire area is defined as a detached structure, it should be separated from other structures by an appropriate distance (see NFPA 80.4, Recommended Practice for Protection of Buildings from Exterior Fire Exposures). Fire area boundaries typically are provided as follows:

(a) To separate manufacturing areas and radioactive materials storage areas from each other and from adjacent areas

(b) To separate control rooms, computer rooms, or combined control/computer rooms from adjacent areas. Where a control room and computer room are separated by a common wall, the wall might not be required to have a fire-resistance rating

(c) To separate rooms with major concentrations of electrical equipment, such as switchgear rooms and relay rooms, from adjacent areas

(d) To separate battery rooms fi-om adjacent areas

(e) To separate a maintenance shop(s) from adjacent areas

472

NFPA 801 - - F97 ROP

(0 To separate the main fire pump(s) f rom the reserve fire

~ ump(s) , where these pumps provide the only source of water for re protect ion

(g) To separate fire pumps f rom adjacent areas

(h) To separate warehouses and combustible storage areas f rom adjacent areas

(i) To separate emergency generators f rom each other and f rom adjacent areas

(j) To separate fan rooms and p lenum chambers from adjacent areas

(k) To separate office areas f rom adjacent areas

. . . . : ~ . 1 . . ^ . . 1 . ~ 1 k ^ 1 : . * ^ ~ ^ - ^ t . . ^ . . I . - 1 ~ ^ ^ . ~ 1 ~ . . . . . . : . . . . . * . ^¢

. . . . . . . . . . ' . . . . . . . . J . . . . . . 6 . . . . . . . . . . . . . . . . . . . . . . / " ~ J . . . . . . . . '

A-3-6.1 Fire barriers also w-ght 5c pcrm".::c~ t~ serve as radiation shields, kP/AC aL- cn;-clc.~cz ventilation barriers, and f lood or watertight enclosures; these concerns also should be taken into considerat ion.

A-3-9 Ventilation of a nuclear facility involves balanced air differentials between building areas, comfort ventilation, and heat removal f rom areas where heat is genera ted by equipment. This need also includes fire area isolation and smoke removal equipment , as well as equ ipmen t for filtering radioactive gases.

AS 9.! ~ p ! ~ c duct: :--c uzcd, the 7 :hc.u!d 5c !':ted firc rcterde.n: Wpc: and ~hc.u'd ~z z;r2uz.tcd "n ".hz ritz h=:=rd: =.==!7=-.

A-$-9.1 In addit ion, see NFPA 204M, C, uidefor Smoke and Heat Venting. A-3-9.4 Self-cleaning filters that pass through a viscous liquid generally yield a radioactive sludge requir ing disposal and, therefore, s t~q-should be avoided in areas where radioactive materials are handled. Because of the combustible nature of the liquid, additional fire protect ion features should be provi. de te rmined by the fire hazards analysis. .,..-~ ~:~.

• ' : ~ ' ~ , ,

A-$-9.5 Exception. The use offf i ters of low c o m b u s ~ ~;" those that comply with UL 586, Standard for Test P~m~i~ Effidency Particulate, Air Filter Units, and UL 900. ,~. .~lar, Performance of Air Filter Units, is r e c o m m e n d e ~ * . ~ e the likelihood of the spread of contaminafi.@~'by f i r ~ absence of protect ion systems within t h e . ~ and for "~." .. banks, fires in combustible filters beco r r t~"~e~ae ly ditii~ It to extinguish. ~ , . j

I ~ ^ . . . . . . . . .-1 , 1 . . . .

A-3-9.7.1 For example, fresh-air inlets should no t be located near storage areas of combustible radioactive waste material that, upon ignition, could discharge radioactive combustion products that might be -:^,.^at . . . . . . up t ransported by the ventilating system.

A-$-9.7.4 Separate smoke control systems are preferred; however, smoke ventilation can be integrated into normal ventilation systems using automatic or manually posi t ioned dampers and motor speed control.

A-S-9.7.6 Stairwells serve as escape routes and fire-fighting access routes. Suitable methods of ensuring a smoke-free stairwell i n d u d e pressurization of stairwells (see N'FPA 90A, Standard for the Installation of Air Conditioning and Ventilating Systems) and the construct ion of smoke p r o o f towers (see NFPA 101, Life Safe O Code. A-3-9.7.7 Where mechanical ventilation is used, 300 cfm (8.5 m 3 / m i n ) is equal to 1 R 2 (0.09 m 2) of natural-convection vent a r e a .

A-$-9.7.8 A breakdown in an air-cleaning system can be more serious if the discharged air can be drawn immediately into ano ther system. General isolation of radiation facilities f rom all o ther facilities causes an increase in both construction and opera t ingcos ts but should be under taken if jnst if ied by a study of the possible results o f a contaminat ion incident. In order to avoid unnecessary accidents, such facilities should be located separately from those handl ing explosives or f lammable materials.

A-3-10.1 For fur ther information, see NFPA 15, Standard for Water Spray Fixed Systems for Fire Protection, Append ix A.

A-$-15.1 The lights, ventilation, and operat ion of much remote- control led equ ipment are d e p e n d e n t upon a reliable source of electrical power. The location of transformers, switches, and con t ro lpane l s should be well-removed f rom high-activity areas to ensure that main tenance work can be done without direct exposure to radiation f rom such areas. The need for effective ventilation dur ing and immediately after an emergency such as a fire is of considerable importance.

A-$-15.2 It is important that electrical equ ipment be selected for its ease of decontaminat ion and early restorauon to service in those areas where ~ t he r e is contamination. :.: ccnz:.dered HEel)'.

A-$-15.4 ~ E lec~ca l ~ , ~ circuits and componen t s in reactor facilities nresent the same t w e of fire protect ion nroblems as in o ther industrial fadlities. Thet3r ime concern in the-reactor facility is di rected towards those circuits and components essential to cont inued operat ion of the reactor and oarticuiarlv to those essential to a safe shutdown under emergency conditions. For these rg~ons , special care is devoted to redundancy of systems.

A-3-14.2.2 S remotely fro

m~bmbnstible storage fadlit ies located facility might be necessary Ln ~c.mz c~z~.

of combustion of waste materials ; : ~ ..h~hly active radioactive materials are . . a " ~ e n t i l a t i o n , ~ air conditioning, or ms4.~ decontaminat ion prob lem of serious

A-4-1 "~ . . fac i l i t i e s covered in this document vary widely in terms of f u n c : t ] ~ . ~ d , # h e type of operations, as well as the type and

~luantity o ~ ' ~ 6 a c t i v e material that might be present. The intent of

~ ctio~.4g to specify the fire protect ion requirements for only ~ n ~ % ' ~ r e a s (or the w h o l e ) o f the facility where radioactive

~. are present.

,A41 :~ In handl ing fissile materials, precautions should be taken to protect against the normal radiation hazard but also only

~ a i n s t the criticality hazard caused by the assembly of a m i n i m u m critical mass. To avoid criticality dur ing fire emergencies, fissile materials that have been arranged to minimize the possibility of a criticality hazard should be moved only if absolutely necessary. If it becomes necessary to move such fissile materials, it should be done under the direction of a responsible person on the staff of the facility and in batches that are below the critical mass, or the materials shall be moved in layers that minimize the possibility of a criticality occurring. Since water is a reflector and a modera tor of neutrons, concern for a criticality hazard sometimes leads to the unjustified and unevaluated exclusion of fire protect ion water from the area where fissile materials are stored or handled. The possibility of water modera t ion and reflection caus inga criticality acc iden t can be calculated in advance. If, in fact, such a hazard exists, combustible material that would necessitate the use of water for fire f ighting should be eliminated. W h e n water-based manual fire fi~htin~ Doses a potential criticalitv hazard under th~ wg l~ condit ions.- then it is'essential that anv reuuired fire-extinLmishin~ canabilitv be self conta ined and automatic in operation. In many facilities, fissile materials are stored and handled in sprinklered a r e a s .

A-4-2.1 Water quality can p r e s e n t a long-term problem r-ela~,~l-to fire protect ion water supplyed. Factors to be considered should include water hardness, corrosiveness, presence of micro- organisms, and other problems that are unique to the type of facility.

A-4-2.2.2 For fur ther information, see NFPA 20, Standard for the Installation of Centrifugal Fire Pumps. For una t t ended facilities, see Section 4-9.

A-4-2.2.$ For fur ther information, see NFPA 22, Standard for Water Tanks for Private Fire Protection.

Auk2.2.4 The 8-hour requ i rement for refilling can be extended if the initial supply exceeds the recommendat ions of 4-2.1. ncrmzl l 7 ::. The prefer red m e t h o d for the refilling operation i s t ~ ~.^ ^ ~ ^ ~ , : . L . ^ a . . . . automatic ~a~,~.

A-4-8 All fire protect ion water system control valves should be supervised as r e c o m m e n d e d in NFPA 96, Recommended Practice for the Supervision of Valves Controlling Water Supplies for Fire Protection.

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N F P A 8 0 1 - - F 9 7 R O P

A-4-7.1 For the des ign of c losed-head foam-water spr inkler systems, see NFPA 16A, Standard for the Installation of Closed-Head Foam-Water Sprinkler Systems.

A-4-9 Facilities tha t are opera ted u n a t t e n d e d or with min imal staffing p r e sen t special fire pro tec t ion concerns . Considera t ion s h o u l d b e given bo th to the delayed response t ime for the fire brigade or public fire-fighting pe rsonne l a n d to the lack o f pe r sonne l available to alert o thers on-site o f ~ a fire condition°

A-5-1 The principal fire hazards e n c o u n t e r e d in special radiat ion facilities will vary with the part icular occupancy. In general , the r equ i r emen t s of this s t andard apply to all facilities hand l i ng radioactive materials within the scope o f the d o c u m e n t . Special occupancy fire hazards associated with part icular opera t ions are descr ibed in this chap te r a long with the special fire protec t ion me thods tha t apply to those hazards, with the except ion o f hazards associated with nuc lear power plants ~ ~'-~2c^-.r rc~carch r-eac-t-~-s-.

A-5-2 Radioactive materials are used in hospitals for a variety of purposes , inc lud ing biomedical tracers, disease therapy, and laboratory analysis. Ccncr~2 firc prctcc'dc.n r cqu ' r cmcn tz for

. . . . r . . . . . . . . ": 77 ~ . . . . . . . . . . . . . . . . . . . . . . . . ' . . . . . . . . J ~ '

Radioactive materials used in hospitals rarely const i tute a fire hazard themselves. Most often, the fire hazard associated with these materials is con tamina t ion of personnel , equ ipmen t , buildings, or the env i ronmen t as a result of fire damage to conta iners and the s u b s e q u e n t release o f radioactive materials.

Biomedical Tracers. Radioactive solut ions can be admin i s t e red to a pat ient intravenously or orally. T h e m o v e m e n t of the solution, as t raced by mon i to r ing the radioactivity level in di f ferent parts of the body, indicates the rate of various metabol ic processes or the flow rate o f blood. By compar i ng research data on heal thy individuals with tha t of those known to have specific diseases, a pa t ien t ' s condi t ion can be d iagnosed without surgery. ~

Disease Therapy. Radioactive solut ions can be admin i s t e red to a pat ient intravenously or orally. T h e solution is des igned to concent ra te in specific o rgans or diseased tissue. The irrac ~ of the organ or tissue by the concen t ra ted solut ion can alter# ~ func t ion ing of the organ (such as the thyroid gland) o ~ ' i ~.¢ diseased tissue (such as certain cancer cells). <#i~."-:i~::::::, ~ - . ' ~ :

Laboratory Analysis. Radioactive mater ia ls in solut ions o~'~"'~ ~ ~ concen t ra t ion are f requent ly used for laborato~:..~.~.is.._.:_:: !~< ~:~-

A-5-3.2 Combust ib le gases - - such as hydrqg~i #~' '~*~?'~ a, e t h ~ . ' ~ ~< , : " acetylene, a n d natural gas - - p re sen t bo .t~..-'.'~.e a n d e x l S ~ 4#" hazards. They shou ld be used only in a ~ " ~ g c e with o ~ mg controls a n d limits requi red by the a p p l i c a b ] ~ i ~ A s ~ . ards.

A-5-$.2.5.1 Where solvents are used in fuel p r o c ~ : considera t ion shou ld be givefi to us ing solvents wi~..';~,~'~:-~-lowest fire a n d explosion hazard consis tent with the requ~rem#Sts of the process.

A-5-3.2.5.2 Explosion-relief panels shou ld be provided for solvent recovery areas.

A-5-3.2.5.$ ~ Exner ience and exner iments have conf i rmed that us ing nitric acid cluring scrap recovery, e x p c - c n c c z..'=~ . . . . . .~. . . . . t. . . . . . . . ~ . .~^a .t.^+ can result in exo thermic react ions of distinctive violence ~ between t r ibutylphosphate and uranyl ni t rate or between t r ibutylphosphate a n d nitric acid, or both .

A-5-3.2.5.4 Fines a n d cutt ings f rom materials, such as z i rconium, const i tute a pyrophor ic hazard.

A-5-4.2 The pre fe r red m e t h o d of suppress ion is an au tomat ic spr inkler system, a l t hough o ther m e t h o d s of suppress ion also may be permi t ted when,aher-~ installed in accordance with the applicable NFPA s tandard .

A-5-4.4 The external radiat ion hazard p resen t du r ing fabricat ion of Uranium-235 fuel e lements is o f a low order. Uran ium-233 a n d Plutonium-239 p r e sen t severe inhala t ion hazards to personnel ; therefore, an enclosed pro tec t ion system shou ld be requ i red to be used. These systems are called glove boxes. They can be extensive, with an appreciable a m o u n t of glass, a n d can p r e sen t u n i q u e fire pro tec t ion problems. U n d e r no rma l condit ions, substant ial protect ion can b e p r o v i d e d against the existing radia t ion hazard. On the o ther h a n d , if a criticality inc iden t shou ld occur, the type a n d quant i ty of radiat ion emi t ted can create grave hazards to personnel . Even a small fire within a glove box can p roduce serious consequences if no t control led properly. Fire control systems and

procedures for glove boxes shou ld be carefully developed an d i m p l e m e a t e d before the boxes are used. Generally, such protective systems are cus tom-des igned for the specific application.

A-5-4.6.2 Where h igh reliabilitv is needed , the circuit shou ld be a r ranged to nroduc-e the a larm signal even if a b roken wire or a g r o u n d accidental ly occurs. Und¢~r these condit ions, tlae a r r a n g e m e n t of circuit a n d harts shou ld be such tha t an audible

v

signal c anno t be s i lenced wi thout a cor resoond ing visual signal.

A-b-4.6.$ The _ n r ime concern in the reactor facility is dire¢~¢d towards those circuits and svstems essential to con t inued ooerat ion of the reactor and DarticulaJ'lv to those essential to a safe sfiutdown u n d e r emergency condit ions. The possible effects of heat, smoke, and corrosive gases on the ooera t ion of control systems alOd e o u i n m e n t reo-uire a t tent ion- to features of good nractice a n d fire nro tec t ion so as to min imize interference; vdth overa t ion of these svstems. If a fire involving a reactor con~-ol system causes reactor shutdown, the need for con t inued cooling of fuel e l emen t s will be r educed bu t will not. in mos t cases, be eli 'minated. For these reasons, snecial care is devoted to r e d u n d a n c y of svstems. emergency vower sunnl ies (see 5-5.2.53. separat ion, vhvsical

A-5-4.7 As an examvle, the ~S¢ of liouid metal as a

Justify the exclusion of water systems f rom the area. W h e n such cond i t ion exists, it may imoose m o r e severe l imitat ions on the o resence of combust ib le oils. vlastics, insulat ions, an d o ther materials tha t general ly reouire water for fire ex t inguishment . Where such mixed hazards-exist, it is imoor t an t tha t careful considera t ion be given to the notentials i'or a failure in one system to cause a f a i l u r e in the incomnat ib le system. In such cases, ei ther a orotec t ion system shou ld be t~rovided tha t can insure the ex t i ngu i shmen t of fire in ei ther swstem before it can cause a run ture of the o ther svstems, or a single vrotec t ion system (such as inert ing) shou ld be develoned that is adeoua te for ei ther hazard.

Appendix B Sources o f Radiation - - The Nature o f the Fire Prob lem

B-I General .

B-I.1 Radioactive materials are substances tha t spontaneous ly decay, emi t t ing energet ic rays or particles in the process. Certain radioactive e lements occur in more t h a n one form. The various forms are chemically identical bu t differ in their a tomic weights a n d are called isotopes. Those tha t are radioactive are called radioactive isotopes (radioisotopes). It is possible for an e l emen t to have one or m o r e nonradioact ive (stable) isotope(s) an d one or m o r e radioactive isotope(s) ( radionucl ides) . Each of the radioisotopes emits a definitive type or types of radiation. In discuss ing radioactive material , therefore , it is always necessary to use the te rminology that identif ies the part icular isotope, such as Uranium-238 or, alternatively, 238 Uran ium.

• B- I . I . I Some radioisotopes occur in na tu re a n d can be separated by various physical or chemical processes; o thers are p ro d u ced in particle accelerators or nuc lea r reactors.

4 7 4

N F P A 8 0 1 - - F 9 7 R O P

13-1.1.2 Emissions from radioactive materials cannot be detected directly by any of the human senses. Radioactive materials themselves present no unusual fire hazards, as their fire characteristics are no different from the fire characteristics of the nonradioactive form of the same element.

B-l.l.3 The presence of radioactive materials can complicate a fire-fighting situation by presenting hazards unknown to the fire fighter andcauslng real or wrongly anticipated hazards to fire fi~htecs that can inhibit normal fire-fighting operations. The dispersal of radioactive materials by fumes, smoke, water, or by the movement of personnel can cause a radiation contamination incident that can contribute significantly to the extent of damage, complicate cleanup and salvage operations, delay the restoration of normal operations, and affect personnel safety.

B-2 Fire Problems.

B-2.1 Facilities handling radioactive materials should be designed and operated with special recognition given to the properties of radioactive materials. The effects of the presence of radioactive substances on the extent of loss caused by fire or explosion include the following:

(a) Possible interference with manual fire fighting due to the fear of exposure of fire fighters to radiation.

(b) Possible increased delay in salvage work and in resumption of normal operations following fire, explosion, or other damage due to radioactive contamination and the subsequent need for decontamination of buildings, equipment, and materials.

(c) Possible increase in the total damage due to buildings and equipment contaminated beyond the point where they are usable.

B-2.2 Radioactive materials can be expected to melt, vaporize, become airborne, or oxidize under fire conditions. None of these alterations will slow or halt radioactivity. It is conceivable that certain radioactive materials under fire conditions might be converted to radioactive vapor or oxidized to a radioactive dust or smoke. This dust or smoke could be carried by air currents and subsequently deposited on other parts of the burning buil:.~ ~.'X~r r even on neighboring buildings or land. These aggra~at.ed~i personal injury characteristics of radioactive m a t e r i a l ~ t i f degree of protection against fire and explosion at t l ~ / ~ . where these potential hazards exist The use of least corn~ buiidimz components and equipment is highly d~ts~hle in ge areas w~iere radmacave m a t e n ~ are to be ~ ~ . ~ : ~ " form of automatic protection, such as nut. .atlc spri " ' ~ " highly advantageous whe rever c o m b u s t i ~ ~ i u ~ l~e installation of automatic extinguishing s ~ uces t~ . .need for personnel exposure to possible danger, ~ . ~ . r e c o b o l process automatically, sounds an a l a r m ~ ~ g n t use of the available water supply. However, caution s h o u V ~ exercised to ensure that the hazards of criticality and reactivit~re considered•

B-2.3 Some commonly encountered radionuclides are pyrophoric (e.g., uranium, plutonium) and, as such, should be given special consideration. Radionuclides generate heat and might need to be cooled in storage; these also require special consideration•

B-2.4 In view of the possibility of the spread of radioactive materials during a fire, certain precautions and procedures should be incorporatedinto emergency planning for fire-fighting operations.

B-2.5 The property maqager should keep the local fire department advised of the locations and general nature of radioactive materials available. Emergency planning is essential so that fire fighters can function at maximum efficiency without exposure to harmful radiation and without unwarranted fears of the radiation hazard that can inhibit the fire-fighting effort Where criticality incidents or exposure to radioactive materials is possible, mutual aid arrangements should maximize the use of on-site expertise. Specific provision should be made where necessary by the property manager and the fire department for monitoring service, protective clothing, and respiratory protective equipment, the need for which should be determined by the nature of the specific hazard. The radiation hazard usually can be anticipated in emergency planning studies.

B-3 Radiation Hazards and Protection Methods.

13-3.1 Significant levels of radiation exposure can occur under emergency conditions and can cause acute injury or death.

However, fire fighters should be aware that radiation exposures that are tolerable in the event of a fire or other accident, especially where rescue operations are warranted, are unacceptable on a regular basis.

1]-3.2 Nature of the Hazard of Radioactivity. In order that fire- fighting personnel understand how to protect themselves against dangerous amounts of radiation effectively, it is necessary that they be familiar with the basic nature of radiation and the safeguards that generally are provided under normal operating conditions at those facilities where this hazard exists. While quite brief and simplified, the followingparagraphs should assist the fire fighter in identifying those areas of concern:

(a) Radioactivity can be defined as the spontaneous emission of rays or particles during a change in an atom's nucleus. Radioactive decay is the spontaneous disintegration of a nucleus. Each radioactive isotope has a half-life - - a period of time that is a characteristic of the particular isotope in which the intensity of nuclear radiation ascribable to that isotope progressively decreases by half. However, products formed by the radioactive decay of the original isotope can, in turn, be radioactive.

(b) The units for measuring the quantity of radioactivity in the source material are..~.the curie, the millicurie (one one-thousandth curie), and the ~ u r i e (one one-millionth curie). The term curie was origiq~ll., y d~ilgnated as the standard for measuring the disintegratio...~,.~of radioactive substances in the radium family

- - ~ l a ~ 10 of radii, ~'I~has i en adapted to all radioisotopes and refers to t h ~ { ~ b f the ~ ' t h a t has the same disintegration rate

,.~.-.~ ~ l.~.of radium• ~,~- .d~.ri !c~.~.~.the curie 4 ~as been, and remains, the most commonly uset~ ~ - F 6 1 ~ * o u r c e strength. However, the SI unit for source strenl i ~ e becquerel.. One becquerel is equal to one disinte I g r g ~ r second. Hence, one curie is equal to 3.7 H 1010

I R e

~ sources of radiation likely to be encountered induce U i.~pha~, t tides, beta particles, gamma rays, and neutrons. The first th reeemi t from many radioactive materials, and neutrons are likely

~g.~Se present in the vicinity of nuclear reactors or accelerators only lie reactors or accelerators are in operation, or they can emit

[rom certain special neutron source materials. Neutrons, alpha partides, and beta particles are small bits of matter - - smaller than an individual atom. Gamma rays (and x-rays) are electromagnetic radiations (similar to radio waves but with much shorter wavelengths).

(d) All radioactive emissions are capable of injuring living tissue. The fact that these radiations are not detectable by the senses makes them insidious, and serious injury can occur without an individual's awareness. Because of their relatively high penetrating power, gamma rays and neutrons can be a serious external hazard (i.e., potential severe danger even when from a source outside the body). Beta particles, which are less penetrating, can be somewhat of an external hazard if encountered within inches but are mainly an internal hazard; alpha particles, because of their extremely low

[~ enetrating power, are entirely an internal hazard (i.e., injure the ody only if emanating from a source within the body after having

entered the body by inhalation or ingestion or through a wound).

(e) These radiations are measured in roentgens, a unit representing the amount of radiation absorbed or the amount that will produce a specific effect Radiation doses are measured in reins, a dose unit that will produce a specified effect in humans. The ultimate effect upon the human body depends on how and where the energy is expended. In industry, safeguards are provided for the purpose of keeping radiation exposure to personnel to a practical minimum and under certain amounts.

Historically, the roentgen and rein have been, and remain, the most commonly used units for radiation dosage. The current SI unit for dosage is the sievert One sievert is equal to 100 rein. A sievert is equivalent to one joule per kilogram.

(f) In an emergency case, such as a necessary rescue operation, it is considered acceptable for the exposure to be raised within limits for single doses. The EPA 520/1-75-001, Manual of Protective Action Guide and Protective Actions for Nuclear Incidents, has recommended that, in a life-saving action, such as search for and removal of injured persons or entry to prevent conditions that would injure or kill numerous persons, the planned dose to the whole body should not exceed 75 reins. During circumstances that are less threatening to life - - where it is still desirable to enter a hazardous area to

475

N F P A 801 - - F97 R O P

protect facilities, to eliminate further escape of effluents, or to control fires - - it is recommended that the planned dose to the whole body should not exceed 25 rems. These rules can be applied to a fire fighter for a single emergency; further exposure is not recommended. Internal radiation exposure by inhalation or ingestion can be guarded against by adequate respiratory equipment.

B-3.3 Personnel Protection Methods. Monitoring is the process of measuring the intensity of radiation associated with a person, object, or area. It is done by means of instruments that can be photographic or electronic. Instruments used by personnel for radiation detection or measurement include the following:

(a) Film badge, a piece of photographic film that records gamma and beta radiation

(b) Pocket dosimeter, measures gamma radiation

(c) Geiger-Muller counter, measures beta and gamma radiation

(d) Scintillation counter, measures alpha, beta, and gamma radiation

(e) Ionization chamber, measures alpha, beta, mad gamma radiation

(f) Proportional counter, measures alpha radiation

(~.) Gamma survey meter, measures intensity of gamma radiation

(h) TLD (Thermoluminescent Dosimeter). a crystal chip that records beta, gamma, and neut ron radiation.

B-3.3.1 Common effects of excessive (200 roentgens or more) nuclear radiation on the body include vomiting, fever, loss of hair, loss of weight, decrease in the white blood cell count, and increased susceptibility to disease. Radioactive materials absorbed into the body often tend to accumulate at a particular location (e.g., plutonium and strontium tend to collect in the bone). The radioactivity concentrated in a particular organ gradually destro.ys the cell tissue so that the organ is no longer capable of pe ~ n g its normal function, and the entire body suffers. .~

rompt, highly s p e ~ ( B-3.3.2 Radiation injury requires IcP)rovided to d e t e c t ~ f ~ treatment. Instruments should b e contamination in clothing oror orion mtile skin. There should

routine ~ n d i ~ t o r ~ moni to r ingof the degree of exposure ~t~l~gg~'ol

p articl e s a n d rays.Personnel workit~g in t h e ~ ~ required to wear pocket radiation meters $/t examined periodically, and records of t ~ " ~o~ure sho )t for future reference. "~" ~... ~ : ~ .

B-3.3.3 The practice of placarding dangerous ; ae protection of both r%mlar operating personnel .-, fire fighters, who might have to deal with an emerg .y sltt

they fire fighters are to have the best protection, ' sPt fl inspect the Pdremises where there might be radiation hazards to consider

uring fire operations well before a fire occurs. Also, by frequent follow-up inspections, they should reach an agreement with the emergency director or other personnel directing the fadlities regarding steps to be taken in case of fire.

B-3.3.4 Fire fighters who might attend fires in properties where there are hazards of radioactivity should be given special training in Pthroper protective clothing and cleanup or decontamination of

eir persons, clothing, or equipment. In all cases, they should have available and be t ra ined in the use of suitable radiation monitoring equipment or have monitoring specialists with them.

B-3.4 Protection from External Radiation. In the case of external nuclear radiation, the dosage and resulting injury to humans may be kept to a minimum in several ways:

(a) The smallest possible portion of the body only should be exposed (e.g., the hands, rather than the entire body).

(b) The time spent in the hazardous area and, therefore, the time of exposure, may be kept to a minimum by efficient organization of the work procedure.

(c) The intensity of radiation during exposure may be minimized by maintaining the greatest possible distance from the radiation source (e.g., 'by using long-handled tools for manipulating radioactive materials) or by the use of suitable materials interposed between the radiation source and the person to serve as a shield. Radiation intensity decreases inverselyby an amount equal to the square of the distance from the source only where the source is a

such as situation. If

point source. This relationship is more complex with multiple point sources and does not apply to large sources until the distance is equal to one-half the maximum dimension of the source. Practically speaking, this could be 30 ft to 50 ft (9.1 m to 15.2 m). The cases in which a fire fighter will encounter a single point source are probably in the minority, and, therefore, the more conservative formula should be used.

17,-3.5 Protection from Internal Radiation. The possibility of radioactive materials entering the body may be reduced by wearing protective face masks and clothing while in a hazardous area. - These masks should fit properly and be of a type that prevents the entry into the lungs or digestive system of the particular radioactive materials encountered. Clothing should be of such type to prevent the entry of radioactive materials into the body through wounds, scratches, or skin abrasions. Eating, drinking, smoking, and chewing should be prohibited while exposed to, or while awaiting decontamination after being in, radioactive areas.

B-3.5.1 Personnel working with radioisotopes are commonly subjected to routine biomedical checks for possible ingested radioactivity. Where applicable, routine checks also are made to verify that a permissible concentration of radioactive material in the body, the air, or elsewhere has not been exceeded.

13-3.5.2 B i o m e d i ~ e c k s are promptly conducted whenever human ingesf io~. ,~f~.gerous quantities of radioactive materials is susj?ected f o r . ~ e a s o n . When fire fighters are exposed to radiation ax~.~ "f i f t ies any doubt as to the severity of the exposure, they shou l~ -~ g i ~ biomedical examination.

B-4

~ F o .~.~.rposes o f ~ i s standard, a "sealed" radiation source is ~ n ~ ~ t l y encapsulated (or the practical equivalent by b o n d i ~ other means) and is not intended to be opened at the facility. ~i~.~n~:aled" source is one that is not so sealed or is intended t ' i~ '~opened at the facility, or both.

_ _ q ~ 51 ~ l ~ g ~ ' r o t e c t i o n of properties against the spread of radioactive

£ ~ i i ' ~ t i o n as the result of fire or explosion is simplified ~onsiti~t'ably by the fact that many radioactive materials are shipped, stored, and, in some cases, used without ever exposing ~ radioactive material itself to air. In many cases the shipping

atainers, or even the use containers, might have sufficient integrity to withstand a fire or an external explosion. Examples include metallic cobalt-60 sources tightly encapsulated in steel and sealed sources used in "beta gauge" thickness and measuring devices. There have been several instances of stainless steel encapsulated beta gauge sources surviving appreciable fire exposures without release of the radioactive isotope contained therein.

IM.$ The principal reason radioactive materials are sealed is to prevent spread o f contamination. In some cases, the manufacturer of the container might no t thoroughly consider fire resistance, and it is important to remember that a sealed source can burst if its contents are subject to thermal expansion as a result of exposure to fire.

B4.4 Unsealed sources, such as can be found in laboratories during their transfer and use, can be spread about readily during a fire or an explosion.

B-5 Applications.

B~.I The specific application for ionizing radiation is governed somewhat by the physical makeup of its source, its sealed or unsealed form, and sometimes by its radiation intensity.

B-5.2 Most of the thousands of scientific and industrial uses of radioactive materials take advantage of one or more of the types of radiations emitted; i.e., alpha, beta, gamma rays, and neutrons. Certain radioisotope applications take advantage of the ultra sensitive detection capability of certain instruments for extremely small amounts of radioisotopes. Other uses take advantage of the ability of radiation to penetrate matter, while the extremely energetic sources have the ability to bring about biological, chemical, and physical changes. - --

B6.3 The most common nuclear radiation applications can be grouped into the following categories:

(a) Radioisotope "tracer" applications utilize small amounts of short-lived, unsealed sources, involving easily detectable radiation emissions of the particular radioisotope employed. Such applications have found wide use in medical diagnosis, biological

476

N F P A 8 0 1 - - F9 7 R O P

a n d agricultural explorat ions, water surveys, i rr igation control, u n d e r g r o u n d leak a n d seepage detect ion, a tmospher i c pollution, flow and t ranspor t rates in process ing operat ions, lubricat ion a n d wear measu remen t s , rapid chemical analysis for con t inuous process control, a n d activation analysis.

(b) Radioactive gauges a n d process control i n s t rumen t s utilize the more pene t ra t ing types of radiat ion f rom sources tha t are sealed to prevent the radioactive material f rom leaking. T he radioactive mater ia l in no way enters into the system or process. This includes a wide range of operat ions, f rom measu r ing thickness or densi ty to mon i to r ing he igh t and levels in storage and process equ ipmen t .

(c) Certain of the intensive sources of radiat ion have the ability to ionize gases. One of the impor t an t applicat ions is the prevent ion of the accumula t ion of static electricity on moving machinery. The ionized air affects an "a tmospher ic g round ing" a n d prevents bu i ldup of static charges ( rad ium and p o l o n i u m as low-penetrat ing a lpha emitters have been used, a long with the m o r e pene t ra t ing beta emitter, krypton-85). These sources also are be ing used as activating agents with se l f . luminous (phosphorescen t ) paints and coatings for various markings, emergency lighting, and in s t rumen t

to protect t h e m f rom the effects of an otherwise inconsequent ia l fire•

B-7 Nuclear Fuel Reprocess ing.

11-7.1 Reactors general ly are capable of utilizing only a very small por t ion of the fuel conta ined in thei r e lements , and, as a result, it is economical to recover the r ema in ing fuel by process ing the so- called "spent" e lements in specially des igned facilities• These facilities conta in large quant i t ies of radioactive materials (fission products) extracted f rom spen t nuc lear fuel e lements tha t were p roduced as by-products du r ing nuc lear fission• Processing opera t ions usually involve large quant i t ies of f l ammable or corrosive liquids, or both. Fire a n d explosion hazards are present , and the possibility of an accidental criticality incident , a l though gua rded against and remote , also is present•

B-7.2 The large quant i t ies of highly radioactive materials p resen t necessitate massive sh ie ld ing for pe r sonne l safety, and mos t chemical process ing and m a i n t e n a n c e operat ions are conduc ted entirely by remote controls. Fire hazards are p resen t du r ing the sawing and chopp ing of fuel e lements con ta in ing combust ib le metals, e i ther in the fo rm of fuel or cladding, a n d in the chemical

panels• process ing operation• Specially des igned fire detect ion and control . . . . . systems are used to:.~rotect these operations• Venti la t ing systems

• (d ) Radioacuve ma te r mls are be ing employed in the . . . . shou ld be a r r a n ~ . / 4 t n a i n t a i n their integrity u n d e r fire a e v e i o p m e n t o t a tomic oatteries Las "isotopic power tuets"), l n e condit ions. Suc.~'faciliiffi~s hand l ing large quanti t ies of highly small cur rents gene ra ted :ire utilized in low-current d e m a n d micro- radioactive ~ d e m a n d the aoolicat ion of a hil~h degree of circuits; also, the l iberat ion of the rmal energy du r i ng radioisotope fire o r o t e c ~ " " o t ~ g in all areas - v decay is converted into useful electricity t h r o u g h thermoelec t r ic " ~:::. ~#. - ~ , . ~ , • couples or t h e r m I o m c systems. T he sources inc lude some fission !i-8 P . ~ i i ' . ~ c e l e r a f ~ . . : : ~ . - p roducts and some of the radioactive materials obta ined by ..~¢t.:" . ":::.': "-:-:~'..:~.-" n e u t r o n irradiation of special target materials, l~.~:.. P ~ l e accelerate% include Van de Graaff generators , l inear

. . . . . . . . . . . . . . . tt%"'~tat~;'~<~yclotrons, synchro t rons betatrons, a n d bevatrons• re) vowertui sources are useo in mctustnal ractiograpny a n a ~ . -,.~:.-::.,~._...... _ . , • ' . . . . . . ,, . . . . . . . • _ ~ , . ,• l n e s e ~ l t l c n m e s are nsect, as their n a m e impnes, to accelerate m e

n o n o e s t r u c U v e t e s t m g o t c r i t i c a l p r o c e s s e q u i p m e n t . 1 h e l e a 0 L l n g . x..:..:~:..::.. . . . . . . . . . • . . . , • . • • • . . - - various m m ~ e a oa rnc les m a t compose a toms to t r e m e n a o u s industrially u s e a lsotone of n igh-energy emission is cooalt-00 .(~ _ - ~ ....::x . . . . . . . . . . . . . . . . . . . . . . t . . . . . . . . . . ' ~-'::i.".-~:~,x speens aneg~.'.tk~sequenny, to m g n energy levels• Kaa lauon wnicn is ob tmneo oy m e , tcuvauon oi cobalt In a reactor .x-~ ~ • ~ " . . ' ~ h i n e s f ~ i s h scientists with a tomic particles in the form of a . . . . . :~" : : ~ - ~ . .-'x.- • . . - • .

The industr ial r ad iographer has a choice of x-ray mach i ne s or % ~ f ~ a n be utilized for f u n d a m e n t a l s tudies of a tomic radioisotopes. In m a n y cases the latter offers the mos t advantages. ~'}h , ~ u ~ . ~ ' I n addi t ion they furnish hitth-energrv radiat ion tha t can The increased availability of cobalt-60 a n d i n d i u m s o u r c e ~ ! . . - ? . ~ # ~ e u t i ~ e d for radiography, therapy, or chemical processmg. resul ted in radiographic inspect ions becomi ng c o m m o t , ~ c ~ . ~!~'.,. . . . . . . . . . . . . . . . . . . .

• I ' • . -- .'-'~'.~ ~i'~ "~.?~.1.1 i n e s e m a c n m e s emi t raoaaUon t roy W h i l e i n operaUon, Steel thicknesses f rom / 9 in. to 6 m. (12.7 m m to l ~ m ) ~ b e ~. ~ d a t temots to ext inguish a fire in the immedia te vicinity of the evaluated radiographicallv, a n d m a n y companies ard n t ~ g . . q ¢ ~ g ~ @ ~ "~ m a c h i n e shou ld be delayed u n u l the mach ine power supply can be to proxade such e x a m m a t i o n services. .,.,~.,~.,..::.. • ...... d i sconnec ted .

. . . . . ~ ' . . - : . - . . ".::~<.-~-,~ . . . . . . . O the r radioisotopes tha t have less energeta.qt~,*&-T~ ~ e m ~ o ? . ' - " B-8.1.2 Certain target materials become radioacuve when

than cobalt-60 a r e ' c o m i n g into wider use f o ~ : l i g h t e r ' ~ i a l s f f ~ " b o m b a r d e d by a tomic particles and, for this reason mon i to r ing as a l u m i n u m , copper, zmc, and thin s e ~ i ~ o f steel• :~:~: ~" e q u i p m e n t shou ld be used du lang fire-fightang operataons to

":~ ~{~... ~i!.~i est imate the radiat ion hazard. The usual hazard p resen ted by (f) Powerful sources of h igh intensity r a d i a t ~ , , such .al}.:~.~:obalt- particle accelerators is largely tha t posed by electrical equ ipment .

60, are used in food preservat ion and in r a d i o l ~ i ~ l st..egJ/ization of The re are however some o ther sio-oificant hazards Some pharmaceu t ica l a n d medical, supplies. Research a ~ e l o p m e n t installations have used such haza rdous materials as ' l iquid indicate considerable p romise in polymenzataon o.f..;.~lastics, hydrogen, or o ther f l ammable materials, in considerable vulcamz.atao.n of rubber , i m p r o v e m e n t of wood ~r0~.erti-es, g~..~ft quanti t ies. Large a m o u n t s o f paraffin have been used for neu t ro n poiymerlzataon ot piastacs, a n a catmyzaUon o t chemical reacuons , sh ie ld ing purposes , and the possible p resence of combust ib le oils

13-6 Nuclear Reactor Fuel E lement Manufac tu re used for insula t ing a n d cooling is an addi t ional hazard.

!!-6.1 Certain radioactive nucl ides are fissile. Neu t rons absorbed by such n u d i d e s emi t addit ional neu t rons p lus energy, largely in the form of heat. Because more neu t rons are emit ted than are absorbed, a self-sustained nuc lea r cha in react ion is possible when certain condi t ions are met . These condi t ions inc lude a m i n i m u m sq~antity of fissile material (critical mass) and o ther factors such as

ape, geometry, reflection, a n d mode ra t i on (or slowing of neu t rons ) . Fissile materials used in a nuc lear reactor are a r r anged in specific arrays us ing fuel e l emen t s in order to optimize condi t ions for fission to take place. W h e n a nuc lear chain react ion takes place where it was n o t in tended , a criticality acc ident is said to have occurred.

11-6.2 In addi t ion to the hazards of radiat ion a n d the potential for accidental criticality, fuel e l emen t manufac tu re of ten involves the use of combust ib le metals, such as u r a n i u m and p lu ton ium, and combust ib le d a d d i n g material such as zirconium. T he prevent ion of fires involving combust ib le metals requires special techniques . (See NFPA 480, Standard for the Storag~ Handling, and Processing of Magnesium Solids and Powders; NFPA 481, Standard for the Production, Processing, Handling, and Storage o f Titanium; and NFPA 482, Standard for the Production, Processing, Handling, and Storage of Zirconium. )

11-6.3 It is impor tan t to r e m e m b e r tha t nuclear fuel e lements are extremely valuable, and ext raordinary precaut ions may be necessary

B-8.2 Industr ial appl icat ions inc lude chemical activation, accelerat ion o f polymerizat ion in plastics product ion , and the sterilization a n d preservat ion o f packaged drugs a n d sutures• Th e genera l fire protect ion a n d prevent ion measures for these mach ines shou ld inc lude the use of noncombus t ib l e or l imited-combust ible (Type I or Type It) cons t ruc t ion hous ing , noncombus t ib l e or s low-burning ( see IE, F_,~383, Standard for T3pe of Glass IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations) wiring a n d inter ior f inishing, a n d the e l iminat ion of as m u c h o ther combust ib le material as possible (see NFPA 220, Standard on Types of Building Construction). Automat ic spr inkler pro tec t ion shou ld be provided for areas having hazardous a m o u n t s of combust ib le material or equ ipmen t . Special fire protect ion shou ld be provided for any high-voltage electrical equ ipment .

B - 9 I s o t o p e P r o d u c t i o n F a c i l i t i e s .

1]-9.1 General . Practical m e t h o d s for p roduc t ion of radioactive isotopes inc lude n e u t r o n activation of natural ly occurr ing e lements in reactors, fission of fissile mater ia l in reactors and extract ion of radioactive fission products , a n d absorp t ion of suba tomic particles by a toms exposed in reactors or particle accelerators.

B - 9 . 2 I s o t o p e P r o d u c t i o n in R e a c t o r s . Radioisotopes are p r o d u c e d in nuc lear reactors by ei ther b o m b a r d m e n t of stable a toms with n e u t r o n s or o ther suba tomic particles tha t cause

477

N F P A 8 0 1 - - F 9 7 R O P

transformation of the stable nucleus of the atom into an unstable or radioactive nucleus, or by separation of radioactive fission products f rom uranium used in the reactor.

B-9.2.1 Activation of isotopes in reactorsgeneral ly is the result of the exposure of an element to a neu t ron flux resulting in a transmutation of the element due to neu t ron capture and alpha, beta, or proton decay. Fire ha==rdz ~_~s-~czlatcd ;;~ r~ztc . r ope . . . . . . . . . . . . . . . lg" . . . . . . . . L " - L" . . . . . . . . . . . . . . . . . . . . . . . N T U ' D A o f ~ o D . . . . . . . . / . 2 1L~2--. D - - . * - - * 2 - - - - D - - - - . * 2 . . # ' - - . 7 L T . . . I ^ - - - - D . . . . . . I .

B-9.2.2 Various radioisotopes are produced as the result of fission of uranium in reactors. These isotopes can be removed f rom the fuel by chemical extraction following removal of the fuel f rom the reactor. Fire protection for reactor opc~f iona i: ~czcr:~c~ in

A Q t ~ O D . . . . . . . . 7 . . 7 I ~ 2 . . D - - . ~ - . + 2 ^ - - D . - - . ~ 2 . . P~- E T . . . I . - - - - D . . . . . . K NFP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . . . . . . . . . . . . . . . _ ~ . / D- - - - L . _+2__ D~ - - . , - - -

B-9.3 Radiation Machines. Some radioisotopes are produced by exposing stable isotopes to hlgh-energy subatomic particles. High- velocity subatomic particles are accelerated in particle accelerators such as Van de Graaff generators, linear accelerators, cyclotrons, or synchrotrons. These machines involve high-voltage electric and magnetic fields and produce radiation only while operating. Fire hazards associated with such machines are similar to any large electrical installation.

B-10 Research and Production Reactors.

control room, cablewavs, emer~encv Dower SuPPlY. and electrically or hvdraulicallv operated eouin-ment in genera)-is of nrime importance. Protection for the control room should/3e fully consistent with that for imnortant comnuter rooms. ~+++ ~ r ~ , ~¢

I ~ . . , : J . ~__ * - - - ~l ~ ,~ D. ,&12 . - - #2 - - - TX IA (~LT 1QA~ 1 c~ , - - . I - - . 1 ~^ - ~ ' ; - .

I~-10,5,~ While comnrehensive, automatic control systems are essential elements in reactor safety, the effecfveness of the total safeguards also deoends on the oroner execution of oneratin~ nrocedures that are technically sound and comnrehensive.

B-10.6 Classification. There is no sinvle system of reactor classification. Reactors are venerallv classified bv a combination name indicatin~ one or more of its uronerties such as end-use, woe of coolant or moderator, fuel form. neu t ron soeed, and others. These are ~enerallv shor tened to an acronym in common usage. Thus we have HTGR (High Temoera ture Gas-Cooled Reactor) and LMFBR (Liouid Metal. Fast l~reeder ReactorL

B-10.7 Hvdro~en Exnlosions.

B-10.7.1 ~ 1 -

B-10,1 Power Level. High Dower levels are itenerallv associated with Dower and oroducfi-on reactors. Small units, such as some oacl<age research reactors, may Dose problems due to their ~pabil i ty of being located in ex~tstin~-facilities or multiple o¢cuoancv buildings. While the maximum credible losd in nuclear tel-Ins mav be much reduced, the fire exnosure may actually be eagr_~tm.

B-10.2 Coolants and Moderators. These may run the wamut f rom ~ a d e o u a t ¢ to prevent concentrations of

such forms are not subiect to fire exnosure, such as in a water nool rea¢tor, the manufacture, storage, arid handling of the fuel may pose fire protection nroblems.

B-10.4 Shieldlnm The nature of the shield material used for b~Ological l~diafion protection varies f rom massive concrete to t)araffln or wood-plastic comnositions. Beyond the fuel contribution of some material, a fire bum i n~ or melting shielding can DOSe a radiation exnosure problem to resnonding emergency forces. - -

B-1021 Control Systems. Reactor control systems and safety sys~gms are of utmost imoortance. The control system desian is f i r ed to the technical characteristics of the reactor and can-able of pro~tudng power changes at acceptable rates. The c o n t r o i system desian also makes it nossible to produce and maintain the desired power level within the reactor i n such a m anne r that excessive temoeratures are avoided. The safety system also is adapted to the ¢bafacteristics of the reactor and the ins t rument and control sy~¢¢ms. It resnonds to signals f rom the instruments in such ways as tO pF¢ vent- bygutomat ic action, onerational variables f rom eT¢¢¢eding safe limits. It also. on a'ooronriate . . . . sitrnals, warns of incipient chan~es in nerformance and. if necessary, shuts down the

I3-10.5.1 Since the control system is vital to the adeuuate functionin~ and safe onerarion of the reactor, the nrotection of the

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v. y~. . . . . . . . . . . . . . . . . . . . I - I . . . . . . . . . . . . . . . . . . . G . . . . . .

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- !-~.~°.S ~. 5.2.2 2~-c c='.'.2c.72 c : :~c-racnt dccz na t produce a ~S:: ~ - -^~ . . . . . . . a =.nt . . . . . t : ~ . ^A~ k , + - - k l . . . . . . , 1 ; - ~ . t ~ ' . , ~ ~ ' : . . . " . . . . . . . . . .

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478

N F P A 8 0 1 - - F 9 7 R O P

+ I , . ^ - - ~ * ^ 0 : ' - 1 . . . . ; ~ - - k l - - ¢ ^ - * k . . . . . . . . . . . . , , : - - - - c . . . . . . . 1 - + - I . ,

. . . . . . . . . . . . . . . . . . . . . . . . . . t " ~ " V . . . . . , b ' ~ . . . . . . . . . . . I ; " . . . . . ;

B 1 N 0 0 A E i P ~ - - + . - - I ~ T E - - ~ . , ~ * . * . ~ 1 . . . . . 1. , . I . . . . . . . . I 1 . . ,~. : ~ , ~ + = . 1 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ] ; = ~ . . . . . . . 7

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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 ~ . . . . . . . . . . . . . . . 1 ~ . . . . . . . . . . . . . . . " J L "

. . . . . . . ~ . . . . . . . . . . . . . . . 7 . . . . . . . ~ . . . . . . ~ . . . . . . . . . . . . . ~ . . . . . . .

hi~her the enr i chment the smaller the fuel core can be.) A cluster of-rods or nlates is arranged in a core susnended bv a cage in the water f rom a movable bridge across the ton o f the nool . -

B-11.4 4-6,4 Controls. Control of the rate at which neutrons are o ro d u ced is nrovided bv inserting boron or cadmium rods in the proper geometrical oattern between the fuel e lements to absorb gg~trous. Usually two or three rods are used as control rods and one or two are safety shutdown rods in combinat ion with from 15 to 30 fuel elements. T h e m o v e m e n t o f control rods and fuel ¢lements is accomnl i shed by control mechani sms electrically or hydraulically onerated. These are so arranged that. in case of electric or hydraulic failure, the control rods will return by ~ravitv to a pos i t ion that will shut down the reactor.

~ Criticalltv. In this w o e o f reactor, a critical mass can be reached with about 6 Ib (9.7 k~) of 90 percent enriched uran ium fuel in a pool of the dimensions-described. With lesser de~rees o f enr ichment , m o r e fuel would be reouired.

B-ll.fi ~ Hazards. This being a water-moderated reactor. hydrogen and o x w e n are oroduced in small amounts bv the action

. . . . . S

I

B-II Onen Pool Reactor (Swimmin~ Pool Reactor). v

B-II.I 4 - 6 ~ Field o f Use. The ooen nool ( swimming nool ) reactor is useful for research Durnoses and is considere~i versatile. economical , and relatively safe. The shie lding that can be nrovided bv the water moderator and the visibility afforded bv its t sansparency are onerat in~ advantages.

~ Description. The reactor itself is basically an oDen- top tatlk filled with purif ied water. The water in the tank serves as coolant, moderator, reflector, and shield. One pool of this tvoe is c0ncret¢, 4~0-f~ long. 20-ft wide. and 20-ft deeo (12.2-m long. (~.l-m wide. and 6.1-m deen) . S o m e reactors have a considerable numb er Of ports (beam holes) in the wall so that various exoerimental anoaratus may be set uo for the use of the radiation nroduced ( see ~ u r e B-I1.6.1 4 - (~) . "l~he buildin~ housing the reactor and the working snace around it would ordinarily have a tight wall and roo f of metal or concrete.

4-#,g- Fuel. The fuel is usually ~ enriched uran ium in rods or olates. A tvoical e l ement consists of a luminum-clad nlates grouped" into fuel assemblies usually about 94 in. by 3 in. by'3 in. (610 mitl by 7(} m m bv 76 m m ) . (Enriched uran ium simply means that the percentage of U-235 is h lgher than in natural uranium. The

4 6 , ¢ ~ Defects in fuel e l ement cladding may permit v . A

~ Combustible acoustic or other wall f inishes introduce unnecessary fire hazards. Furniture should be noncombus t ib l e .

B-11.6.4 ~ General nrotective measures should include nortable extinguishers ancl automatic ext inguishing systems.

4 6 , 6 ~ Normal use of this w o e of reactor is at Dower levels where ordinary convect ion will (iissiDate heat nrociuced at the core. Heat might be 'oroduced rapidly e n o u g h to release steam at the nool surface in the event of fa.ilure or slow onerat ion of ¢onta'ol~, Vio lent boi l ing may spread contaminat)on outside of the reactor nool . This might nrevent the use of the reactor for an extended neriod of t ime ~md nresent a decontaminat ion oroblem. The worst-conceivable (but highly imnrobable) disturbar~ce might produce steam violent e n o u g h to cause local structural damage. blow off any apparatus at the too of the noo l and nrobablv da~na~e the building.

B-11.7 ~ Site Factors. While this w o e of reactor could, under ~;onditious of n o o r bui ldin~ desima• introduce some exnosure hazard, its fire exnosure hazard, on the whole, is low. and the radioactive contaminat ion hazard does not anoear to be excessive. Because of the reactor's r eou irement for water, it would likely be located io a olace where a satisfactory water sunDlv for fire fighting could be provided. _. v

B-11.8 44k~ Orwanization for Fire Protection. There should be a fire orotect ion organization. The use of a research reactor means that*teams of scientists from a n u m b e r of senarate agencies (several d e n a r t m e n t s o f a u n i v e r s i t y , f o r e x a m D l e ) a r e l i k e l y t o b e o c c u n v i n g

the oremises at any given time. Each mav be oerforming exneriments that introduce some fire hazard-condit ion.

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Cont ro l console

drives rod

MovaL bridge

level

Pool walls

Suspension

Beam absor

Beam pOrt

Core assembly

Beam w i n d o w

I r rad ia t ion room

.~.~,:. ~, '~ ...~" ~ ' ~ . - ~ "

F'tgur ~)pen

B-11.8.1 4-g,8,-1- The a~encv resnonsible for the onera t ion o f the reactor or n lan t s h o u l d cons ider havin~ on duty clurin~ all workin~ t imes nersons technically c o m n e t e n t to -handle the overall use and- onera t ion of the reactor and the bui ldinm W h e t h e r the reactor and the bui ldin~ may safely be left in the har~ds of a custodian a t t imes wheel it is no t used. such as niithts, weekends, or holidays, shou ld De considered. In addit ion, t h e custodial force shou ld be fully ins t ructed in fire f i~htin~ and venti lat ion nrocedures , and a r r a n g e m e n t s shou ld be made in advance-so that. if m e m h e r s of a nubl ic fire deDarffnent are likelv to r e spond to a fire call. the re will i3e some resnonsib le adminis t ra t ive ofiqlcer or custodian who will know u n d e r w h a t a r r angemen t s the nubl ic fire force m a y t i t to work. Such a r r a n g e m e n t s shou l d be worked ou t between the adminis t ra t ion of-the reactor n roner tv a n d the officials o f the citv

Append ix C - - R e f e r e n c e d Pubfications

C-1 T h e following d o c u m e n t s or por t ions t he reo f are re fe renced within this s t andard for informat ional purposes only a n d are thus no t cons idered par t of the r equ i rements of this s t andard unless also listed in Chapter 6. T he edi t ion indica ted he re for each reference is the cu r r en t edit ion as of the date of the NFPA issuance of this s tandard.

pool (swimming pool) reactor assembly.

C-I.1 NFPA Publications. National Fire Protec t ion Association, 1 Bat terymarch Park, P.O. Box 9101, Quincy, MA 02269-9101.

NFPA 15, Standard for Water Spray Fixed Systems for Fire Protection, 1990 edition.

NFPA 16A, Standard for the Installation of Closed-Head Foam-Water Sprinkler Systems, 1994 edition.

NFPA 20, Standard for the Installation of Centrifugal Fire Pumps, 1993 edition.

NFPA 22, Standard for Water Tanks for Private Fire Protection, 4-00,3 1996 edition.

NFPA 26, Recommended Practice for the Supervision of Valves Controlling Water Supplies for Fire Protection, 1988 edit ion.

NFPA 30, Flammable and Corabu~tible Liquide Code, 1996 edition.

NFPA 51B, Standard for Fire Prevention in Use of Cutting and Welding Processes, 1994 edition.

NFPA 80A, Recommended Practice for Protection of Buildings from Exterior Fire Exposures, 1993 edition.

NFPA 90A, Standard for the Installation of Air Conditioning and Ventilating Systems, 1996 edition.

NFPA 101, Life Safe 0 Code, 1997 edition.

NFPA 204M, Guide for Smoke and Heat Venting, 1991 edition. NFPA 220, Standard on Types of Building Construction, 1992 edition.

NFPA 480, Standard for the Storage, Handlin~ and Processing of Magnesium Solids and Powders, 1993 edition.

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N F P A 8 0 1 - - F 9 7 R O P

NFPA 481, Standard for the Production, Processing, Handling, and Storage of Titanium, 1987 edition.

NFPA 489, Standard for the Production, Processing, Handling, and Storage of Zirconium, 1{t87 edition.

NFPA 600, Standard on Industrial Fire Brigades, 1992 edition. NFPA 601, Standard on Guard Service in Fire Loss Prevention, 1992

edition.

_ _ . . / / 3 ~ ^ 2 . . * * : _ _ D . - - - , ^ - - 1 ( 3 ( 3 ~ ~ . 4 : t l ~

NFPA 803, Standard for Fire Protection for Light Water Nuclear Power Plants, 1993 edition.

NFPA 804, Standard for Fire Protection for Advanced Light Water Reactor Electric Generating Plants, 1995 edition.

NFPA 901, Uniform Coding for Fire Protection, 1990 edition. NFPA 1500, Standard on Fire Department Occupational Safety and

Health Program, 1992 edition.

C-1.2 Other Publications.

O1.2.1 ASTM Publication. American Society for Testing and Materials, 1916 Race Street, Philadelphia, PA 19105.

ASTM E380, Standard Practlce for Use of the International System of Units, Rev A-89.

O1.2.2 EPA Publication. Environmental Protection Agency, 401 M Street SW, Washington, DG 20460.

EPA 520/1-75-001, Manual of Protective Action Guide and Protective Actions for Nuclear Incidents.

C-1.2.3 IEEE Publication. Institute of Electrical and Electronics Engineers, 345 East 47 Street, New York, NY 10070.

IEEE 383, Standard for Type of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations, 1974 edition.

C-1 .2 .40SHA Publication. Occupational Safety and Health Administration, 200 Constitution Avenue, NW, Washingtot~

OSHA 1910.156, Fire Brigades, 1981. ~ ~ii!i'}" ~....-~:~ ~-:! O1.2.5 UL Publications. Underwriters Laboratones'ln~.ii~ ~ Pfingsten Road, Northbrook, IL 60062.

UL, Building Materials Directory, 1996. ,>~j . "~:.~.-'.;~

UL 586, Stanaard for Test Perfo.~nce of.~!~ E f l i . ~ ~ " Air Filter Units, sixth edition. .~ ' i . : : .'.':i:~: ~ '

UL 900, Standard for Test Performance of A i r ' ~ i Units, f edition. :~-~)~-:. ..:i

Appendix D Additional Publications

This appendix is not a part of the requirements of this NFPA document but is included for informational purposes only.

The following is a selection of additional reference materials. The National Council on Radiation Protection and Measurement

has issued a number of reports on specific radiation protection subjects. These reports are available from NCllP Publications, P.O. Box 4867, Washington, DC 20008, or from the U.S. Government Printing Office. Some applicable publications include:

NCRP 30, Safe Handling of Radioactive Materials-NBS Handbook 92, 1964.

NCRP 38, Protection Against Neutron Radiation, 1971. NCRP 39, Basic Radiation Protection Criteria, 1971. Standards of the U.S. Nuclear Regulatory Commission for

protection against radiation are published in the Code of F~eral Regulations, Part 20, Chapter 1, Title 10, available at most libraries. Revisions are pr in ted in the Federal Register, available at subscribing libraries or by subscription from the U.S. Government Printing Office.

Nuclear Safe~, a bimonthly magazine is available from the U.S. Government erinfi.3~Office. It covers many areas of interest, including g e n e ~ . , , accident analysis, operating experiences, and current ev . .~ . :":"

Specific r ~ f i ' i ~ ' ~ t s for facilities handling radioactive materials have bee g ' l ~ e d American Nuclear Insurers, Town Center, Suite 3..~-!....~.~ot ' S~eet, West Hartford, CT 06107-2445, a n d . . ~ " ~ R e i n s ~ Association, 1151 Boston-Providence

481

N F P A 8 0 2 / 8 0 3 m F97 R O P

PART lI

( Log #CP 1) 802- 1 - (Entire Document): Accept SUBMITTER: Technical Committee on Atomic Energy RECOMMENDATION: Withdraw NFPA 802, Recommended Practice for Fire Protection for Nuclear Research and Production Reactors. SUBSTANTIATION: The Atomic Energy Committee is combining NFPA 801, Standard for Facilities Handling Radioactive Materials and NFPA 802, Recommended Practice for Fire Protection for Nuclear Research and Production Reactors because many of the fire protection requirements are the same for both facilities. The combined document will be a more useful document as the users will only have to reference a single document for both types of facilities. COMMITTEE ACTION: Accept.

PART III

(Log #4) 803- 1 - (Entire Document): Reject SUBMITTER: Donald A. Diehl, Alison Control Inc. RECOMMENDATION: Cancel entire document. SUBSTANTIATION: On several occasions I have voiced my opinion that NFPA 803 ought to be discontinued because some of our members have said essentially that 803 is of little value, nobody uses it and probably no more light water plants will be built. I cannot see the point or revising it at this late date when NFPA 804 covers the same material plus new material which appears to be acceptable to the industry and the NRC.

if, by chance, the committee decides to drop 803, Tables 9-2, and 10-1.2 should be added to 804. These tables contain a lot of good information and should not be lost forever.

On the other hand, if the committee decides to keep 803, then the sections in 804pertaining to safe shutdown should be added. Now we would have 803 much closer to 804. Another reason for dropping 803.

The main difference between a light water plant and an advanced light water power plant is the method of making steam. The electric generating part of the plant is the same, i.e. control rooms, generators, cable spreading rooms, tunnels, battery rooms, etc. As a matter of fact coal fired plants should be included here. COMMITTEE ACTION: Reject. COMMITTEE STATEMENT: The Committee determined that NFPA 803 can be used as a vehicle to establish performance based surveillance testing objectives for fire protection features. In the future the committee will propose an entirely new performance based document on light water reactors which will address safe shutdown capability and fire protection for the entire facility.

Also see Committee Proposal 803-3 (Log #CP3).

(Log #CP2) 803- 2 - (1-3 (New)): Accept ;UBMITTER: Technical Committee on Atomic Energy

RECOMMENDATION: Add new 1-3 as follows: 1-3 Equivalency Concepts. 1-3.1 Nothing in is standard is intended to prevent the use of

systems, methods, or devices of equivalent or superior quality, strength, fire resistance, effectiveness, durability, and safety as alternatives to those prescribed by this standard, provided technical documentation is submitted to the authority having jurisdiction to demonstrate equivalency, and the system, method, or device is approved for the intended purpose

1-3.2 The specific requirements of this standard shall be permitted to be modified by the authority having jurisdiction to allow alternative arrangements that will secure as nearly as practical the level of fire protection intended by this document, but ]'n no case shall the modification afford less fire protection than that which, in the judgment of the authority having jurisdiction, would be provided by compliance with the corresponding provisions contained in this standard.

1-3.3 Alternative fire protection methods accepted by the authority having jurisdiction shall be considered as conforming with this standard.

Renumber accordingly.

SUBSTANTIATION: The new wording on equivalency was added to be consistent with NFPA 801 and NFPA 804. COMMITTEE ACTION: Accept.

(Log #CP3) 803- 3 - (1-4.5 (New)): Accept SUBMITTER: Technical Committee on Atomic Energy RECOMMENDATION: Add new 1-4.5 as follows:

1-4.5 Inspection, Testing and Maintenance of Fire Protection Systems.

Fire Protection Systems. Fire protection systems designed and installed in accordance with chapters 9, 10, 11, 12 and 13 shall be considered as meeting the objectives of this standard.

Equivalency. Nothing in this chapter is intended to prevent the use of calculation methods, test methods, systems, methods, or devices of superior strength, fire resistance, effectiveness, durability and safety as alternatives to those required by this standard,

~ rovided technical documentation is submitted to the authority avingjurisdiction to demonstrate equivalency, and the system,

method, or device is approved for the intended purpose. Prescriptive Based Option. Fire protection systems designed and

installed in accordance with chapters, 9, 10, 11, 12 and 13 shall be inspected, tested and maintained in accordance with the referenced publications in chapter 18, section 18-1.1.

(NOTE: Add reference to NFPA 25 to chapter 18, section 18-1.1. Performance-Based Option. Fire protection systems designed

and installed in accordance with chapters, 9, 10, 11, 12 and 13 shall be permitted to be inspected, tested and maintained based on a )erformance-based program accepted by the authority having urisdiction. Performance-Based Program. Performance-based programs for

]re protection system inspection, testing and maintenance shall be Lpproved by the authority having jurisdiction. Technical ustification for inspection, testing and maintenance intervals shall )e provided. The performance goal for operability is to provide • easonable assurance that the fire protection system or feature will perform it's intended function on demand. This shall include historical data acceptable to the authority having jurisdiction. Plant-specific failure rate data shall be reviewed on a case-by-case basis to determine if extensions are warranted. SUBSTANTIATION: The Committee feels the nuclear industry has the data and history of the success/failure of the fire protection systems and components because of the extensive surveillance/inspection programs being conducted. This data can be used to support a performance-based approach for inspection, testing and maintenance of fire protection systems. COMMITTEE ACTION: Accept.

(Log #CP1) 803- 4- (10-1.1): Accept SUBMITTER: Technical Committee on Atomic Energy RECOMMENDATION: 1. Add NFPA 2001 to 10-1.1.

2. Change tide to "Gaseous Suppression S~stems" in 10-3. 3. Change "liquefied compressed gas" to 'gaseous" in paragraph

10-3.1 and 10-3.2 to read as shown below. 4. Add "Clean Agents-NFPA 2001" to the end of 10-3.1. 5. Change note 2 in 10-3.2 to read as follows:

"For normally occupied areas ensure clean agents are suitable for application."

10-3 Gaseous Suppression Systems. 10-3.1 In areas where appreciable Class C hazards exist and

where the. use of other agents might, result in equipment malfunction or damage as determined by the fire hazard analysis, gaseous extinguishing agent systems shall be installed. These systems, where required, shall be designed, installed, and maintained in accordance with the appropriate agent standard as follows:

Halon 1301 - - NFPA 12A Halon 1211 - - NFPA 12B Carbon Dioxide - - NFPA 12 Clean Agents - - NFPA 2001 10-3.2 When gaseous extinguishing agent systems are used, they

shall be automatically actuated by an approved method of detection meeting the requirements of NFPA 72. To ensure rapid detection, particular attention shall be given to file choice of actuation means, the air flows usually involved, and the heat release rates for the hazard under fire conditions.

NOTE 1: For carbon dioxide total flooding systems that are automatically actuated in normally occupied areas, a predischarge

482

N F P A 8 0 3 - - F 9 7 R O P

alarm and time delay are required to allow for personnel evacuation of the area~

NOTE 2: For normally occupied areas ensure clean agents are suitable for application.

NOTE 3: Electrical equ ipment need no t be de-energized pr ior to the discharge of these extihguishing agent systems, but shut-down is desirable if it can be accomplished. SUBSTANTIATION: Items 1, 2, 3, and 4 were editorial. Item 5 was added to be compatible with the Commit tee Action on Proposal 803-5 (Log #3). COMMITTEE ACTION: Accept.

(Log #3) 803- 5 - (Table 10-1.2): Accept in Principle in Part SUBMITTER: Donald A~ Diehl, Alison Control Inc. RECOMMENDATION: Revise Table 10-1.2 as follows:

(a) Change "Liquefied Compressed Gases" co lumn to "Gaseous Systems".

(b) Eliminate columns "Halon 1301" and "Halon 1211" and add a new column in its place enti t led "Clean Agents".

(c) In the "Hazard Column" add a new note for "Computer Rooms (including under t loor space)". The note to read "Not for Underf loor Use". This for clean agents only. Note 4 CO2 should be left in. SUBSTANTIATION: (a) Some of the new clean agents are no t l iquefied compressed gases.

(b) The Halons are discontinued. (c) Underf loor spaces could contain Class A material which

could have deep seated fires. NFPA 2001, "Clean Agents". Section 3-4.2.2.2 ment ions only Class A surface fires. Deep seated fire are ignored. Section 2-4.2 of NFPA 12 ment ions deep seated fires for CO2. COMMITIT.~ ACTION: Accept in Principle in Part.

I Accept Part (a) Accept Part (b) and, add a new note 7 to the new "Clean Agent"

column: "For normally occupied areas ensure clean agents are suitable for application. Existing Halon systems are acceptable for cont inued use. '

Reject Part C. COMMITTEE STATEMENT: Part (b) was revised to add a cautionary note and provide more informat ion to the user.

Part (c) was rejected because the intent o f the proposal was no t clear.

. (Log #2) 803- 6 - (13-1.2): Accept in Principle SUBMITFER: Lvnn K. Underwood, Alliance of American Insurers RECOMMENDAII'ION: Delete 13-1.2, 13-1.1.2, 13-1.2.2, 13-1.2.3, and 13-1.2.4.

Renumber 13-1.3 as 13-1.2. Renumber 13-1.4 and 13-1.3.

SUBSTANTIATION: This material is outdated and is in NFPA 10. COMMITTEE ACTION: Accept in Principle.

The Commit tee acce~ts the submitters recommendat ion. In addit ion add "selected after the words "~hall be" in 13-1.1 so that it reads:

13-1.1 Portable and wheeled fire extinguishers shall be selected, installed, inspected, maintained, and tested in accordance with NFPA 10 a n d a p p r o v e d or listed by a testing laboratory.

13-1.1.2 should be 13-1.2.1 in the proposal. COMMITTEE STATEMENT: The revision was made for clarification.

The error in the referenced paragraph was corrected.

(Log #1) 803- 7 - (13-2.2): Accept in Principle SUBMITrER: Lynn K. Underwood, Alliance of American Insurers RECOMMENDATION: Delete 13-2.2, 13-2.2.1, 13-2.2.2, 13-2.2.3, 13-2.2.3.1, 13-2.2.3.2, and 13-2.2.4.

Renumber 13-2.3 as 13-2.2. Renumber 13-2.4 as 13-2.3.

SUBSTANTIATION: This material is outdated and can be found in NFPA Standards 14, 11, 12, and 17. COMMITTEE ACTION: Accept in Principle.

Accept the proposers recommendat ion with the following addit ions:

Add the word "selected" after the words "shall be" in 13-2.1 so that it reads:

13-2.1 Hand hose lines utilizing water, foam, carbon dioxide, or dry chemical shall be selected, installed, inspected, and mainta ined in accordance with the following NFPA standards, respectively: NFPA 14, NFPA 11, NFPA 12, and NFPA 17.

Also delete 13-2.2.3.3. COMMITTEE STATEMENT: Editorial and clarification. One reference was inadvertently left out.

483