ML033440503

E-mail from Karla Smith to Art Howell Regarding ANO Fire Protection Backfit Panel. Partially Wittheld

ML033440503
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/22/2003
From:	Smith K NRC Region 4
To:	Brockman K, Chamberlain D, Gramm R, Hannon J, Howell A, Mizuno G, Nease R, Qualls P, Smith K, Vasquez G, Weiss E NRC/RGN-IV/DRP
References
FOIA/PA-2003-0358
Download: ML033440503 (8)

Text

i MicnaeI vasquez - AND FAre Protection Backfit Panel Paqne From:

Karla Smith To:

Art Howell; Dwight Chamberlain; Eric Weiss; Geary Mizuno; John Hannon; Karla Smith; Ken Brockman; Michael Vasquez; Phil Qualls; Rebecca Nease; Robert Gramm Date:

10122/01 6:07PM

Subject:

ANO Fire Protection Backfit Panel Based on the poll taken, the RIV ANO Backfit Panel will take place this Friday, October 26, 2001, in the Executive Conference Room at 3:00 akST, 2:00 p.m. CST. For headquarters participants, the bridge number is!,301-231-5539, passcodIe Since we have ordered only four lines, we encourage headquarfers participants if possible eet together for the call. I have attached five documents for your review prior to the panel. You will need to open the fifth document using Adobe Acrobat since it is a

.pdf file. Also, you may want to review the backfit rule,.10 CFR 50.109. If I have missed anyone in this e-mail, please pass it on to them. If you have any questions, or H you will be unable to attend, please contact me. Thank you in advance for your participation.

Karla D. Smith RIV Regional Counsel 817-860-8271 (w) 817-860-8122 (f) kds1 @nrc.gov CC:

Ellis Merschoff; Pat Gwynn t

.;I.

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' WAiS Docuffint Retrieval htp://frwebgate.access.gpo.gov/cgi-bin/get-

[Code of Federal Regulations]

(Title 10, Volume 1]

[Revised as of January 1, 2001]

From the U.S. Government Printing Office via GPO Access

[CITE: 1CFR50.109]

[Page 786-788]

TITLE 10--ENERGY CHAPTER I--NUCLEAR REGULATORY COMMISSION PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES--Table of Content.

Sec. 50.109 Backfitting.

(a)(1) Backfitting is defined as the modification of or addition to systems, structures, components, or design of a facility; or the design approval or manufacturing license for a facility; or the procedures or organization required to design, construct or operate a facility;

((Page 787))

any of which may result from a new or amended provision in the Commission rules or the imposition of a regulatory staff position interpreting the Commission rules that is either new or different from a previously applicable staff position after:

(i) The date of issuance of the construction permit for the facility for facilities having construction permits issued after October 21, 1985; or (ii) Six months before the date of docketing of the operating license application for the facility for facilities having construction permits issued before October 21, 1985; or (iii) The date of issuance of the operating license for the facility for facilities having operating licenses; or (iv) The date of issuance of the design approval under appendix M, N, or 0 of part 52.

(2) Except as provided in paragraph a)(4) of this section, the Commission shall require a systematic and documented analysis pursuant to paragraph (c) of this section for backfits which it seeks to impose.

(3) Except as provided in paragraph (a)(4) of this section, the Commission shall require the backfitting of a facility only when it determines, based on the analysis described in paragraph (c) of this section, that there is a substantial increase in the overall protection of the public health and safety or the common defense and security to be derived from the backfit and that the direct and indirect costs of implementation for that facility are justified in view of this increased protection.

(4) The provisions of paragraphs (a)(2) and (a)(3) of this section are inapplicable and, therefore, backfit analysis is not required and the standards in paragraph (a)(3) of this section do not apply where the Commission or staff, as appropriate, finds and declares, with appropriated documented evaluation for its finding, either:

(i) That a modification is necessary to bring a facility into compliance with a license or the rules or orders of the Commission, or into conformance with written commitments by the licensee; or (ii) That regulatory action is necessary to ensure that the facility provides adequate protection to the health and safety of the public and is in accord with the common defense and security; or (iii) That the regulatory action involves defining or redefining what level of protection to the public health and safety or common defense and security should be regarded as adequate.

(5) The Commission shall always require the backfitting of a facility if it determines that such regulatory action is necessary to ensure that the facility provides adequate protection to the health and

- NYMS Docuffent Rctrieval http://frwebgate.access.gpo.gov/cgi-bin/get-cI safety of the public and is in accord with the common defense and security.

(6) The documented evaluation required by paragraph (a)(4) of this section shall include a statement of the objectives of and reasons for the modification and the basis for invoking the exception. If immediately effective regulatory action is required, then the documented evaluation may follow rather than precede the regulatory action.

(7) If there are two or more ways to achieve compliance with a license or the rules or orders of the Commission, or with written licensee commitments, or there are two or more ways to reach a level of protection which is adequate, then ordinarily the applicant or licensee is free to choose the way which best suits its purposes. However, should it be necessary or appropriate for the Commission to prescribe a specific way to comply with its requirements or to achieve adequate protection, then cost may be a factor in selecting the way, povided that the objective of compliance or adequate protection is met.

(b) Paragraph (a)(3) of this section shall not apply to backfits imposed prior to October 21, 1985.

(c) In reaching the determination required by paragraph (a)(3) of this section, the Commission will consider how the backfit should be scheduled in light of other ongoing regulatory activities at the facility and, in addition, will consider information available concerning any of the following factors as may be appropriate and any other information relevant and material to the proposed backfit:

((Page 788))

(1) Statement of the specific objectives that the proposed backfit is designed to achieve; (2) General description of the activity that would be required by the licensee or applicant in order to complete the backfit; (3) Potential change in the risk to the public from the accidental off-site release of radioactive material; (4) Potential impact on radiological exposure of facility employees; (5) Installation and continuing costs associated with the backfit, including the cost of facility downtime or the cost of construction delay; (6) The potential safety impact of changes in plant or operational complexity, including the relationship to proposed and existing regulatory requirements; (7) The estimated resource burden on the NRC associated with the proposed backfit and the availability of such resources; (8) The potential impact of differences in facility type, design or age on the relevancy and practicality of the proposed backfit; (9) Whether the proposed backfit is interim or final and, if interim, the justification for imposing the proposed backfit on an interim basis.

(d) No licensing action will be withheld during the pendency of backfit analyses required by the Commission's rules.

(e) The Executive Director for Operations shall be responsible for implementation of this section, and all analyses required by this section shall be approved by the Executive Director for Operations or his designee.

(53 FR 20610, June 6, 1988, as amended at 54 FR 15398, Apr. 18, 1989]

Enforcement

Pt. 50, Hp. R chapter or Is a testing facility The ci sions of the Stafr Site iReport will be ret Ined by the staff where five years or have elapsed between the Issuance o Staff Ste Report and Its Incorporatl(

reference in a construction permit apt tion.

6. Issuance of a Staff Site Report hal constitute a Commitment to Issue a pl or license, to permit on-site work V lSO.lO(e), or In any way affect the auth, of the Commission. Atomic Safety an(

censing Appeal Panel, Atomic Safety and censing floard. and other Presiding office any proceeding under subpart P and/or part 2 of this chapter

7. The staff will not conduct more than review of site suitability issues with re, to a particular site prior to the full const tion Permit review required by subpart part 51 Of this chapter. The staff may decl to prepare and Issue a Staff Site Report response to at submnitWa under this appen where it appears that, (a) In cases where review of the relative merits o the a mitted %Ite and alternative sites under,

Part A of part 5i of this chapter is request there s a reasonable likelihood that furt)

Staff review would dentify one or more pr erable alternative ites and the Staff revIi of one or more site suitability Issues wo' lead to an rreversible and rretrievable coti mitment of resources prior to the submitt of the analysis of alternative sites in the E vironmental Report that would prejudice ti later review and decision on alternative siti under subpart and/or of part 2 and sul part A of part 51 of this chapter; or (b) I cases where, n te judgment of the tar early review of any site suitability issue Issues would not be n the public interest considering (2) the degree of likelihood tha.

any early findings on those issues would re tamn their validity in later reviews. (2) thi objections. f any, of cognizant state or loca government agencies to the conduct of an early review on those ssues, and (3) the posy sible effect on the ublic nterest of having an early, It not necessarily ocuie eo lution of those ssues.

ycoluiers-(42 PR 22887,IMay 5, 1977. as amended at 49 FR 9405. MLar. 12, 1981: S1 PR 4M~I,. Nov. 6.

1986; 53 PR 43420. Oct. 27, 1988; 64 R 48952, Sept. 9, 19991 APPENDIX Ri To PART 50-Firt PRoTC..

TION POORANI Poll NUCLEAR PWER FACILITIES OPERATI11G PRIOR To JANUARY 1, 1979 I. IrrOoUCTION AD SOPE This appendix applies to licensed nuclear power electric generating stations that were operating prior to January i, 1979, except to the extent set forth In i50.48(b) o this part.

With respect to certain generic issues for 10 CFR Ch. I (1-1-l Edno Bnciu-such facilities t ets forth fire Proteut1 exam-features required to satisfy Criterion 3 of a more pendix A to this pt at syCiein3o onthe Criterion 3 ofaPPendix A to this pr in by flees that "Structures systems, andcop.

dlica-nents important to sfety shall be d=sLs and located to minimize, consistentv" I not other safety requiremeag the pro

• rmIt and effect of fires and explosions" inder When onsidering the effectsoo fire, arity systems associated With achev Ing andi*-

I L-taing safe shutdown conditions Li.

major Importance to safety because dams6 ra In to them can lead to core damage resulu of from loss Of coolant through bolorf.

The phrases "important to safety. o one "safety-related.. will be used throughout rard this aendix, ' as applying. to all afety muc-functions.The phrase --safe shutdowns will

t. of be used throughout this appendix as applywr line to both hot and cold shutdown functions.

In Because fire may affect e

t dx temns and because the loss of function of 1no temns used to mitigate the consequenceg Byt ub-design basis accidents under Postfire coni tib-tions does not per e mpact ublic arnt~

ed, te nee to Iit fire damage to systems re..

ter quired to achieve and maintain safe aslu!

ef-down conditions s greater than the edt Dw limit fire damage to those system e eed id to mitigate the consequenceso dsgn~

11i-accidents. Three levels of f aaelmia al are established according tothsaeyie.

It-tions f the structure. systeocoi.

le nent:

hxSaft unton Fr aaeSu nn hutdow trai of equipme nes ecdle" hot ahutdow fm silhe ti control toom O emergency e

t

~~~~~sft"On(s) must bemairtainad fm fr damage by a sgl ire, hck6i Cold Shutdown kVan eX~s t.

Both trains of equipment ncesay to achirve cold shiutdown may be ds aged by a sgl firo, inckutfe an 6*pos fire

%e but damage Ms be limited so that at least one ti Mh Design A313 Accl.

Bot train o aveableufi dents.

traismof nt necossasy itigation, ofconequees 1 design balls cdnts maybeam daig.I n ft oueS.Iftr iagvnae edlaent o tht sme aof shliret sehall emotie, het,

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reaITheoemact t_

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1.I Nuclear Regulatory Commission shutdown may be lost to a single exposure re. However, protection shall be provided so that a fire within only one such system will rot damage the redundant system.

11.

ERAL REQUIREMENTS

A. Fire protection program. A fire protection ysogram shall be established at each nuclear power plant. The program shall establish the Are protection policy for the protection of structures, systems, and components mpor-tast to safety at each plant and the proce.

dares, equipment, and personnel required to Jmplement the program at the plant site.

..The fire protection program shall be under the direction of an ndividual who has been oelegated authority commensurate with the

responsibilities of the position and who has available staff personnel knowledgeable In both fire protection and nuclear safety.

. The fire protection program shall extend the concept of defense-in-depth to fire pro-tection In fire areas important to safety wIth the following objectives:

To prevent fires from starting;

To detect rapidly, control, and extin-guish promptly those fires that do occur

a To provide protection for structures, sys-teme, and components important to safety so that a fire that Is not promptly extinguished by the fire suppression activities will not prevent the safe shutdown of the plant.

B. Fire hazards analysls. A fire hazards analysis shall be performed by qualified fire protection and reactor systems engineers to (1) consider potential in situ and transient fire hazards: (2) determine the consequences of fire In any location In the plant on the billty to safely shut down the reactor or on the ability to minimize and control the re-lease of radioactivity to the evironment:

and (3) specify measures for fire prevention, fire detection, fire suppression, and fire con-tainment and alternative shutdown capa-bility as required for each fire area con-taining structures, systems, and components important to safety In accordance with NRC guidelines and regulations.

C. Fire prevention features. Fire protection features shall meet the following general re-quirements for all fire areas that contain or present a fire hazard to structures, systems, or components Important to safety.

1. In situ fire hazards shall be Identified and suitable protection provided.

2. Transient fire hazards associated with normal operation, maintenance, repair, or modification activities shall be Identified and eliminated where possible. Those tran-sient fire hazards that can not be eliminated shall be controlled and suitable protection provided.

3. Fire detection systems, portable extin-guishers, and standpipe, and hose stations shall be Installed,

4. Fire barriers or automatic suppression systems or both shall be Installed as nec-3, App. R essary to protect redundant systems or com-ponents necessary for safe shutdown.

5. A site fire brigade shall be established, trained, and equipped and shall be on site at all times.

6. Fire detection and suppression systems shall be designed, installed, maintained. and tested by personnel properly qualified by ex-perience and training in fire protection sys-tems.

7. Surveillance procedures shall be estab-lished to ensure that fire barriers are in place and that fire suppression systems and components are operable.

D. Alternative or dedicated shutdown capa-bility. In areas where the fire protection fea-tures cannot ensure safe shutdown capability In the event of a fire In that area. alter-native or dedicated safe shutdown capability shall be provided.

III. SPECIric REQUIREMENTS A. Water supplies for fire suppression systems.

Two separate water supplies shall be pro-vided to furnish necessary water volume and pressure to the nre main loop.

Each supply shall consist of a storage tank, pump, piping. and appropriate Isola-tion and control valves. Two separate redun-dant suctions In one or more Intake struc-tures from a large body of water (river, lake, etc.) will satisfy the requirement for two separated water storage tanks. These sup-piles shall be separated so that a failure of one supply will not result in a failure of the other supply.

Each supply of the fire water distribution system shall be capable of providing for a pe-riod of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> the maximum expected water demands as determined by the fire hazards analysis for safety-related areas or other areas that present a fire exposure hazard to safety-related areas.

When storage tanks are used for combined service-water/lfire-water uses the minimum volume for fire uses shall be ensured by means of dedicated tanks or by some phys-lcal means such as a vertical standpipe for other water service. Administrative controls, Including locks for tank outlet valves, are unacceptable as the only means to ensure minimum water volume.

Other water systems used as one of the two fire water supplies shall be permanently con-nected to the fire main system and shall be capable of automatic alignment to the fire main system. Pumps, controls, and power supplies In these systems shall satisfy the re-quirements for the main fire pumps. The use of other water systems for fire protection shall not be Incompatible with their func-tions required for safe plant shutdown. Fail-ure of the other system shall not degrade the fire main system.

B. Sectional isolation valves. Sectional Isola-tion valves such as post Indicator valves or key operated valves shall be Installed in the

Pt. 50, Apt.. d f1re main loop to permit Isolation of por of the fire main loop for maintenance pair without Interrupting the entire supply.

C. Hydrant soatton talpeg. Valves sha Installed to permit solation of Outside drants from the fire main for maintenan, repair without nterrupting the Water su to automatic or manual fire suppression tems In any area containing or presentj fire hazard to satety-related or afe down equipment.

D. Manual fire suppression.* StAndpipe hose systems shall h Installed so thal least one erfective hose stream will be to reach any location that contains or sents an exposure fire hazard to structu systems or components mportant to sate Access to permit effective functioning the fre brigade shall be provided to all ar that contatn or Present an exposure fire ard to structures systemS Or componel important to safety.

Standpipe and hose stations shall be Ins' WR containments and BIVR contAfnmer that are not nerted. Standpipe and hose l tions Inside containment may be connect to a high quality water supply of sufficle qutntity and pressure other than te n

main oop plant-speefci features prevei extending the fire main supply nside tainment. For WR drywells standplpe at hose stations shall be laced outside the di well with adequate lengths ot hose to reac any location nside the dry well with an fective hose tream.

E. )ly1drostatic hose tests, Fire hose shall b hydrostatically tested at a pressure of 15o pb or 50 si above mnaximum, fire main operatini Pressure. whichever s greater.

ose store(

In outside hose houses shall be tested atnnu ally. Interior standpgpe hose shall be testee every three years.

F. Automatic fire detection. Automatic fire detection systems shall be Installed in all areas of the plant that contain or Present an exposure fire ha2ard to safe shutdown or safetY-related systems or components. These fire detection systems shall be capable of op-erating, with Or without affelte Power.

. Fire protection of safe shutdown cpa-bttity. I. F re protection features shall be pro-vided or structures systems, and compo.

nents important to safe shutdown. These fea-tures shall be capable of limiting fire dm-age so that:

a. One train of systems necessary to achieve and maintain hot hutdown condi-tions romn either the control room or emer-rency control station(s) is free of fire dam.

%ge: and

b. Systems necessary to achieve and maln.

ain cold shutdown from either the control

'Oom or emerglency control station(s) can be lepalred within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2. 13xcept as provided for in aragraph 0.3

.'f this section. where cables or equipment.

10 CFR Ch. I (1-4-ot Fdto~

-tions including associated non-safety eirculthZ

)r re-could prevent oprtin or cg eater maloperation due tohrthorn or cttki cults, or shorts to ground, Of redundnt 11 be trains of systems necessary to achieve anj eey.

maintain hot shutdown conditions re0let Cs or cated within the same fire area cutslde'~

pply primary containment. one of the flow Y1'-

means of ensuring that one the redu nga trains s free of fire damage shall bri hut-vided:

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a. Separatlon of cables and equipmert s;I and associated non-safety circuits of reduftdt It trains by a fire barrier baving a 3houra iPe tnog. Structural tee forming part or pr-supporting such fire barriers shall be di

res, tected to povide fire resistance equiyale~

rty.

to that required of the barrier.

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b. Separation of cables and equipment anJj

&aZ associated non-safety circuits of rfundftan a

trains by a horizontal distance of more thaE dits 20 feet with no intervening combustible o-il ide fire hazards. In addItion, fire detectors an&'."

besal automatic fire suppression system sblt.

be nstalled In the fire area-or ed C. Enclosure of cable and equIpment andij nt associated non-safety circuits of one redun ntdant train in at fire barrier having a -hout.

1it rating, In addition, fire detectors and an n-atutom'atic fire suppre55ion systern shall be id Installed In the fire area:

Inside noninerted containments one of the' fire protection means specified above or one Of the following fire protection means ehal be provided:

e

d. Separation of cables and equipment and 1

associated noni-safety circuits of redundant trains by a horizontal distance of more than' 20 feet with no intervening combustibles or fire hazards;

e. Installatlon of ire detectore and an automatic fire uppression system n the fire area: or

f. Separation of ables and equipment and associated non-safety circuits of redundant trains by a noncombustible radiant energy shield.

3. Alternative of dedicated shutdown caps-bility and ts associated crcuits la 1def.

pendent ot cables. systems or components in the area, room, zone under consideration should be rovided:~n

a. Where the protection of systems whose function s required for hot shutdown does not atify he equremnt f Pragraph 0.2

b. Wereredndat tain ofsystems re-quied or ot hutownloctedinthe same-fireare maybe ubjct t daagefrom fire 3Aierntiv sutdown apabflity is pro-vidd b reoutng, relocating, or modifying exitin sstes;dedicated shutdown capa-bilty s poviedby nstalling new struc-ture an s~semsfor the function of ost-fire shutdown

~ ~ ~ ~ ~

Nuclea Regulatory Commission oareslon activities or from the rupture or Wdvertent operation of fire suppression sys-addition, fire detection and a fixed fire oppression system shall be Installed In the a, room, or sona under consideration.

'5. Fire brigade. A site flre brigade trained d equipped for fre fighting shall be estab-ilbd to ensure adequate manual tire fight-capability for all areas of the plant con-laing structures, systems, or components important to safety. The fire brigade shall be Jeast fve members on each shift. The bri-gade leader and at least two brigade mem-bers shall have sufficient training, in or owledge of plant safety-related systems to uderstand the effects of fire and fire sup-etssants on sate shutdown capability. The ualification of fire brigade members shall Inelude an annual physical examination to d4termine their ability to perform strenuous fire fighting activities. The shift supervisor

.*ah1 not be a member of the fire brigade.

The brigade leader shall be competent to as-

~aess the potential safety consequences of a fire and advise control room personnel. Such competence by the brigade leader may be evIdenced by possession of an operators i-cense or equivalent knowledge of plant safe-ty-related systems.

The minimum equipment provided for the brigade shall consist of personal protective eqptDment such as turnout coats, boots, gloves. hard hats. emergency communica-tions equipment, portable lights, portable ventilation equipment, and portable extin-gulsbers. Self-contained breathing apparatus using full-face positive-pressure masks ap-proved by NIOSII (National Institute for Oc-cupatlonal Safety and Health-approval for-merly given by the U.S. Bureau of Mines) shall be provided for fire brigade, damage control, and control room personnel. At least 10 masks shall be available for fire brigade personnel. Control room personnel may be furnished breathing air by a manifold system piped from a storage reservoir If practical.

Service or rated operating life shall be a minimum of one-half hour for the self-con-tained units.

At least a I-hour supply of breathitng air In extra bottles shall be located on the plant site for each unit of self-contained breathing appratus. In addition, an onsite 6-hour sup-ply of reserve air shall be provided and ar-ranged to permit quick and complete replen-ishment of exhausted air supply bottles as they are returned. It compressors are used as a source of breathing air, only units ap-proved for breathing air shall be used and the compressors shall be operable assuming a loss of offsite power, Special care must be taken to locate the compressor In areas free of dust and contaminants.

1. Fire brigade training. The fire brigade training program shall ensure that the capa-bility to fight potential fires Is established F..

, App. R and maintained. The program shall consist of an Initial classroom nstruction program followed by periodic classroom instructon fire fighting practice and fire drills:

1. Instruction

a. The Initial classroom Instruction shall include:

(1) Indoctrination of the plant fire fighting plan with specific Identification of each indl-vidual's responsibilities.

(2) Identification of the type and location of tire hazards and associated types of fires that could occur in the plant.

(3) The toxic and corrosive characteristics of expected products of combustion.

(4) Identification of the location of fire fighting equipment for each fire area and ta-millarization with the layout of the plant, including access and egress routes to each area.

(5) The proper use of available fire fighting equipment and the correct method of fight-Ing each type of fire. The types of fires cov-ered should Include fires In energized elec-trical equipment, fires In cables and cable trays, hydrogen fires, fires involving flam-mable and combustible liquids or hazardous process chemicals, fires resulting from con-struction or modifications (welding), and record file fires.

(6) The proper use of communication, light-ing. ventilation, and emergency breathing equipment.

(7) The proper method for fighting fires In.

side buildings and confined spaces.

(8) The direction and coordination of the fire fighting activities (fire brigade leaders only).

(9) Detailed review of fire fighting strate-gies and procedures.

(10) Review of the latest plant modifica-tions and corresponding changes in fire fighting plans.

NoT': Items (9) and (10) may be deleted from the training of no more than two of the non-operations personnel who may be as-signed to the fire brigade.

b. The nstruction shall be provided by qualified Individuals who are knowledgeable, experienced, and suitably trained In fighting the types of fires that could occur in the plant and In using the types of equipment available In the nuclear power plant.

c. Instruction shall be provided to all fire brigade members and fire brigade leaders.

d. Regular planned meetings shall be held at least every 3 months for all brigade mem-bers to review changes In the fire protection program and other subjects as necessary.

e. Periodic refresher training sessions shall be held to repeat the classroom instruction program for all brigade members over a two-year period. These sessions may be concur-rent with the regular planned meetings.

2. Practice Practice sessions shall be held for each shirt fire brigade on the proper method of

Pt. 50, Ap,,

fighting the various types of fires that could occur in a nuclear power plant. These ses-slons shall provide brigade members with ex-perlence In actual fire extinguishment and the use of emergency breathing apparatus under strenuous conditions encountered In fire fighting. These practice sessions shall be provided at least once per year for each fire brigade member.

3. Drills

a. Fire brigade drills shall be performed In the plant so that the fire brigade can prac-tice as a team.

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b. Drills shall be performed at regular In-tervals not to exceed 3 months for each shift fire brigade. Each fire brigade member should participate in each drill, but must participate In at least two drills per year.

A sufficient number of these drills, but not less than one for each shift fire brigade per year, shall be unannounced to determine the fire fighting readiness of the plant fire bri-gade, brigade leader, and fire protection y.

tems and equipment. Persons planning and authorizing an unannounced drill shall en-sure that the responding shift fire brigade members are not aware that a drill is being planned until It Is begun. Unannounced drills shall not be scheduled closer than four weeks.

At least one drill per year shall be per-formed on a "back shift" for each shift fire brigade.

c. The drills shall be preplanned to estab-t lish the training objectives of the drill and 8

shall be critiqued to determine how well the I

training objectives have been met. Unan.

8 nounced drills shall be planned and critiqued by members of the management staff respon.

c sible for plant safety and fire protection.

h Performance deficiencies of a fire brigade or t.

of Individual fire brigade members shall be T

remedied by scheduling additional training for the brigade or members. Unsatisfactory tI drill performance shall be followed by a re-cc peat drill within 0 days.

ul

d. At 3-year Intervals. a randomly selected cI unannounced drill must be critiqued by Ot qualified Individuals Independent of the li-ar censee's staff. A copy of the written report from these individuals must be available for sa NRC review and shall be retained as a record sty as specified In ection 11l.1.4 of this appendix, tic

e. Drills shall as a minimum include the I

following:

ie (1) Assessment of fire alarm effectiveness fla time required to notify and assemble fire bri-uci gade, and selection, placement and use of bul equipment and fire fighting trategies.

or (2) Assessment of each brigade member's and knowledge of his or her role in the fire fight-firs Ing strategy for the area siumed to contain 4.

the fire. Assessment of the brigade member's spo conformance with established plant fire viei fighting procedures and use of fire fighting pot4 equipment, Including self-contained emer-reqt gency breathing apparatus communication war 10 CFR Ch. I (1-1-01 Edition) tNucleo Regulatoty Commission equipment, and ventilation equipment to the extent practicable.

(3) The simulated use of fire fighting equip-ment required to cope with the situation ad type of fire selected for the drill. The area.

and type of fire chosen for the drill should differ from those used in the previous drill so that brigade members are trained in fighting fires In various plant arena The situation s lected should simulate the size and arrange-ment of a fire that could reasonably occur n the area selected. allowing for fire develop:

ment due to the time required to respond, to obtain equipment, and organize for the fire, assuming loss of automatic suppression ca-pability.

(4) Assessment of brigade leader's direction of the fire fghting effort as to thoroughness accuracy, and eftectiveneas.

4. Records Individual records of training provided to each fire brigade member, Including drill cri-tiques. shall be maintained for at least 3 years to ensure that each member receives training n all parts of the training rogram.

These records of training shall be available for NRC review. Retraining or broadened training for fire fighting within bulldirgs shall be scheduled for all those brigade mem-bers whose performance records show defl-clencles.

J. Eergency Ihting. Emergency lighting units with at least an -hour battery power supply shall be provided In all areas needed or operation of safe shutdown equipment (nd in access and egress routes thereto.

K. Administrative controls. Administratloe ontrols shall be etablished to mnimize fire azards In areas containing structures, sys-ems, and omponenx Important to safety.

'hese controls shall establish procedures to:

t. Govern the handling and limitation of Se use of ordinary combustible materials,

'mbustIble and flammable gases and liq.

da, high efficiency particulate air and iarcoal filters, dry on exchange resins, or her combustible supplies In safety-related

2. Prohibit the storage of combustibles In fety-related areas or establish designated

)rage areas with appropriate fire protec.

in.

I. Govern the handling of and limit tran-nt fire loads such a combustible and mimable liquids, wood and plastic prod-

s, or other combustible materials in Idings containing safety-related systems equipment during all phases of operating, I especially during maintenance modl-Wtion, or refueling operations, Designate the onsite staff member re-aneible for the Inplant fire protecton re-w of proposed work activities to Identify tentia transient fire hazards and specify lired Additional fire protection In the rk activity procedure.

I I

ilI 4.. 5. Govern the use of ignition sources by use

1. of a name permit systetr to control welding flame cutting, brazing, or soldering oper-ations. A separate permit shall be ssued for each area where work Is to be done. I work continues over more than one shift, the per-mit shall be valid for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the plant Is operating or for the dura-tion of a particular job during plant shut-down.

0. Control the removal from the area of all waste. debris, scrap, oil spills. or other com-bustibles resulting from the work activity Immediately following completion of the ac-tivity, or at the end of each work shift.

whichever comes first.

7. Maintain the periodic housekeeping in-spectIons to ensure continued compliance with these administrative controls.

S. Control the use of specific combustibles In safety-related areas. All wood used in safety-related areas during maintenance.

modification, or refueling operations (such as lay-down blocks or scaffolding) shall be treated with a name retardant. Equipment or supplies (such as new fuel) shipped In un-treated combustible packing containers may be unpacked In safety-related areas it re-quired for valid operating reasons. However.

all combustible materials shall be removed from the area immediately following the un-packing. Such transient combustible mate-rial, unless stored In approved containers.

shall not be left unattended during lunch breaks, shift changes, or other similar peri-ods. Loose combustible packing material such as wood or paper excelsior, or poly-ethylene sheeting shall be placed in metal containers with tight-fitting self-closing metal covers.

P. Control actions to be taken by an ndl-vidual discovering a fire, for example. notifi-cation of control room, attempt to extin-guish ire, and actuation of local fire sup-pression systems.

10. Control actions to be taken by the con-trol room operator to determine the need for brigade assistance upon report of a fire or re-ceIpt of alarm on control room annunciator panel, for example, announcing location of fire over PA system, sounding fire alarms, and notifying the shift supervisor and the fire brigade leader of the type, size, and loca-tion of the fire.

12. Control actions to be taken by the fire brigade after notification by the control room operator of a fire, for example, assem-bling In a designated location, receiving di-rections from the fire brigade leader. and discharging specific fire fighting responAlbil-Itles Including election and transportation of fire fighting equipment to fire location.

selection of protective equipment, operating Instructions for use of fire suppression sys-tems, and use of preplanned strategies for fighting fires In specific areas.

.50, App. R

12. Define the strategies for fighting fires in all safety-related areas and areas pre-senting a hazard to safety-related equip-ment. These strategies shall designate:

a. Fire hazards In each area covered by the specific prefire plans.

b. Fire extinguishants best suited for con-trolling the fires associated with the fire hazards In that area and the nearest location of these extingulshants.

c. Most favorable direction from which to attack a fire In each area in view of the ven-tilatlon direction, access hallways, stairs, and doors that are most likely to be free of fire. and the best station or elevation for fighting the fire. All access and egress routes that involve locked doors should be specifi-cally Identified In the procedure with the ap-propriate precautions and methods for access specified.

d. Plant systems that should be managed to reduce the damage potential during a local fire and the location of local and re-mote controls for such management (e.g.,

any hydraulic or electrical systems In the zone covered by the specific fire fighting pro-cedure that could Increase the hazards in the area because of overpressurtzatfon or elec-trical hazards).

e. Vital heat-sensitive system components that need to be kept cool while fighting a local fire. Particularly hazardous combusti-bles that need cooling should be designated.

f. Organization of fire fighting brigades and the assignment of special duties according to.

job title so that all fire fighting functions are covered by any complete shift personnel complement. These duties Include command control of the brigade, transporting fire sup-pression and support equipment to the fire scenes, applying the extingulsbant to the fire. communication with-the control room.

and coordination with outside fire depart-ments.

8. Potential radiological and toxic hazards in fire zones.

h. Ventilation system operation that en-sures desired plant air distribution when the ventilation flow Is modified for fire contain-ment or smoke clearing operations.

1. Operations requiring control room and shift Engineer coordination oi authorization.

J. Instructions for plant operators and gen-eral plant personnel during fire.

L. Alternutive and dedicated shutdown capa-billy. 1. Alternative or dedicated shutdown capability provided for a specific fire area shall be able to (a) achieve and maintain sub-critical reactivity conditions in the reactor; (b) maintain reactor coolant inventory ()

achieve and maintain hot standby' condi-tions for a PWR (hot shutdown' for a nWR):

(d) achieve cold shutdown conditions within 2As defined in the Standard Technical Specifications.

Pt. 50, App.

72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s: and (e) maintain cold shutdown conditions thereafter. During the postfire shutdown, the reactor coolant system proc-ess variables shall be maintained within those predicted for a loss of normal a.c.

power, and the fission product boundary In-tegrity shall not be affected. i.e., there shall be no fuel clad damage. rupture of any prl-mary coolant boundary, of rupture of the containment boundary.

2. The performance goals for the shutdown functions shall be:

a. The reactivity control function shall be capable of achieving and maintaining cold shutdown reactivity conditions.

b. The reactor coolant makeup function shall be capable of maintaining the reactor coolant level above the top of the core for BWRs and be within the level indication In the pressurizer for PWRs.

c. The reactor heat removal function shall be capable of achieving and maintaining decay beat removal.

d. The process monitoring function shall be capable of providing direct readings of the process variables necessary to perform and control the above functions.

e. The supporting functions shall be capa-ble of providing the proqess coolbig. lubrica-tion. etc.. necessary to permit the operation of the equipment used for safe shutdown functions.

3. The shutdown capability for specific fire areas may be unique for each such area. or it may be one unique combination of systems for all such areas. In either case, the alter.

native shutdown capability shall be Inde-pendent of the specific fire area(s) and shall accommodate postfire conditions where off-site power Is available and where offaite power Is not available for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Proce-dures shall be in effect to Implement this ca-pability.

4. If the capability to achieve and maintain cold shutdown will not be available because of fire damage, the equipment and systems comprising the means to achieve and main-taln the hot standby or hot shutdown condi-tion shall be capable of maintaining such conditions until cold shutdown can be achieved. If such equipment and systems will not be capable of being powered by both on-site and offsite electric power systems be-cause of fire damage, an independent onsite power system shall be provided. The number of operating shift personnel, exclusive of fire brigade members, required to operate such equipment and systems shall be on site at all times.

5. Equipment and systems comprising the means to achieve and maintain cold shut-down conditions shall not be damaged by fire. or the fire damage to such equipment and systems shall be limited so that the sys-tems can he made operable and cold shut-down can be achieved within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Mate-rials for such repairs hall be readily avall-in rtD t-h i IIti..flI c,45S~in

-jttMh~pe Dga~J^,m,#j'r f^mmieel,.,

I W 1

w1

• -%DI

-4III able on site and procedures shall be In effect to Implement such repairs. If such equip-ment and systems used prior to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the fire will not be capable of being powered by both onsite'and offaite electric power systems because of fire damage an independent onsite power system shall be provided. Equipment and systems used after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be powered by offaite power only.

B. Shutdown systems installed to ensure postfire shutdown capability need not be de-signed to meet seismic Category I criteria.

single failure criteria, or other design basis accident criteria, except where required for other reasons. e.g.. because of interface with or Impact on existing safety systems. or be-cause of adverse valve actions due to fire damage.

7. The safe shutdown equipment and sys-tems for each fire area shall be known to be Isolated from associated non-safety circuits In the fire area so that hot shorts, open cir-cuits, or shorts to ground In the associated circuits will not prevent operation of the safe shutdown equipment. The separation and barriers between trays and conduits con-taining associated circuits of one safe shut-down division and trays and conduits con-taining associated circuits or safe shutdown cables from the redundant division, or the isolation of these associated circuits from the safe shutdown equipment, shall be such that a postulated fire Involving associated circuits will not prevent safe shutdown.3 M. Fre barrier cable penetration seal quaff-fIcation. Penetration seal designs must be qualified by tests that are comparable to tests used to rate fire barriers. The accept-ance criteria for the test must include the following:

1. The cable fire barrier penetration seal has withstood the fire endurance test with-out passage of name or gnition of cables on the unexposed side for a period of time equiv-alent to the fire resistance rating required of the barrier:

2. The temperature levels recorded for the unexposed side are analyzed and demonstrate that the maximum temperature Is sufit-clently below the cable insulation ignition:

temperature: and

3. The fire barrier penetration seal remains.

Intact and does not allow projection of water beyond the unexposed surface during the hose stream test.

N.

re doors. Fire doors shall be self-clos-.

ing or provided with closing mechanisms and

'An acceptable. method of complying with this alternative would be to meet Regulatory Guide 1.75 position 4 related to associated circuits and IEEE Std 384-1974 (Section 4.5) where trays from redundant safety divisions are so protected that postulated fires affect trays from only one safety division.

1 1~

.4i 1-lvu-n tO vu.*S*l 5 s

shall be inspected semiannually to verify that automatic hold-opeh, release, and clos-Irg mechanisms and latches are operable.

One of the following measures shall be pro-vided to ensure they will protect the opening u required In case of fire:

1. Fire doors shall be kept closed and elec-trically supervised at a continuously manned location;

2. Fire doors shall be locked closed and In-spected weekly to verify that the doors are In the closed position;

.3. Fire doors shall be provided with auto-natic hold-open and release mechanisms and Inspected daily to verify that doorways are free of obstructions; or

4. Fire doors shall be kept closed and in-spected daily to verify that they are In the closed position.

The fire brigade leader shall have ready ac-cs to keys for any locked fire doors.

Areas protected by automatic total flood-Ing gas suppression systems shall have elec-trically supervised self-closing fire doors or shall satisfy option above.

0. Oil collection system for reactor coolant pump. The reactor coolant pump shall be equipped with an oil collection system If the containment Is not nerted during normal eperation. The oil collection system shall be so designed, engineered, and Installed that fllure will not lead to fire during normal or design basis accident conditions and that there Is reasonable assurance that the ys-tem will withstand the Safe Shutdown Earthquake.'

Such collection systems shall be capable of

. ollecting lube oil from all potential pressur-

id and unpressurized leakage sites in the reactor coolant pump lube oil systems. Leak-

)iae shall be collected and drained to a vent-

.ed closed container that can hold the entire

• lbe oil system Inventory. A flame arrester

,i, required in the vent if the flash point characteristics of the oil present the hazard Of fire flashback. Leakage points to be pro-tected shall Include lift pump and piping, Overflow lines, lube oil cooler, oi fill and I&Sn lines and plugs. nanged connections on il lines, and lube oil reservoirs where such features exist on the reactor coolant pumps.

the drain line shall be large enough to ac-tcommodate the largest potential oil leak.

isFR 76611, Nov. 19. 1980; 46 FR 44735, Sept.

I, 1981, as amended at 53 FR 19251, May 27, tiXIsi 65 FR 38191, June 20, 2000]

4See Regulatory Guide 1.29-"Seismic De-sign Classification" paragraph C.2.

PT. 50, App. S APPENDIX S TO PART 50-EARTI[QUAKE ENGINEERING CRITERIA FOR NU-CLEAR POWER PLANTS GENERAL INFORMATION This appendix applies to applicants for a design certification or combined license pur-suant to part 52 of this chapter or a con-struction permit or operating license pursu-ant to part 50 of this chapter on or after Jan-uary 10, 1997. However, for either an oper-ating license applicant or holder whose con-struction permit was Issued prior to January 10, 1997, the earthquake engineering criteria In Section VI of appendix A to 10 CFR part 100 continues to apply.

I. INTRODUCTION (a) Each applicant for a construction per-mit, operating license, design certification, or combined license is required by 550.34 (a)(12), (b)(10). and General Design Criterion 2 of appendix A to this part to design nuclear power plant structures, systems, and compo-nents mportant to safety to withstand the effects of natural phenomena, such as earth-quakes, without loss of capability to perform their safety functions. Also, as specified in 550.54(ff), nuclear power plants that have Im-plemented the earthquake engineering cri-teria described herein must shut down if the criteria In Paragraph IV(a)(3) of this appen-dix are exceeded.

(b) These criteria implement General De-sign Criterion 2 insofar as It requires struc-tures. systems, and components Important to safety to withstand the effects of earth-quakes.

II. SCOPE The evaluations described In this appendix are within the scope of investigations per-mitted by f 50.10(c)(l).

III. DEFINITIONS As used in these criteria:

Combined license means a combined con-struction permit and operating license with conditions for a nuclear power facility Issued pursuant to subpart C of part 52 of this chap-ter.

Design Certiflcation means a Commission approval, issued pursuant to subpart B of part 52 of this chapter, of a standard design for a nuclear power facility. A design so ap-proved may be referred to as a "certified standard design."

The Operating Basis Earthquake Ground Mo-tion (ORE) Is the vibratory ground motion for which those features of the nuclear power plant necessary for continued operation without undue risk to the health and safety

WAIS Document Retreval http:I/frwebgateaccess.gpo.gov/cgi-bin/get-c

[Code of Federal Regulations]

[Title 10, Volume 1]

[Revised as of January 1,2001]

From the U.S. Government Printing Office via GPO Access

[CITE: 10CFR50.48]

[Page 713-714]

TITLE 10--ENERGY CHAPTER I--NUCLEAR REGULATORY COMMISSION PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES--Table of Content; Sec. 50.48 Fire protection.

(a) (1) Each operating nuclear power plant must have a fire protection plan that satisfies Criterion 3 of appendix A to this part.

This fire protection plan must:

(i) Describe the overall fire protection program fr the facility; (ii)

Identify the various positions within the licensee's organization that are responsible for the program; (iii)

State the authorities that are delegated to each of these positions to implement those responsibilities; and (iv)

Outline the plans for fire protection, fire detection and suppression capability, and limitation of fire damage.

(2)

The plan must also describe specific features necessary to implement the program described in paragraph (a) (1) of this section such as--

(i) Administrative controls and personnel requirements for fire prevention and manual fire suppression activities; (ii)

Automatic and manually operated fire detection and suppression systems; and (iii)

The means to limit fire damage to structures, systems, or components

((Page 714))

important to safety so that the capability to shut down the plant safely is ensured.

(3)

The licensee shall retain the fire protection plan and each change to the plan as a record until the Commission terminates the reactor license. The licensee shall retain each superseded revision of the procedures for 3 years from the date it was superseded.

(b) Appendix R to this part establishes fire protection features required to satisfy Criterion 3 of appendix A to this part with respect to certain generic issues for nuclear power plants licensed to operate before January 1, 1979.

(1) Except for the requirements of Sections III.G, III.J, and III.0, the provisions of Appendix R to this part do not apply to nuclear power plants licensed to operate before January 1, 1979, to the extent that--

(i) Fire protection features proposed or implemented by the licensee have been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch Technical Position (BTP)

APCSB 9.5-1 reflected in NRC fire protection safety evaluation reports issued before the effective date of February 19, 1981; or (ii)

Fire protection features w,4 accepted by the NRC staff in comprehensive fire protection safety evaluation reports issued before Appendix A to Branch Technical Position (BTP)

APCSB 9.5-1 was published in August 1976.

(2)

With respect to all other fire protection features covered by Appendix R all nuclear power plants licensed to operate before January 1,

1979, must satisfy the applicable requirements of Appendix R to this part, including specifically the requirements of Sections III.G, III.J, and III.O.

I