ML19323C781

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Amend 17 to License DPR-6,revising Tech Specs Re Administrative Controls & Fire Detection Sys
ML19323C781
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/06/1978
From: Ziemann D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19323C736 List:
References
FOIA-80-162 NUDOCS 8005190180
Download: ML19323C781 (19)


Text

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O C) 8 00519 0 lyo umnD STAMS NUCLEAR REGULATORY COMMISSION WASHING TON. D C.'0555 CONSUMERS POWER CO'tPAtlY I

DOCKET N9. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO OPEPATING LICENSE Amendment No. 17 License No. DPR-6 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Consumer Power Company (the licensee) dated October 28, 1977, as amended by letter dated December 15, 1977, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, f

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2.

.sccordingly, the license is amended by changes to the Technical 3pecifications as indicated in the attachment to this license a nendment and paragraph 2.C(2) of Facility License No. DPR-6 is hereby amended to read as follows:

(2) Technical Specificatir;ns The Technical Specifications contained in Appendix A, as revised througn Amendment No.17, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective 30 days after its date of issuance.

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l FOR THE NUCLEAR REGULATORY COMMISSION s

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,Lin>s m Dennis L. Ziema

, Chief Operating Reactors Branch #2 Division of. Operating Reactors f

Attachment:

Changes to the Technical Specifications Date of Issuance: March 6,1978 t

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1 ATTACH"ENT TO LICENSE At'E!D"EfiT fM.17 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50 155 The following changes r..te to the Appendix A portion of the Big Rock Technical Specifications.

The changed areas on the revised pages are shown by a aarginal line.

Remove Pages_

Insert Pages iv iv 10-1 10-1 10-2(Figure 6.2-1) 10-2 (Figure 6.2-1) 10-3 (Figure 6.2-2) 10-3 (Figure 6.2-2) 10-5 10-5 10-10 10-10 10-20 10-20 12-1 (new) 12-2 (new) 12-3 (new) 12-4 (new) 12-5 (new) 12-6 (new) 12-7 (new) 12-8 (new) r s

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  • e CONIENTS (Contd)

Fage !;o'.

6.5.1 Plant Review Commit tee (PRC)......................

10-5 6.5.2 Safety and Audit Review Board (SARB).

10-7 6.6 Reportable Occurrenes Action..............................

10-11 6.7 Saf ety Limit Vio'.ation.

10-11 6.8 Procedures.

10-11 6.9 Reporting Rer,uirements.

10-12 6.10 Record Reter. tion.

10-20 6.11 Radiation Protection Program.

10-22 i

11.0 (Section 3.1.4/4.1.4) Emergency Core Cooling System 11-1 ()

(Section 3.1.5/4.1.5) Reactor _Depressurization System 11-8 (Section 3.3.4/4.3.4) Containme'at Spray System.

11-15 (Section 3.5. 3/4.5. 3) Emergency Power Sources 11-18 12.0 Fire Protection Program (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation 12-1 (Section 3.7.11.1/4.7.11.1) Fire Suppression Water Systen 12-1 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems 12-5 (Section 3.7.11.5/4.7.11.5) Fire llose Stations 12-6 (Section 3.7.12/4.7.12) Penetration Fire narriers.

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Iv Amendment. flo. Jp,17

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)_*.],1 * }....}. y '; 5 CMI. : '111; d.1 RESPO':0~h!LITY 6.1.1 Tae Plaat Superi:.t.endent shall be rcaponsible for overc11 1.lsnt.:peratio:. ca.1 :.hal delecate in writirg the succession to this respor.sfbility during hia absence.

6.2 CRGA';IS.iTIO:t CFFSITE o.2.1 The offsite organization for plant rsnage:: lent and technical support shall be as shown en Figure 6.2-1.

PLAST ST SF d.2.2 The plan orscnization shall be as.shown on Figure 6.2-2 and:

a.

Each on-duty shift shall be composed of at least the minimu:: shift crew cc2po,sitior. shovn in Table 6.2-1.

b.

At least one licensed Operator shall be in the control roo:1 vhen fuel ic in the reactor.

c.- At least two licensed Operators shall be present in the control roon during reacter.startup (to a nower level >5 percent), scheduled reactor shutdown and during recovery fro-. reactor trips.

d.

Aa individual qualified in radiation protection procedures sha!! be on site when t'uel i.

in the reactor, All cora alteratior.s after the initial fuel lo:,diny, r.h::11 cither be periorue.: by a l ina :::.ed e.

Oncrator under the supervision of a licensed Scalor Operater or a non-licer.:.ed 0.erator 1

d'irectly supervised by a licensed Senior Operator (cr a licensed Senior Operator Limited to Fuel Handling) who has no other concurrcnt responsibilities during this operation.

f.

A fire brigade of at least 3 members shall be' maintained on site at all times. This excludes 2 members of the minimum shift cretr necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

6.3 PLA ;T STAFF QUALIFIC.iTIO ;S 6.3.1

_Sch a'.c.b:.r cf the pier.t stcff chd1 ccc-t er c:::cEl

'.c cinire._:. gudifi tiona cf./;i;: :;10. ;-2 ; i_

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6.3.2 Either the *!calth Physi:i st, or the Ch.e:cir.tr.' ar.d ;;:..ll st.ici. Prot.u. i. n a.;.. ni :.

exce+:d '.t:e ;.uili ficat i.on'; of l(epila.ory Giri-le 1.!!, ;i..e

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Consumers Power C,ompany

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OFF-SITE ORGANIZATION PRESIDENT EXECUTIVE VICE PRESIDENT I

EXECUTIVE vlCE PRESIDENT VICE PRESIDENT GENER Al. SERVICES O

SAFETY AND AUDIT i

DIRECTOR OF VICE PRESIDENT REVIEW PROPERTY PROTECTION PRODUCTION & TRANSMI6SION BOARD I

I I

I MANAGER OF MANAGER OF DIRECTOR OTilER PRODUCTION-NUCLEAR MAINT &

ASSURA CE ADM SERVICES pgy PLANT GENERAL SUPT OA C.

SUPERINTENDENTS ADM SEltVICES ADMINISTRATOR (NUCLEAR)

NUCLEAR

  • Responn Hile' for cnreraH M n*

TRAINING

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ADMINISTRATOR FIGURE 6.2-1 10-2 Amendment No. 9, 11, 17

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t Consin cn's I nus:r Coupany BIC itOC. K l'Oltli Organization QA-AD21Ita OFF-SITE PLANT SUPI:RINTENDEK[

Pl.Alli ItEVI Elf.

QA SUPT

_ _ _.! C0!!:llTTEE 1

I PERS0tlNEl.

TECllttICAL Di tt ECTun__

ENGINEEtt g

TRAINING OPEll ATIOllS ADilltilSTRATIVE IIEAl.Til TECilNICAL

!!A l tlTE;IAllCE l00HDINATOR SUPE!tlNTENDENT SiiPERVISOR PilYSICIST SUPEnlllTEllllEllT SitPERlilTEllllE!!T SOI. (a) gge SECURITY CilEli & HAD 32JG friggjt:1 13'M UN U

OR IW SHW TitAINING OPEllA'fl0NS l

C l ti. " t n II*"A" C (NSTRUCTOR SUPI:ltVIS0lt QC d ""I" "

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IIAlilTI:ilAllt:E EtiCIllEER OPEllATORS Q

RI:1 AI13tEll 001, - Senior Operator Ltcensee (s) The Operations Supurinteadent need not hold un 301. patsvided he neeLa Llie other reiluirciuenta or (3.3.1 or these specifications and the pas! Lion of "OpernLionn Supervicor" is filled. Under thesu conditionu, tho Operations Supervisor shall be responsible for directing the activlLies of licenaud operators.

(b) This positio.n need not be filled if thu Operuttons Superintendcat holda an SOL.

  • Rosponsible for overall implementation of the plant i f re Protect ion Pr o ;r.ux.

figure 6.2-2 Amendment No. 9. J7, 17 IM

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6.h TRAINIllG 6.k.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Plant Shperintendent and shall meet or exceed the requirements and reconsucndations of Section 5.5 of AllSI N10.1-1971 and Appendix "A" of 10 CFR, Part 55 6.4.2 A training program f5r the Fire Brigade shall be maintained.under the direction of the P1nnt Training Coordinator and shall acet or exceed the requirements of Section 27 of the NFPA Code-1975 except for Fire Brigade training sessions which shall be held at least quarterly.

6.5 REVIDI AND AUDIT, 6.5.1 PLANT REVIDI CO!CIITTEE (PRC) 6.5 1.1 The Plant Review Committee (PRC) shall function to adiise the Plant Superintendest on all matters related to nuclear safety.

6.5.1.2

_ COMPOSITION The PRC o%11 be composed of the:

Chnirman:

Plant Superintendent Member:

Operations Superintendent Member:

Technical Superintendent

!!cmber:

!!aintenance Superintendent

!!cmber:

Instrument and Control Engineer I!cmber:

Reactor Engineer Member:

' Health Physicist Member:

Shift Supervisor End ncer or Technologist with at Least One-Year. Plant Experience O.

i 11cmber:

6.5 1.3 ALTERNATES Alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; howcVer, no more than two alternates shall participate in PRC activities at any one time.

10-5 Amendment'ilo. P, 17. Il

6.5.2 (c:ntid) h.

The status of deficiencies identified by the Quality Assurance Program, including the effective-ness of the corrective actions completed and Implemented, at least once every six (6) month::.

i. Audits of tne Security Program required by the " Nuclear Power Plant Security Plan."

6.5.2 9 AtmITs Audits of safety-related facility activities during operations are performed by the Quality Assur-ance Department - P&T in accordance with the policies and procedures of the Consumers Power Company Quality Assurance Program.

Quality Assurance audit reports are sent to SARD for review.

In addition.

technical audits ard'.the responsibility of the Operating Services Department an;" shall be reviewed by SARB. These technical audits encompass:

a.

The conformance of facility operation to all provisions contained within the Technical Speelrica-tions and applicable license conditions at least once per year.

b.

The performance, training and qualifications of the entire facility staff at least once per year.

O c.

The facility Site Emergency Plan and implementing procedures at least once per two years.

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d.

Any other area of facility operation considered appropriate by SARD or the Vice President - P&T.

e.

The facility Fire Protection Program and implementing procedures at least once per 2 years.

f.

An independent fire protection and loss prevention inspection and audit shall be performed un-nually utilizing either qualified off-site licensee personnel or an tutside fire protection firm.

g.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

6.5.2.10 AUTlIORITY SARB shall report to and advise the Vice President - P&T on those areas of responsibility specified in 6.5.2.8 cnd 6.5.2.9 6.5.2.11 nl.:Conin Records of SARB activities shall be prepared and distributed as indicated below:

O a.

Minutes of each SARB meeting shall be prepared and forwarded to the Vice President - I%T and each SARB member within fourteen (11) days following each meeting. Minutes shall be approved 4

at or before the next regularly scheduled meeting following distribution of the minutes.

b.

If not included in SARB meeting minutes, reports of reviews encompassed by Section 6.5.2.8 above shall be prepared and forwarded to the Vice President - P&T within' fourteen (11 ) days 4

following completion of the review.

10-10 Amendment No. $,.72, 17

6.9.3 (C:nt'd)

(b)

Total number of samples.

(c)

Number of-locations at which levels are found to be significantly above 1,ocal backgrounds.

(d) lii gh es t, lowest, and the annual average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.

(2)

If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 1% of those that could result from' continuous annual exposure to the concentration values listed in Appendix B Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups an'd assumptions upon which estimates are based shall be provided..

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J (3)

If statistically 'signif'icant variations of offsite environmental concentrations with time are observed, correlation of these results with effluent release shall be provided.

6.9.4 Special Reports Special Reports shall be submitted "to the Director of the appropriate Regional office within the time period specified for each report. "Ihese reports shall be submitted covering the activities identified below pursuant to the requirements of the applicablei technical specification section:

a.

In-service inspection reports.

b.

Fire' system reports.

6.10 RECORD RETENTION O

(Becorda not previously required to be retained shall be retained as required below commencing January 1, 1976.)

6.10.1 The following records shall be retained for at least five yearst Reco'rds and logs of facility operation covering time interval at each.pover level.

,s.

Amendment No. $ 17 10-20 3

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5 yg,9;gc'ENTATION T

I FIRE DETECTION

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_LIMITIS", CO:DI ION FOR CPERATION l

3.3.3.8 As a minimum, the fire detection instrumentation for each fire deccetion zone shown in Table 3.3-8 shall be OPERA 3LE.

i APPLICABILITY: At all times when the equipment in the' area is required to be OPERABLE.

ACTION:

With the nu:ber of instruments OPERABLE less than required by Table 3.3-8; Within one (1) hour, establish a fire vacch patrol to inspect the :one uith a.

the inoperable instrument (s) at least once per hour, and

.b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in ' lieu of any other report required by Spqci-fication 6.9.2, prepare and submit a Special Report to tha i

Co.T. mission pursuant to Specification 6.9.4 within the r. ext 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring.the instrument (s) to OPERABLE status.

_ SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above fire detection instru=ents shall be deconstrated OPERABLE:

Once per six mont}is by a CHANNEL FUNCTIONAL TEST, and a.

b.

Once per 31 days by verifying proper alignment of power sources to the circuits.

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I 12-1 Amendment No. 17

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TABLE 3.3-8 FIRE DETECTION INSTRUMENTS INSTRMENT LOCATION TOTAL MINIMUM INSTRDENTS INSTROENTS OPERABLE HEAT SMOKE 1.

Electrical Eqdipcent Room Zone 1 Elevation 614' 5

3 Zone 2 Elevation 603' 2

1 2.

Exterior Cable Penetration Room Zone 1 Elevation 614' 5-3 3.

Interior Cable ' Penetration Room Zone 1 Elevation 614' 6

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12-2 Amendment No.117

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,n/NT S /sTC45 FIP.E SUPPRESSICN WATER SYSTC4 LIMITING CONDITION FOR OPERATIO'N

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3.7.11.1' THE FIP.E SUPPRESSION WATER SYSTDi SHALL BE OPERABLE WITH:

j

' a.

Both the electric and diesel driven fire pumps each with a capacity of 1000 gpm, their discharge aligned to the fire suppression header and supplying sprinkler t

and hose systems described in 3.7.11.2 and 3.7.11.5.

I b.

Level of the Intake Bay above the 570' elevation.

J c.

Automatic starting of.the pumps on decaying fire system pressure.

APPLICABILITY: At all times.

ACTIONS:

a.

With the Fire Suppression Water System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9.2, prepare and sutmit a Special Report to the Commission pursuant to Specification 6.9.4 within the next 30. days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

b.

Comply with Specification 11.3.1.4D, c.

If both fire pumps (electric and diesel) or the piping systems are inoperable:

1.

Initiate procedures to provide a B'ackup Fire Suppressfon Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by notifying the Charlevoix Fire Department to, standby, and 2.

Restore the inoperable fire pump or piping system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.2, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.4 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the pump or piping system to OPERABLE status.

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A5andmentNo.17 t

SORVEILLANCE RE0VIRD4ENTb 4.7.11.1.1 The FIRE. SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE:

a.

Once per 7 days verifying the Intake Bay water level is above 570' elevation.

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b.

Once per 31 days by starting each pump and operating the electric driven pump for at least five minutes and the diesel pump for at least 30 minutes, c.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM-D975-74 with respect j

to viscosity, water content and sediment.

d.

Once per 18 months:

1.

By a system flush and by verifying that each valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

2.

By performing a system functional test which includes simulated automatic actuation of the s,ystem throughout its operating sequence.

3 By verifying that each pump will develop a flow of at least 1000 gpm at a system head of 110 psi.

4.

Subjecting the diesel to an inspection in accordance with procedures prepared in connection with its manufac-turer's recommendations for the class of service.

e.

Once per 3 years by performing flow tests to meet or exceed the requirements of Section II, Chapter 5 of the Fire Protection Handbook,14th Edition published by National Fire Protection Association.

4.7.11.1.2 The fire pump diesel starting 24-volt hattery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each battery is above the plates, and 2.

The overall battery voltage is > 24 volts, b.

At least once per 92 days by verifying that the specific grcvity is appropriate for continued service of the battery.

c.

At least once per 18 months by verifying that:

1.

The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.-

12-4 Amendment No. 17

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_PUJIT SYSTD!S FIRE SPRAY A**D/OR SP?.INILER SYSTDS g

LIMITIMG CONDITION FOR OPERATION 3.7 11.2 The spray and/or sprinkler syste=s located in the following areas shall be OPERABLE:

Cable spreading area under the control roo:n.

a.

b.

Exterior cable penetration area.

APPLICA3ILIkT: At all times when the equipment in the area is required.

ACTIOUS:

With one or more of the above required spray and/or sprinkler a.

systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.2, prepare and sutrait a Special Report to the Commission pursuant to Specification 6.9.4 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SURVEILLANCE REQUIREMENTS I

4.7.11.2 The spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

a.

Once per 18 months:

1.

By visual inspection of spray headers to verify their integrity.

2.

By visual inspection of each nozzle e.o verify no external blockage.

I b.

Once per 3 years by an airflow test of the open head spray and/or open head sprinkler system and verifying each open j

head spray and/or sprinkler nozzle is unobstructed.

I knendment No. U 12-5 t_

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PL' ANT SYSTE"3 FIRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 3.7.11.5 The fire hose stations in the following locations shall be OPERABLE:

1.

Electrical equipment room.

2.

Emergency condenser level.

l 3.

Equipment lock laydown area.

4 Third floor corridor.

1 5.

Screen house.

APPLICABILITY:

Whenever equipment in the areas protected i'

by the fire hose stations is required to be OPERABLE:

i ACTION:

With a hose station inoperable, provide an additional hose for the unprotected area at an OPERA 3LE hose station within one hour and designate the new hose and I

station as safety related.

SURVEILLANCE REOUIREMENTS 4.7.11.5 Each fire station shall be verified to be OPERABLE:

I a.

Once per 31 days by visual inspection of the station to assure j

all equipment is available at the station.

i b.

Once per 18 moaths by removing the hose for inspection and re-racking and replacing (as required) all gaskets in the couplings, I

that are degraded.

c.

At least once per 3 years by:

i 1.

Partially opening each hose station valve to verify valve OPERABI.LITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station.

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i 12-6 4 Esdaent No. 17

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. b>LANT SYSTEMS 9

I~ I 3/4.7.12 PEliETRATION FIRE BARRIERS I

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I LIMITING CONDITIONS FOR OPERATION 3.7.12 All penetration fire barriers protecting sa'fety related areas shall be functional.

APPLICABLITY: At all times l

ACTION:

With one or more of the above required penetration fire barriers.

a.

I non-functional and with the area of the affected barrier (s) monitored by UPERABLE (pursuant to Specification 3.3.3.8) fire detection instrumentation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol and inspect the affected area (s) at least once per hour.

b.

With one or more of the above required penetration fire barriers non-functional and with the area of the affected barrier (s) not monitored by OPERABLE (pursuant to Specification i

3.3.3.8) fire detection instrumentation, establish a continuous fire watch on at least o..a side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

i SURVEILLANCE REQUIREMENTS I,

l 4.7.12 Each of the above required penetration fire barriers shall be

verified to be functional by a visual inspection; i

ll a.

At least once per 18 months, and i

I, b.

Prior to declaring a penetration fire barrier functional j '

following repairs or maintenance.

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i 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures 'that adequate warriing^ capability is available for the prompt detection of, fires. This capability is required in order to detect and locate fi'res in their early stages.

Prompt detection of fires will reduce the poten-

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tial for damage to safety related equipment and is an integral element in the ovprall facility. fire protection program._

l In the event that a portion of the fire detect ~ ion instrumentation is inoperable, the establishment of frequent fire patrols in the affected.

areas is re. quired to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that' adequate fire suppressi.on capcbility is available to confine and extingui'sh fires occuring in any portion of the facility where safety related equipment is located.. The fire suppression system consists of the water systea*,

spray and/or sprinklers, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required.to be made available in the affected are until the inoperable equipment is restored to service.

In the event the fir'e' sup; ssien water sistem becomes inoperab1'e, f

intnediate corrective measures must be 'talten since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Co~ mission provides for prompt evalua-l tion o.f tha acceptability of the corrective measures to provide adecuate j

fire suppression capability for the continued protection of the nuclear i

plant.

j 3/4.7.12 PENETRATION FIRE BARRIERS i

The functional integrity of.the penetration fire barriers ' ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility, prior to detection and extinguishment.

The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

Y' During periods of time when the barriers are not functional, routine fire watch patrols in cenjunction with OPERABLE fire detection instrumentation or a continuous fire watch are required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

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