ML19320A429

Tech Specs 1.0-3.21 Re Fire Protection

ML19320A429
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/28/1977
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19320A425	List: ML19320A424 ML19320A429 ML19320A430
References
NUDOCS 8005050431
Download: ML19320A429 (34)

Text

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- TABLE OF CONTOi?S PAGE SECTION TITLE 1

- 1.

DEFINITICNS 1

1.1 RATED PCwCR 1

1.2 REACOR CPE!L\\ TING CD::DITIONS 2

,1.3 OPERA 31.E 2

1.4 PROTECTION INSTRU>lE.TATION LCG1C 3

1.S INSTRIMENTATION 5UTNEILLN:C3 4

1.6 QUADMNT POWER TILT' 4

1.7 REACTOR SUILDING 5

j 1.8 FIRE SUPPRESSION WATER SYSTEM 7

SAFETI LDtITS M;D LIMITING S. FETY SYSTE! SETTING 5 2.

7 2.1 SAFETY LD11T5, REACTOR CJRE 10 SAFETY LDIITS, REACTOR SYSTE't PRESSURE 2.2 LIMITING SAFETY SYSTS! SETTINGS, PROTECTIVE INSUU-2.3 11 MENTATION 16 LIMITING CONDITIONS FOR OPEMTION 3.

16 3.1 REACOR CCOLAAT SYSTRt 16 3.1.1 Operationsi Cearenents Pressurt:st.cn. nesta and Cooldewn Limitations 18 3.1.2 21 3.1.3 Minimu= Condit:.ons for Criticality 22 3.1.4 Reactor Coolant Systen Ac :vity 25 3.1.S Chem serv 27 3.1.6 Leakage Moderator Te=rerature Coefficient of Reactivity 30 3.1.7 3.1.8 Low Power inysics Testing Restrict :ns 3;

32 3.1.9 Control Roc coeration 34 3.2 MAKEUP ASD ChStICAL ADDITION SYSTE!S DIERGENCY CORE CCOLING, REACOR BUILDING COOLING, 3.3 36 AND REACTOR BUILDING SPRAY SYSTDiS 40 3.4 STE.Cl AND pct:ER CO:NERSICN SYSTDI 42 3.5 INSTRU>2NTATION SYSTE!S 3.5.1 Coerational Safety Instrumentation 42 Control Roc Grous anc ? wer Dist :cution Limits 46 3.S.2 49 3.5.3 Safety Features Actuation system Setroints 51 3.5.4 In-Core Instru:entatten 53d l'

react 0R SUILDINu, INSTRUMENTATION 3.5.5 FIRE DETECTION S4 3.6 S6 3.7 AUXILIARY ELEC5 1 CAL SYSTBt 58 3.8 FUEL LOADING AND REFUELING CONTROL RCO>t DtERGENCY AIR CONDITIONING SYSTDI 60 3.9 66 3.10 SECONDARY SYSTCt ACTIVITY 66a 3.11 E!ERGENCY COOLING POND 3.12 MISCELL\\NEOUS RADI0 ACTIVE R\\TERIALS SCURCES 66b 66c 3.13 PENETRATION ROCSI VENTILATICN SYSTEL 66e 3.14 HYDROGEN PURGE SYSTDI 3.15 FUEL ILUDLING AREA VENTI 1ATICN SYSTDI 66g 3.16 SHOCK SUFFRESSORS (SNUBBERS) 661 3.17 FIRE SUPPRESSION WATER SYSTEM 66m 3.18 '

CABLE SPREADING ROOM SPRINKLER SYSTEM 3.19 CONTROL ROOM HALON SYSTEN 3,20 FIRE HOSE STATIONS 3.21 PENETRATION FIRE BARRIERS J

klendment No. 23, j

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PAGE S'CTION TITLE

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SURVEII.I.ANCC P.ECUIRE!F.TS 67 4.1 OPERAT10:.AL.i.ai+.TY 17515 76 REACOR COOLANT SYSTDI SURVEILL\\NCE 4,2 78 REAGOR COOLANT SYSTDI ILTEGR!iY FOLLOWING E'.TRY 4.3 79 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Lenk ce Tes:

SS 4.4.2 5tructural Integrity 4.5 DERGENCY CORI. CSOLI:5 S'/STE't AND REACOR BUILDING 92 CDOLING SYSTE!! PERIODIC TESTING 92 4.5.1 Emergenev Core Ceolint S.ste:

95 4.5.2 Reactor Eutidinz Coc int 5. s c.ms 200 4.6 AUXILIARY ELECTRICAL 5Y5TE! TESTS 102 4.7 REACTOR CONTFOL ROL SYSTE'l ESTS 102 4.7.1 Control Red Drive System Functions! Tests 104 4.7.2 Control Rod P:ct;x.'vertitca ton 105 4.8 EMERGENCY FEEWATEA PU'l? TESTING 106 4.9 REACTIVITY ANom LIES CONTROL R0051 D'ERGENCY AIR CONDITIONING SYSTDI 4.10 107 SURVEILLANCE PENETP.ATION R00't VENTILATICN SYSTDi SURVEILLANCE 109 4.11 109b 4.12 HYDROCEN PURGP SYSTEM SURVEILLANCE 110a 4.13 DERGENCY CGOLING POND 110b 4.14 RADIOACTIVE MA;ERIA1.5 SOURCES SURVEILLANCE AUGifENTED INSERVICE INSPECTION PROGRMt FOR HICH 4.15 110e ENERGY LINES OUTSIDE OF CCNTAISMENT 110e 4.16

$ ROCK SUPPRESSORS (SNUBBERS) 110e 4.16.1 Hydraulic Shock Suporessors FUEL HANDLING AAEA VESTILATION SYSTDI SURVEILLANCE110r.

4.17 4.18 STEAM GENERATOR TUBING SURVEILIANCE 110j 4.19 FIRE DETECTION INSTRUMENTATION 110p 4.20 FIRE SUPPRESSION WATER SYSTm 4.21 CABLE SPREADING ROOM SPRINKLER SYSTm 4.22 CONTROL R0m HALON SYSTm 4.23 FIRE HOSE STATIONS 4.24 PENETRATION FIRE BARRIERS 111 5.

DESIGN FEAT 1JRES 111 S.1 SITE 112 S.2 REACTOR SUILDING

' l 114 S.3 REACTOR S.4 NEW AND SPENT FUCL STORAGE FACILITIES 116 117 6.

ADMINISTRATIVE CCNTROLS 117 6.1 RESP 0h516IL1TY 117 6.2 PLANT STAFF ORGANIZATION 118

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6.3 QUALITICATIONS i

121 6.4 REVIEN AND AUDIT 6.5 ACTION TO BE TA.U.N IN THE EVENT OF A REPORTABLE OCCUR.RENCE DESCRISED IN TECHNICAL SPECIFICATION 127 6.22 3 2 123 ACION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 6.6 129 6.7

PLANT CPERATING PROCEDURES RADIATION AliD RESPIRATORY PROTECTION PROGR#1 130 6.S 136 CM RC. *;CY PLANNING 0.9 137 6.10 INDUSiTIAL SECURITY PRCCPXI 133 6.11 RECWO! RETEM ICN 140 6.12 PLA;.T REPORTING RIQUIREMENT3

'Amendnerit No. 23, 74 fi I

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1.7 REACTOR BUILDING Reactor building integrity exists when the following conditions are satisfied:

The equipment hatch is closed and sealed and both doors of the a.

personnel lock and emergency lock are closed and sealed, or b.

below.

b.

At least oz.e door on each of the personnel lock and emergency lock is closed and sealed during personnel access or repair.

All non-automatic reactor, building isolation valves and blind c.

flanges are closed as required.

d.

All autc=atic reactor builling isolation valves are operable or deactivated in the closed positicn.

The reactor building leakage determined at the last testing e.

interval satisfies Specificatien L.4.1 1.8 FIRE SUPPRESSION WATER SYSTDi The fire suppression water system consists of: water sources, pumps, and distribution piping with associated sectionalizing isolation valves.

Such valves. include yard hydrant valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe, or spray system riser.

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INCORE INSTRUMENTATICN SPECIFICATIO:3 ARKANSAS P0h'ER & LIGHT CO.

FIG. I:0.

ARF /JISAS I;UCLD.R ONE-UNIT 1 3.5.4-3 r

53c Anendment ?!o.

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o 3.5.5 Fire Detection Instrumentation Applicability This specification applies to fire detection instrumentation utilized within fire areas containing redundant safety related equipment or circuitry for the purposes.of protecting that redundant safety related equipment or circuitry.

Objective To provide immediate initiation of protection and notification of fires in areas where there exists a potential for a fire to disable redundant trains of safety related systems.

Specification 3.5.5.1 A minimum of three main control room heat detectors, two auxiliary control room ceiling heat detectors aad one auxiliary control room floor heat detector shall be operable.

3.5.5.2 If less than three main control room heat detectors, two auxiliary control room ceiling heat detectors and.one auxiliary control room floor heat detector are operable, within one hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour and restore the equipment to operable status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.12.3.1(b) within the next 30 days out-lining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to operable status.

i Bases l

The control room heat detectors initiate fire protection and that initiation provides alams that notify the operators of the existence of a fire in its early stages. Redundant safety related circuitry is located within the control room. No other areas in the plant meet these applicability criteria.

The heat detectors required to be operable in the various areas represent 1/2 of those installed to actuate each of 3 separate Halon systems, one in the main control room, one in the auxiliary control room ceiling and one in the auxiliary control room floor. Any single heat detector can actuate its respective system.

Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is requred in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establisinent of frequent fire patrols in the affected areas is required to provide" detection capability until the inoperable instrumentation is restored to operability.

Amendment No.-

53d

o 3.6 REACTCR BUILDING Applicability Applies to the integrity of the reactor building.

Objective To assure reactor building integrity.

Speci fi cation 3.6~.1 Reactor building integrity shall be maintained whencver all three (3) of the following conditions exist:

f a.

Reactor coolant _ pressure is 300 psig or greater.

b.

Reactor coolant terperature is 200 F or greater.

c.

Nuclear fuel is in the core.

3.6.2 Reactor building integrity shall be maintained when the reactor coolant system is open to the reactor building atmosphere and the requirements fo'r a refueling shutdown are not met.

3.6.3 Positive reactivity insertions which would result in the reactor

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being suberitical by less than 1% Ak/k shall not be made by corat2ol rod motion or boron dilution whenever reactor building integrity is not in force.

3.6.h The reactor shall not be taken critical or remain critical if the reactor building internal pressure exceeds 3.0 psig or a vacuum of 5.5 inches Hg.

3.6.5 Prior to criticality following a refueling shutdown, a check shall be made to confirm that all manual reactor building isolation valves which should be c1csed are closed and locked, as required.

3.6.6 If, while the reactor is critical, a reactor building isolation valve is determined to be incperable in a position other than the closed position, the other reaclor building isolation valve (except for check valves) in the line shall be tested to insure operability.

'If the inoperable valve is not restored within 48 h6urs, the reactor shall be brought to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the operable valve will be closed.

Bases The reactor coolant system conditions of cold shutdown assure that no stean vill be forced and hence there will be no pressure buildup in the reactor building if the reactor coolant system ruptures.

Sb Anendment No.

3

• 3.17. Ftrh ~ Suppression Water' Systen Applicability This specification applies to the portions of the fire suppression water system necessary to provide fire protection to safety related equipment.

Objective To assure that fire suppression is available to redundant safety related equipment which is located in a common area and prvided with fire protection.

Specification 3.17.1 The fire suppression water system shall be operable at all times with two high pressure pumps, each with a capacity of at least 2500 GPM, with their discharges aligned to the fire suppression header, and with an operable flow path capable of transferring water through distribution piping with operable sectionalizing control or isolation valves to the yard hydrant curb valves and the front valve ahead of the water flow alarm device on each sprinkler, hose standpipe, or spray system riser.

3.17.2 With one pump inoperable, restore the inoperable equipment to operable status within seven days or prepare and submit a Special Report to the Commission pursuant to Specification 6.12.3.l(b) within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

3.17.3 With the fire suppression water system inoperable:

a.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and b.

Submit a Special Report in accordance with Specification 6.12.3.l(b):

1)

By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and ii)

In writing within 14 days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status, If a. above cannot be fulfilled, place the reactor in Hot Standby c.

within the next hour and in Cold Shutdown within the following thirty (30) hours.

Bases The fire pumps supply the only source of water for all fire suppression systec.:s utilizing water. Each pump is individually capable of providing full flow required for proper fire suppression water system operation. The pumps start automatically on low system pressure, in the event that the fire suppression water systen becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the plant.

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j 66m

3.18 Cable Spreading Rcom Sprinkler System Applicability This specification applies to the fire suppression sprinkler system located in the cable spreading room.

Objective To assure that fire suppression is available to safety-related cables located in the cable spreading room.

Specification 3.18.1 The cable spreading room sprinkler system shall be operable at all times.

3.18.2 With the cable spreading roon sprinkler system inoperable, establish a continuous fire watch with backup fire suppression equipnent for the cable spreading room within one hour. Restore the system to operable status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.12.3.l(b) within the next 30 days outlining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the system to operable status.

Bases Redundant safety related circuitry located in the cable spreading room is protected by a wet pipe sprinkler system. The operability of this system ensures that adequate fire suppression capability is available to confine and extinguish a fire occurring in the caple spreading room.

In the event

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this system is inoperable, alternate backup fire fighting equipment is required to be made available until the inoperable equipment is restored to service.

Anendnent No.

66n l

3.19 Control Room Halon System Applicability This specification applies to the Halon system utilized as the fire suppression system for the control room.

Objectiv,e To assure that fire suppression is available to the safety related equipment in the control romn.

Specification 3.19.1 The cot. trol room Halon system shall be operable at all times with the storade tanks having at least 95% of full charge weight and 90%

of full charge pressure.

3.19.2 With the control room Halon system inoperable, establish a continuous fire watch with backup fire suppression equipnent for the control room within one hour. Restore the system to operable status within 14 nays or prepare and submit a Special Report to the Commission pursuant to Specification 6.12.3.l(b) within 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.

Bases Redundsat safety related circuitry located in portions of the control room is

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protected by the Halon system. The operability of this system ensures that adequate fire suppression capability is available to confine and extinguish a fire occuring in the control room.

In the event that this system is inoperable, alternate backup fire fighting equipnent is required to be made available in the control room until the inoperable equipment is restored to service.

Anendnent No.

66o

3.20 Fire Hose Stations Applicability This specification applies to fire hose stations located in areas containing safety relatea equipment.

Objective To assure that manua.1 fire suppression capability is available to all safety related equipment.

Specification 3.20.1 All fire hose stations in areas containir.g safety related eoutpment i

shall be operable whenever the equipment in these areas is required to be operable.

3.20.2 With one or more of the fire hose stations of 3.20.1 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an operable hose station within one hour.

Bases The operabilf t," of the fire hose stations adds additional assurance that adecuate fire suppressic' capability is available to confine and extinguish fires occurring in any cortion of the facility where safety-related equipment is S:ated.

In the event that portions of this system are inoperable, backup fire hose equipment is required to be made available in the affected area (s) until the inoperable equipment is restored to service.

Amendment No.

66p

3.21 Penetration Fire Barriers Applicability This specification applies to penetration fire barriers relied on for restriction of fire damage such that safety-related equipment in areas other than the main fire area are not affected.

Q;'Lective To assure that penetration fire barriers protecting safety-related areas perform their separation function.

Specification 3.21.1 All penetration fire barriers protecting safety related areas shall be functional at all times.

3.21.2 With one or more of the required penetration fire varriers non-functional, estabitsh a continuous fire watch on at least one side of the affected penetration within one hour.

Bases The functional' integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the fact 11ty. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguis hment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

e Anendment No.

66q

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4.19 FireDetectiot Instrumentation Applicability -

Applies to surveillance of fire detection instrumentation requirid operable by Specification 3.5,5 Objective To assure that the fire detection instrumentation required operable by Specification 3.5.5 is available and operable when needed.

Specification 4.19.1 Each required fire detection instruments shall be denonstrated operable at least once per six months by performance of a channel functional test.

4.19.2 The NFPA Code 72D Class A supervised circuits supervision associated with the detector alarms of each required fire detection instruments shall be demonstrated operable at lear.t once per six months.

4.19.3 The non-supervised circuits between the local panels in Specification 4.19.2 and the control room shall be demonstrated operable at least once per 31 days.

Bases These required demonstrations will assure operability of the fire detection instrumentation.

Amendment No, 110p

4.20 Fire Suppression Water System Appitcability Appifes to surveillance of fire protection equipnent required operable by Specification 3.17.

Objective To assure that the applicable fire protection equipment is available and operable when needed.

Specification 4.20.1 The fire protection water'systen shall be demonstrated operable:

a.

At least once per 31 days on a staggered test basis by starting each pump by automatic actuation and operating it for 15 minutes with flow through the relief line; b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position; c.

At least once per six months by performance of a system flush; d.

At least once per 12 months by cycling each testable valve in the flow path through at least once complete cycle of full trave!;

e.

At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating secuence, and:

1) Verifying that each automatic valve in the flow path actuates to its correct position on a low pressure test signal;

2) Verifying that each pump develops at least 2500 GPM at a discharge pressure of 125 psi;

3) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel; and

4) Verifying that each high pressure pump starts (sequentially) to maintain the fire rappression water system pressure > 85 psig.

f.

At least once per three years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook,14th Edition, published by the National Fire Protection Association.

Amendment No.

110q 4

n 4.20.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying;

1) The fuel storage day tank contains at least 105 gallons of fuel, and

2) The diesel starts from ambient conditions and operates for at least 20 minutes, b.

At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance wtih ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM-0975-74 with respect to viscosity, water content and sediment.

c.

At least once per 18 months, during shutdown, by:

1) Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction.with its manufacturer's recommendations for the class of service, and

2) Verifying the diesel starts from ambient conditions on the auto-start signal and operates for > 20 minutes while loaded with the fire pump.

The fire pump diesel starting 24-volt battery bank and charger shal 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 gravity 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 indicattor, of physical damage or abnonnal deteriora-tion, and

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

Amendnent No.

110r 4

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Bases These required demonstrations, tests, and verifications will assure the availabtitty of the fire suppression water system.when it is needed, The intention of 4.20,1 a is to test each fire pump (not including the jockey pump) and the automatic starting logic, This can be accomplished by allowing the fire system pressure to drop to the automatic start setpoint.

The pump will then start and discharge through the relfef line until stopped by the operator.

For purposes of the annual system main flush, the system main consists of lire KE-1-12,

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Amenhent No.

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4.21 Cable Spreading Room Sprinkler System Applicability Applies to surveillance of the cable spreading room sprinkler system, which is required to be operable by Specification 3.18.

l Objective To assure that the cable spreading room sprinkler system is available and operable when needed.

Specification 4.21.1 The cable spreading room sprinkler system shall be demonstrated operable:

a.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel; b.

At least once per 18 months by inspection of the spray headers to verify their integrity.

Bases The cable spreading room sprinkler system is a wet pipe system actuated only by heat action on the fusible head sprinkler. The only maintainable aspect of the system is the verification of system alignment.

The' required inspections will assure availability of the cable spreading room sprinkler system when it is needed.

Anendnent No.

110t 4

4.22 Control Room Halon System App' ica bility Applies to surveillance of the control room Halon system, which is required to be operable by Specification 3.19 Objective To assure that the control room Halon system is available and operable when needed.

Specification 4.22.1 The control room Halon system shall be demonstrated operable:

a.

At least once per 6 months by verifying Halon storage tank weight and pressure; b.

At least once per 18 months by:

1) Verifying the system, including associated ventilation dampers, actuates manually and automatically (upon receipt of a simu-lated test signal), and

2) Performance of a flow test through headers and nozzles to assure no blockage.

Bases Performance of the testing required by these specifications will assure that the Control Room Halon system is operable when needed.

Amendment No.

110u

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,s 4.23 Fire Hose Stations Appifcability Applies to those fire hose stations in safety-related areas, which are required to be operable by Specification 3.20.

Objective To assure that 'the fire ' hose stations in safety-related areas are operable to provide manual fire suppression capability when needed.

Specification 4.23.1 Each of the fire hose stations in safety-related areas shall be demon-strated operable:

a.

At least once per 31 days by visual inspection of the station to assure all required equipment is at the station; b.

At least once per 18 months by:

1) Removing the hose for inspection and re-racking; and

2) Replacement of all degraded gaskets in couplings.

c.

At least once per 3 years. by:

1) Partially opening each hose station valve to verify valve operability and no flow blockage.

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

Bases The required inspections and test will assure that fire hose stations serving safety-related areas are mai-'ained operable and ready for use when needed.

Amendment No.

110v t

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4.24 Penetration Fire Barriers Applicability Applies to surveillance of the penetration barriers required functional by Specification 3.21.

-Objective To assure that significant barrier degradation is detected and corrected.

Specification 4.24.1 Each of the penetration fire barriers protect 1ag safety-related areas shall be verified to be functional by a visual inspection; a.

At least once per 18 months, and J

b.

Prior to declaring a penetration fire barrier functional following repairs or maintenance.

Bases The visual inspection will detect cracking, spalling, etc. that may degrade the functionability of the barrier. Degraded barriers will be corrected per Specification 3.21.

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Amendment No.

110w i1

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6.0 ADMINISTRATIVE wNTROLS_

6.1 RESPONSIBILITY 6.1.1 The Superintendent of Power Plant sh 11 be responsible for overall i

facility operation.

In his absence, the Assistant Superintendent of Power Plant shall assume all responsibility and perfom all duties of the Superintendent of Power Plant.

If both the Super-intendent of Power Plant and his assistant are absent, these respon-sibilities and duties are assumed by the Supervisor of Plant Operations followed by the Technical Support Engineer, t.1 ORGANIZATION OFFSITE The of,fsite organi:stion for facility management and technical 6.2.1 support shall be as shown on Figure 6.2-1.

i FACILIW STAFF The Facility organi:stion shall be as shown on Figure 6.2-2A and 6.2.2 6.2-2B and each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.

6.3 FACILIU STAFF QUALIFICATIONS Each member of the facility staff shall meet or exceed the minimer 6.3.1 qualifications of ASSI N18.1-1971 for comparable position, excep-for the licalth Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING A retraining and replacement training program for the facility 6.4.1 staff shall be maintained under the direction of the Supervisor of Plant Operations and shall meet or exceed the requirements l

and recomendations of Section 5.S of ANSI N18.1-1971 and Appendix

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"A" of 10 CFR Part SS.

i 6.4.2 A training program for the Fire Brigade shall be maintained under the

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director of the Supervisor of Plant Operations and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.

6.S REVIEW AND AUDIT 6.S.1 Plant Safety Committee (PSC) Function 6.S.1.1. The Plant Safety Committee shall function to advise the Super-intendent of Power Plant on all matters related to nuclear safety.

COMPOSITION 6.S.1.2 The Plant Safety Committee shall be composed of the:

j Amendment No. M,

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TABLE 6.2-1 4

ARKANSAS NUCLEAR ONE MINIMLSI SilIFT CREW COMPOSITION #

UNIT 1 i

COLD AND REFUELING LICENSE CATEGORY ABOVE COLD S!!UTDOWN SHUTDOWNS 1

1*

SOL 2

1 OL 2

NON-LICENSED

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited te Fuel llandling, supervising refueling operations after the initial fuel loading.

8 Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Tab le 6. 2 - 1.

Additional Requirements:

1.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

At least two licensed Operators shall be present in the control 2,

room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

An individual qualified in radiation protection procedures shall

- I 3.

be on site when fuel is in the reactor.

All refueling operations after the initial fuel loading shall be 4.

directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no

)

other concurrent responsibilities during this operation.

A Fire Brigade of al least S members shall be maintained onsite at S.

The Fire Brigade shall not include the minimum shift all times.

crew necessary for safe shutdown of the unit (2 members) or any personnel required for other essential functions during a fire emergancy.

Amendment No. 16,

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SENIOR VICE PRESIDENT PRO D.,TR ANS.

g_

8 ENGRG.

SAFETY REVIEW u

CUALITY ASSURANCE COMMITTEE E

COMMITTEE DIRECTOR power PRODUCTION I

1 ASST. OtRECTOR POWER PRODUCTION *

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MANAGER MANAGER MANAGER l

OUAUTY NUCLEAR NUCLEAR ASSURANCE PROJECTS.

FUEL i

LAN S TY SUPERINTENDENT COMMITTEE l,

b

' CORPORATE RESPONSIBILITY FOR FIRE PROTECTION PROGRAM l

ARKANSAS POWER 6 LIGilT CO.st!'ANY MANAGDIENT ORGANIZATION C11 ART ARKANSAS NUCI. EAR ONE - IINIT 1 6.2-1 Amendment fin.M 119 -

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9 SUPERi*iTENDEN T OP POWE9 PLANT CE i

l AS$tSTAMT SUPT OF P0wCR PLANT CE L50 SEE FIGt!RF.

6.2-2B l

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TEC AL s ORT ugg SUPVSR*PLNT 0.PS Q.C. ENGINEER CE LSO I

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• • D'0 " "

CHEW ah EW H. P.

PERFORW ASST.$UPV$R PLT Q.C INSPEC TORS SUPVSR SUPVSR SUPVSR ENGR.

L50' su Pr oPsuPvsR TRAINING C0ORDINATOR Asst.H P.

SUPYSR L80 PLANT OPER

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LO RADIO CLN. LAB.

CHEMISTS CHEW 1373 H. P.'s ASST PLNT OPER I

LO WSTd.

'l CONT.

OPER.

C - Degree or (quivalent Required AUX.

CE Ingineering Degree or fquivalent pecuircJ L50. Senior Opera *or License acquired LO-OperatheLiienseAequired'

• owssis ntsurca.i y ev.: ting emottettom PnoonAM l

ARKANSAS P0hIR G LIGifT CO.

FUNCTIONAL ARKANSAS MJCLEAR ONE-UNIT 1 GRCANI M TION FOR FIGURE PLAAT OPERATION 6.2 2A Amendment No. M) 120 -

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- REVIEW 6.5.2.7 The SRC shall review:

The safety evaluations for 1) changes to procedures, equip-s.

ment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

Proposed changes to procedures, equipment or systems whi:h b.

involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

_c.

. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or licenses, Violations of applicabic statutes, codes, regulations, orders, c.

Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

>l-f.

Significant operating abnormalities or deviations from normal that affect nucitar and espected performance of plant equipment safety.

the Reportable occurrences requ. ring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification a g.

Commission.

h.

Reports and meeting mir.ates of the PSC.

AUDITS Audits of facility activities shall be performed under the 6.5.2.8 cognizance of the SRC. These audits shall encompass:

The conformance of facility operation to all provisions a.

contained within the Technical Specifications and applicabic license conditions at least once per year.

The performance and retraining of all members of the plant b.

management and operations staff, and the performance, training, and qualifications of new members oi the entire plant staff at least once per year.

The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method c.

of operation that affect nuclear safety at least once per six months.

least The Facility Emergency Plan and implementing procedures at d.

once per two years.

The Facility Fire Protection Program and implementing procedures e.

at least once per 24 months.

Amendment l'o 16,

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C.

De F.

11ty Security Plen cnd inplemen--

3 procsdures ct least once per two years.

f.

Any other area of facility operation considered appropriate by the SRC or the Senior Vice President (PT4E) 6.5.2.9 Special Inspections and Audits A.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection finn.

B.

An inspection and audit of the fire protection and loss pre-vention progran shall be performed by a qualified outside fire consultant at least once per 36 months.

AUTHORITY 6.5.2.10 The SRC shall report to and advise the Senior Vice President (PT4E) on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.11 Records of SRC activities shall be prepared, approved and dis-tributed as indicated below:

a.

Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice Pre',ident (PTLE) within 30 days following each meeting.

.b.

Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved and forwarded to the Senior Vice President (PTGF) within 30 days following completion of the review, c.

Audit reports encompassed by Section 6.5.2.8 above, shall ba forwarded to the Senior Vice President sPT6E) and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions sh::11 be tak:

for Reportabic Occurrences:

a.

De Commission shall be notified and/or a report submitted pursuant to the requireme.. 3 of Specification 6.12.

b.

Each Reportable Occurrence requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PSC and submitted to SRC, the Assistant Director, Praer Production by the Superb.

tendent of Power Plant.

6.7 SAFETY LIMIT VIOLATION 6.7.1 ne following actions shall be taken in the event a Safety Limit is violated:

-a.

The facility shall be placed in at least hot shutdown within one hour.

i b.

De Nuclear Regulatory Comnission shall be notified and a j'

report submitted pursuant to the requirements of 10 CFR 50.16 and Specification 6.12.3.1 Anendnent No. E

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s 6.8 PROCEDURES

.6.8.1 Written procedures shall be established, implemented and reintained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33, November,1972.

b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security. Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the Superintendent of Power Plant prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of the original procedure is not altered.

a.

b.

The chcnge is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on +he unit affected.

The change is documented, revieweo by the PSC and approved c.

by the Superintendent of Power Plant within 14 days of implementation.

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