ML19326B901
| ML19326B901 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/03/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B899 | List: |
| References | |
| NUDOCS 8004180626 | |
| Download: ML19326B901 (29) | |
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UMTED STATES y*
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS HUCLEAR ONE - UNIT NO. l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Com;:.i.j (the licensee) dated June 16, 1977, as atended by lette; dated January 17, 1978, complies with the standards and reovirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth 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 Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendr.ent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.c(2) of Facility License No. OPR-51 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the dste of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3,1978
ATTACHMENT TO LICENSE AMENDMENT NO. 30 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Accomplish page changes to the Appendix A portion of the Technical Specifications as noted below. The changed areas on the revised pages are identified by a marginal line.
Remove Existing Page Add Revised Page i
i 11 11 5
5 53c 53c*
53d (new) 54 54*
66m (new) 66n (new) 66o (new) 66p (new) 66q (new) 110p (new) 110q (new) 110r (new) 110s (new) 110t (new) 110u (new) 110v (new) 110w (new) 117 117 118 118 119 119 120 120 2
125 1?S 126 126 127 127
- There were no changes on these pages. They are included as a matter of convenience in updating the Technical Specifications.
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TABLE OF CONTESTS PAGE TITLE SECTION_
1
- 1.
DEPINITICNS 1
1.1 AATED pct.ER 1
REACTOR OPEMTING CONDITIC.'.5 2
1.2
- 1. 3 0FERA3LE 2
PROTECTION INST 7.UME'.TATION LCC1C 3
1.4 INSTRU'tENTATION SU".VEILLN:C2 4
1.5 1.6 QUADRANT POWER TILT-4 1.7 REACTD.i JUILDING 5
}
FIRi SUPPRESSION WATER SYSTEM 1.8 7
SAFErf LI; TITS CD LIMITING SAFEU SYSU.! SETTINC5 7
2.
5AFETY LDili5, afACTOR CJRE 10 2.1 SAFETY LDlITS, REACTOR SYSTE't PRESSURE LIMITING SAFETY SYSTO! SETTINGS, PROTECTIVE INSTRU-2.2 11 2.3 HENTATION 16 LDffTING CONDITIONS FCR OPEMTICN 16 3.
REACT 0A CCOLN.T SY5TE 1 16 3.1 0::erations1 Coarenents_
is 3.1.1 Pressurt:st.cn. ne::n and Cool:tewn Lir.itations 21 3.1.2 Minist= Concinens :or Cr: 1 21::v 22 3.1.3 Reactor C:oiant 5vs:en ctiv :y 25 3.1.4 3.1.S Chemis trv 27 Leaka ge 3.1.6
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Moder: tor Te=:ersture Ceefficient of Reactivity 3.1.7 3.1.8 Low Power invsics Tes tir.e aestrien:.s_
32 3.1.9 Control Roc Goera: ten 34 MKEUP A.ND CbDlICAL.CDITION SYSTE !S 3.2 DIERGENCY COM CCOLING, REAC OR SUILDING COOLING, 36 3.3 AND MACTOR BUILDING SPRAY SYS TDiS 40 STE.Ol AND PC'.1ER CONVE.MICN SYSTDI 42 3.4 INSTTEENTATION SYSTE!S 42 3.5 Coerations1 Safetv Ins t r=enta tion 3.5.1 Control noa Groco anc icwer 01stnaution Limits 46 3.5.2 Secroints 49 Satety Features Actuatten syste 3.5.3 51 3.5.4 In-Core Instru:entation 53d l
3.5.5 ppe DETECTIOM, INSTRUMENTATION S4 3.6 REAi )R SUILDING S6 AGILIARY ELECTRICAL SYSTS!
58 3.7 FUEL IDADING AND REFUELING 3.8 60 CONTROL RCOM BtERGENCY AIR CONDITIONING SYSTDI 66 3.9 SI!CONDARY SYSTCl ACTIVITY 66a 3.10 DtERGENCY CCOLING POND 66b 3.11 MISCELL\\NEOUS RADIDACTIVE %\\TERIALS SCURCES 66c 3.12 PESETMTION RCCM VENTILATICN SYSTDI 3.13 66e HYD3CGEN PURGE SYSTDI 3.14 66g FUEL l').NDLING AREA VENT!1ATICN SYSTDI 3.15 3.16 SHOCK SL7FRESSORS (SNUBBERS) 661 FIRE SUPPRESSION WATER SYSTEM 66m 3.17 FIRE SUPPRESSION SPRINKLER SYSTDIS 66n CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON 3.18 660 3.19 66p FIRE HOSE STATIONS 3.20 PENETRATION FIRE BARRIERS 66q 3.21 klendment No. gJ, 30 9
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PACE SECT 104 TITLE _
67 SURVUII.LANCC PFCUIRE!!!'TTS 67 4.
~ OFr.MTIC:.AL 4Mr.iY i! EMS 76 4.1 REACTOR COOLANT SYSTEl SurVEI'.LMCO 78 REACT 03 CCOLANT SYSTSt II.TEGRIiY FOLL0t!!.NG E'."TRY 4.2 79 4,3 REACTOR BUILDING 79 4.4 Reactor Building Leak:ce Tes:
85 4.4.1 S~t m etursl Integrity EMERGE.NCY CCar. C00LI:.G S'.'STE'! AND RSAC OR BUILDIS 4.4.2 92 4.S CDOLING SYSTE!! PERIODIC TESTING 92 Emergenev Core Ccoling Syste.
95 4.S.1
_Reacter 2ninnr coeu:.e S.s:er.s_
100 4.S.2 ELECTRICAL S u iE'1 T35T3 4.6 AUXILIARY 102 REACTOR CONTRO*. RO, SYSTI'! T"5TS 102 4.7 Control Red Drive Systen Functions! Tests 104 4.7.1 4.7.2 Control Red Pres:2-vertitention 10S 4.8 StERGENCY FEES;AfEA PU'i? IESTI.G 10 t.
REACTIVITY.t.NO:BLIES CONTROL ROch! DERGENCY AITs CONDITIONING SYSTDI 4.9 107 4.10 SURVEILLANCE 109 PENETRATION ROO.'-l VESTILATICN SYSTDI SURVEILLKiCE 109b 4.11 HYDROGEN PURGP SYSTE!! SURVEILLANCE 110s 4.12 DERGENCY (GOLING POND 1105 4.13 RADICACIVE.\\tATERIALS SOURCES SURVEILLANCE 4.14 AUGMENTED INSERVICE INSPECTION PROGR&t FOR li1CH 110e 4.15 ENERGY LINES OUTSIDE CF C:.TADOLENT 110e 4.16 SROCK SUPPRESSORS (SNUBBERS) 110e 4.16. 1 liydraulie Shock Superessors 11Lc FUEL llANDLING AREA VE:.TILATICN SYSTDI SURVEILIANCE 4.17 110)
STEAM GENERATOR TUBING SURVEILLANCE 4.18 110p 4.19 FIRE DETECTION INSTRltMENTATION 110q 4.20 FIRE SUPPRESSION WATER SYSTEM 110t SPRINKLER SYSTEMS 4.21 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON SYSTE 110u 4,22 11ov 4.23 FIRE HOSE STATIONS 110w 4.24 PENETRATION FIRE BARRIERS 111 5.
DESIGN FEATURES _
111 S.1 SITE 112 S.2 REACTOR SUILDING 114 S.3 REACTOR 116 NEW AND SPENT FUEL STORAGE FACILITIES S.4 117 ADMINISTRATIVE _ CCNTROLS_
117 6.
l 6.1 RESP 0hS131LITY 117 PLANT STAFF ORC.2J4I:ATION 118 6.2 6.3 QUALIFICATICNS 121 REVIEW AND AUDIT ACTION TO DE TAKEN IN T1iE EVENT OF A REPORTABLE 6.4 OCCURRE';CE DESCRISED IN TECHNICAL SPECIFICATION j
6.5 6.22 3 2 123 ACION To BC TAKEN IF A SAFETY LDlIT IS E:tCEEDED 129 6.6 PLANT CPEllATING PROCEDURES 130 6.7 RADIATION AND RESPIMTORY PROTECTION PROGRM1 6.S 136 D.fRCTNCY PLANNING 137 0.9 INDU57r I AL SECURITY PRCLPXI 133 6.10 l
RU Jr.01 RE1LM 1C:1 140 6.11 PIA.T PIPORTINC REQUIRff!ENTS 0.12 Amendmerit No. 23, 7#, 30 11 l
1.7 REACTOR BUII. DING Reactor building integrity exists when the following condit'icas are satisfied:
The equipment hatch is closed and sealed and both doors of the personnel lock and emergency lock are closed and sealed, or b.
a.
- below, At least one door en each of the personnel icek an'd e=ergency b.
lock is closed and sealed during personnel access or repair.
All non-automatic reactor building isolstica valves and blind c.
flanges are closed as required.
All aute=atic reactor building isolstien valves are cperable d.
or deactivated in the closed positien.
The reactor building leaka6e determined at the last testing e.
interval satisfies Specifiestice L.k.1 1.8 FIRE SUPPRESSION WATER SYSTDi The fire suppression water systen consists of: water sources, pumps, and distribution piping with associated sectionalizing isolation valves.
Such valves include the hose standpipe shutoff valves and the first valve ahead of the water flow alarm device on each sprinkler system.
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~3-Amendment No. 30 t
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INCORE IliSTRUMEtiTATION SPECIFICATI0:1
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3.5.5 Fire Detection Instrumentation-Applicability This specification applias to fire detection instrumentation utilized within fire areas containing safety related equipment or circuitry, for the purposes of protecting that safety related equipment or circuitry.
Objective To provide immediate notification of fires in areas where there exists a potential for a fire to disable safety related systems.
Specification 3.5.5.1 A minimum of 50% of the fire detectors in each cf the following locations, shall be operable,:
a.
each of the four reactor building cable penetration areas.
b.
each of the four cable penetration room penetration rooms.
c.
each of the two emergency diesel generators rooms, d.
north switchgear room, e.
south switchgear room, f.
main control room, g.
auxiliary control room ceiling.
h.
auxiliary control room floor,
- i. each diesel generator fuel vault, J.
cable spreading rooms.
3.5.5.2 If less than 50% of the fire detectors in each of the locations designated in 3.5.5.1 arc 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 report to the Commission pursuant to Specification 6.12.3.2(b) within the next 30 days outlining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the instrument (s) to operable status.
Bases The various detectors provide alarms that notify the operators of the existence of a fire in its early stages thus providing early initiation of fire protection.
The detectors in the main and auxiliary control rooms also provide automatic fire protection initiation.
The detectors required to be operable in the various creas represent 1/2 of those installed.
Operability of the fire detection instrumentation ensures that operable warning ' capability is available for the prompt detection of fires. This capability is required 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 inoperabla, the establishment of frequent fire patrols in the affected area (s) is required to provide detection capability until the inoperable instrumentation is restored to operability.
l Amendment No. 30 53d
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o 3.6 REACTCR BUILDING Applicability Applies to the integrity of the reactor building.
Objective To assure reactor building integrity.
Speci fication 3.6.1 neactor building integrity shall be maintained whenever all three (3) of the following conditions exist:
a.
Reactor coolant pressure is 300 psig or greater.
0 b.
Reactor coolant temperature is 200 F or greater, c.
Nuclear fuel is in the core.
3.6.2 Reactor building integrity shall be maintained when the reacter coolant system,is cpen to the reactor building atraocphere and the requirements for a refueling shutdown are not met.
3.6.3 Positive reactivity insertions which would result in the reactor being suberitical by less than 1% ok/k shall not te made by control 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 vacuu:n 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 valvec which should be closed are closed and locked, as required.
3.6.6 If, while the. reactor is critical, a reactor building isolation valve. is determined to be inoperable 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brought to the cold shutdown condition within an additiona) 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 ctean will' be formed and hence there will be no pressure buildup in the reactor building if the reactor coolant system ruptures.
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3.17 Fire Suppression Water Syste
. 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 safety related equipment.
Specification The fire suppression water systen shall be operable at all times with 3.17.1 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 valves to the shutoff valve ahead of each hose standpipe and the water flow alarm device on each sprinkler system.
With one pump inoperable, restore the inoperable equipnent to operable 3.17.2 status within seven days or prepare and subnit a report to the Commission pursuant to Specification 6.12.3.2(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:
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 a.
b.
Submit a Report in accordance with Specification 6.12.3.l(b).
If a. above cannot be fulfilled, place the reactor in Hot Standby c.
within the next six (6) hours and in Cold Shutdown within the following thirty (30) hours.
Bases The fire pumps supply the only source of water for all fire suppression t
Each pump is individually capable of providing full l
systems utilizing water.
The pumps flow required for proper fire suppression wate-system operation.
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start automatically on low system pressure.
In the event that the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the The requirement for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> major fire suppression capability of the plant.
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.
hardnent No. 30 66m
3.18 Fire Suppression Sprinkler Systems Applicability This specification applies to the following fire suppression sprinkler systems protecting safety-related areas:
Euch of the four reactor building cable penetration areas, a.
~
b.
Each of the four cable penetration rcoms.
c.
Each of the two emergency diesel generator rooms, d.
Cable spreading room, e.
Each of the two diesel. generator fuel vaults.
Objective To assure that fire suppression is available to safety-related equipment located in the above-listed areas.
Specification 3.18.1 The above-listed sprinkler systems shall be operable at all times.
3.18.2 With one or more of the above-listed sprinkler systems incperable, establish a continuous fire watch (or operable smoke and/or heat detection equipment with control room alarm) with backup fire suppression equipment for the applicable area (s) within one hour. Restore the system (s) to operable status within 14 days or prepare and submit a Report to the Commission pursuant to Specification 6.12.3.2(b) within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system (s) to operable status.
Bases Safety related equipment located in various areas is protected by sprinkler sys tems. The operability of these systems ensures that adequate fire suppres-sion capability is available to confine and extinguish a fire occurring in the applicable areas.
In the event a system is inoperable, alternate backup fire fighting equipment or operable detection equipment is required to be made available until the inoperable equipnent is restored to service.
Amendment No. 30 66n
n 3.19 Control Room and Auxiliary Control Room Halon Systems Applicability This specification applies to the Halon systems utilized as the fire suppression system for the control room and auxiliary control room.
Objective To assure that fire suppression is available to the safety related equipment in the control room and auxiliary control room.
Specification 3.19.1 The three control room and auxiliary control room Halon systems shall be operable at all times with the storage tanks having at
- least 95% of full charge weight and 90% of full charge pressure.
3.19.2 With any of the control room and auxiliary control room Halon systems inoperable, establish backup fire suppression equipment for the affected area within one hour. Restore the system (s) to operable status within 14 days or prepare and subnit a Report to the Commission pursuant to Specification 6.12.3.2(b) within 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable s ta tu s,.
Bases Safety related circuitry located in portions 'of the control room and auxiliary control room is protected by the Halon systems.
The opera-bility of these systems ensures that adequate fire suppresamn capability is available to confine and extinguish a fire occurring in the control room or the auxiliary control room.
In the event that the system (s) is inoperable, alternate backup fire fighting equipment is required to be made available in the affected area until the inoperable equipment is restored to service.
i l
i Amendment No. 30 66o
3.20 Fire Hose Stations Applicability This specification applies to fire hose stations protecting areas containing safety related equipment.
Objective To assure that manua.1 fire suppression capability is available to all safety related equipnent.
Specification 3.20.1 All fire hose stations protecting areas containing safety related equipment 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 operability of the fire hose stations adds additional assurance that adecuate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipnent is located.
In the event that portions of this system are inoperable, backup fire hose
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equipment is required to be made available in the affected area (s) until the inoperable equipment is restored to service.
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Aneninent No. 30 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.
Objective To assure that penetration fire barriers protecting safety-related areas perfom their separation function.
Specification 3.21.1 All penetration fire barriers protecting safety related areas shall be intact at all times.
I 3.21.2 With one or more of the required penetration fire barriers not intact, establish a continuous fire watch (or operable smoke and/or heat detection equipment with control room alarm) on at least one side of the affected penetration within one hour.
i The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions J
of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and ex tinguishment. 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 continuo n fire watch or operable detection equipment is required to be maintained in the vicinity of the af f ected barrier until the Darrier is restored to tura -
tional status.
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/cendment No. 30 66q
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4.19 Fire Detection Instrumentation Applicability Applies to surveillance of fire detection instrumentation required operable by Specification 3.5.5.
Objective To assure that the fire detection ~ ins ~trumentation required operable by Specification 3.5.5 is available and operable when needed.
Specification Each required fire detection instrument shall be demonstrated operable 4.19.1 at least once per six months by performance of a channel functional test.
The NFPA Code 72D Class A supervised circuits supervision associated 4.19.2 with the detector alarms of each required fire detection instrument shall be denonstrated operable at least once per six months.
The non-supervised circuits between th.e local panels in 4.19.3 Specification 4.19.2 and the control room shall be demonstra-ted operable at least once per 31 days.
Bases These required demonstrations will assure operability of the fire detection instrumentation.
Amendment No. 30 110p
4.20 Fire Suppression Water System Applicability Applies to surveillance of fire protection equipnent required operable by Specification 3.17.
Objective To assure that the applicable fire protection equipnent is available and operable when needed.
Specification 4.20.1 The fire protection water' system shall be demonstrated operable:
a.
At least once-per 31 days on a staggered test basis by starting each pump by autanatic 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 which is not locked, sealed or otherwise secured in its correct position) in the flow path is in its correct position; c.
At least once per six months by performing a flush of-the systen main; d.
At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and:
- 1) Verifying that each pump develops at least 2500 GPM at a discharge pressure of 125 psi;
- 2) Verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure > 85 psig.
At least once per three years by performing a flow test of the e.
system in accordance with Chapter 5, Section 11 of the Fire "rotection Handbook,14th Edition, published by the National
.tre Protection Association.
Amendment No. 30 110q
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4.20.2 The fire pump diesel engine shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying the fuel storage day tank to be at least 5/8 full of fuel (approximately 155 gallons).
- b. ' 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-0975-74 with respect to viscosity, water content and sediment.
c. At least once per 18 months, during shutdown, by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommenda-tions for the class of service.
4.20.3 The fire pump diesel starting 24-volt battery 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 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 indication of physical damage or abnormal deteriora-tion, and
- 2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
A7.endnent No. 30 110e i
, Bases These required demonstrations, tests, and verifications will assure the availabt11ty 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 automat \\ starting logic. This can be accompitshed by allowing the fire system pre..tre to drop to the automatic start setpoint, The pump will then start and disenarge through the reitef ifne until stopped by the operator.
For purposes of the annual system main flush, the system main consists of i f ne KE-1-12, Amendment No, 30 110s 1
4.21 Sprinklcr Systre Applicability Applies to surveillance of the sprinkler systems which are required to be
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operable by Specification 3.18.
Objective To assure that the various sprinkler systems are available and operable when needed.
Specification 4.21.1 The cable spreading room sprinkler system shall be demonstrated operable at least once per 31 days by verifying that the system is aligned to the fire pumps.
4.21.2 The sprinkler systems located in the four reactor building cable penetration areas and four cable penetration rooms shall be demonstrated operable:
a.
At least once per 31 days by verifying that each system is aligned to the fire pumps; b.
At least once per 12 months by cycling each testable valve in the flow paths through at least one complete cycle of full travel.
4.21.3 The sprinkler systems located in the two emergency diesel generator rooms and two diesel generator fuel vaults shall be demonstrated operable:
a.
At least once per 31 days by verifying that each system is aligned to the fire pumps; b.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel; c.
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 sprinkler systems in the four cable penetration areas and 'our cable penetration rooms are manually e erated closed-head (fusible head) systems which are remotely operated from the control room.
The sprinkler systems in the two emergency diesel generator rooms and two diesel generator fuel vaults are (nanually-operated open-bead systems which are remotely operated from the control room.
The required inspections will assure availability of the various sprinkler systems when they are needed.
Amendment No. 30 '
110t
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4.22 Control Room and Auxiliary Control Room Halon Systems Applicability Applies to surveillance of the control room and auxiliary control room Halon systems which are required to be operable by Specification 3.19.
Objective To assure that the contrr.1 room ar.d auxiliary control room Halon systems are available and opera' ole when needed.
Specification The control room and auxiliary control room Halon systems shall be 4.22.1 demonstrated operable:
At least once per 6 months by verifying Halon storage tank a.
weight and pressure; b.
At least once per 18 months by verifying the systems actuate manually and automatically (upon receipt of a simulated test signal).
Bases Performance rf the testing required by these specificatio.ns will assure that the Control Room and Auxiliary Control Room Halon iyitems are operable when needed.
J
' Amendment No 30 110u
4.23 Fire Hose Stations Applicability Applies to those fire hose stations protecting safety-related areas, which are required to be operable by Specification 3.20.
Objective To assure that the fire hose stations. protecting safety-related areas are operable to provide manual fire suppression capability when needed.
Specification 4.23.1 Each of the fire hose stations protecting safety-related areas shall be denonstrated operable:
At least onc.e per 31 days by visual inspection of the station a.
to assure all required equipmant is at the station; b.
At least once per 18 months by:
- 1) Renoving the hose for inspection and re-racking; and
c.
At least once per 3 years by:
- 1) Partially opening each hose station valve to verify valve operability 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.
Bases The required inspections and test will assure that fire hose stations serving safety-related areas are maintained operable and ready for use when needed.
1 Amendment No. 30 110v
4.24 Penetration Fire Barriers Applicability Applies to surveillance of the penetration barriers required intact 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 protecting safety-related areas shall be verified to be intact by a visual inspection; a.
At least once per 18 months, and b.
Prior to declaring a penetration fire barrier intact 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.
4 Anendment No. 30 llow
6.0 - ADMINISTRATIVE CONTROLS -
~
6.1 RESPONSIBILITY of Power Plant shall be responsible for overall 6.1.1 The Superirtendent In his absence, the Assistant Superintendent facility operation.
of Power Plant shall assume all responsibility and perform all of Power Plant.
If both the Ruper-duties of the Superintendent are absent, these respon-intendent of Power Plant and his assistant sibilities and duties are assumed by the Supervisor of Plant Operations followed by the Technical Support Engineer.
6.2 ORGAN 11ATION OFFSITE The offsite organi:stion for facility management and technical 6.2.1 support shall be as shown on Figure 6.2-1.
FACILITY STAFF The Facility organitation shall be as shown on Figure 6.2-2A and 6.2-2B and each on duty shift shall be composed of at least the 6.2.2 composition shown in Table 6. 2-1.
minimum shift crew FACILITY STAFF QUALIFICATIONS 6.3 Each member of the facility staff shall meet or exceed the minir r qualifications of ANSI NIS.1-1971 for comparable position, excep 6.3.1 or exceed the for the ficalth Physics Supervisor who shall meet qualifications of Regulatory Guide 1.S, September 1975.
6.4 TRAINING training program for the facility A retraining and replacement staff shall be maintained under the direction of the Supervisor 6.4.1 of Plant Operations and shall meet or exceed the requirementsand Appendix and recommendations of Section 5.5 of ANSI N18.1-1971 "A" of 10 CFR Part 55.
A training program for fire protection training shall be maintained 6.4.2 and shall meet or exceed the requirements of Section 27 of, the NH'A Code-1975 with the exception of frequency of r r ainiog which Cmii be six times per year.
6.5 REY 1BW AND AlfDIT 6.5.1 Plant Safety Committee (PSC) Function Safety Committee shall function te advise the Super-6.5.1.1 The Plant on all matters related to nuclear safety.
intendent of Power Plant COMPOSITION Safety Committee shall be composed of the:
6.5.1.2 The Plant 117 -
Acendment No. yp, 30
m TABLE 6.2-1
~.
ARKANSAS NUCLEAR ONE MINIMUM Sil1FT CREW COMPOSITION #
UNIT 1 COLD AND REFUELING LICENSE ABOVE COLD SilUTD0hN SHUTDOWNS CATEGORY l'
1 SOL I
1 2
OL 1
2 NON-LICENSED
'Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel llandling, supervising refueling operations after the initial fuel loading.
- Shift crew composition may be less than the minimun requirements for a 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 period of time notabsence of on duty shift crew members provided immediate ac f
restore the shift crew composition to within the minimum requirements o Table 6.2-1.
Additional Requirements:
At least one licensed Operator shall be in the control room 1.
when fuel is in the reactor.
in the control At least two licensed Operators shall be present room during reactor start-up, scheduled reactor shutdown and 2.
during recovery from reactor trips.
An individual qualified in radiation protection procedures shall 3.
be on site when fuel is in the reactor.
All refueling operations after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator 4.
or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
At least 3 individuals with fire protection training shall be f
i F.
These individuals shall not maintained onsite at all times. crew necessary for safe shutdown of include the minimum shift (2 members) or any personnel required for other the unit esse.tial functions during a fire emergency.
n
.o Amendmeet No. I6, 30
- 1.18 -
1 1
1
~
SENIOR VICE PRESIDENT PROD. TRANS.
(
& ENCRG.
SAFETY REVIEW I
CUALITY ASSURANCE E
COMMITTEE COMMITTEE DIRECTOR POWER PRODUCTION I
ASST. OIRECTOR POWER PRODUCTION
- MANAGER MANAGER MANAGER O
QUALITY NUCLEAR NUCLEArs ASSURANCE PROJECTS
, FUEL LANT SMETY SUPERINTENDENT COMMIT TEE i.
' CORPORATE RESPON$1BILITY FOR FIRE PROTECTION PROGRAM l
ARKANSAS P0lifR G LIClir COMi%Y MANAGEMENT ORGANIZATION C11 ART 6
'-l ARKANSAS NUCLEAR ONE - 11 NIT 1 Amendment. un. J){ 30 Il9 i
SUPER 4TENotwT or POwC9 PLANT CE assistant supt or PowtR PL ANT CE LSO SEE FIGilici.
6.2-2B 1
I I
TECEj$gt7 "
svevsR PLNT OPS 0.C. EmetMEta s
CE LSO I
I I
I I
10 CM H. P.
PERFORW ASST.$UPV$R PLT OP Q.C IN$PEC T OR S CHEW & E,NV SUPVSR gypyg gypygg gygg-LSO TRAINING C0ORDINATOR Assi MP.
sNiPToPsuPvsR SUPYSR Ls0 PLANT CPER
CHEWISTS CHEMISTS H. P.'S ASST Pt.NT OPER LO
]
WSTd. e CONT.
OPER.
C - Degree or [quivalent acquired AUX.
CI - Ingf acering Degree or Equivalent RequirrJ L50 Senior Opere'or License acquired LO - Operato'r License acquired -
l
FUNCTIONAL ARKANSAS NUCLEAR ONE-UNIT I GRCANIL\\ TION FOR FICURE PLANT OPERATION 6.22\\
Amendnent No. //; 30 120 -
REVIEW-6.5.2.7 The SRC shall review:
The safety evaluations for 1) changes to procedures, equip-ment or systems and 2) tests or experiments comp!cted under s.
50.59, 10 CFR, to verify that such the provision of Section actions did not constitute an unreviewed safety question.
or systems which Proposed changes to procedures, equipment b.
involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
or experiments which involve an unreviewed Proposed tes*'
50.59, 10 CFR.
c.
safety questivn as defined in Section Proposed changes in Technical Specifications or licenses.
d.
Violations of applicable statutes, codes, regulations, orders,
Technical Specifications, license requirements, or of internal c.
procedures or instructions having nuclear safety significance, Significant operating abnormalities or deviations from normal f.
that affect nucitar and espected performance of plant equipment safety.
Reportable occurrences rcTu; ring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the g.
Commission.
Reports and meeting mir.utes of the PSC.
h.
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 proyisions contained within the Technical Specifications an'd applicable a.
license conditions at least once per year.
The performance and retraining of all members of the plant
~ >
and operations staff, and the performance, training, b.
management an'd qualifications of new members of the entire plant staff at 1 cast once per year.
The results of all actions taken to correct deficienciesstructures, sy c.
occurring in facility equipment,
least once per six of operation-that affect nuclear safety at months.
least The Facility Emergency Plan and implementing procedures at
'd.
once per two years.
The Facility Fire Protection Program and impicmenting procedures e.
at least once per 24 months.
Amendment t'o.16, 30
- 125 -
.6
Th2 Fac.sity Security Plcn end implement.
procsduras ct
. o.
least once per two years.
Any other area of f acility operation considered appropriate f.
by the SRC or the Senior Vice President (PT4E) 6.5.2.9 Spect.1 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 et_ther qualified offsite licensee personnel or an outside fire protection firm.
AUTHORITY to and advise the Senior Vice President The SRC shall report 6.5.2.10 (PT6E) 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:
Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice President (PT6E) within 30 a.
days following each meeting.
Reports of reviews encompassed by Section 6.5.2.7 e, f, g b.
and h above, shall be prepared, appros ed and forwarded to the Senior Vice President (PT6E) within 30 days following completion of the review, reports encompassed by Section 6.5.2.8 above, shall be c.
Audit forwarded to the Senior Vice President (PT6E) 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 chall be taken for Reportable Occurrences:
The Commission shall be notified and/or a report submitted a.
pursuant to the requirements of Specification 6.12.
b.
Each Reportabic 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, Power Production by the Superin-tendent of Power Plant.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least hot shutdcwn within one hour, b.
The Nuclear Regulatory Commissior. shall be notified and a report submit ted pursuant to the requirenents of 10 CIR 50. %
and Specification 6.12.3.1 Amendment No. J6, 30
- 126 -
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained 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:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by the PSC and approved c.
by the Superintendent of Power Plant within 14 days of implementation.
Amendment No. J$, 30
- 127 -