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| 'B'O AEP:NRC:00313 REVISED TECHNICAL SPECIFICATION PAGES DONALD C.COOK NUCLEAR PLANT UNIT NOS.1 AND 2 7 l CHANGE NO.AEP: NRC:00313 PLANT SYSTEMS AUXILIARY FEEDHATER SYSTEM LIMITING CONDITION FOR OPERATIOiN 3.7.1.2 At least three steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with: a.Two*feedwater pumps, each capable of being powered from separate emergency busses, and b.One feedwater pump capable of being powered from an OPERABLE steam supply system.APPLICABILITY:
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| MODES 1, 2 and 3.ACTION: With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered frorii separate emergency busses and one capable of being powered by an OPERABLE steam supply system)to OPERABLE status withlni 72 hours or be in HOT SHUTDOWN within the next 12 hours.SURVEILLANCE REQUIREIMEi ITS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a.At least once per 31 days by: 1.Verifying that the steam turbine driven pump develops a discharge pressure of>1285 psig at a flow of>700 gpm when the secondary steam supply pressure is greater than 310 psig.2.Verifying that each valve (manual, power operated or automatic) in the f 1 ow pathi nc1 udi ng va1 ves whi ch are locked, sealed or otherwise secured in position, is in its c'otrect position.b.At least once per 18 months by: l.Verifying that each automatic valve in the flow path actuates to its correct.posi.tion on a Safety Injection test signal.8 are iwi.th'0;G COOK.-UN!T"l.-D.C.COOK-UNIT 2 3/4 7-5
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| PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 3.Verifying that each pump operates for at least 15 minutes.4.Cycling each testable power operated or automatic valve in the flow path through at least one complete cycle of full travel.5.Verifying that each valve (manual, power operated or automatic) in the flow path, including valves which are locked, sealed or otherwise secured in position, is in its correct position.b.At least once per 18 months during shutdown by: 2.Cycling each power operated valve in the flow path that is not testable during plant operation, through at least once complete cycTe of full travel.Ver ifying that each motor driven pump starts automatically upon receipt of each of the following signals: a)Loss of main feedwater pumps.b)Safety Injection.
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| c)Steam Generator Mater Level--Low-Low from one steam generator, 2 out of 3 channels.3.Verifying that the steam turbine driven pump starts auto-matically upon receipt of each of the following signals: a)Steam Cenerator Mater Level-Low-Low from two steam generators, 2 out of 3 channels.b)Reactor Coolant Pump Bus Undervoltage.
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| D.C.COOK-UNIT 1 3/4 7-6 CHANGE NO.~2 AEP:NRC:003l3 s.~C~j I tea assaW v w~a~>>>>~~wl'aeaA~t~~t I~~e n~O O I rQ aa 2600 2400 2200 200,0 1800 1600'1400 u a120fjj 1000 500.'00 i 400'00.~~e~I as'';jl,'ill I ill:iii I st~I rig.~I t~~a','I;:I: is I~I~~)t:};!sf i I~e~~a~~~~~e al~~~I~~I e~~ll)i~~I l}l',.}tli J.jj I:it~I t~I s a~~~sl~~~~a~ll",;si'.j t, I st~~s,i~~II I~f-'l: SI i'I I'II~I tl'Ii.Ii ,'I))}I!)~~~~~~~am@~~~~~>>st:)Jl'>>.~~I I.S~I'~>I iiie I I~~~~~~, e el~i tl'ifj I:NI j'l)it!sa~~I I I'I~~Jljj ,J I I ilsi)jjl~J~I ili'.}}l Ij)-'f jttl j).l I,',: 4~ls*~I I~a I:U:!lji'}l}')'i I}',,};I;I" lilt.:T.IZE I~I I~I i:.i'~a II:I'il i!;Ii I':I'CS'it t it'h I~Il f'jth.I'.I Ir~'.,:,f: ,'J}, I J1~lsj I I~~f"ll I!al!I!'I~t~~ti I e~I~~e I I I;)-.;i I'ls I~fi je~~~~~~alj~I t,'.~e li)i l,"'!.!I): jj l I:e~~e i!1 i':.j': N'Ill)I'I I I I f~I~I tip~!ili H(~et): i:,ill iii: llew!i I a'.::Ii II II I~;I.'I~I~~~",'}I i),'}~et;)J.l''I Ij):f, r'j.!Ia.i:,fl: il}l'Yl ill'}'.Iiti;I,:.I ,}I I~~I'I I~I I f!, Is.!!: DL-C'f"4""~~,"it jr'~a il'-.I~Ii l:)I!', ii a I},t!ll'i.~hei i}.i::.C., I I~~~~~I Ri'"~".I:.'I~ils~ii~~~)....I,,:.}all!.:Ii i)R!:~I~~~~~~~~~II I~~'I.Jl)t ij}i~~a I~tlf: al~I e~e ii),'t)}I!1i::i})}ji!~)T).:{lP.J:HR'-~~~~~t~.C t':J~I'~~~~I I'I~~I: I~1'!)}a t.;I)e~'l I~~~a~~~I}l;):):i...l~~e~it a~I I~I~I i~~~~~I~~I~I~ie)!i'ast fit~~!I:I I e~',.'Ai)4'ss'I I I~I~~~..t,0 tG.)L~Illj I'!f!iri ttif Hl,'jll~I I I I~~t.,~~~-~~~!il a i})I'.;)I itl if):'iff I'(I I!s~~~I~a i)i li'I'I~'a s'll e I II)I JI I j}I.I)I i;:l}i', I~I'I{[Ir;J)'gf r~I)I~~i S I I)ii!I:I:'';jl It!i K>i!a jj ji Ii if)j))'.J, I ,",r"I",I':r Hj ilil aat'~,)',~is I~I~~~~!!i!};I.;I~ll):)'s))i j;~f llii'.;t~I: li'.f j,}}off.)I;ii',.r: t}i')t list 1 II~~~~I~II';;i L:ri]rs I II II t i)I}.', I',I t'l l)),I I j'I I I;I;:)I~~I I l'f'I~~~I I i.ti tall s~~ti'jts II Iia~Ii~.I),, I I~a~I~~I till jl~~j:t~ii Qi~~~~I~gl rs I~e I~s>I~"I"tiÃ('II j<', Jlr~II I~Ir~~I~~~~I~it I~I','I I ,if i~}I!'I)I ,'l!4~itl j}I)~)~t;.}I.I I I!I/~.I)s, S I~~~~~.~~.I~al i~~~~~P,"t l7-60 100 150 200 250 300 350 400"~~a Indicated Temperature, de@F I I fjgUIe 3,Q-2 DONALD C.'OOK UNIT NO.1 REACTOR COOLANT llHATUP LIMITATIONS APPLICABLE l e)@A'a aeMMes a e MAC~tates'O O esC e e 2600 ala~'I lJ (~~~s I (l'I~t'I>>I!11 1~I Isa~)I I s~f s~~a~~~Le;;I 4:,'1 fs'tss!':1 ala elf',(,.::.I,'ti e~e s si~!'!I 2400~~l":i: 2200 s:..(~I s'2000'.I!~~lt a:,':".:.<<.l (: I t(t(.1800 Q tt(1600 1400 1200 1000'el.~~~~I I'ii(g~.e.s'i(i"(I, te'it!I'~~s It t,~=~a~~~s e~s~s~;II'"I~.!1 e t~~I s ,I e~*t~t~s lf all~~~1~800~~~~r~s't~s s~~~el~~600 e'I (e'':~~400 s 200~~~, s it: I 4'-'-f s sl I st 1'll I'ti st((;11;I],:!ff i;).e(I I~ll~~t.:I e4 s I I i.ll e~7:lh1 l J]}:t:.".':GQ I~~~e~~~e~~~I'I tt I s"1 (ss s~~s'~("P~I~,~l~~~~I(;s.'I t e t's ll~'tt e~I~'~~~s~s''~~I:~: 5(R'0.'P.,'((: (~1 l!I~~I('ta I , f,~s e'1 r''~I~~t).~~s':::: sa'!I~~I~~~I tl~~~'s r,t I: I!'i'-l.li e~~s as t ,s~~ss:e'f)~s s~~~I~~~s st~~tl~I-"'(.';I, I I:ef>>ilia sr(,~t)~e~I'~.'1 1 t~.i!.'i'pe;.Il.:,'.I~~-af~~fa~i: ':::.'I!'I
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| ~~~:::I e r(~~s)!i.'1 ti-;rlj sts'~lit a~~~1 I\s 1 I j I~t ,,;a*~~t sass!tt s I~as s~(j'1..s e e~~~~~~s~~~s s(s,~w~~~~s'I'~~~~;l~~at s~1 s 1 as t)s~sal s~~~e f I''s 1!)!t re 1].+s e S e~'as'i(i s I l)~s~, I!I~s (~~~I essa~I':i:~~~s-'tel I~st~a s sj(I sw e(~~~~~s~ss"'I".L~.s(e~I~a~I~I st!l~s a I e+a sf.t', a~~'!t a~~~I(sf~~~~~'I't~'s~I PEX LAT Y!a~,;ls~I~-.:C,.'0.)45: I'i.pat<..PL~~~~w~I~~~~~~~i!I)I~~~II~~~~~~~e~t~~1's'I~~~s~~1~fi~~Ilfi::.'..::,-,.I
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| ,:I ti~e I at~~;~I~I t~~~t ls esi s'et:~I~s~'-:fl;'I I':: tjt Issi~s~alta.I t~~~,I~~~II~e~~~~~~).fl ts t I e I t as s~~~s~~~~~~~t~tl e t e~1 e ,~~:lt~~t AT!~s~t~'I.t..~s I T::.I~" s t'~a t~tt t'~t~!'ft s I I's I~)I'I 1st~~a l't a I e s~~~s I., a~~'I e~.'I e'}~s~~~~;~1~~':1,: I~t,s~.:a:I:f)(Q";i:)s t~I s''~~~~I'-'s~~i:ta~~~~~~~~s s~I-'~s~1 s~a~~~I~~s~~~.I~~~~.g,~'t"Pl:,(" I.I~I s~~~~~.r t I 1,':~I(I'~~I~~t~~~s~~~~t~~~sf~~s~~-.(a 1(s:-~I~".s I~s~~'~e e e~s s'1 liji:~'.".I'.''~la~*~s'e t~~t~~~~'I!~~~~~I~~e'e's 1 lH!~'r.w~s'I e~s~I~I~~~~1 I (I l~s~j't s;I s li ls~1 e~~t~al~II~s P@l HSI~~l a;I 1)1'"'I:: I~~~:)t e t e"I~e~~~~'s~"~~s-"s''!: 1.s.:I s~~*~stf: e~s I~S~~~~~~~1~~~~~II's s s 1st P:0 33EG:.-F.:
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| PYY-';': t I~*~~~e~l,l s t~-I~ia;:~~~;i'~~~~~~t ala~~et cia I saba I~~~~e s~~s~~'I 1~~~/~t t ,!.I s~~~~~'t~~~a~s ,:,1~s t''1 t e t~a~e''~~a ea~t s'1(I',(l I~.s~~~~~ss~t I!~s s (ts~eQ e~!('~~i I~~s~~t:i!f;!', I t I~s~T<~t~~1(';'I 1~'st'1~*~r~~.: I'~e I~~I>!ATT~~~.;1'I~e~~~~~::I~~!i(I.!.~e~I\''s~e s~~~~~~aet st't t~'I~T~t et't~I~t I s la~~~as~-I~r t~ts I!ass:i:j~e~'~i(tts;~e r~~I E,.aI'E,-F!:C.R.200 250 Indicated Temperature, deg F 60 100 300 350 400 FjgU(e 3,4-3 DONALD C.COOK UNIT NO.1 REACTOR COOLANT CQOLDOMN LIMITATIONS APPLICABLE
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| ~vo>>.vraznos up To 12 EFFECTzvE FULL powER YEARS I CHANGE NO.AEP'NRC:00313 II'],~I~~
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| )~(i RONIHI STRATI V"=CONTROLS 6.9 RcpOR ING R QVIRc.~~~TS (Continued)
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| Seismic event analysis, Specification 4.3.3.3.2.
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| Sealed Sourc leakage on exc ss of limits, Specification 4.7.7.1.3.
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| g.Fire 0etection Instrumentation, Specification 3.3.3.7.h.Fire Suppression Systems, Specifica.ions 3.7.9.1, 3.7.9.2, 3.7.9.3 and 3 7.9.4.6.10 RECORD RK=NTION 6.10.1 The following records shall be retained for at least five years: a.Records and logs of unit operation covering time interval at each power ievel.~e b.c Records and legs of principal maintenance ac.ivities, inspec-tions, repair and replacement o-principal items'f equipment related to nuclear safety.All REPGPTA3L OCCURR='(CKS submi t d to the Ccmmission.
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| ~f.Records o st r ieillanc activi.ies, inspections and calibra-tions required by these Technical Specifications.
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| Records of reactor tests and experiments.
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| Records of changes mad to the proc dures required by Soecific;tion 6.8.'1.g, Records of radioactive shipments.
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| h.Records of sealed sourc leak tests and resul.s.Records o, nnual physical inventory of all seal d sourc material of record.1 6.10.2 Tne following r cords shall be retained, or the duration of the Facili:y Operacing Lic nse: a.Records and drawing chances re=lecting Jnit design radifi-..,::....cati cns" mad.to.,sys:~ms.
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| and,.equi p(-,inc",descry ibad., in.:he:-F inal Sa ety"Analysis Repcr.b'."Records of r'ew and ii radi:a:ed'uel inventory; fuel-transfers and assembly burnup h scories.0.C.CCCi<-U(lIT 1 6-19 Amendment io gg 23 CHANGE NO.AEP:NRC:00313 j~~AOMINISTRATIVE CONTROLS J occurrence of the event.The written report shall include, as a minimum, a completed copy of a licensee event report form.Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.a.Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not.prevent the fulfillment of the functional requirements of affected systems.b.c~Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.
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| Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.d., Abnormal degradation of systems other than those specified in 6.9.1.8 c above designed to contain radioactive material resulting from the fission process.SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Oirec.or of the Office of Insp'ection and Enforcement Regional Office within the time period specified for each report.These reports shall be submitted covering the activities indentified below pursuant to the requirements of the applicable reference specification:
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| a~b.ECCS Actuation, Specifications 3.5.2 and 3.5.3.Inoperable Seismic t<onitoring Instrumentation, Unit No.1 Specification 3.3.3.3.c.Inoperable tteteorological tlonitoring Instrumentation, Un'it No.1 Speci fication 3.3.3.4.d.Fire Detection Instrumentation, Specification 3.3.3.8.e.Fire Suppr ssion Systems, Specifications, 3.7.9.1, 3.7.9.2, 3.7.9.3 and 3.7.9.4.f.Seismic event analysis, Specification 4.3.3.3.2.
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| D.C.'OOK'-'UNIT 2 6-18 DONALD C.COOK NUCLEAR PLANT UNIT NO.1 CHANGE NOS.5 AND 6 AEP: NRC: 00313 a'UNCTIONAL UNIT 8.13.Steam Generator Water Level-Low-Low I.14..-Steam/Feedwater Flow~.,-: Mismatch and Low Steam Generator Water Level>17/of narrow range instrument span-each steam generator 6<0.71 x 10 lb/hr of steam flow at RATED THERMAL POWER coincident with steam generator water level>25%of narrow range instru-ment span--each steam generator>ypfpf narrow range instrument
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| ~span-each steam generator<0.73 x 10 lbs/hr of steam flow 6 at RATED THERMAL POWER coincident with steam generator water level>24K of narrow range instru-ment span--each steam generator TABLE 2.2-1 (Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS i TRIP SETPOINT ALLOWABLE VALUES'-.l5;Undervoltage-Reactor.Coolant Pumps-'.16.llnderfrequency-Reactor Coolant Pumps a.;17.Turbine Trip'.A.Low Trip System Pressure:-'.Turbine Stop Valve Closure:.18..Safety Injection Input from ESF 19.:Reactor Coolant Pump Breaker Position Trip>2750 volts-each bus>57.5 Hz-each bus>800 psig>lX open Not Applicable Not Applicable
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| >2725 volts-each bus>57.4.Hz-each bus>750 psig>lX open Not Applicable Not Applicable
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| ~TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low 3/Stm.Gen.2/Stm.Gen.any Stm.Gen;2/Stm.Gen.1,2,3 14*b.4 kv Bus Loss of Voltage 2/Bus 2/Bus 2/Bus 1,2,3 14*7.TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low 8.LOSS OF POWER 2/Stm;Gen.2/Stm.Gen.1, 2, 3 3/Stm.Gen.any 2 Stm.Gen.a.4 kv Bus Loss of Voltage b-4 kv Bus Degraded Voltage 3/Bus 3/Bus 2/Bus 2/Bus 2/Bus 2/Bus 1,2,3 1,2,3 14*14*
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| ~~'i I a TABLE 3.3-4 Continued t ENGINEERED SAFETY FEATURE ACTUATION SYSTEt1 INSTRUMENTATION TRIP SETPOINTS J'FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES.6."-t)OTOR DRIVEN AUXILIARY FEEDMATER PUMPS a.Steam Generator Mater Level--Low-Low b.4 kv Bus Loss of Voltage>174 of narrow range instrument span each steam generator 3196 volts with a 2 second delay>17%%d of narrow range instrument span each steam generator 3196+18 volts with a 2+.2 second delay.7.~>17%of narrow range instrument span each steam generator t"8.'."LOSS OF Pt'MER 3l96 volts with a 2 second delay l 3596 volts with a 2.0min.'ime delay 4 kv Bus Loss of Voltage b 4 kv Bus Degraded Voltage h TURBINE DRIVEN AUXILIAP".
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| FEEDMATER PUMPS.a.Steam Generator Mater Level--Low-Low>17%nf narrow range instrument span each steam generator I I 3196+18 volts with a 2+.2 second delay 3596+18 volts with, a 2.0 minute+6 aectnd time delay*
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| I I I TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION U VEILL NCE E UIREMENTS FUNCTIONAL UNIT 4.STEAM LINE ISOLATION a.Manual b.Automatic Actuation Logic c.Containment Pressure--
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| High-High d.Steam Flow in Two Steam Lines--High Coincident with T--Low or Steam Line'flksure--Low 5.TURBINE TRIP AND FEEDWATER ISOLATION a.Steam Generator Water Level--High-High CHANNEL CHECK N.A.N.A.CHANNEL CALIBRATION N.A.N.A.R CHANNEL FUNCTIONAL TEST M(1)M(2)M(3)MODES IN WHICH SURVEILLANCE RE VIREO 1,2,3 1,2,3 1,2,3 1, 2, 3 1,2,3 6.MOTOR DRIVEN AUXILIARY FEEDLIATER PUMPS a.Steam Generator Water Level--Low-Low b.4 kv Bus Loss of Voltage 1, 2, 3 1 2 3 TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHECK Steam Generator Water Level--Low-Low r;8.'OSS OF POWER'.4 kv Bus Loss of Voltage 4 kv Bus Degraded Voltage;FUNCTIONAL UNIT:, 7..: TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS CHANNEL CALIBRATION R CHANNEL FUNCTIONAL TEST MODES.IN WHICH SURVEILLANCE RE UIRED 1,2,3 1,2,3=-1,2,3 DONALD C.COOK NUCLEAR PLANT UNIT NO.2 CHANGE NOS.5 AND 6 AEP:NRC:00313 C)TABLE 2.2-1 Continued)
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| 'FUNCTIONAI UNIT~'13:;Steam Generator Water Level-Low-Low 14~Steam/Feedwater Flow , Hismatch and Low Steam Generator Water Level REACTOR TR!P SYSTEM INSTRUHENTATION TRIP SETPO!NTS TPIP SETPOINT ALLOWABLE VALUES~01=2~of narrow range instrument
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| >>Af narrow range instrument span-each steam generator.span-each steam generator I 6<1.47 x 10 lb/hr of steam flow<1.56 x 10 lbs/hr of steam flow 6 t at RATED THERMAL POWER coincident at RATED THERHAL POWER coincident with steam generator water level with steam generator water level>25-of narrow range instru->24K of narrow range instru-ment span-each steam generator ment span-each steam generator.15;-Undervoltage
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| -Reactor.: 'Coolant Pumps 16'.Underfrequency
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| -Reactor.Coolant Pumps'17;Tur bi ne Tr i p:.A.Low Trip System Pressure-".-B.Turbine Stop Valve'losure I 18e Safety Injection Input;from ESF 19;Reactor Coolant Pump.: Breaker Position Trip>2750 volts-each bus!>58.2 Hz-each bus 1/>58 psig I>lX open Not Applicable Not Applicable h bus~58.1 Hz-eaa>57 psig<ll open Not Applicable
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| >2725 volts-'each bus TABLE 3.3-3 (Cont)nued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION
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| : "FUNCTIONAL UNIT TOTAL NO.OF CUANNELS CNANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION~7 b, 4 kv Bus 2/Bus Loss of Voltage TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS'6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low 3/Stm.Gen.2/Bus 2/Bus 2/Stm.Gen.any Stm.Gen.2/Stm.Gen.1,2,3 1,2,3 14*14+a.Steam Generator Water, Level--Low-Low 3/Stm.Gen.2/Stm.Gen.2/Stm.Gen.any 2 Stm.Gen.1 s 2o'14*8.LOSS OF POWER a.4 kv Bus Loss of Voltage I g/Bus 2/Bus 2/Bus 1, 2, 3 14*b.4 kv Bus Degraded Voltage 3/Bus 2/Bus I 2/Bus 1,2,3~~
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| e~V TABLE 3.3-4 (Continued
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| \ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS n CD CD FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 6.-MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Mater Level--Low-Low b, 4 kv Bus Loss of Voltage 7;.TURBINE DRIVEN AUXILIAPY FEEDWATER PUMPS'-a.Steam Generator Water Level--Low-Low I>2lgof narrow range instrument span each steam generator 3196 volts with a 2 second delay>21$of narrow range instrument span each steam generator>2lpf narrow range instrument span each steam generator , 3196+18 volts with a 2+.2 second delay>2lgof narrow range instrument span each steam generator'8;LOSS OF PG'HER a.4 kv Bus Loss of Voltage b.4 kv Bus Degraded Voltage 3196 volts with a 2 second delay I 1 3596 volts with a 2.0min.time delay 3196 a 18 volts with a 2+.2 second delay 3596+la volts vfth, a 2.0 minute+6 second time delay' 4.A<<~a 4a<~-4>>y'>>0 aL>>sk w.>>$i,>><<u>>>>u>>>>
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| iW>>~O>>h>>>>J>>t
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| <<>>lrA4llllA4'4<<~CA>>w&l>>lsA&rJa~
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| >>WWe<<>><<>><<>>W>>a<<1>>>>WWel>>~t<<w>>>>krwL'l o~aul Q Pl C)C)7%CHANNEL FUNCTIONAL UNIT CHECK 7..'URBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level--Low-Low S 8,.LOSS OF POWER a.4 kv Bus Loss of Voltage b.4 kv Bus Degraded Voltage CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIOH SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS MODES IN WHICH SURVEILLANCE RE UIRED 1,2,3 1,2,3 1,2,3.
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| ATTACHMENT
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| 'C'O AEP:NRC:00313 SOUTHWEST RESEARCH INSTITUTE REPORT;SWRI:.'ROJECT 02-4770 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FOR DONALD C.COOK UNIT NO.1 ANALYSIS OF CAPSULE T}}
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