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Text

Proposed Tech Specs Deleting Footnotes Re Surveillance Interval Extensions
	ML17325A921
Person / Time
Site:	Cook
Issue date:	09/15/1988
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17325A922	List: ML17325A921; ML17334B228;
References
	NUDOCS 8809230206
	Download: ML17325A921 (103)
	v • d • e

3/4'APPLICABILITY SURVEILLANCE REQUIREMENTS b.Surveillance intervals specified in Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice ins ection and testin criteria Required frequencies for performing inservice inspec-tion and testin activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days C.The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 Amendments 100, 107 and 108 granted extensions for certain surveillances required to be performed on or before July 31, 1987, until the end of the Cycle 9-10 refueling outage.For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Uni.t 1 1987 refueling outage.r, os>"oo>>', Oggg02C)~P50 Pgg ping P Donald C.Cook-Unit 1 3/4 0-3 Amendment No.

v 3/4.3 INSTRUMENTATION 3 4 3 1 REACTOR R IP'5 YST~INSTRUMENTATION LIMITING CONOITION FOR OPERATION s a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.Appl.ICABIl.ITY:

As shown in Table 3.3-1.ACTION: As shown in Table 3.3-1.SURVEILLANCE RECU IRB",ENTS 4,3.1.1.1 Each reactor trip system instrumentation channel shall be demonstra:ed OPERABLE by the per formance of the CHANNEL CHECK, CHANNEl.CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the NODES and at the freouenc'es shown in Table 4.3-1.4.3.1.1.2 he logic for the interlocks snail be demonstra:ed OP=o~SLK.prior'o each reac:or star.up unless per".rmed dur ing tne pr eceding 92 days.The total interlock function shall ze demonstrated OPERABLE at least once per 18 months during CHANNEL C'LIBRATION testing of each channel a f fec:ed by interlock operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reac.or.rio function shall be demonstrated to be within i: s limit at least:nce oer 18 months.Each test shall include at leas: one logic train such that both logic trains are tested at least once per 36 months and one channel"er function sucn that all channels are tested at least once every N times 18 months where N is the.otal number of redundant channels in a specific reactor trip fvnc:ion as shown in the"Total No.of Channels" column.of Table 3.3-1.D.-C.COOK-UtiTIT 1 3/4 3-1 Amendment No.

CI 8 O I FUNCTIONAL UNIT 1.Manual Reactor Trip A.Shunt Trip Function B.Undervoltage Trip Function CHANNEL CHECK N.A.N.A.N.A.N.A.S/U(1)(10)S/U(1)(10)CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST MODES IN WHICH SURVEIL~MHCE le 0 s3*e4+e5*2.Power Range, Neutron Flux 3.,1'ow~r R.>f1(Ju, Neutron Flux, High k'ositive Rate 4.Power Range, Neutron Flux, High Negative Rate S N.A.N.A.D(2,8),M(3,8)

M and S/U(l)and Q(6,8)R (6)R (6)1, 2 and+1, 2 1, 2 5.Intermediate Range, Neutron Flux R(6,8)S/U (1)2 and*6.Source Range, Neutron Flux 7.Overtemperature AT 8.Overpower hT 9.Pressurizer Pressure-Low 10.Pressurizer Pressure-High 11.Pressurizer Water Level--High o 12.Loss of Plow-Single Loop S R(6, 16)R(9)R(9)R(8)M (14)and S/U (1)M (7)3 (7)4 and 5 1, 2 1, 2 1, 2 1, 2 1, 2

TABLE 4.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS A O O I FUNCTIONAL UNIT 13.Loss of Flow-Two Loops 14.Steam Generator Water Level-Low-Low CHANNEL CHECK CHANNEL CALI BRATION R(8)CHANNEL FUNCTIONAL TEST N.A.MODES IN WHICH SURVEILHlNCE RE UIRED 1, 2 15.Steam/Feedwater Flow Mismatch and S Low Steam Generator Water Level 1, 2 16.Undervoltage-Reactor Coolant Pumps 17.Underfrequency-Reactor Coolant Pumps 18.Turbine Trip A.Low Fluid Oil Pressure B.Turbine Stop Valve Closure 19.Safety Injection Input from ESF 20.Reactor Coolant Pump Breaker Position Trip 21.Reactor Trip Breaker A.Shunt Trip Function B.Undervoltage Trip Function N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.,R N.A.N.A.N.A.N.A.N.A.N.A.S/U (1)S/U (1)M(4)M(5)(ll)and S/U(l)(11)M(5)(ll)and S/U(l){ll)1/2 1, 2 1, 2 N.A.3*4*5*3*4*5*Q 22.Automatic Trip Logic 23.Reactor Trip Bypass Breaker N.A.N.A.N.A.M(5)N.A.M(12)and S/U(l)(13)3*4*~5*1 2 3*4*5*

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFKTY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.2.1 The Engineer ed Safety Feature Actuation Sp'stsn (ESFAS)inst tion channels and interlocks shown in Table 3.3 3 shall~OPE~BLE with their'riP setPoints set consistent with the values shown in the.Trip Setpoint column of Table 3.3-4 and with RESPONSK Tl?IKS as shown in Table 3.3-5.APPLICABILITY:

As shown in Table 3.3 3.ACT10N: il a, With an ESFAS instrumentation channel trip setpoint less conserva tive than the value shown in the Allowable, Values column of Table 3.3-4, decla.-'e'.he channel inoperable and apply the applicable AcTIGN rcouirement of Table 3.3-3 until the channel is restored to GpER'BLE sta.us with the trip setpoint ad)usted consistent with".the T ri p:Se t po in t va 1 ue.b, With an sS~AS ins.rumentation channel inoperable., take the ACTION shown>n aoie 3.3-3.SUR'Is ILLANCK R(QU I Rc~sNTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERASLE by the performance of the CHANHKL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the.'tODES and at the f r equ enc i es shown in Tab 1 e 4,3-2.4.3.2.1,2 The logic for the inter locks sha11 be demonstrated OPERABLE during the automatic actuation logic test.The total interlock function shall be demonstrated OPERABI.E at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1,3 The ENGINEERED SAFETY FKATURKS RKSPONSK TIME of each KSFAS function shall be demonstrated to be within the limit at least once per 18 months.Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 mon.hS where N iS the.tOtal number Of redundant ChannelS in a SpeCifiC ESFAS function as shown in the"Total No.of Channels" Column of TabIe 3.3-3.O.C.COOK-UNIT 1 3/4 3-1S hzaendmeat No.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS n o O I g FUNCTIONAL UNIT CHANNEL CHECK 1 SAFETY INJECTION I TURBINE TRI P~FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE RE UIRED a.Manual Initiation b.Automatic Actuation Logic c.Containment Pressure-High d.Pressurizer Pressure-Low e.Differential Pressure Between Steam Lines-High f.Steam Flow in Two Steam Lines-High Coincident with T-Low or Steam Line PNRsure-Low N.A.N.A.N.A.N.A.M(1)M(2)M(3)1, 2, 3, 4 1, 2, 3, 4 1, 2, 3 1;2, 3 1, 2, 3 1, 2, 3 2.CONTAINMENT SPRAY O a.Manual Initiation b.Automatic Actuation Logic c.Containment Pressure-High-High N.A.N.A.S N A.N.A.M(1)M(2)M(3)1, 2, 3, 4 1, 2, 3, 4 1, 2, 3 TABLE 4.3-2 Continued EtiGIHEERED SAFETY f EATURE ACTUATIOtt SYSTEH INSTRUHENTATION

~5II E ELLE E NE III ENINIE FUNCTIONAL UNIT 3.COHTA I NHEHT I SOLAT ION a.Phase"A" Isolation 1)-Hanua I 2)Fran Safety Injection Automatic Actuation Logic b.Phase"0" Isolation~j)Hanua 1 2)Automatic Actuation Logic 3)Containment Pressure--

Hi gh-Hi gh c.Purge and Exhaust Isolation 1}Hanual 2)Containment Radio-activity-tligh CHANNEL CHECK N.A.N.A.N.A.tI.A.N.A.CHANNEL CAL I BRAT IOH N.A.H.A.N.A.N.A.N.A.CHANNEL FUNCTIONAI.

TEST tt{1)ti(2)tt{1)ti(2)ti(3)V(I)INDES IH MHICB SURVE ILLAHCE NEIL I E 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4-1,2,3 1,2,3,4 1,2,3,4

O 0 0 I U z g.0 TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUM NTATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL TEST CHANNEL CHECK CHANNEL CALIBRATION FUNCTIONAL UNIT 4.STEAM LINE ISOLATION M(l)N.A.a.Manual N.A.b.Automatic Actuation Logic N.A.N.A.M(2)c.Containment Pressure-S High-High M(3)d.Steam Flow in Two Steam Lines-High Coincident with T-Low-Low PBRsure-Low 5.TURBINE TRIP AND FEEDWATER ISOLATION M a.Steam Generator Water Level-High-High 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low b.4 kv Bus Loss of Voltage c.Safety Injection d.Loss of Main Feed Pumps M(2)N.A.N.A.N.A.N.A.MODES IN WHICH SURVEILuiNCE REOUIRED 1/2, 3 1/2 l/2/1/2, 3 I/2/3 2, 3 11 2(3 l/2 n A O 0 I R H TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNCTIONAL UNIT CHANNEL CHECK CHANNEL CALIBRATION CHANNEI MODES XN WHICH FUNCTIONAL"URVEILLANCE T1.'RE UIRED 7.TURBINE DRXVEN AUXILIARY FEEDWATER PUMPS a.Steam Generator Water Level-Low-Low M l, 2, 3 b.Reactor Coolant Pump Bus Undervoltage 8.LOSS OF POWER a.4 kv Bus Loss of Voltage b.4 kv Bus Degraded Voltage N.A.S M 1, 2, 3 I, 2, 3, 4 1, 2, 3, 4 0

.TABLE 4.3-4 SEISMIC MONI TORI tlG ItISTRUMENTATIO I SURVEILLANCE REnul REMENTS INSTRUMCthT CIIAt<NCL 1.STRONG MOTION TRIAXIAL ACCELEROGRAPIIS a.Reactor Pit Floor 1.Time History Recorder 2.Seismic Trigger b.Top of Crane Wall 1.Time History Recorder c.Free Field 1.Time History Recorder 2.Seismic Trigger 2.PEAK RECORDING ACCELEROGRAPIIS a.=-Containment Spring Line b.Diesel Generator Room Floor c.Sp'ent fuel Pool CHANNEL CHECK M I'lA M M.NA tlA NA NA CHANNEL CAL I BINT IOtl.R-R CHANNEL fUNCTIONAL TEST=M tlA M tlA NA flA TABLE 4.3-6 BEHOlf SHUTOOWN HOHITOR IHG IHSTRUHEHTATION YuuiPiKDNi.'Hi[

fKANK IHSfR<NEHf I.Reactor frlp Breaker lndlcat ion Presswi.l ver Pressure Press<<>iver level 4.Steam Generator Level 5.Steam Generator Pressure CllAHHEL CllECK H.A.QIAHHEL CAL I GRAT ION H.A.

ThBLE 4.3-7 POST-hCCIDENT HONITORINC UNENThTION SURVEILlhNCE R UIREMENTS A INSTRUMENT A 8 1.Containaent Pressure 2.Reactor Coolant Outlet Teaperature

-T (Mide Range).HOT 3.Reactor Coolant Inlet Teaperature

-T (Mida Range)COLD I 4.Reactor'oolant Pressure-Mide Range 5.Pressurizer Mater Level 6.Steaa Line Pressure CHhmlEL CHECK CllhNNEL ChLIBRhTION 7.8.Steaa Generator Mater Level-Narra@Range RMST Mater Level ,H w 9.lo: I u~11.Ch 12.13.14.15.16.17.18;I'1)(2)(3)Boric hcid Tank Solution Level huxiliary Feeduater Floe Rate Reactor Coolant Systea Subcooling Hargin Honitor PORV Position Indi'cator

-Liait Switches PORV Block Valve Position Indicator-Liat.t SMitches Safety'Valve Position Indicator-hcoustic Honi.tor Zncore Theraocouples (Core Exit Theraocouplos)

Reactor Coolant Inventory Tracking Systea (Reactor Vessel Level Indication)

Containaent Suap Level~Containaent Mater Level**H(2}R(l)R(3)Partial range channel calibration for sensor to be perforaed bolo+P-12 in HODE 3.Qith one train of Reactor Vessel Level Indication inoporabl S b li H i nopora o, u coo ng argin Indication and Cora Exit Theraocouples aay be used to perfora a CHhNNEL CHECK o if OPERhBLE.to ver y the reaaining Reactor Vessel Indicat on train Coapletion of channel calibration for sensors to be perforaed baloM P-12 in MODE 3**The requireaents for these instruaents vill becoae eff i f h 1 1 replaced and becoae operational.

The schedule for aodificatio ecoae e act ve after t e oval transaitters are aodi fied 0 e or in tlm Saies.e or ao ication or replaceaent.of the transmitters is described ACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLP~T SYS Df LEAKAGE LEAXACE DETECTION SY~S LQQTWG CONDITION 7OR OP~MTION J 3.4.6,1 The foll~g Reactor Coolant System leakage detection systems shaIl be OP~~L--: a.One of the containment at osphere particulate radioact vity monitozing channels (ERS-130L oz ERS-1401), b.The contai=cnt sump level and floe monitozing system, and w c.Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-1305 or ERS-l405).AP.ICASILITY:

NODES 1, 2, 3 and 4.ACTINO'M: Pith only ter of the above required leakage detection systems OPHASLE, operation may continue foz up to 30 days provided grab samples of the containment at=ospheze are obtained and analyzed at least ence per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months vhen the required gaseous and/oz particulate radioactivity mon'or'ng chatnels are inoperable; othea<se, be m at least HOT=STA%)SY a~thin the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s<and in COLD SHUTTER".i vithm the follcnMg 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RECUI3.~aS 4.4.6.1 The leakage detection systems shall be demonstrated OP~LE by: b.Co Containment a~sphere particulate and gaseous (if bei"g used)monitoring system-performance of CMNEL MCK>CHANNEL CALZBRAT ION and CBANNEL FUNCTIONAL TEST at the frequencies specified in Table 4,3-3, n Containment sump level and flov monitoring system-pezformance of CKQiNEL CALZ3RATZON at, least once pez 18 months, Containment humidity monitor (if being used)perfoz=>>ce o CP~N~i CALI3RATIOH at least once pez 18 months.D..Co COOK-CN: 1 3I4 4-14 Amendment Ho.

RE C 0 COO T SYST LIMITING COND TION FOR OPERATION Continued 2.With two or more block valves inoperable, C.within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1)restore a total of at least two block valves to OPERABLE status, or,(2)close the block valves and remove power from the block valves, or (3)close the associated PORVs and remove power from their associated solenoid valves;and apply the portions of ACTION a.2 or a.3 above for inoperable PORVs, relating to OPERATIONAL MODE, as appropriate.

With PORVs and block valves not in the same line inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1)restore or (2)close and de-energize the Apply the portions of ACTION a.2 OPERATIONAL MODE, as appropriate unavailable.

the valves to OPERAB'status other valve in each line.or a.3 above, relating to for two or three+ne~d.The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREME TS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE: a.At least once per 31 days by performance, of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.A't least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.The block valve(s)do not have to be tested when ACTION 3.4.ll.a or 3.4.11'is applied.4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries.

This testing can be performed in conjunction with the requirements of Specifications 4.8.1.1.2.b and 4,8.2.3.2.d.

PORVs isolated to limit RCS leakage through their seats and the block valves shut to isolate this leakage are not considered inoperable.

D.C.COOK-UNIT 1 3/4 4-36 AMENDMENT NO~

5URVEILLA 1CK RKQUfR-""~"T5 (C ntinued)b.At le s-.onc".er 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after eacn solution volume i,".-," se or~1'" of t'ni<volume by verifying the boron conc ntra:i"n o...".ac".,"..ulator solution.c.At le st"n"."er.'1 days when the RCS pressure is above 2000 psig, by verify'ng:hat "ower to the isolation valve operator is disconrec:ed by removal of the breaker from the circuit.d.'lerifying a.1 as::nce per 18 months that each accumulator isolation valve ope..s autoratically upcn receipt of a safety injection:

st signal.0~C.C v'OK U!e i T 3/4 5-2 Amendmenc Vo.

g~GDCY CDRE CDOLIlf6 SYSTEMS SURY<)t.LANCE RK"UIRQ.I S tCert<<ued)

At 1ust once per 18 months by: 1.Verifying auto..atc fsolation and fnterlock ac fcn oi'he RHR system from the Reector Coolant Sys N~hen the Reactor C"olant Sys:cn pressure is aNve 600 psig.2.A vfsual fns".ec..cn of the contafnent Sump and ver'.fy',ng

'that the subsystea suction inl e.s are.tet restrfc:ad by debr(s and that the sumo cceponents (trash racks.screens, ea.)shoe no evidence of structural dfstress or abnormal co s'n~At least once.'per 18 months, during shutdown by: 1, Ye.i ying that each automatic valve fn the floe path actuates to its correct pas;t.'cn on a Safety tnjectlon t st s;gr~l.2.'er"..ping that each o.the f:jl~~.:ng pumps start au.omatically u""n rece'.'pt of a safety injectior.

test s'goal: a)Centrifugal charging pump b)Safety fnjectfon pump c)Resfdual heat removal pump 8y verifying that each of the following pumps develops the fndfcaced discharge pressure on recirculation flow~hen tasted pursuant to Specii'fcation 4.0.5 a" Leos=once per 31<<Ys on a STEERED TEST BhS:S;1.Cen.-.ffugal c."urging ptas>24CS psig 2.Safety ln jecf.".on pump i 1445 psig 3.Resfdual heat".c",.oval pump+195 psfg g.Py ver..'y<<g the cor rect posi ti n cf each mechanical stop for th the follo~irg Eme.gency Ccr e Cooling System throttle valves: Qfthfn 4 h".urs following completion cf each valve stro">n9 ot:erat:Qn

".r,"aintenance cn the valve~hen the gC{',S sub-sysiCes are req>red io be.GPEVBLE.

hw g ea u~e yo a lf o Oo Co C<C.(i<>fŽg 3/4 5-5 EqERQf'HCY CORE COOL?MQ SYSTEMS SURVEILLANCE RE'IRE.".EATS 4.5,3.1 The E;.CS subsystem sna11 be demonstrated QpERABL=per the applicable Survei 1 lance Requi'r ements o f 4.S.2.4.S.3.2 All charging pumos and safety injection pumps, except the above required OPERABLE cha.ging pumo, shall be demonstrated inoperable, by verifying that the motOr CirCuit breakerS have Ceer r'emoved from their electrical po~er supply circuits, at least once oer'..2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months whenever the temperature of one or more of the RCS cold legs is less than or edual to 170'F as determined at least once per hour~hen any RCS cold leg temperature is between 170 F and ZOO~F.9~C~COOK UNIT 1 3/4 5-8 Amendment No

C QHTAIHMKHT SYSTFHS 3/.6.2 oE HSURIZATEOH ANO COOLING SYSTEMS CON'AIHHBT SPINY SYS-p LEHITTHG CONOITTOH FQg Op@PAT,OH"" en-s"ray systams shall be OPeyBLg with each spray system capable of taking suction fran tnc RMST and transferr ing suction to".ne containment sump.APPLICABILITY:

MOORS 1, 2, 3 and 4, ACTION: MICh one containm nt spr ay system inooerable, restore the inoperable spray systen Co OP"=RABLK stat"s<<,thin 72 hcurs or be in a.leas-HOT S AHOBY wi thin the next 6 hcurs;res:"r:he incpe.abl e spray systarr to OPGRABL:-status with n t.".e nex-48 hours or be in C"LQ SHUTOOMH wi:nin the fol lcwing 30 hcur s.SL'RVE'N K RE@'IFK."ANTS

<.6.2.1 a.Each c"ntainmer.t spr ay systen shall be da"..cnstrated 0?KRABLE: At least once per 31 days by ver.'!ying that each valve (manual, power cperated cr automat c)in the flow path tnat is not locked, sealed.or otherwise sec red in-csi:ian, is in its carr ect,osi:-n.

C.d.By ver ify'.'ng, that an r ecirculation flow, each pump develops a discharge pr ssur e of~-2 psig at a.lcw of~700 gpm, when teSted purSuant CO SpeCifiCatiOn 4.0~5 a"'east once oer 31 days 0 iAuv<<d 3 T 8<~At 1 east once:cr 18 months during shutdcwn, by: I.Verifying:.-at each automatic valve in the flow path actuates to i: s correct posi:ion cn a Contairmen-

?reSSur e--ri'."h-High teSC Signal.2.Yer i y>"",:.".at each s"ray puma starts automa ically on a ConCainment

?ressur e-High High est signal.At least, once t;c 5 years by performing an air or smoke flo test Chraugh ea=.".scrzy header and verifying each sp~ay nozzle is uncbs=.-.ct c.D.C.Cock-Unit 1 3/4 6-10 Amendment No.

CQVTA>>i+I:NT SYST"uS 5,.~'iC l)r.I~c.At least once oe.18 months dur'.'ng shutdown, by: 1.Cyclino each oower operated (evcluaing automatic}

valve in the f.cw pat.".t.".at is not testao',e curiing plant operat on, through 1gsri's r s~q g.~t air isa'It 4~tc wv~alia~w wjw~a Gl iul i trcvel 2.Verifying that each automatic valve in the flow path actuates to its correc-oosItion on a Containment Pressure--High-Hign 51gi1a I.d.At least once per 5 years by veri fying a water flow rate o at least 20 gpm (>20 opm)but not to exceed 50 gpm (<50 gpm)from the spray additive tank tept line to each c ntainment spray sys'em with the spray pump opera ing or recirculation with a pump discharge pressure>255 ps'g.3/~6" 13 Amendmen Ho.

COi')TA I ill'.E LIT<<v5~~1IS SURVEILLAi<C" REO<l;~"-'J=" S (C ntinue")valve or its assoc at d ac.uator, con:ro1 or power circu.'.by performance of the cycling test, above, and verification of isolation time.4.6.3.1.2 E ch isolat on'alve soecified in Table 3.6-1 shall he de...on-strated OPEiMBL during the COLO S'OUTDO'Jig or REFUE'HG MOOE at le st once per 18 months by: a..b.Verifying that on a Phase A containment isolation tes.signal, each Phase A isolation valve actuates to its isolation position.\Verifying that on a Phase 8 containment isolation test sianal, each Phase 8-isolation valve actuates to its iso)ation position.c, Verifying that on a Containment Purge and Exhaust isolation-signal, each Purge and Exhaust, valve actuates to fts, isolation position.4.6.3.1.3 The f.so'atf.on t'=e of each povet ope"ates ot automt1c valve or.Table 3.6-E s;"sU.be detenf.".ed to be vi"hie its l&~t vhen testeC pu"suant to Spec'=~cat'cn 4.0.5.O.C.CCOY-"!lIT 1 2/4 6-15 P.ec"-e..t'V~io~

CON SURV L C U REMENTS Continued shall be constituted of one baske" each from Radial Rows 1, 2, 4, 6, 8 and 9 (or from the same row of an adjacent bay if a basket from a designated row,cannot be obtained for weighing)within each bay.If any basket is found to contain less than 1220 pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed.The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1220 pounds/basket at a 95%level of.confidence.

The ice condenser shall also be subdivided into, 3 groups of baskets, as follows: Group 1-bays 1 through 8, Group 2 bays 9 through 16, and Group 3-bays 17 through 24.The minimum average-ice weight'of the sample baskets from Radial Rows 1, 2, 4, 6, 8 and 9 in each group shall not be less than 1220 pounds/basket at a 95%level of confidence.

The minimum total ice condenser ice weight at a 95%level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not.be less than 2,371,450 pounds.Uerifying, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of 3/8 inches.If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visually inspected.

If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.

More than one restricted flow passage per bay is evidence=of abnormal degradation of the ice condenser.

c~,At least once per 40 months by lifting and visually inspecting the accessible portions of at least'wo ice baskets from each 1/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear, cracks, corrosion or other damage.The ice baskets shall be raised at least 12 feet for this inspection.

D.C.COOK-UNIT 1~~3/4 6-27 Amendment Ho~

@OS Owe'3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPE~LE.U&SliilX: d5ZIM: Mich one or more ice condenser doors open or othervf.se inoperable, PQ'~ZR OPEBhTION may continue for up to 14 days provided the i.ce.bed temperature is monitored at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the maximum ice bed temperature is maintained

<27 F;otherwise, restore the doors to their'closed 0 positions or OPERhBLE status (as applicabl.a) vithin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY vichin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN Mich'.n the.following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .4.6.5.3.1 Inlet Doors-Ice condenser inlet doors shall be: a.Continuously monitored and determined closed by the inlet door position monitoring system.and b.Demonstrated OPERhBLE during shutdown at least once per 9 months by: I 1.Verifying that the torque required to initially open each door is g 6?5 inch pounds.2.Verifying that opening of each door is not impaired by ice, frost or debris.3.Testing a sample of at least 50%of the doors and verifying that the torque required to open each door is less than 195 inch-pounds when the door is 40 degrees open.This torque is defined as the"door opening torque" and is equal to the nominal door torque plus a frictiona1 D.C.COOK~UNIT 1 3(4 6-30 Amendment No~

II~~I~I]I~I~~I~~~~~~~I~~)~~~~~~g o l~~~~~~4~~~I~I~~~~~~~~~~~~~~~I~I I I 0 g~~~0~~I~~~~~~~~~~~~~~~0~~~~~~~~~

PCAg A T~I~~I tl~S YS OIV I".SARRIER?c..SO.",,"cl RC=5 OQO?S.<"u'U I"!='iT'.'A LIHITI'IG CONOITTQN FOR 0?c~A, ION 3.6.5.5 Tne personnel access doors and eauioment hatches between the ,containment's uoper and lower compartments shall be OP RABi'nd closed, APPLICABILITY:

IiOQES I, 2, 3 and 4.ACTION: With a personnel access door or equioment hatch inooerable or open exceot for personnel transit entry and T>200'F, restore the door or hatch to OPEP~BLE status or to its close3 3osition (as aoolicable) within I hour or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTOOMN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE REQUIRcllE!iTS

'4.6.5.5.1 The personnel access doors and eau.'oment hatches between the c"ntainment's upper and lower comoartments shall be determined closed by isual insoection prior to increasina the R actor Coolant Syst~~Tabove 200'F and after each oersonnel transit entry when the Reactor, Coolant Svstem lav is above 200'F<.6.5.5.2 The personnel ac"ess doors and equipment hatches between the containment's uppe.and lower compartments snail be det rmined OPEPABLE bv visually.inspec"ing the seals and sealina sur aces of these penetra-tions and verifyira no detrimental misaIign~ents, cracks or defects in the sealing surfac s, or aoparent deterioration o, the seal material: a.Prior to final closure of the penetration each time it has.been ooened, and b.At least ence oer 10 years-"or penetrations containing seals fabrica.e=

-.ro~resilient materials.

AK ssasl.3/4 6-34 Amendment No..

DIVIDER BARRIER SEAL LIMITING CONDITION.=OR OPERATION 3.6.i.9 The divider barrier seal shall be OP%ABLE.APPLICABIL.ITY:

NODES I, 2, 3 and 4.AC TON: Mfth the divider barrier seal inooerable, rcs.ore the seal to OPBABLE status prior to',ncrc sing tne Reactor Coolant System emoerature above 200'F.StlRVEILDNCE REOU IRK".~." 4.5.6.9 The divider barrier seal shall be dete~incd OPEQELK,at Icas.once per 18 months during shutoown by: a.Removing-.m divide.barrier seal test couoons and veri ying..hat thc onysical properties o,'the test couoons are within the acceotaole range of values show'n in aole 3.6-2, b.Visually insoecting at Icas 96 percent o.the seal's entire length and: Ycrifying>at the seal and seal mount ng bolts arc pro-oerly insuIIcd, and 2.Verifyi ng that the seal mater ia1 shows no visual cvioence of deterioration due w holes, ruoturcs, chemical attack, abrasion, r adiat'.on carnage, or changes in pnysical aooearanc s.0~C~CQOK<NIT I 3/4 6 38 Amendment No.

PLANT SYSTEHS SURVEZ~CE RE UIREMNTS (Continued>

3, verifying that each non>>automatic valve in the low pathat's not Locked, sealed, or otj crwise secured in"-s"'cn is in its correct position.4~verify'ng that each automatic valve in the flow path is in"he ully open pos'tion whenever the auxiliary feedwater system is placed in automatic control or when above L01 RATED THEPMAL POWER.This requirement is not applicable

="" those por"ions of the Auxiliary~eedwater System being used intermi tert'y to maintain steam generator level.b.At'east csee"er l8 months dur'ng shutdown by: ':e'<<ying that each autcmatic valve in the flow path ac"ua es tc its correct-os'ion upon receipt of the a"prcor'=e encineered safes" features actuation test s=na l recuired"y Spec'ication 3/4.3.2.S C~yinet that each auxiary feedwater pump starts as" s'oned autcma ical'y upor.receipt of the appropriate e.",g'neered sa e v fea"ures a""uatior.

test signal, required.'y Specification 3/4.3.2.D.C.CQQK UNIT 1 3/4 7 6 Amendment No

PLANT SYSTEM 3 4.7,3 COMPONENT CCOLING MATER SYS-i LIH[TING CONOITION FOR OPERATION 3.7.3.1 At least two independen.

component cooling water loops shall be QPE APPLICABILITY:

HOOES 1, 2, 3 and 4.ACTION: With only one comoonent cooling water loco OPERABLE, restore at least..two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANQSY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and:in COLO SHUTGOWN within the fo11ow-ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE REQUIR..9iS 4.7.3.1 At least twc campcnent cooling water loops shall be demonstrated OPERABLE: a..At least once per 31 days by verifying that each valve (manual, power aperated cr automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its-correct posi tion.b.At least once per 18 nanths during shutdown, by verifying that each autcmatic vaive servicing safety re1aced equipment actuat es'o its correct pasitfan on a Safety Injection test signal.C.At least once"er 31 davs on a STg~GZp"0-..==-.gASZS, by verifying that each pump develops a='east 93li of the discharge=ressure for the aPplicable lo>rate as de=rm ned from the manu"acturer's puma performance Curve.0.C.COOK-UNIT L~~3/4 7 15 Amendmen No PLANT SYSTEHS 3/4.7.4 ESSENTIAL SERVICE MATER 5YST LINITING CONOITIQN FOR OPERATION 3.7.4,1 At least two independent essential service water loops shall be OPERABLE.APPLECABE'TY:

MOCES 1, 2, 3 and 4.ACTION: Nth only one service water loop OPERABLE, restore at least two Toops to OPERABLE status wi:hin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months cr be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months anc in COLO SHUTGO'AN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVE.'LL.'NCE o=""-U:"-.=.

=.'(.4.7.4.1 A: least tNo essential service water loops shall be demonstrated OPERABLE: a.At least once per 31 days by v'erify'.ng that each valve (manual, power operated or automat.c) ser vie'ng safety related equip-ment, that is not locked, sealed, or otherwise secured in position, is in its correct position.b.At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct, position on a Safety Injection test signal.c.At least onc-"er 3l days on a STA~EBEO.EST BASIS, hy verifying that each pump develops a=least 93'f the discharge pressure for the appli<<le flow rate as=e"ew..ed from the manufacturer's pump performance Cu>e~.C.COOK-UNET 1 3)4 7-17 Amendment No.

e PL.-'.LT SYST""!iS SURVEILLANCE RE"UIREHE

.'TS (Continued) e.At 1 east once per 18 months by: l.Verifying that the pressure droo across the combined HEPA filters and charcoal adsorber banks is (6 inches Wa ter Gauge while operating the ventilation system at a flow rate of 6000 cfm+10.':..2.Verifying that on a Safety Injection Signal from either Unit 1 or Unit 2, or on a containment phase A isolation signal, the system automatically diverts its inlet flow through the HLPA filters and charcoal adsorber bank and that either fan can then be manually started in the re-circulation mode.I 3.Verifying that the system maintains the control room at a positive pressure of>1/16 inch W.G.relative to the outside atmosphere at a system flow rate of 6000 cfm+10':.f.After each complet or part al replacement of a HEPA filter bank bv verifying that the HEPA filter banks remove>99: of the CCP when they are tested in-place in accordance with ANSI ll510-1975 while operatirg the ventilation system at a flow rate of 6000 cfm+10;;.g.After each comolete or partial reolacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove.-99" cf a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with AllSI N510-1975 whiIe operating the ventilation system at a.flow rate of 6000 c n+10"..0.C.CCOi<-UllIT 1 3/4 7-22 Amendment No.

~~<7 vg<<~~I<<<e<~~SU"'<<L'"",CE

."-=J'-"=""-"<

='r-iruea')c,.;",ptyina a longitudinal samole from an adsorber tray, mixing the adsoroent thoroughly, and obrainirg samples az lees-rwo irches in diameter and with a length equal to the thickness or the bed.Subsequent to reinstalling the adsorber tray used for obraining the carbon sample, the system shall be demonstrated OPERABLE by also: a)Verifying that the charcoal adsorbers remove>99;.;of a halogenazed hydrocarbon refrigerant test gas when they are tested in-place in accordance wi th ANSI i!510-1975 while ooeratinc the ventilation system at a flow rate of 25,000 cfm+10" and b)Verirying that the HEPA filter banks remove>99:;of the 00P when they are tested in-place in accordance with At!SI<1510-1975 while ooerating the venti<ation system at a flow rate or 25,000 crm+10:;.d.At least once per 18 months by: 1.Veriryina that the pressure drop accross the combined HEPA filters and charcoal adsorber banks is<6 inches':later Gauge while operatina the ventilation system at a flow race of 25,000 c-.m.10';, 2.Verifying that the air flow distribution is uniform within 20";: accross HEPA ilters and harcoal adsorbers when test-ed in accordance with A<'SI<!510-1975.Ver.'fyira that the standby fan starts automatic'lly on a Containm<ent Pressure--High-High Sigral and diverts its exhaust flow through the HERA filters and charcoal adsorber banks on a Containment Pressure-High-High SignaI.I After each c..:.oie e or oar: ai replacement of HEPA filter band by verify',na h-t the HERA f..iter banks re-:.ove>99" of.the GO?when they are tested in-pi:ce in ac=ordance witn At!SI!510-1.,=.while ooe.a-...-

=..'.e venciiarion system a a flow rate of 2" 0" c I~C<~,C ha r.<~~---<ri in" 8 A<<<<<<~~p~5 H>~A~4 in-~'c-" C."<~'ete or partial re~lacemen:

of a chare"al<adsoroer-".<<=r.i+cn<a1 aa I aaso 4~s<-"~'4>'<r+c roon errige.ant tes-.gas when ihe<'1=.".ac"".rdance with"SI<'"10-1975 wnile oo.a--=:"n sys-;=-.-., a-.a io': rate of.25,003 cfm-D.C.COO'r'flIThe snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.The inspection interval shall not be lengthened more than one step at a time.4The provisions of Specification 4.0.2 are not applicable.

D-C-Ccok Unit 1 3/4 7-28 Anendnent No'.

P~~SYS~S SURVEILLANCE REOQI~~VtS

~Co.b.ht least once per 18 none&: By per-orming a.system>functional cast vhich includes xMulaced automatic ao uation of the system, and: a)Verifying that the automatic valves in che flcv path aocuaca to their cornet positions on a tesc signa', and b)CycLing each valve ia cha fLo~pach chat ia not tesmble during plant operation through ac Least ona compLece cycle of full ccaveL.X" By inspection of deLuge and preaction type system soray beadeis'to verify their incagn.ty.

3.By inspection o!etch open head deLuge notable to verify no bLochage.c.ht 1cast once per 3 years by performing an, air fLo~cast through each open head deluge header and ver'fying aaoh open head deluge nozzle is unobstructed.

9 C COOR UNIT 1 3/4 7-4$gg~ndment No ELECTRICAL P6RER SY5 i:.">ILLANCc RE IRIS (Continued)

Verifying CA@Pue1 level in Na fuel storage can%, Vorffying chal a sa&le of diesel tuel~~,ha fqI1 s~'ra<+tank is~jtNin">>he ace p bio Iimfu spec<ied$n Table 1 of ATTN 0975-68 when checked'or viscosity, water'and sedigqn, 4.Yerif'ying Ne'ue1 transfer peio can be.starters fry@q contwl panel and runs, e fuel frigo~ie s orage systgg<Ne day ink, 5.Yerifying-Ne diesel starts from ambient condition, 6.'erf.ying the generator, is synzj;r nixed>loaded to~1756 hv, and operates for~60 minutes, and 1 7.Yeri.ying.he diesel genera-.or is a1igned w provide s zncay power to the associated em.gency busses.At 1cast once" r 18-=nths 4 ring shutdown by: Eub'e~t:n:.

the diesel-" an'nsper-.fon in accordance with proceaur>>s prepar ec in c."n'unction wi'.".i+a manufacturer's r>>c."rn:en at.'ons for tris c',ass of standby servic>>, 2.c)Ye.'yi.the g ne.ato," caoabi1'y to r epee-.a load of QQ r.w w t.".ou.tr p", Illg, E Si~u'ia",'rg a loss o, cf.s':owe,".

'.n conjunc-ion xi"5 a saf ty n.'.i-n sigr.al, and: a)Yerifyf ng de-ence",:at-'.on o-..he emergency.asses and load sneodinj f~~-.he esierg ncy.usses.Yerifying.he diesel s:ar.s free ambien condi.ion on:he auto-sMrt signal, nergi zes-'ie emergency busses with pewa~en:y connect>>4 loads, ene".git>>s

~~e auto-connected eery n"y loads'ir ugn toe loa'4 sequencer and ope.at s for~S a inutm while its generator'.s loa4 4 with".he emergency loads..Verify nq that an 4:esel generator trip, the leads are rag t.",>>emaJ-,ency bi:ses and..".Ofesa)r>>starts on..;e aut.-s:art si,nal fal lowirg manual." setting.",=-the oiesel trio'icckou relay, tne~~er,-ency buses'are energi e4 with oernanently con-".e ted loads, the auto-ccnnecte4 emergency loads are".!r"'tee tnrauan tne load seouencer an4-he diesel socrates fo.)6 minutes wnile its generator is ic" 4 wi th the omergercy loads.'.C.C60Y.-UH[T 3/4 8-3 Anendment Ho.

E ECTRIC L OW R STEMS SHt>TDOMg L'I ITING CONDIT 0 FOR OPERATION 3.8.1.2: As a minimum, the following A.C.electrical power sources shall be'PERABLE: a 0 One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b.One diesel generator with: l.A day tank containing a minimum of 70 gallons of fuel, 2.A fuel storage system containing a minimum of 42,000 gallons of fuel, and 3.A fuel transfer.pump.APPLICABILITY:

MODES 5 and 6.ACTION: With less than the above minimum required A.C.electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes*until the minimum required A.C.electrical power sources are restored to OPERABLE status.SURVEILLANCE RE UI EMENTS 4.8.1.2 The above required A.C.electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2.a.6.

For purposes of this specification, addition of water from the RWST does not constitute a positive reactivity addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3.1.2.7.b.2.

D.C.COOK-UNIT 1 3/4 8-5 AMENDMENT NO.

e E~EC TRrC~POWER 8YS Eu>SURVEZLLANCE RE UIREMEVTS (Cort'nued) o 2..he pilot cell soecific gravity, ccrrected to 77 F and=ull electrolyte level (f'uid at the bottom c the nax num'e'dicat'cn nark), is 1.200, 3.The pilo" ceil voltage is 3 2.10 volts, and 4.The overall"attez'y voltage is~250 volts.b.At'east once oer 92 days by veri ying that: 1.The vc':age of each ccnnected cell is K 2.10 volts under."oat charge ard has not decreased more than 0.05 volts rom the value cbsezved duzing the original acceptance test, and:he scec'gravi y;corrected to 77=" and full elec=roly-.e'evel (fluid at the bcttom of the maximum'evel nd'=a".on nark), of each connected ceis'.200 and".s rot decreased mere than 0.03 fzom the va'ue observed during the previous test,, and 3.The elec""c.vte

'eve'f each connected cell's between'.e".cp"-="he minimum level indicat'on mark and the bottc...c=-he maximum'evel indicatŽn mark.c.At'east ence per 18 non"hs by ver'irg that:.he cel's, cell plates are batte v zacks show no visual indicat'on of physical damaae cr abnormal deterioration..he cell-to-cell ard te mzral connections aze clean t'cht, free of ccrzosion ard coated with anti-corrosion mater'l.3.The battery cha ger will supply at least 140 ampezes at 250 vc'"s for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .d.A" least once."=" 18 months, duz'ng snutdown (MODES 5 or 6),"y veri.fy.".=.that the battery capacity is adequate to su"ply are na n=ain zn CPERABLE status the emeraency loads=or the t nes soecif'ed in Table 4.8-1A with the battery charcer disccnnected.

The battery terminal voltaae shall be ma ntained-:'olts throughout the battery service test.e.At least cree pe 60 morths, duzing shutdown (MODES 5 or 6), by veri y'nc tha" the battery capacity is at least'04 of the ma..u acturer's rating when subjected to a performance dischazce test.Th's pezfornance discharge test shall be pe" ormed in p'a=e of the battery service test.D.C.Cook-Unit 1 3/4 8-9 Amendment No.

v vELECTRICAL PO'+ER SYST=MS O.C.DISTR ISUTIQ.'l-S:-'UT~C'~"l

[qT~r~~rv aviv~sa rv Typal g re pa~g I~rpss L 3.8.2.4 As a minimum, the'ol lowing O.C.elec rical equipment and bus shall be energized and C?ERASLE: 1-250-volt O.C.bus, and 1-250-volt battery bank and charger associated with the above O.C.bus.APPLICABILITY:

MODES 5 and 6.ACTiON: Mith less than tl e above comple...ent of O.C.equipment and bus OPERABL:-, eStabl iSh CONTAINME!T'T ItG'EGRITY within 8 hOurS.SURVEILLA"CE REQU IREMENTS 4.8.2.4.1 The above required 250-volt O.C;bus shall be deter-.ined OPERASLE and energized at least once per 7 days by verifying correct breaker-alignment and indicated power availability.

4.8.2.4.2 The abov required 250-volt bat.ery bank and ct arger shall be demonstrated OPER'BLE per Surveillance Requirerwnt 4.3.2.3.2.

0 0 C~C"GK-U'lI.1 3/4 8-12'Amendment No.

ELECTRICAL POWER SYSŽEMS SURVEILLANCE RE UIREMEb S (Continued)

~~".he oilot ce'1 specific gravity, corrected to 77 F and o=ull electrolyte level (fluid at the bottom cf the.-.,zx mum level indicat'cn mark), is K 1.200, 3..he pilot ce'1 vc'"ace is~2.10 volts, and 4..he overall battery voltage is?250 volts.b.At east once per 82 days bv verifying that:.he vc'"age cf each ccnnected cell is K'2.3.0 volts under=cat cha ge and has not decreased more than 0.05 volts r"m"he value cbserved during the or'ginal acceptance"es", and~~...e s"ec'='c=rav"y, corrected to 77"-and full level (fluid at the bottom of the maximum';."'ca=icn ma k), o'ach connected cell's t and..".as nct de"eased mere than 0.03 from the".='e=bser"ed during=he previous test, and.;".e ele""=c vte'eve'.ea"h connected cell's between="."-"=".".e m'n mum leve: indicaticn mark and the=.".e max'mu.,'ve'dicaticn mark.c.At'eas"=::ce pe" 16 months bv.ver'ing that:.he ce's, cell plates and battery racks show no visual indica"on oi phys-al damage or abnormal deterioration.

.he ce ll-to-ce l 1 ar d re rmi..a l connections are clean,"ight, ree o: ccrrosion and coated with anti-corrosion mater'a.3.'he battery cha ger will supplv at least 10 amperes at 250 vclts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .At'east once pe 18 mcnths, dur'ng shutdown (MODES 5 or 6),'=, ver='y'ng that the battery capacity is adequate to su".='".and naxntain in CPERA8LE status the emergency loads:"==:".e t mes soec'f'd xn Table 4.8-2 with the battery c:":==sr disccnnected.

The battery terminal voltage shall be=a-'net-"10 volts throughout the battery service test.e.At'east once per 60 months, during shutdown (MODES 5 or 6)-": verifying that, the battery capacity is at least 80%o"'.".e manufacturer's rating when subjected to a performance disc.-.arce test.+his performance discharge test shall be pe" c.-...ed in place of the battery service test.D.C.COOK UNIT 1 3/4 8 14.Amendment No.

e 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS b.Surveillance intervals sperified in Section ZI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda for the inservi.ce inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applirable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice~ine ection ani teetin criteria Required frequencies for performing

'nservice inspec-"S Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least At least At least At least At, least once per.once per once per.once per once per 7 days 31 days 92 days 184 days 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 Amendment 78 granted extensions for certain surveillances required to be performed on or before March 31, 1986, until" the end of the Cycle 5-6 refueling outage.For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1986 refueling outage.4.0.7 Amendments 97 and 99 granted extensions for certain surveillances required to be performed on or before July 1, 1988, until the end of the Cycle 6-7 refueling outage.For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1988 refueli.ng outage.Donald C.Cook-Unit 2 3/4 0-3 Amendment No.

REACTIUITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3,3'At least one rod position indicator channel (excluding demand position indication) shall be OPERABLE for each shutdown or control rod not fully inserted.APPLICABILITY:

MODES 3x¹, 4x-and 5*=ACTION: Pith less than the above required position indicator channe'1(s)

OPERABLE, immediately open the reactor trip system breakers.SURVEILLANCE P,E UIR~it~"TS 4.1.3.3 Each of the above required rod position indicator channel(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.*With the reactor trip system breakers in the closed position.¹See Special Test Exception 3.10.5.D.C.COOK.-UNTT 2 3/4 1-22 Amendment No.

3/4.3 INSTRUMENTATION 3/4,3.1 REACTQR TRIP SYSTEM INSTRUMENTATION LIMITING CQNOITION FOR OPERATION 3.3.1.1 As a minimum, the reactor tr ip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIME5 as shown in Table 3.3-2.APPLICABILITY:

As shown in Table 3.3-1.ACTION: As shown in Table 3.3-1.SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of'he CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MOOES and at the frequencies sho~n in Table 4.3-1;~4.3-1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reacto~startup unless performed during the preceding 92 days.The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operatio'n, 4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each.reactor trip function shall be demonstrated to be within its limit at least once per 18 months.Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the"Total No.of Channels" column of Table 3.3-1, 0.C.COOK-UN I 7 2'3/4 3-1 hmendmenc Ho.

l' INSTRUMENTATION 3)4.3.2 ENGINEEREO SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION LIMITING CONOITION fOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS)instrumenta-tion channels and interlocks shown in Table 3,3-3 shall be OPERABLE witn their trip setpoints set consistent with the values shown in the Trip Set-point column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5, APPLICABILITY:

As shown in.Table 3.3-3.ACTION: 'a~b.With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table.3.3-3 until the channeI i's restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint.value.With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK,.CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for-the MOOES and at the frequencies shown in Table 4.3-2;4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.The total interlock function shall be demonstrated OPERABLE at leas't once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

I 4.3.2.1.3 The ENGINEEREO SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once pei N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown, in the"Total No.of Channels" column of Table 3.3-3;0.C.COOK-UNIT 2 3/4 3-14 Amendment No.

n~<<<<R~~'-'<<<<<<

-<<<<sm<<<<<<<<<<<<r

<<<<<<J<<<<<<i<<<<qiRsiir n 8 I XQHCrLgKh~)i~

CHhNNEL MHLCK CNhNNEL CilhNNEL FUNCTZONhL C&4I DMSO~KQT HODES IN WIIICII SURYEILDLNCE

~KQHRED Oo Containaent Pressure-High-High 4.GTEAH LINE ISOLhTION a.Hanual b.hutoaatio hctuation Logic H.h.H.h N.h.N.h.H(1)H(2)H(3)le 2e 3 1, 2, 3 l, 2, 3 d, Steaa Plov in Two Steaa Lines-'-S Nigh Coincident with T-Los-Low avg l~--2~3~.Steaa Line Pressure-Los 5~TURBINE TRIP hHD MEDMhTER ISOLhTION a.Steaa Generator Mater Level-High-High 6 MOTOR DRIVEN hUXILIhRY FEEDWhTER PUHPS lt 2e 3 1, 2, 3 and 4 a.I b.c<<d.Steaa Generator Mater Level-Low-Low 4 kv Bus Loss of Voltage Safety In)ection Loss of Hain Peed Puaps N.h.N.h.N.h.N.h.H(2)2e 3 1~2, 3 1, 2, 3 1~2-TABLE 4-3-10 POST-ACCIOfNT MONITORING INSTRUHENTATION SURVEILLANCC RE UIREHENTS.INSTRUHENT CllANNEL Clif CK CEIANNE L, CALIBRATIOrl 17.18.Containment Sump Level*Containment Mater Level*1.Containment Pressure 2.Reactor Coolant Outlet Temperature

-TlrOT (Mide Range)3.Reactor Coolant Inlet Temperature

-TCOLO Wide Range)4.Reactor Coolant Pressure-Wide Range 5.Pressurizer Mater Level 6.Steam Line Pressure 7.Steam Generator Water Level-Narrow Range 8.RWST Water Level 9.Boric Acid Tank Solution Level 10.Auxiliary Feedkater Flow Rate ll.Reactor Coolant System Subcooling Hargin Monitor 12.PORV Position Indicator-Limit Switches 13.PORV Block Valve Position Indicator-Limit Switches 14.Safety Valve Position Indicator-Acous~lc Monitor 15.Incore Thermocouples (Core Exit Thermocouples)

(4)16.Reactor Coolant In'ventory Tracking System (Reactor Vessel Level Indication)

H~i H H H M M M H M M M M H M(2)R R R R R R R'R R R R R R r(1)R(a)R R (1)(2)3)(4)Partial range channel calibration for sensor to be performed below P-12 in MOOE 3.Mith=one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CllECK to verify the remaining Reactor Vessel Indication train OPERABLE.Completion of channel calibration for sensors to be performed below P-.12 in HOOE'3.'he'core exit thermocouples will not be installed until the 1988 refueling outage;therefore, surveil-lances will not'e required until that time.See license amendment dated April 10, 1907.The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational.

The schedule for modification or replacement of the transmitters is-described in the Bases.I

REACTOR COOLANT SYSTEM 3/4.46 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION EOR OPERATION 3.4~6~1 The following Reactor Coolant System leakage detection systems shall be OPERABLE: a.One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or.ERS-2401), b.The containment sump level and flow monitoring system, and c.Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION: With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days providedŽrab samples of the containment atmosphere are obtained and analyzed=-=least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radic ctivity monitoring channels are inoperable>

otherwise, be in at least HOT STAi'"BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , SURVEILLANCE RE UZREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by: a~Containment atmosphere particulate and gaseous (if being used)monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL PUNCTZONAL TEST at the frequencies specified in Table 4.3-3, b.Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months, c~Containment humidity monitor (if being used)-performance of CHANNEL CALIBRATION at least once per 18 months.D.C.COOK-UNIT 2 3/4 4-14 Amendment No.

0 REACTOR COOLANT SYSTEM LIMITING CONG!TION FOR OPERATION Continued 2.With two or more block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either.(1)'restore a total of at least two block valves to OPERABLE status;or (2)close the block'alves and remove power from the block valves, or (3)close the associated PORVs and remove power from their associated solenoid valves;and apply the portions of ACTION a.2 or a.3 above for.inoperable PORVs, relating to OPERATIONAL MOOE, as appropriate.

c.With PORVs and block valves'not in the same line inoperable,~

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either (1)restore or (2)close and de-energize the Apply the portions of ACTION a.2 OPERATIONAL MOOE, as appropriate unavailable.

the valves to.OPERABLE status other valve in each line.or a.3 above, relating.to for two or three lines d.The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.11.1 Each of the three PORVs shall be demonstrated OPERABLE: a.At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and r b.At least once per 18 months by performance of a CHANNEL CALIBRATION.

4.4.11.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.The block valve(s)do not have to be tested when ACTION 3.4.ll.a or 3.4.ll.c is applied.4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant batteries.

This testing can be performed in conjunction with the requirements of Specifications 4.8.1.1.2.c and 4.8.2.3.2.d.

~PORVs iso1ated to limit RCS leakage through their seats and the block valves shut to isolate this leakage are not considered inoperable.

0.C.COOK-UNIT 2 3/-4-4-33 Amendment No.

~~~~~~e~~~~~~~~~~~I~~~~~.III~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

r EMERGENCY CORE COOLING SYSTEMS SURVEZLI~CE RE UZREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE: a.At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed: Valve Number Valve Function Valve Position a.IMO-390 b.ZMO-315 a RWST to RHR a.Open b..Low head SZ b.Closed to Hot Leg c.IMO-325 c.Low head SZ c.Closed to Hot Leg d.IMO-262>>d.Mini flow'line d.Open e.ZMO-263*e.Mini flow line e.Open f.ZMO-261*f.SI Suction f.Open g.ZCM-305*g.Sump line g.Closed ZCM-,306*h;Sump line h.Closed b.At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or...otherwise secured in position, is in its correct position.c.By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.)is present in the containment which could be transported to the containment sump and c use restriction of the pump suctions during LOCA conditions.'his vi ual inspection shall be performed:

1.For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.Of-the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.

These valves must change position during the switchover, from injection to recirculation flow following LOCA.D.C'OOK-UNIT 2 3/4 5-4 t Amendment No.'
EMERGENCY CORE COOLING SYSTEMS SVRVEELLAiVCE RE CEREMENTS Continued)
At least once per 18 months by: 1.Verifying automat'c isolation and interlock action of the RHR svstem from the Reactor Coo)ant, System when the Reactor Coolant System pressure is above 600 psig.2.A visual inspection of the cbntainmenc sump and verifying that the subsystem suction inlets a.e not restricted by debris and that the sump components (t-ash racks, screens, etc.)show no ev'dence of structural distress or corros ion.e.At least once per 18 months, during shutdown, by: 1.Veri.fying that each automatic valve in the flow path actuates to its correct, position qn a Safety Injection test signal.2.Verifying that each of the following pumps start automatically upon receipt of a safety dnjection test signal: a)Centrifugal charging pump b)Safety inj ec" ion pump c)Residual heat removal pump f.By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5: 1.Centrifugal charging pump>24G5 psig 2.Safety Inj ec t ion pump>1445 psig 3.Re s i dual heat removal pump>195 ps ig By veri."";ng the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves: l.'i=hin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.D.C.COOK-UNIT 2 3/4 5-5 Amendment No.
, 1 EMERCENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.4.5.3.2 All charging pumps and safety infection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their e'lectrical po~er supply circuits, at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s~h'enever the temperature of one or more of the RCS cold legs is less than or equal to 152'F as determined at least once per hour when any RCS cold leg temperature is between 152'F and 200'F.COOK".UNIT 2 3/4 5-8 Amendment Ho.
CON TAI'lfiENT SYSTEMS 3 4.6.2 OEPRESSURIZAT'ION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent con:ainment sp~ay systems shall be OPERABLE with each spray syste,.capable of taking suction from the RWST and transferring suction to the containment sump.APPLICABILITY:
MODES 1, 2, 3 and 4.ACTION: With one containment spray system inoperable, restore the inoperable spray'~stem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RE UIREMENTS 4.6.2.1 a.b.Co d.Each containment spray system shall be demonstrated OPERABLE: At least once per 31 days by verifyin that each valve (manual, power operated or automatic) in the flow path that is not locked sealed, or otherwise secured in position, is in its correct position.By verifying, that on recirculation flow, each pump develops a discharge pressure of>255 psig at a flow of>700 gpm, when tested pursuant'o Specification 4.0.5.At least once per 18 months during shutdown, by: 1.Verifying that each automatic valve in the flow path actuates to i ts correct position on a Containment Pressure--High-High test signal.2.Verifying that.each spray pump starts automatically on a Containment, Pressure-High-High test signaI.At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
D.C.COOK-UNIT 2 314 6-10 Amendment No.
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.d.At least once oer 18 months during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure--High-Hiqh test signal, At least once per 5 years by verifying a water flow rate of at least 20 gpm (>20 gpm)but not to exceed 50 gpm (<50 gpm)from the spray additive tank test line to each containment spray system with the spray pump operating on recirculation with a pump discharge pressure>255 psig.0.C.COOK-UNIT 2 3/4 6-12 Amendment No.
'ONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continu~ed 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING'lODE at least once per 18 montns by: a.Veri fying that on a Pha'e A containment isolation test signal, each Phase A isolation valve actuates to its isoiation position.b.Verifying that on a Phase B containment isolation test signal, each Phase 8 isolation valve actuates to its isolation position.c.Verifying that on a Containment Purge and Exhaust isolation test signal, each Purge and Exhaust valve actuates to its isolation position.4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.D.C.COOK-UNIT 2 3/4 6-14 Amendment No.
CONTAINMENT SYSTEMS DIVIDER BARRIER SEAL LXMITZNG CONDITION FOR OPERATION 3'.5.9 The divider bar ier seal shall be OPERABLE.APPLICABILITY:
MODES 1, 2, 3 and 4.ACT" O.'I: With the divider barrier seal inoperable, restore the seal to OPERABLE status, prior to increasing the Reactor Coolant System temperature above 200 F.'SURVEILLANCE RE UXREMENTS a 4.6.5.9'he divider barrier'seal shall be determined OPERABLE at least, once per 18 months during shutdown by: a~b.Removing two divider barrier seal test c=upons and verifying that the physical properties of the test coupons are within the acceptable range of values shown in Table 3.6-2.Visually inspecting at least 95 percent of the seal's entire length and: 1.Verifying that the seal and seal mounting bolts are properly installed, and 2.Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.
D.C.COOK-UNIT 2 3/4 6-47.Amendment No.
PLANT SYSTEMS.SURVEILLANCE RE UIREMENTS Continued 3.Verifying that each non-automatic.
valve in the flow path that is~ot locked, sealed, or otherwise secured in position is in its correct positon.4.Verifyina that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10,.RATEO THERMAL POWER.This requirement is not applicable for those portions of the Auxiliary Feedwater System being used intermittently to maintain steam generator level., b.At least once per 18 months during shutdown by: l.Verifyino that each automatic valve in the fl'ow path actuates to its coreect position upon receipt of the appropriate engi-neered safety features actuation test signal required by Specification 3/4.3.2.2.Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of the appropriate engineered safety features actuation test'signal required by Specification 3/4.3.2.'l 4 i 0.C.COOK-UNIT 2 3/4 7-6 Amendment No.
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONOITION."QR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.APPLICA8ILITY:
MOOES 1, 2, 3 and 4.ACTION: With only one component cooling water loop OPERABLE, restore at least two loops to OPERA8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTQOWN within the follow-'ng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RE UIREMENTS 4.7.3.1.At least two component cooling water loops shall be demonstrated OPERABLE: a.At least once per 31 days by verifying that each valve (manual, power.operated or automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.b.At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.0, C.COOK-UNIT 2 3/4 7-12 Amendment No.
PLANT SYSTEMS 3/4.7.4 ESSENTIAL SE.'-."ICE WATER SYSTEM LIMITING CONOITION FOR Q>ERATION 3.7.4,1 At least two independent essential service water loops shall be OPERABLE, APPLICABILITY:
MOOES 1, 2, 3 and 4.ACTION: With only one service water loop OPERABLE, restore at least two" loops to OBERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOSY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTOOWN wi thin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated, OPERABLE: a.At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.b.At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.O.C.COOK-UNIT 2 3/4 7-13 ,Amendment No.
PLANT SYSTEMS SURVEILLANCE REQUIRENeN,S~Con~tinued e.At least once per 18 months by: 2.Verifying that: the pressure drop across the combined HEPA filers and charcoal adsorber banks is~6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm+10>>.Verifying that on a Safety Injection Signal from either Unit 1 or Unit 2, or on a containment phase A isolation signal, the system automatically diverts its inlet Flow through the HEPA filters and charcoal adsorber bank and that either fan can then be manually started in the re-circulation mode.3.Verifying that the system maintains the control room at a positive pressure of>1/16 inch W.G.relative to the outside atmosphere at a system flow rate of 6000 cfm+10".f.After each complete or partial repla.ment of a HEPA filter bank by verifying that the HEPA filter banks remove>99" of the OOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm+10".g.After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal.adsorbers remove~99" of a halogenated hydrocarbon refrigerant test gas when Bey are tested in-place in accordance with ANSI N510-1975-while operating the ventilation system at a flow rate of 6000 cfm+10".0.C.COOK-UNIT 2 3/4 7-16a Amendment No.
PLANT SYSTE.IS SURVEILLANCE RE UIREHENTS Cont nued e.3.Verifying that the standby fan starts automatically on a Containment Pressure--High-High Signal and diverts its exhaust flow through the HEPA filters and charcoal adsoroer banks on a Containment pressure--High-High Signal.After each complete or partial replacement of HEPA filter bank by verifying that the HEPA filter banks remove>99>>of the OOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm+10"...After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove>99K of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm+10>>.0.C.COOK-UNIT 2 3/4 7-19a Amendment No.
PUQIT SYSTEHS 3/4,7.7 SHUSSKRS LIHITIN6 CO~OITtaN FQQ OP RA, ION All snubbers listed in Ta e 3 7-9 h APPLICABLITY:
HOOKS 1, 2, 3 and 4 (HOOES 5 and 6 for snubbers located on systems rcauired OPERABLE in those HOOKS): ACTION: lith one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber(s) to OPERABLE status and perform an enginee~ing evaluation per Specification 4.7.7.1.c on the supported component or declare the'uppor ted system inoperable and follow the appropriate ACTION st'atement for that system.SLIRVKILLANCE R EOUIREHENTS 4.7.7.1 Each scrubber shall be demonstrated OPERABLK by performance of the followii'g augmented inser'vice inspection program and the requirements of Specification 4.0.5.a.Visual Insoec: ".n The first inservicc visual inspec ion of snubbers shall be perfor...ed af;er four mon:hs out wrthin 1O nonths of ccmmencing POQKR OPERATION ard shall include all snuboers listed in~<<ble 3.7-9.If less than two (2)snubee s are found inoperable during the first inservice visual insoec cn,-.he second inservice vis.al inspection shall be performed 12 cnthS-25" from the da e of the fi rst inspection.
Otherwise, subseq.en'isual ir.spections shall be performed in ac"ordanc w cn:re follcw..ng schedu'e: No.Inoo.a'.e Srubbers".er r.n'soecticn
."-.'.od Subseouent V':sual,<Ins"ec.ion P.iod 0 1 2 3, B Thc snubbers may those inaccessibl independently
.'n 18 months=254 12 months-=25~6 months-25'24 days 25%62 days 25~31 days"e c tegorized into two groups: Those accessible and c curing reactor operation.
Each group may be inspected actor."ance with the above schedule.g>>I g.g g g g g g g~The provisions of Specification 4.0,2 are not applicable.
D.C.Cook Unit'3/4 7<<20 Amendment No.
PLANT SYSTEMS SURVEILLANCE REQUlREHENTS (Cont f nuedb.Visual inspection Acceptance Criteria Visual inspections shall verify (l)that there are no visible indications of damage or impaired OPERABlLlTY,-"(2) attachments to the foundatfon or supportfng structure are secure, and (3}fn those locations~here snubber movement can be manually induced withaut dfsconnectfng the snubber, Chat Che snubber has freedom of movement and is not frozen u'p.Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1)the cause of the rejection is clearly established and remedied for thaC particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7,7.l.d as applicable.
Ho~ever, when the fluid port of a hydraulic snubber is found to be uncovered, the:nubber shall be determined inoperable and cannot be determined OPERABLE via functfanal testing for the purpose of establishing the next visual inspection interval.All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.c.Functi'anal Tests At least once per 24 monChs during shutdown, a representative sample (14'b)or the total of each type of snubber in use in the plant: shal 1 be functionally tested either in place or in a bench test.For each snubber that does not meet the functional test acceptance criteria of Specifica ion 4.7.7.l.d an additional 10-'f Chat type of snubber shall be functionally tested.The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.At least 25" of the snubbers in the represenCatfve sample shall include snubbers from the following three categories:
l.2.3.The first snubber away from each reactor vessel nozzle Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)Snubbers within LO feet of the discharge from a safety relier valve Amendment Ho.3/4 7-21 Snubbers fdentified in Table 3.7-9 as"Especially Oifficult to Remove" or in"High Radiation lanes Ourfng Shutdown" shall also be included in the representative sample.+Permanent or other exemptions rrom unctional testfng for indfvfdual snubbers fn these categorfes may be granted by the Commfssfan anly if a justfffable basis for exemptfon is presented and/or snubber life destructive testing was performed ta qualify snubber operability for all desfgn condftfons at either the completion of thefr fabrication or at a subsequent date.0.C.COOK-UNlT 2
PLANT SYSTEMS SURVEI)~CE RE UIREHENTS (Continued) b.At least once oer'B month-: 1.By performing a system functional test which includes simulated automatic actuation of the system, and: a)Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal and b)Cycling each valve in the flow path that is not testable during plant operation-hrough at leas" one ccmplete cycle of full travel.2.By inspection of deluge and preaction system spray headers to verify their integrity.
,3.By inspection of each open head deluge nozzle to verify no blockage.I c.At least'nce per 3 years by performing an air flow test through each open head deluge header and verifying each open head deluge nozzle is unobstructed.
Do C.COOK-UNIT 2 3/4 7-40 Amendment No.
ESECTRZCSS POWER SYSTEMS ACTION (Continued)
With two of the above required offsite A.C.circuits inoperable, demonstrate the OPERABILITY of two diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, unless the dies 1 generators are already operating; restore at, least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .with only one offsite source restored, restore at lea'st two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time qf initial'oss oz be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .d.With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C.circuits by performing Surveillance Reauirement 4.8.l.l.l.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .Restore at least two diesel generators to OPERABLE.status'within'2
'hours from time of initia1 loss oz be.in least HOT STANDBY'ithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RE UIREMENTS 4.8.1;1.1 Each of the above required independent
=ircuits between the offsite transmission network and the onsite Class 1E distr bution system shall be a.Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and b.Demonstzated OPERABLE at least once per 18 months by transferring the unit power source automatically from the normal auxiliary source to the preferred reserve source and by transferring manually to the alternate reserve source.4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE a.In accordance with the fze'quency specified in Table 4.8-1 on a STAGGERED TEST BASIS by: 1.Verifying the fuel level in the day fuel tank.2.Verifying the fuel level in the fuel storage tank.D.C.COOK-UNIT 2 3/4 8-2 Amendment No.
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMFNTS Continued 3.Verifying the fuel transfer pump can be started, and trans,ers fuel from the storage systet'"., to.the day tank.4.Verifying the diesel starts from ambient condition and accelerates to at least 514 rpm in (10 seconds.'.
Verifying the generator is loaded to>1750 kw, and operates for)60 minutes and verifyirg that the generator output breaker to the emergency bus is OPERABLE.6.Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-0270-65 is within the acceptable limits specified in Table 1 of ASTM-0975-74 when checked for viscosity, water 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 recomnendations for this class of standby service.2.Verifying that, the automatic sequence timing relays are OPERABLE with each load sequence time within+5 of its required value and that each load is sequenced on within the design allowable time limit..3.Verifying the generator capability to reject a load of'600 kw while maintaining voltage at 4160+420 volts and frequency at 60+1.2 Hz.4.Verifying the generator capability to reject a load of 3500 kw without exceeding 75" of the differ ence between nominal speed and the overspeed trip setpoint.5.Simulating a loss of offsite power by itself, and: a)Verifying de-energization of the emergency busses and load shedding from the emergency busses.0.C.COOK-UNIT 2 3/4 8-3 Amendment No.
0 EL C C POWE SYSTEMS SSHULDDO LIMI I G CONDI ION FOR OPERAT ON 3.8,1.2 As a minimum, the following A.C.electrical power sources shall be OPERABLE: a~b.E One circuit between the offsite transmission network and the onsite Class lE distribution sys'em, and One diesel generator with: 1,-A day fuel tank containing a minimum volume of 20 gallons of fuel, 2.3.A fuel storage system containing a minimum volume of 42,000 gallons of fuel, and't A fuel transfer pump.APPLICABILITY:
MODES 5 and 6.~CT TON: With less than the above minimum required A.C.electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes*.SURVEILLANC RE UIREMENTS 4.8.1.2 The above required A.C.electrical power sources shall be demonstrated OPERABLE by the performance of each.of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for Requirement 4.8.1.1.2.a.5.
For purposes of this'specification, addition of water from the RWST does not constitute a positive reactivi.ty addition provided the boron concentration in the RWST is greater than the minimum required by Specification 3,1.2.7,b.2.
D.C.COOK-UNIT 2 3/4 8-5 AMENDMENT NO.
ELECTRICAL POWER SYSTEMS D.C.DISTRIBUTION
-OPERATING LIMITING CONDITION FOR OPERATION 3.3 The following D.C.bus trains shall be energized and OPERABLE with tie breakers between bus trains open: TRAIN AB consisting of 250-volt D.C.bus AB, 250-volt D.C.battery bank No.2 AB, and a full capacity charger.TRAIN CD consisting of 250-volt D.C..bus CD,'50-volt D.C.battery bank No.2 CD, and a full capacity charger.APPLICABILITY:
MODES 1, 2, 3 and 4.ACTION: a.With one 250-volt D.C.bus inoperable, restore the inoperable bus to OPERABLE.status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within'he following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .b.With one 250-volt D.C.battery and/or its charger'inoperable, restore the inoperable battery and/or charger to CPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the.".~xt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .SURVEILLANCE RE UIREMENTS 4.8.2.3.1 Each D.C.bus train shall be determined OPERABLE and energized with the breakers open at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.3.2 Each 250-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 pilot cell is between the minimum and maximum level indication marks, D.C.COOK-UNIT 2 3/4 8-8 Amendment No.
ELECTRICAL POWER SYSTFBB D.C.DISTRIBUTION
-SHUTDOWN LIMITING CONDITION FOR OPERATION 3,8.2'As a minimum, the fol'owing D.C.electrical equipment and bus shall be energized and OPERABLE: 1-250 volt D.C.bus, and 1-250 volt battery bank are.'harger associated with the above D.C.bus.APPLICABILITY:
MODES 5 and 6.ACTION: With less than the above complement of D.C.equipment and bus OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .SURVEILLANCE RE UIREMENTS 4.8.2.4.1 The above required 250 volt D.C.bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 250 volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
D.C.COOK-UNIT 2 3/4 8-11 Amendment No.
REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9,4 The containment building penetrations shall be in the following status;a.Ihe equipment door closed and held in place by a minimum of four bol tsb.A minimum of one door in each airlock is closed, and c.Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either: 1.Closed by an isolation valve, blind flange, or manual valve, or 2.Be capable of heing closed by an OPERABLE automatic Con-tainment Purge and Exhaust isolation valve.APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION: Mith the requirements of the above specification not, satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment bui'ing.The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE UIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed/isolated condition or capable of being closed by an OPERABLE automatic Containment Purge and Exhaust isolation valve within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by: a.Verifying the penetrations are in their closed/isolated condi-tion, or b.Testing the Containment Purge and Exhaust isolation valves per the applicabl portions of Specification 4.6.3.1.2.
D.C.COOK-UNIT 2 3/4 9-4 Amendment No.
Attachment 3 to AEP:NRC:1072 Modified Pages from AEP:NRC:0967L Submittal 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS b.Surveillance intervals specified in Section XI of the ASME Boiler and'ressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice ins ection and testin criteria Required frequencies for performing inservice inspec-tion and testin activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
4.0.6 Amendments 100, 107 and 108 granted extensions for certain surveillances required to be performed on or before July 31, 1987, and until the end of the Cycle 9-10 refueling outage.For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1987 refueling outage.4.0.7 Amendment granted extensions for certain surveillances required to be performed on or before April 1, 1989, until the end of the Cycle 10-11 refueling outage.For these specific surveillances under this extension, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1989 refueling outage.Donald C.Cook-Unit 1 3/4 0-3 Amendment No.
3 4.3 INSTRUMENTATION 3 4.3.1 REACTOR TRIP SYSTBI INSTRUMENTATIOM LINITIHg CONOITION FOR OPERATION 3.1.1 As a minimum, the reactor trip system instrumenta~
channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.APPLICA81LITY:
As snown in Table 3.3-1.ACTION: As shown in Table 3.3-1~SURVEILLANCE RECU IR~ENTS 4.3.1.1.1 EaCh reaCtar trip SyStem inStrumentatiOn Channel Shall be demonstra:ed GPEMLE by the performance of'he CHANNEL CHECK, CHANNEL CAL[3RATION and CHANNEL FUNCTIONAL TEST operations for the NODES and at the freouencies snown in Table 4.3-1.4.3.1.1.2 he logic for the interlocks s."all be demonstra:ed OP=o~9LE prior.o each reactor startup unless per".rmed during tne preceding g2 days.The total interlock function snail ae demonstrated OPERA8LE at least once per 13 months during CHANNEL C'LIBRATION testing of each channel arfecced by interlock operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor.rio function shall be demonstrated to be within i: s limit at leas.nce oer 18 months.Each test shall include at least one logic train such that both logic trains are tested at least once per 3S months and one channel"er function sucn that all channels are tested at leas once every N lmes 18 months where N is the total number of redundant cnanneis in a SPeCifiC reaCtOr trip funCtiOn aS ShOwn in the"TOtal NO.Of ChannelS" column of'able 3.3-1.3.C.C"CX-~:-3/4 3-1 Amendment No.
TABLE 4.3-1 n n C)o FUNCTIONAL UNIT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL MODES IN WHICH FUNCTIONAL SURVEILLANCE TEST 1.Manual Reactor Trip A.Shunt Trip Function B.Undervoltage Trip Function N.A.N.A.N.A.N.A.S/U(l)(lo)
S/U(1)(10)1$2$3*$4*$5*2 3*4*5*2.Power Range, Neutron Flux D(2,8),M(3,8)
M and S/U(l)1, 2 and*and Q(6,8)3.Power Range, Neutron Flux, High Positive Rate 4.Power Range, Neutron Flux, High Negative Rate 5.Intermediate Range, Neutron Flux N.A.N.A.R (6)R (6)R(6,8)S/U (1)1, 2 1$2 1$2 and a R 6.Source Range, Neutron Flux 7.Overtemperature hT 8.Overpower hT 9.Pressurizer Pressure-Low 10.Pressurizer Pressure-High ll.Pressurizer Water Level-High 12.Loss of Flow-Single Loop R(6,8)R(9)R(9)R R(8)M(8)and S/U (1)2(7),-3(7), 4 and 5 1$2 1$2 1$2 1, 2 1$2 INSTWWEHTATIOH 3/4.3.2 EHQIHEERE9 SAFETY FEATURE ACTUATION SYSTEM INSTRNENTATIQH L!M!TING COHO!TIOH FOR OPERATION 3.3.2.1 The Engineered Safety Feature ACtuatiOn SyStgp (ESFAS~ition channels and inter1ocks shown in Table 3.3 3 shall be OPERABLE w)th their trip setpoints set consistent with the values Shee in th Trip Setpoint column gf Table 3.3 4 and>ith RESPONSE TI~ES in Tab1e 3.3-5.APPLICABILITY; As shokn in Table 3 ACTION:.a.kith an ESFAS, instrumentation channel trip setpoint less conse tive than the value shown in the Allowable Values column of Table 3.3-4, decia.-e the channe1 inoperable and apply the applicable ACTION reouirement of Table 3.3-3 until the channel is restored to GpERASLE status with the trip setpoint adjusted consistent with'..tne Trip'Setpoint value.b.Qith an ES~AS instrumentation channel inoperab1e, take the ACTION snore~n aoie 3.3-3.SURVEILLANCE RQQU I R<A'EHTS" 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATIOH and CHANNEL FUNCTIONAL TEST operations for the NODES and at the frequencies sheen in Tab1e 4,3-2.4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE duri~g the automatic actuation logic test.The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CAI.IBRATION testing of each channel affected by interlock operation.
4.3.2.1.3 The EHGINEEREO SAFETY FEATURES RESPONSK TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.=.~".h test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function i~.n that all channels are tested at least once per H times 38 months~I'e" s is tne total number of redundant channels in a specific ESFAS fun@::."n as shown in the"Total Ho.of Channels" Column of Table 3.3-3.I t 0.C.COOK-UNIT I~endmaat IIo.
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM XNSTRUMENTPTXON SURVEILLANCE RE UXREMENTS o O PC I FUNCTIONAL U IT CHANNEL CHECK 1.SAFETY INJECTIONS TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEXLLANCE a.Manual Initiation b.Automatic Actuation Logic c.Containment Pressure-High d.Pressurizer Pressure-Low e.Differential Pressure Between Steam Lines-High f.Steam Flow in Two Steam Lines-High Coincident with T-Low;Low or Steam Line PNNsure-Low N.A.N.A.N.A.N.A.M(1)M(2)M(3)1, 2, 3,.4 1,2,3,'4 1, 2, 3 1, 2, 3 1, 2, 3 1, 2, 3 2-CONTAINMENT SPRAY a.Manual Initiation N.A.b.Automatic Actuation Logic N.A.c.Containment Pressure--High-S High N.A.N.A.M(1)M(2)M(3)1(2(3(4 1, 2, 3, 4;1, 2, 3 r
TABLE 4.3-2'ontinued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS FUNC IONAL UN 4.STEAM LINE ISOLATION CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL MODES IN WHICH SURVEILLANCE a.Manual b.Automatic Actuation Logic N.A N.A.N.A.N.A.M(1)l, 2, 3 M(2)l, 2, 3 c.Containment Pressure-High-High'.
Steam Flow in Two Steam Lines-High Coincident with T-Low-Low PPKRsure-Low M(3)le 2e 3 le 2e 3 5.TURBINE TRIP AND FEEDWATER ISOLATION a.Steam Generator Water Level-High-High 6.MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS l, 2, 3 O a.Steam Generator Water.Level-Low-Low b.4 kv Bus Loss of Voltage c.Safety Injection d.Loss of Main Feed Pumps S N.A.N-A.N.A.N.A.M(2)R l, 2, 3 l,*2 0
e I tlSTRUt1ENT4T I ON POST-ACC IDENT I t)STRUtfEN TATI ON LIHITItiG CONOITIOt)
FOR OPERATION 3,3.3.8 The post accident monitor in'nstrumentatfon channels shown fn Table 3.3-11 shall be OPERABLE.APPLICABILITY:
NODES 1, 2, and 3.ACTION: a.Mith the number of OPERABLE post-accident monitorfno channels less than required by Ta'ble 3.3-11, either r estore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTGQHN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .b.The provfsfons of Specification 3.0:4 are not applfcable.
SURVE ILLAt,CE REOUI RE;.IEtlTS 4.3.3.8 Each post-accident monitoring instrumentatfon channel shall be demonstrated OPERABLE by performance of'he CHANNEL CHECK and CHAt/t/EL CALIBRATION operations at the frequencies shown fn Table 4.3-7.e+Ql l r)'<<(~3/4 3-54 Amendment No.
POST-hCGIDEHT HOHITORINC STRUHEHTATIOH SURVEILIAHCE R 1RENEHTS;n INSTRUHENT n 8 1.Conte lnaenc Pressure I 2~Q 3.5, Roactor Coolant Outlet Toaporature
-T (Mlde Range).HOT Reactor Coolant Inlet Teaparaturo
-T~~(Mldo Range)Reactor'oolant Pressure-Mida Range Pressurizer Mater Lovel'.Scoaa Line Pressure Scoaa Generator Mater Level-Harrow Range RMST lister Level 5uclc hcid Ta>>k Solution Lovel huxlilary Feedvacer Flow Race Reactor Coolant.Syscea Subcooling Hargln Honlcor PORV Position Indicator-Llait Switches ar.15.16.Safety Valvo Position Indicator-hcoustic Honitor Incoro Thoraocouples (Core Belt Thoraocouples)
Reactor Coolant Inventory Tracking Systea (Reactor Vessel Level Indication)
Contalnaent Suap Levels>>Containaenc Mater Level**13.PORV block Valve Position Indicator-Llait Switches CHECK H H(2)CHhNHEL ChLI DRhTIOH R(1)R(3}t l I I (1)'artial range channel calibration for sensor co be Perforod below P-12 ln NODE 3.(2)Mich ona train of Reactor Vessel Levol Indication inoparabla, Subcoollng, Hargln Indication and Coro Exit g'horaocouples asy be used co perfora a QlhNHEL CHECK to verify the reaainlng Reactor Vessel indication train e OPERhbLE.(3}Coapletlon of channel callbraclon for sensors co be perforaad below p-12 in NODE 3.I-*+Tho requlreaancs for cheso lnscruaencs will bocoao effective after the lovel cranssmlccers are aodlfiad or roplacad and bacoae oporacional.
The schedule for aodl f Ication or raplaceaenc of che cransalccara ls described In cha Sssas.
~CO.~gH~RXRK s v~~ITS r~tinued shalL be constituted of one basket each from Radial Rows 2, 4, 6, 8 and 9 (or from, the same row of an,ad]acent bay i f a basket from a designated row cannot, be obtained for weighing)within earth bay.If any baskot is found to contain less than 1220 pounds of ice, a representative sample cf 20 additional baskets from the same bay shall be weighed.The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1220 pounds/basket at a 954 level of confidence, The ice condenser shall also be subdivided into 3 groups of baskets, as follows: Group 1-bays 1 through 8, Group 2 bays 9 through 16, and Group 3-bays 17 through 24, The minimum average ice weight of the sample baskets from Radial Rows 1, 2;4, 6, 8 and 9 in each group shall not be less than 1220 pounds/basket at a 95%level of confidence.
r The minimum total ice condenser ice weight at a 958 level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,371,450 pounds.3.Verifying, by a visual inspection of at Least two flow passages per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of 3/8 inches.If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visually inspected, If these additional flow passages are found acceptable, the surveillance program.-may proceed considering, the single deficiency as unique and.acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.
c, At least once per 40 months by 1;ifting and visually inspecting the accessible portions of at least two ice baskets from each 1/3 of the ice condense".
and verifying that the ice baskets are free of detrimental st".uc"ural wear, cracks, corrosion or other damage.The ice baskets shall be raised at least 12 feet for this inspection.
D.'C.COOK-UNIT 1~~3/4 6-27 Amendment No.
t y CO i 0 t<<-.~'iG CON-'0~.OP 3.6.5.3, The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPE~lUaULIXX MODES 1, 2, 3 and 4.SVJ.QE: With one or more ice condenser doors open or otherwise inoperable, PQ'~'ZR OPERATION may continue for up to 14 days provided the ice.bed temperature is monitored at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and the maximum ice bed temperature
~is maintained
<27 F;otherwise,.restore the doors to their'closed 0 positions or OPERABLE status (as applicable}
within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN with'n the.-'following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .4.6.5.3.1 Inlet Doors-Ice condenser inlet doors shall be: a.Continuously monitored and determined closed by the inlet door position monitoring system, and b.Demonstrated OPERABLE during shutdown et least once per 9 months bye I Uerifying that the torque required to initially open each door is g 675 inch pounds.2.Verifying that opening'f'ach door is not impaired by ice.frost or debris.V 3, Testing a sample of at least 50%of the doors and verifying that the torque required to open each door is less than 195 inch-pounds when the door is 40 degrees open.This torque is defined as the"door opening torque" and is equal to the nominal door torque plus a frictional D.C.COOK-MiTT 1 3g4 6-30 Amendment No.,
S IS~~I I~~~~~~I~~~~~~~~I I~~~~~~~~~~-~-'I I'~~~~~~~~~~~~~I~I'~~~~~~~~~~~~~~~~~~~I~~I~~~~'~~~~~~0~~~~~~~~~~~~~
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