ML041200412
| ML041200412 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/06/2004 |
| From: | Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:4901 | |
| Download: ML041200412 (471) | |
Text
{{#Wiki_filter:Attachment 1, Volume 17, Rev. 0, Page 1 of 471 VOLUME 17 CNP UNITS 1 AND 2 IMPROVED TECHNICAL SPECIFICATIONS CONVERSION UNIT 1 CTS MARKUP PAGES IN CTS ORDER Revision 0 Attachment 1, Volume 17, Rev. 0, Page 1 of 471
Attachment 1, Volume 17, Rev. 0, Page 2 of 471 ITS 5.5 ITS JA N2 7200 4 (2) Technical Sp~ecifications The Technical Specifications contained InAppendices A and ,a's revised through Amendment No. a%t'are hereby Incorporated Inthe license. TheI licensee shall operate the facility Inaccordance with the Technical Specifications. (3) Less than Four LooR Ogeration The licensee shall not operate the reactor at power leVels above P-7 (as defirned InTable 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four reactor coolant loops Inoperation until (a)safety analyses for less than I four loop operation have been submitted, and (b)approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
* ~~(4) Indiana Michigan Power Company shall Implement and maintaIn, Ineffect, all
* ~~~~provisions of the approved Fire Protection Pro~gram as described Inthe Updated Final Safety Analysis Report for the facility and as approved Inthe SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 198.5, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11,1996, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only If those changes would not adversely affect the ability to achieve and maIntaIn safe shutdown Inthe event of a fire. (5) Deleted by Amendment No. 279 (6) Deleted by Amendment No. 80 5.5.8 (~~7) Secondary Water ChemIstry Monitoring Program to Inhibit steam generator tube de radatlon. This r sIbeesc~'ed)I etaaion c misty Mhual and shall Include: 5,5.8.a 1. Identification of a sampling schedule for the critical parameters and control points for these parameters; 5.5.8.b 2. Identification of the procedures used to measure the values of the critical parameters; Amendment No. 279 Page 3 of 69 Attachment 1, Volume 17, Rev. 0, Page 2 of 471
Attachment 1, Volume 17, Rev. 0, Page 3 of 471 ITS 5.5 ITS 5.5.8.c 3. Identification of process sampling points; 5.5.8,d 4. Procedure for the recording and management of data; 5.5.8.e S. Procedures defining corrective actions for off control point chemistry conditions; and 5.5.8.f 6. A procedure Identifyng (a)the authority responsible for the interpretation of the data, and (b)the sequence and timing of administrative events required to Initiate corrective actions. (8) Deleted by Amendment No. 279 (9) Deleted by Amendment No. 279 (10) Deleted by Amendment No. 279 (I 1) Deleted by Amendment No. 279 D. Physical Protectio The licensee shall fully Implement and maintain Ineffect all provisions of the Commisbsion-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of110 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: 'Donald 0. Cook Nuclear Plant Security Plan,' with revisions submitted through July 21, 1988; "Donald C.Cook Nuclear Plant Training and Qualification Plan,' with revisions submitted through December 19, 1986; and 'Donald C.Cook I Nuclear Plant Safeguards Contingency Plan,' with revisions submitted through June 10, 1988. Changes made inaccordance with 10 CFR 73.55 shall be implemented Inaccordance with the schedule set forth therein. E. Deleted by Amendment No. 80 F. Deleted by Amendment No.680 G. Inall places of this license, the reference to the Indiana and Michigan Electric Company isamended to read Indiana Michigan Power Company. 5.5.2 H. System lntegrity The licensee shall Implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low a practical levels. The progr-am-is a inclucle the following: Amendment No. 279 Page 4 of 69 Attachment 1, Volume 17, Rev. 0, Page 3 of 471
Attachment 1, Volume 17, Rev. 0, Page 4 of 471 ITS C) 5.5
~~~~~~~~ITS 5.5.2 1. Provisions establishing preventive maintenance and periodic visual inspection Provuisi anceodapigad fremainten lseupet Thicnseredisa
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reactorprotOffce f NcleroRacsrystem.io 3DTi mne ies ate Issuance:anMarch i offetv 30,197t6idigh so h October25, 2014AendentNo.27 of Nclear ReaPageReguoa Office 69 Attachment 1, Volume 17, Rev. 0, Page 4 of 471
Attachment 1, Volume 17, Rev. 0, Page 5 of 471 ITS Chapter 1.0 MS_ 1.0 USE AND APPLICATION 1.1 ~~DEXINEDLE jjJ1 ------ The S of ~~~this section appear in capitalized type and are applicable throughout these THERMAL POWER [] THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. RAfTE DTH ERMAL at ota reactor core beat transfer rate to the reactor coolant of (i 3304 MWt. [Ok~~=MODE [ l CPI. A[ MODE shall correspond to any one inclusive combination of core reactivity mnovedforn~ 1 T wt fel in Table 1,1 J condition, power leve Mad average reactor coolant temperature specified in Table .I S ~~~~~~~~~~~~~~~~~~~~~~the reactor [j ACTIO shllbelbe additional requirements sC~av hpcfe,statements to each pr~0IRCi e33 OPERABLE - OPERABILITY [] Asystem, subsystem, train, corpne rdevice shall be OPERABLE or have OPERABILITY when it efntinsallb the-w mtionjthatc jwhn an.d is capable of performing its secf ction(s ._ ' ad all necessary attendant Instrumentation, controls-, normal emergency electni pwer ouescooling = seal water, lubrication Nother auxiliary equiprment tha 'ae required frtestmsubsystem, train, componenti or device to ~erform its, kfuntion(s) are also capable of promn thir related support function(SAP ][O COOK NUCLEAR PLANT-UNIT I Page 1-1I AMEND1AENT 43, 273 Page 1 of 35 Attachment 1, Volume 17, Rev. 0, Page 5 of 471
Attachment 1, Volume 17, Rev. 0, Page 6 of 471 ITS Chapter 1.0 cI~ii:~ INSERT and reactor vessel head closure bolt tensioning
~~71I~ INSERT 2 that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times Insert Page 1-1 Page 2 of 35 Attachment 1, Volume 17, Rev. 0, Page 6 of 471
Attachment 1, Volume 17, Rev. 0, Page 7 of 471 ITS Chapter 1.0 ITS I,~~~~~~~~~~ 1.8.1 gl pantrations required to be closed during incLdant cnd tions are either:
- a. apable of being closed by an OPDABLE otamn automatic See RTS isolation valve system, or 3.6.1J
- b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, e=ept for valves -that ate orM n der administrative control as pamitted by PL ication 3.6.3.1.Se T 11.8.2 All equipment hatches are closed and sealed~ 3.6.1 1.5.3 Each air lock is in compliance vith the requirments ofSee ITS 1.*8.4 The containment leakage rates are vitbin the Ulmts of See ITS Spag~~~~~~~~~~~~ication ~~~~~~~~~~~~~~~~~3.6.1
= a. en Lre chane ncl gt sensor And INERT A. 0n Ltmotiosc4!g crud th fGo= ineen=Den ntK mn n esrn n came'~afamdb ZAe seisofSvn a.o ppn COOK I!JCLLR PL~IT - 1ThI 1 e 1.2r A.' rn-Ekt 80-8.. .ur 18
*Isteps W-WEATM ~ ~ ~ ~ Pge o 3 Attachment 1, Volume 17, Rev. 0, Page 7 of 471
Attachment 1, Volume 17, Rev. 0, Page 8 of 471 ITS Chapter 1.0 O ~~INSERT 3 all devices in the channel required for channel OPERABILITY. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. Insert Page 1-2 Page 4 of 35 Attachment 1, Volume 17, Rev. 0, Page 8 of 471
Attachment 1, Volume 17, Rev. 0, Page 9 of 471 ITS 3.6.1 ITS R0~~~~~~~tE ~~~~~~~VIN'r ~~~~~~~~~~See ITS 1.7 A REPORTA.BLE EVWN shall be any of those contditions specified in 10 OnR Capter 1.0 50.73. I1.8 CONWNHEN~T II-T=ERTY shall aria: when: 1.8.1 All entr tions required to be ci aed d=urin mcident candt~1* art either: A. Capa aof being closed by an ?DBZcouteimmu atmatic Laol o valve system, or LA.1
- b. Cl d by manual valves, bI flanges, or deacti: ad tomatic val as secured in their CIaLdpatos ep avsta at a Under admmuistratI ottla pemiztad b Sp ciication 3.6.3.1.
SR 3.6.1.1 1.6.4 The containment leakiage rates are within the xlmts of Specification 3.6.1.2
'L.9 A CHAMNLL CAUT.AR~ATION shall be the adjustment. as neeaxisz. of the Channel output such that it responds vith the necessary range end sawracy to kmavu valuqj of the parmaeter which the channel *moitors, The CHAMM CALIBfATION shall encompass the entire channel including the sensor -and la=s and/ar trip functions, end shoall inelude the CHARNU FUNTOM AL TEST. noe OMMNE CALIBUTION may be performed by sany series of sequential. oanrlappiug or total Se MSI channel steps such that the entire channel is calibrated. Catr10
- 1. 10 A CHANNE ChhCK shall be the ulitative assessmuent of channel behavior during operation by observation .Ti deteraination shall Include
- where possible. comparison of the channel indication and/or statu with other
-indications and/or status derived from independent instrummt channels measuring tia. maea jparemocer.
COOK'NUCLEAP PLANT - UNIT 1 1.2 D0IO-.,4.40. 181 Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 9 of 471
Attachment 1, Volume 17, Rev. 0, Page 10 of 471 ITS 3.6.2 See ITS RJP0RTAWtE EVMN Chapter 1.0
- 1. 7 A RPO.MTABLE EVMI shall be any of those' conditions specified in 10 CnR 50.73.
CONT&!RK!W NTEG~KR!TT
- 1. $ cmLAI)4= nM=E~ITY shall exist when:
1.8.21 All yenetrations required. to be closed durn maccdent condtions ax,& ither'. See ITS A. Capable of being closed by an OPDASZZ cmntaftwwa automatic 1.3.6.19 isolation valve system. or
- b. Closed by manual valves, blind flanges, or deactivated auttomatic valves secured in their closed positions. w~pt. for valves -that arom opnwder administrative control as permitzed by Spitciication 3.6.3.1.
LCO 3.6.2 1.3.3 Each air lock is in compliance vith the requiremients; of 3.ee IT 1.9 A CEAMMIE CALIBRATIOR shall be the adJustment, as necesnary, of the channel output such that it responds with the necessary range and awuraCY to 1nowni value4 of the parameter which the channel monitors. The CHAMEL CALIBRAXION shall encompass the entire channhel, including the sensor and alarm and/or trip f~znctons
- and shall include ti* CHAMNE FUNCTIONAL TtST. The CHANME CALIBRATION may be performed by any series of sequential, oenrapping or total See ITS channel steps such that the entire channel is calibrated. Chapter 1.09
- 1. 10 A CHARME CIMECK shall be the qualitative assessment of channel behavior during operation by observation. This dateruiriation shall Include, heare possible, comparison of the channel, indication end/or tata= with other indictinsad/or satms derived from independent lnxtrmext channels measuring; the same ?Vrameter.
COOK NPUCLEA PLANT UNIT 1 1-2 AMENDMWT O.~ hO 8 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 10 of 471
Attachment 1, Volume 17, Rev. 0, Page 11 of 471 ITS Chapter 1.0 ITS DEFINITIONS OPERATIONA:L CHANNE F II fLTf Jhal cto ta simulated to the C 4nni1 as CI.1 to he lUin tensor AApracticable to 10etwithin the reactor NNE vessel with the vessell hedfa ay SHUTD~~~~iN LR ~~subcriical cnrl (RCC~As) [ISH7i] hi I belthe instantaneous mon reactivity Li~~i~ yule !iili o rwoud I belusrter cassmlferais rentai. 1c ntrg) are fully'inserted except for the single Ero~ Suster ass mly,-L of highest reactivity wortlk 5 htch is assumed to bet fully withrawn. MOM.F ED LEAKACEA, from CS~pump sell -orvalve packin conducte !5~smu or Collet Ifia~ediis ta t ISR such (liii)t colecIIIIIIIIIIII 2.b. Lea a a into the containment atmospherfomouesha are ba h pcifically located and, known either not to intrfere' wit oneraion of leakave'detection systems or not to be
- 3. the Eecondary ftste~t)~..-j .
- b. URDETWED LEAKA~G ISR 5 ~~~~LAKAGE Rhj- ,~A which isno 50 C7 LEAAG orC OUED LE6GE.
1D. C. cooK. - UNIT 1 143 M.endment No. 29 Page 5 of 35 Attachment 1, Volume 17, Rev. 0, Page 11 of 471
Attachment 1, Volume 17, Rev. 0, Page 12 of 471 ITS Chapter 1.0 O ~~INSERT 4 of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps. O ~~INSERT 5 fuel, sources, or reactivity control components,
-~~~ ~ ~ IID~~INSERT6 With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM; and
- b. In MODES I and 2, the fuel and moderator temperatures are changed to the nominal zero power design level.
INSERT 7 (except reactor coolant pump (RCP) seal water injection or leakoff), INSERT8 (except RCP seal water injection or leakoff) that Insert Page 1-3 Page 6 of 35 Attachment 1, Volume 17, Rev. 0, Page 12 of 471
Attachment 1, Volume 17, Rev. 0, Page 13 of 471 ITS ~~~~~~~~~~~~~~~~ITS Chapter 1.0 1.1 ~~~DEFINITIONS LEUE} [M~tntW through a nori1~soloble fault inIRe e Co I componenft bodyo pipe willor vessel we1 CONTROLLED AKAGE ,. , 1.17 C~rOLLED LEAKAGE sha bethat Seat water owsupplied to the reacto /oln up Ses. Ii~2~K&IflLMI!~ 3 PTR) MIj QUAD.M IPoin KiLTRA71shallbe the ratio of the maximum urper extort detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of tho maximum lower excore detector calibrated outt to the average of the lower excore detector c~lirate Ufe UhM Myeris astsr Wthone excore detector See ITS inoperable, the rualin ngthree de-tectors shall be used for coputing L J. DOSE-EQUIVALMN 1-1l3lrircE __, DOSE EQUIVALENT 1.131 shall be that concentration of 1.131 G&Vq,'ram)
.F1 thatalone would plroduce the vsa thrid dose as the quantity and ISO-Itoimixture of -31, #1-132.1 -133 1134, and 1-135 actually present.
Tethyroid dose conversion fatr sdfor this calculation shall -be Tabe II of ID-thosi lised alculation of Distance Factors fo r Power and Test'Reactor Sitaq l~ Regulatory Guide 1.10Re1 "M 197 ISR a AEC, -1962, those listed in I4F1NC STASSERED Table EA7 o Ii~IA STAGGIERED, TMS BASIS shall consist oISR
- a. A test Achedule for n ;S tnso subsysteui, ttrail or other deslgsitecl Commonnt ob~ ed by dividtig th secified tost aterval fat MMeu~ subintervalsA1
- b. Ihe/esting COaon yhb subsystemu, Irao other designated Cojdpnmnt atl the beiAigof each subinte al1.
- 0. C.COOK% WUIT 1 1.4 Amendmaent No. 69 Page 7 of 35 Attachment 1, Volume 17, Rev. 0, Page 13 of 471
Attachment 1, Volume 17, Rev. 0, Page 14 of 471 ITS Chapter 1.0 O ~~INSERT Ba or those listed in ICRP 30, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity." O ~~INSERT 9 Ptheit~sting of one of the systems, subsystems, channels, or other desig natedecornponents during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n-is the total number of systems, subsystems, channels, or other designated components~Arthe Mssciated, function. Insert Page 1-4 Page 8 of 35 Attachment 1, Volume 17, Rev. 0, Page 14 of 471
Attachment 1, Volume 17, Rev. 0, Page 15 of 471 ITS 3.2.4 ITS ~I DEFINITIONS PRESSUPRE DOUNDARY LEAKAGE 1.15 PRESSURE BOUNDARY LEAXPGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System
,component body, pipe wall or vessel wall.
CONTROLLED LEAKAGE See ITs 1.17 CONTROLLED LEAMAGE shall be that Seal water flow supplied to the Chapter I 0 rector coolant pump seals. RMADRAHT PCMvER 'TILTRAO 1.18 QUADRANT POWE TILT RATIO shall be the ratio of the maximum. upper extore detector calibrated output to the average of the upper excore detector calibrated outputs, or the retio of the maximun lower excore SR 3.2.4.1 inoperable h eaigtredtcossalb used for computing Note Ith vrPOE 7 DOSE-EQUIVALE?1T 1-131 1,19 -DOSE EQUIVALENT WM13 shall be that concentration of 1-131 (W~/gram) which alone would produce the same thyroid dose as the quantity and iso-toic mixture of 1-131, 1-132. 1-133, 2-134, and 1.135 actually present. Tet9kro Iddose conversion factors usod for this calculation shall -be those listed inTable III of TID-U844, 'Cialculation of Distance Factors for Power and Test 'Reactor Sites.' or In NRC Regulatory Guide 1.109 Rev 1. October 1977. STAGGERED TOST MSAS See MTS rChapter 1.0 1.20 A'STAGGERED `TEST BASIS shall consist of:
- a. A test schedule for ii systems, subsystes trains or other designated ccmponents obtained by dividing the specified test Interval into n equal subintervials,
- b. 1he testing of-one Ilystem. subsystem, train or other designated.
component at the beginning of each subinterval. 0.C.COOK ¶ UNIT 1 1.4 Amendment No. 69 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 15 of 471
Attachment 1, Volume 17, Rev. 0, Page 16 of 471 ITS ~~~~~~~~~~~~~~~~ITS Chapter 1.0 1.21 NOTATION Reauirents shall corre'suo eifie for the perfop 2 of surveillance to eintervals defie inTable 1. 2. (ii r4(RTS) - 1.1~ ~ TeIRA~0P RI ITH hl ef6tm interval from sensor until loss of stationary griper coIl voltage. ISR 0A1 ENGINEERED SAFETY FEATUR REPNE IE ESF Ei~i The I ~T~ F SAEYRESPONSE TIME sbAll,.beh that timeL. interval from when, the monitored parameter exceeds its R ~actuationI setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required A) positions, pump discharge pressures reach their required values, aet.). Tines shall, Include diesel generator starting and sequence loading delays) where applicable.-Q (AFD)
)
AXIAL-FLtJX DIEE FRN,r4 -F L. IAUW Fii IFEW-E hall be the dif ference in normalized flux signals between the top and bottom halves of a two section excore neutron A detector. PHYICS TESTS Ths etsae Initial Tests and Operation, U 1 5PHYSICS TESTS shall be those tests: performed tomaaues b. fundamental nuclear aracteristics of the re core an leieaI~ Instrumentatio v41Idescribed in Chapter 1 fthe FS~~~Vi~torized under the provisio6-nx 10 CFR 30.59 or pthervise Approve te NcerRgltr (ji shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies p. diitgation (in KeV) for isotopes, other than iodines. with half iMes Igry~ae I minutes, 15 maigup at least 951 of the total no odine activit in the coolant. 1.27 A UCE CHECK shalle the qualitative a semsent of Channel respo whn the Channel enor iseaposed t aradioactive source. COOK NUCLEAR PtAM - UNIT 1 1- AMENDHEIRT NO. 199 Page 9 of 35 Attachment 1, Volume 17, Rev. 0, Page 16 of 471
Attachment 1, Volume 17, Rev. 0, Page 17 of 471 ITS Chapter 1.0 INSERT 10 The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.L3 INSERT 11 The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.L. Insert Page 1-5 Page 10 of 35 Attachment 1, Volume 17, Rev. 0, Page 17 of 471
Attachment 1, Volume 17, Rev. 0, Page 18 of 471 ITS Chapter 1.0 ETS rKOCE S CONTROL P&OftM (M See CTS 1.28 The PROCESS COffTROL PROGAM (PCP) shall contain tli. current formulas
- 6.0 sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive vastes based on demonstrated proce sing of actual ot simulated vet solid wastes viii be accauplshed in such a way as to assure compliance with 10 CFJR Pamt 20, 61, a4ndT, state reguAtinburial ground requirements, and other requirements governing
;tI isi'os. of solid radioactive wast..
1129 l~d. 1 . 1 OFFSITK poSl CLtITON KWNAL (ODCHI 1.30 The OP'PSITB DOSE CALCULATION XaURAL (ODOK) shall contain the methodology and parmeters used in the calculation of offsite doses resulting from radioactivea aseous end liudef~et, La the calculation of gaseous and liquid effluent monitorn aar/ti sepints. and in the ____See rrS conduct of the Environmental Ladiologica ontigPors.The ODQ( 5.5 shall contain (1) the Radioactive Effluen CotosadRdooical Environmental Monitoring Programs required by Section 6.S. n (2) descriptions of the information that should be Inc-luded In the AnnuaL Radiological Enviromental Operating and Annual Radioactive Iffluent Kelgaa us eport reurd by SoeciftcaticAs 6.9.1.6 and 6917 1.31 A RADUrSTE SYTMi n tm indand instsale o-reduce radioactv asesefunt cleig primary colat te off-gasex from rmr se o ea or holdup rtepurpose Of rTo g h tt radica iyp rt ees Ito threniomnt 1.32 A I0ON EXHAUST 13 SYSTEM isay sy esga andl Installed reuc aseou ra~dioodn or radioactiv onli particula omi effluents by sing ventilation o etexhaust gases(3 through coal absorbers BalA filters for the Wa of reovning Woines o pacculates crom~g gaseous exhaust stre p r to the release oteuevirontmet. a.system is not c Idrdto have any effect onoble gas efflumnts. Eniered Safe~ Le (ESP) atmospheric cleanup sytes are not consL red to be VETURIUE1DS ZAIET SYSTEM onents. U2orPURGIN Is tec roldprocess ofdi g air at gas from ao metto mainan meatrreseura, mi conentr4, or other operai$ cni repaceentair or gSu is to ion such rdto purify the ctieet
'anrta 1.34 0is the controlled casa of dischargg orga r from a confinemo to maintain twer a tepressure, huii cnentration or other o ating condtion, i manner that epa tiror gas Is not pr dd or requred dun MoG. Vent, use sytem ams, does not Lu2~~~~~~'uITINO ~ ~ ~ ~ Page 11 of 35 Attachment 1, Volume 17, Rev. 0, Page 18 of 471
Attachment 1, Volume 17, Rev. 0, Page 19 of 471 ITS 5.S PROCESS CONTROL Ptfg2=l (PCPU 1.25 The PROCESS CONTROL !POCMh (PCP) shall contain the current formsulus, S.e CTS sampling, analyses.* tests
- and datermiinatiows to be made to ensure that processin end packaging of solid radioactive ventes based on demonstrated L processin of actual or simulated wet solid vastes viii be acoplse In such a v~ay as to assure compliance vith 10 CM Parts 20. 63. an 71. state regplations, burial groumd requirements, and other requirements governing the disposal of solid radioactive vast&.
- 1. 19 Deleted. .
5.5.1 OFSUR~ C =QfKWL(DH 1.30 The CYPSITE DOSE CALCULIATION MANUAL (ODCI) shall contain the 5.5.1.a Usthodology and pareuseters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effuets LA the calculation of gaseous and liquid effluent monitorn aastrip se Itpoin d In the 5.5.1.b Environmental Monitoring Programs reqired by Section 6.8.4 sad (2) descriptions of the information that should be included in the Annual Radiological Envirotasental. Operating and Annual Radioactive Effluent Release Reports required by Specificatious 6.9.L.6 and 6.9.1.7. GASEOUS IMAMVAST TANEMTBBh 1.31 A GASEOUS RADYIASTE TREA11MET SYSTEM is an yta designd and installd to reduce radioactive gaseous effluents bycollectin primary coolant system off-gases from-the primary system and providing for delay or See ITS holdup for the purpose of reducing the total radioactivity prior to release Chapter I1.0J to the environment. VTILATION RM~UST TREATMEN'T SYSTE 1.32 A VENT17ATION WIAUST TREATHENT SYTEK Ls any system designed and installed to reduce gaeu aiidn rradioactive material in particulate form In eflet y asn e tilton or vent exhaust gases through charcoal absores rHR iters for the purpse of removing Aedines or particulatesrm tegseousmzas strsm, prior to the release to the eniomn.Sc ytem LSno considered to have any effect on noble gas effluenc
- n~er S fetyaeture (ES) atnoupheric cleanu systems; are not co" dMe o eVUTMIO.WS? TREADMEN SYSTEM components.
1.33 TM&G or PMJGIIO is the controlled process of discharging air or gas f rem a confinement to maintain temperature, pressure, huaidi~ty, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. 1.34 VENTING is the controlled process of disobirgIng air or gS" from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in ~such manner that replacement air or gas is not provided or required during VENTING. Vent, Used. in syntem names, does not imply a VENTING process. COOK NUCLEAR PlA1NT - VNIT I 1-6 IJDDETNO. "., 189' Page 6 of 69 Attachment 1, Volume 17, Rev. 0, Page 19 of 471
Attachment 1, Volume 17, Rev. 0, Page 20 of 471 CTS 6.0 1.28 TbPROCESS CONTROL V (PCP) shall conta" uretformulas. sampli *a ales, tests, nd termIinations to !be to ensure that L. process uenpackaging of so Idradioactive wastes bad on demonstrated procee tu fatual or studl ed vet solid vwastes vi be accomplished in such vaato"Surecomm anesvithlO llrt O61land 71, tat* re tin Lbral growi qurmue n ohr qieet governing th isoosa2.o solid a'di. etive vaste. QFFSJE 2Q'E C PR HM&NA (ODCHfl 1.30 The OPPITE DOSE CALCMlATION iMNAL (ODQI) sallU contain the methodology and paremtron used in the calculation of offsite doses resulting from radioactive gaseous and lIqudeffluents, In the calculation of gaseous and liquid effluent monitor aa /tip setpoints. and in th Ses ITS conduct of the Environmental Raediologi M itoring Program.' The ODQ( shall contain (1) the Radioactive Effluet Control.s end Radiological Environmental Monitoring Frograms required by Section 6.8.4 and (1) descriptions of the information that should be included In the Annual Radiological Envlrone~ntal Operating and Annual Radioactive Effluent IRelease Reports requirad by Specifications 6.9.1.6 and 6.9.1.7. GASEOUS RADVASZE MRAM&=T SYSTE 1.31 A GASEOUS RADWASTE TBEATIKI SYSTEM is any system designd and Installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from -the primary system and pravidi for delay or holdup for the purpose of redurcing the total rdotvtypirto release SeT to th. environment. VTILATION EXHUST TRAM ENTSYTEI 1.32 A VERTnMAION EVHAUST TRE&2(EN SYTEN is any system designed and installed to reduce gaseous radiotodine or radioactive materiel in particulate form in effluents by passing ventilation or vent exhaust gSuez through charcoal absorbesa and/or HERA filters for theprpose of removing JLodLnxes or partLaulates from the gassous exhaust stremn prLor to the release to the environWmet. Such a, system is not considered to have any effect on noble gas effluents. fngineered Safety Feature (ISF) atmospheric cleanup systems are not considered to be VENTEUMfON.WlWUST TREAHENT SYSTEM components. 1.13 rM1G or IIJCIH is the controlled process of discharging air or gse from a confinement to maintain temperature, pressure, humidity! concentration or other operating condition, in such a manner that replacemeant air or gas Is required to purify the confinement. 1.34 VENTIN is the controlled process of discharging air or gas from a confinement to maintain temperature, 'pressure. himidity, concentration or other operating condition, In such -manner that replacement air or gas Is not provided or required during VENTING. Vent, used In system names, does not imply a VENTING process. COOK NUCLUR flJIT - NIlT I. A-6MIRQKW No0. i, 159. Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 20 of 471
Attachment 1, Volume 17, Rev. 0, Page 21 of 471 ITS Chapter 1.0 ITS 1.0 DEFENMTONS 1.35 113B B)OF TH1E PUBIUC abi is Persons VWhor Mt tinlyassociated with te from category at persona who thfste to serTic ecpuimnt or Mmekdelizies. This category ersms ho Me. h~c~de of fth site for receatin4l tiona' or othe purpome no 136 The BOUNDARY "hl be liebyodbich the land is ownelsed or othewise 1.37 I sAalAe at ar beyond the SITE BO~ iYtwicacesis not dxe lcense for upo froctOn f Wivi'dualf xosr to radiatdon" and' atrlsor any site bouxnday used fo~iei1quarmis or lonatiha],g ngilo and/or Vmffos5C ( )Is tha aimuxio powr evl at which power f(i) COREO L 1 1 cycleTNspecificREPpRrrmoLR 1.1 1 9 COLRis the uniOpecific docment tha proidet~limits Th~~~Me for the canno reload Cycle. 7bt cci clse lmits shall bo dectminlzd for eac reload cyckleai accordance
~~~~1.
Y& tUmit Opeastion wiaki Whse lImits is addressed in indvidual
~~
TADOT ~ ~ ~ ~ %1 !IDP ISR 1 ~~ INSERT 14NSERT11 COOK UCA PLAN~T-UMf I Page 1-7 AMCENDMEN44.I, &U.44A~ 5 Page 12 of 35 Attachment 1, Volume 17, Rev. 0, Page 21 of 471
Attachment 1, Volume 17, Rev. 0, Page 22 of 471 ITS Chapter 1.0 (11111) INSERT 12 all devices in the channel required for trip actuating device OPERABILITY
$I11111~ INSERT 13 The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.
QJ ~~INSERT 14 ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices. MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing all master relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required master relay. The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps. SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing all slave relays in the channel required for channel OPERABILITY and verifying the OPERABILITY of each required slave relay. The SLAVE RELAY TEST shall include a continuity check of associated re quired testable actuation devices. The SLAVE RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps. Insert Page 1-7 Page 13 of 35 Attachment 1, Volume 17, Rev. 0, Page 22 of 471
Attachment 1, Volume 17, Rev. 0, Page 23 of 471 ITS Chapter 1.0 Table TABLE M (21 1.1-1 MODES O~~~~~~~~~IPIRATIOVX [EATO MODE L I] REACTIVITY CONDITION, Z ATED THER1MAL OE AVERAGE COAf~ TEMPERATUEL.. ~
- 1. POWEROPERATION +/-0.99 . O
- 2. STARTUP 99I
- 3. NOT STANDBY c0.99 30
- 4. HOT SHUTDOWN (b) 90.9 S. COLD SHUTDW1 0.920
- 6. REFUELIN () c A [i] N 1OF N .
fclosure boltsls
- exluding decay heat. then fully tensindL.
Moved to definition of MODE, page 1 of 35 D. C.-COOK -UNIT I 1-8 Aenduenit No. 69 Page 14 of 35 Attachment 1, Volume 17, Rev. 0, Page 23 of 471
Attachment 1, Volume 17, Rev. 0, Page 24 of 471 __ 0 Chapter 1.0
~~~~~~~~~~~~~~~~ITS 1.0 DEFINITONS TABILE 1.
FREQUENCY NOTATION NOTATION CYE S At least once 12 hours. D At least once er24 hours. W At least once er7 days. M At least once pr31 days. Q At least on per 92 days.0 2 Months At least onc per 62 days SA At least onc per 184 days. R At least onc per 549 days. S/u Prior to eac reactor startup. P Completed nor to each release. N.A. Not Applic ble. COOK NUCLEAR PLANT-UNIT I Page 1-9 AMENDMENT 2, 277 Page 15 of 35 Attachment 1, Volume 17, Rev. 0, Page 24 of 471
Attachment 1, Volume 17, Rev. 0, Page 25 of 471 ITS Chapter 2.0 ITS 2.8 SAFETY L1M1TIAND461TI SAJiY YTU*S1TNSI( j 2.1 SAWYLIh41S 2.1.1 2*j* 'The coreblnaton of THEmmAL POWER., pressurie Pressur and fthbgestVmt lopei avenge tm4*era=m (r,,Jshalltapxed dhe lig misbm In ------ a ' tm4c AfflM9XIrYl: MODES 1 and 2.e 2.2.1 Wheeve fthpoint defined by tde combifudon of fe highes operaft loop avenge .- pear nd THERMAL. POWER hzs ececeded tOm aproriate presurize prmsur line, be InHOT STANDBY wItn1 bouw. 2.1.2 2.1.2 The RiactrCoolantSystem lpreshalnt eceed 2735 psg APPlA&U=: MODES 1 2.3,4mM S. MODES Iand2 2.2.2.1 ~Whenever the Rw=to Coolan System presure has exceded 2735 pfg, be InHOT STANDBY with the 2.2.2.1 ~~~Reactt Coolan System presur wihin its limt withi I hou. MODES 3, 4 and 5 Wheneve the R-eao Coolan System pteunh baa exceeed 2735 pdg, re=duc ite Reacor Coolan 2.2.2.2 symn Preuzto aiffn kim kvitwllairS mlmzte COOK NUCLZAR PLANT.UNff 1 PAge 2-1 AMIDDT430,168 Page 1 of 20 Attachment 1, Volume 17, Rev. 0, Page 25 of 471
Attachment 1, Volume 17, Rev. 0, Page 26 of 471 ITS Chapter 2.0 ITS ~I 860 650 - - 630 5680 570 0.2 0O4 0.6 0.812 Power (frctlo of rated themia p 1W 610.66). (1.13S5k.T "67714) 2m 02.OSA MQ 9SS 21oo M^S) (103.0.7) t*,W.MM 64616) (1=.03620*3) 1.,66. 240 0.0,66.6) (CAN6,632. 1460.63 21.1 Reactor Core safety Lmimb COOK NUCLEAR PLANTr.NIr Pafge 2- 4,434,M44"1, 1ED(I 214 Page 2 of 20 Attachment 1, Volume 17, Rev. 0, Page 26 of 471
Attachment 1, Volume 17, Rev. 0, Page 27 of 471 ITS Chapter 2.0 ITS This pap Sum~ndle4y lat: b1im.
- 0. C. COOK
- MUT? 2-3 AKM(VMUN~O120 Page 3 of 20 Attachment 1, Volume 17, Rev. 0, Page 27 of 471
Attachment 1, Volume 17, Rev. 0, Page 28 of 471 ITS Chapter 2.0 ITS SAFMl LIAMITSAN LIMITIN. -SAFEM SYSTE srrrufd REATOR TRIP SYSTE INSTRLPEATION SEWO1NT 2.2.1 The meator trip system Instrumenution setpoints shall be set Consistent with the Trip setputat values shown InTable 2.2.1. 8!.PL1CASILITY: As shown for each channel In Table 3.3-1. rS r With a reactor trip syltan instrumentation setpoint less conservative theun the value ihown In the Allowable Values column of Table 2.2-1, declare the channel mnperabl and apply the applicable ACTION state-Mnt requiranet of Seification 3.3.1.1 until the channel Is restored to OPERASLE sutus, wItts trip setpoint adjusted consistent with the Trip Setpoint value. D. C. COOK -UNIT1 2.4 Page 4 of 20 Attachment 1, Volume 17, Rev. 0, Page 28 of 471
Attachment 1, Volume 17, Rev. 0, Page 29 of 471 ITS 3.3.1 ITS SP$EFIMIT AND LIMITING WMTT SVSTm STINGmS 2.2 LIMITING MMtr SYSTOI SETTINGS REACTOR TRIP SYSTU INSTRIMENATION SETPIMT LCO 3.3.1 2.2.1 The reactortl£en lntm tatln setpolntS shall be set consistent with thm vle shown in Table 2.2-1. APPLICUIULTY As shown for each channel In Table 3.3.1. ACTION: ACTION A With a reactor trip systinm insttmwintatlon aetpolnt, less conservative then the, value lihon in the Allowable Values colm of Table 2.2-1, declare the channel Inoperable AMd apply the applicable ACTION state-mlent eqirrnmet of Specification 3.3.1.1 until the channel Is restored to OPRALEstatus with Iti trip setpoiuit adUmsted consistent with the D. C. COOK -UNIT I2. Page 15 of 39 Attachment 1, Volume 17, Rev. 0, Page 29 of 471
Attachment 1, Volume 17, Rev. 0, Page 30 of 471 ITS Chapter 2.0 ITS 2.0_SAFETY LIMMIT &E'~fiImm S (2
- 1. Manual ReacWTor ip Not Applicable Not Applicable
- 2. Power Range. Neutro Low Setpoint leas tha or equal Low Setpolnt. -c thanor equal Flin to 25% of RATED THERMAL .to 26% of RATED THERMAL POWER POWER High Setpolnt- leia thanotequal H4Ahetpoint -lessthkn or equal to 109% of RATED THERMAL to 110% of RATED THERMAL POWER POWER
- 3. Power Rmsge. Neutron Lms than or equal to 5%of Leus tha or equal to 5.5% of Flux High Posithw Rute RATED THERMAL POWER RATED THERMAL POWERrSe s with a time constant gCMri than with a time mmonstantet r 3.3.1 or equal to 2secoaft . or equal to 2secL
- 4. Power Rapg, Neutron Logss atano equal to 5% of. Lea. tha or equal to 5.5% of Flux, HIgh Negatie Rate RATED THERMAL POWER RATED THERMAL POWER with a tme constant esmter tha with a time cons= gmeaer tha or equal to2 euconda or equal to 2seccads S. JntemedlatRange, Less thaaorequal to25%S of Lunshan or equal tos0%of.
Neutron Phix RATED THERMAL POWER RATED)THERMAL POWER
- 6. Source Range, Neutro Lens tma or equal to i05 counts Lens tha or equal to 1.3 x 0 Flux per second counts per mcond
- 7. Overtemperature See Note 1 See Note 3 Delta T
- 8. Overpower DeftaT Sce Note 2 see Note 4
- 9. Pauaurl Pressur - Greater tha or eqal to 1875 pull Greater tha or equal to 1865 pslg L~ow
- 10. PnResUiuar POW=ue Lest tha or equal to 2385 pug Less tha or equal to 2395 psiS High
- 11. Pressurima Water Levl Les than or eqal to 92% of isa tha or equal to 93%S of
- 12. Loss O(fI Greatw dma or equi to 90% of Greater tha or equal to 89.1 %,of design flow per loop* design flow per loop'
'Desi nfow Is 114 Reactor Coolant System total flow rtwe from Table 3.2.-I.
COOK NUCLEAR FLANT-UNIT I -Pug. 2-5 AMENDMENIT K 1, U, 413, 214 Page 5 of 20 Attachment 1, Volume 17, Rev. 0, Page 30 of 471
Attachment 1, Volume 17, Rev. 0, Page 31 of 471 ITS 3.3.1 ITS 2.0 SAFET LIHMF AND liMITiNG SAFETY SYSTEM SETEINGS Table 3.3.1 -1TAL221 1 ~~~~~1. Manual Reactor Trip Not ppllcable Not Applicable 2.a, 2.b 2. Plower Rang. Neut=~ SIrpoint IMs than
- equal Low Setpolat - [ans than or equa Flux to Is Of RATED to 26% of RATED THERMAL.
P0 ~~~~POWER SepICU-ls ta qa High Scipint - lean tha or equal tol SOf RATD 110% ofRATED THERMAL P0 ~~~~POWER 3,a 3. PowerRAP, Neuro thin orequalto S% Df L ad oar equal to 5.5 %of Flux High Positive Rate RA THERMAL PO10E RATED THERMAL POWER a tine constant;p than, with a time cosisatnt greaer tha air taot2lseconds . or equallso2mseconds 3.b 4. Power Rang. Neutron ta or equal to 5%of. Ls than or equal to 5.5% of Flux High Negative Rate THERMAL P0 E RATED THERMAL POWER a dieconstant M tha WIth ktin conastant grete tha ouato 2beconds or equall o 2seconda 4 s. hmnteedlate Range, ccanoequalto 2S of Lensthan or equal to 30%,of. Neutron Flux THERMAL 10RATED THERMAL POWER
- 6. So= Rc a c~n wtum on taor equal to 1I out Lessthanor equAlto la i0~
5 ~~~~FluX second counts Per second 6, including 7. Ovmztmpesiture Note 1 See Nfte 3 NotelI Delta T 7, including B. Overpower Delta T sNote I See Note 4 Note 9. PreSSurirz PM=su - thi or equal to 1875 peig and Greater tha or equal, to 8'a E~~ow 8.b 10. Pressuurizerlpmsume- thSiauOr equal to 2 pus Lensdon atrequul to Spi High
- 11. PressudraWaterle.Lv Liuthanortequal to %of Lessihan or to Maog: U9.6 span .t 10 12. Le M tham or equd t 90% of Greafte tan or equalto ) 1 gaflow perw meloo-p'f-rlop 10K NUCLEAR PLMFNIT4 I 'Pape2 AMENDMENIT 91 41W, SC3, 21d Page 16 of 39 Attachment 1, Volume 17, Rev. 0, Page 31 of 471
Attachment 1, Volume 17, Rev. 0, Page 32 of 471 ITS Chapter 2.0 ITS IAMLEL1Z2a (Conamed) t.3. Steam Gmeaegt Wator Greffdane fzjor tqual to 17% of Grater thaat orqual to 16% of Lzvel - LOW-Low narrow ange lauui mtsa - mnarow rnge nsmirment span-each dtam Seeaw=r eah sluam genrator
- 14. S eFFedae low 1oss dha or oqual to 0.71 x Len, tan or equal to 0.73 x Mismtch and Low Steam 10' lb/br of steam flow at RATED 10 lb/h of steam flw at RAME Generawo WaSe Level THEIIMAL POWER cozinde* THBIMAL,POWER coincden wl& asp eam ewtor water Inde with steam generator water level greater banor eqmlto 25% of Steater banor equul to 24% of narrow rng~e kmmem spa - narrow ranp letrment spa -
esch 5t01 g.Wcatut each steam Immrai rsee fls1
- 15. Underyolap. Reatsr Greatar taroM equa to Grater tianor equa to L3.3.1J Coolad PUMPS 2750 volts - cwh bus272 volta - eah bus
- 16. Unufequeney - Reactor Greatw thaor equa to 57. Hz - Greater Uam or equa to 57. Hz CoolatPump$ each bus. each bus 17 Turbinc Trip A. Low MRui4l' Greaterthanor equal to 800paSg Greater fiuanor equal to ISO pug Pnemm B3.Turbine Stop Valve Greater dwamor equalto 1 open Greafte diaorequal to I S Wpe cansu
- 18. Safey lojection apus Not Applicable Not Applceb frm EiSP
- 19. Reactr Coolant Pump Not Appiable, Nix Appicale Breaker PositionTrip COOK NUCLEAR PLA1NT4JN I lagp 246 APMM ~W 4,1, 168 Page 6 of 20 Attachment 1, Volume 17, Rev. 0, Page 32 of 471
Attachment 1, Volume 17, Rev. 0, Page 33 of 471 ITS 3.3.1 ITS 1.0 SAFE7N WLETS MND LIMUTMG SAMETY sysTEM sE~rNGS I WI(ConanusedD Table 3,3.1-1 14 13. Steam Gneaptr Waecr Ura an or equuto V Sof Oreter thAnorqualwID 15 14. Stem ewater Flow Lgs or equal to 0.7 z Len dum or equa to 0.73 Mlsmatch and Low Steam 10' I of Steam flow at RTD 10' lb/h of sw=a &lwat RATED GeCeator Wate Level THE POWERL di THMRMAL POWER colocident. WMll~ soeslarwa leve wit stea craw~ "ater 9.7 pea duanor equato 2 %of gcwdno qit rapng. ii nt - 1-nnod md w 12, IS. Undervolte- Rcacw On or equalto Oreater thanor equal to cooladftwPms2 volt ec bus 272 vlta - echJ bus 13 16. Undquercwy -Rood da requalto 7.3Hzk-
&or Giestm &hnoreqal to -
Coolan PuM%% bus. 17 Tazbinc Tsip 16.a A. Low Fluid*Oil'smor equaltto Oplg' Greme teual tlo'10pel 16.b S. Tutbim Sop Valv tbnor equal w al%opeL Gneaw gmaor equal to I Sope MMin 17 18. Safety Injetion Lzut NApplicble Not Applicable firvi EiSP 11 19. 'Reactw orclahump AM1"NtANal Breaker Position~rip COOK NUJCLEAR ?LANT-UNW I Page 2-6 AhMEDMMN 4~168 Page 17 of 39 Attachment 1, Volume 17, Rev. 0, Page 33 of 471
o ~~ ~~ ~ ~ ~ ~ ~~~~.i~~~TBE2.2-1(Continued) 0 ~~ ~ ~ ~ ~ ~~~K-0 Note 1: Overtwnperature AT~rAT. [rIK2. TT) .1f(O Where: AT. Tndicated,&T at RATED THERMAL POWER T Average temperature, "P V Titdicated T, at RAMD THERMAL POWER (:g 574.0 OF) P - ~~Pteswuizerpressure psig
-4 ~~~~~~Pr Indicated RCS nominal operating pressure C2235 psig or 2085 peig)0 I + r~~s The fimedon, generated by the lead-lag controller for Tavi dynamic compensation 1+tis Tr,T2 w Time constants utilized Inthe lead-lag controller for Tot~
;"22 sac.m 4 sac. , Volume 17, Rev. 0, Page 34 of 471 S - Laplace transform. operitor Attachment 1, Volume 17, Rev. 0, Page 34 of 471 C/)
VCDr CD 0~~ ~~~ ~ ~ ~ ~~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ co
ITS o Th.D~~~mkT.TSY ll)Jin-umnuc Table 3.3.1-1 Note, I: OvertoniperaturCAT~gAT. (K. -K12I (-T) + K P-P) .fi(I) Note I L + rf Where: &T. llndicated A at RATED THERMAL POWER T Average tempertue, *F r ITndicated Tmw at RATBD THERMAL POWER ( 49 F) 1 2 p Pressurizer pressure, psig PI Indicated RCS nominal oPeratingpressue s~o g
-Cj cosans
'r~~ime n lead-lag controller frot e Irthb , Volume 17, Rev. 0, Page 35 of 471 S - Laplace transform Operator Attachment 1, Volume 17, Rev. 0, Page 35 of 471 (D
co~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~C C/)
TABL1 .L2-1(Continued) R CORTRIP SYSTEM IN-STRUMENTATIO TRIP SMTOINTS NOTATIONS (Continued) Operation with 4 Loops K, =1.17 K2 =0.0230 K3 =0.00110 and f1 (AI) is a function, of tde indicated difference between top and bottom detectors of dhe power-range sucleas ion chambers; with gains to be selected based on measured instrument response during plant startup, tests such that:
- 0) Fr q,- qb between -37 percnt and +3 perce-nt. fj(AI) =0 (where q, and qb arm percent RATED THERMAL POWERI in the top aid bottom halves of the core respectively, and qt + q%is total THERMAL POWER in percent of RATED THERMAL POWER).
(iiJ) For eac-h percent dwthat mhcnagnitde of (qt - qb) exceeds -37 percet, the AT trip setpint shal be automatically reduced by 0.33 percet of fts value at RATED THERMAL POWER. (iH) Foreach percent that the mnagtutude, of (q, - %t)exeeds +3 percent. fthAT trip selpint sball be nutomicatclly reduced by 2.34 percent of its valu at RATED THERMAL POWER. , Volume 17, Rev. 0, Page 36 of 471 Attachment 1, Volume 17, Rev. 0, Page 36 of 471 Cl) (0~~~~~~~~~~~~~~~~~~~ CD - o CD N) N o 0~~~~~~~~~ to
IT'S 0 2.2-1 (Continued)
~~~~~~~~~~~~~~~TABLE in B-F~~~~~~RJACT TRIP SYTEM INSTUMNTTIN TRIP S=TPINS NOgTATIONS (Continued)
Operation with 4 Loops Table 3.3.1 1 K Notel - 3 .0l
%and is a function of the indicated difference between, top and bottom detector of the power-range nuclear ion chambers: with gains to f1 (A&I) be selected based on measured instrumnot response during plant startup tests such that:
(i) For qj - qb betweenan f (A]= -where q and ohar fe nt RATED THERMAL POWER W the top and botmhalves of
~~~~~~in h core rsetvland qt + % is tota THERMAL POWER in percent of RATED t4 ~~~THERMAL POWER).
(ii) For each percent tht the magnitude of (qt - %) excee jds percet, theaT trip setpoint shall be automatically reduced (dii) For each peccnt that the mxgnitude of (a4 - qb) execeeds + percent, the AT trip setpoint shall be automatically reduced y~~~~~b , Volume 17, Rev. 0, Page 37 of 471 Attachment 1, Volume 17, Rev. 0, Page 37 of 471 CD (0
TABLU 2.2-1 (Continued) 1REACTOR TRIP MYTM I-N-7-UMETAIJON TRIP Mg=~NT
]LI1taTIN(onttnued' Note 2: Overpower AT E AT9 (IKs- Ks L ] T-K&(1T-T~)-;(AD].
Where. AT. - Indicated Artat RATED)77INVItAL POWER T - Average temperaturs OF 62
'I"' indiaed T,at RATED THRMAL POWER (:55 -l I)
X4 - ~~1.053 IsC, 0.01771bF for increasing average temperature and 0 for decreasing averge temperature K. = ~0.0015fcsrT> t Ksiin0fbrT:5e
'MTe fhnctotio generated by the rate hg controller for Ttw dynamic compensation 1+
= lmcosttstilizrdMthe ratelgc ontrollerfotTs ,g' 10secs.
S - Laplace transform operator AT span. Note 3: The channer s,maximum trip pown shail not exceed its computed trip point by more than 3.4 percent T spa. t-j Note 4: The channe's maximum tippoint shll not exceed its computed trip point by more than 2.5percnt q-& , Volume 17, Rev. 0, Page 38 of 471 Attachment 1, Volume 17, Rev. 0, Page 38 of 471 C/) (D (0 C9D rN3 0
2 fIl2Z (Continued) IU~CTR TIPSYTEMINTRMENATONTRIP SETPQINm NOTATION (Cotined) r -r-s I Table 3.3.141 Note 2.- Overpower AT AT- CK IiJV]s T-K4CT-T)f 2 (Aflj. Note 2 w hiare AT. Indicated T at RATED ITEfRMAL POWER. T - Average temperatuire, "F
- Indicafte Tm.. at RATED THERMAL POWER (5~ F IX4 n ~~~ ~~Ks~ t~~fricesn vrg femperatur and krlor decreasing average temnpertuue KA pJfor T> lFrK.-& r T:5 K.
Time stnsutilized in the raeI otolrfor Tm.-,- sees
-~~~~ S
~~~~Laplav transfom operator Table 3.3.1-1 f3 A 5 Note 3: The channer s maximum trip point shal not exceedi its coinputed trip point by more than4 tTspn Note 1 1 . Note 4: The channe's mximdmwtrip pont shall not exceed its computed trip point by more than cntTsp.
Table 3.3.1-Note 2 , Volume 17, Rev. 0, Page 39 of 471 Attachment 1, Volume 17, Rev. 0, Page 39 of 471 r-%)~~~~~~~~~A (0 CO)
-h CD
Attachment 1, Volume 17, Rev. 0, Page 40 of 471 ITS Section 3.0 lfm=IN CONDITONS FOR OPERTION k9)MjMCER 3.0.1 3.0.1 an AM _______C____fo____anI ia e duin the LCOTM ODSoroh f theAppliasbil l6dfctio oity d in 3.0.2 3.0.2 Adhertnce the requirements of the i Condition for Operaidon andi sscated ACJ1ON within Cho spcf tieinterval shalcnW ttcmlac with the spedict exetas provided in Specifiaton 3...In VWe event heliig tion for Operation is rexrd O2 OCpiration of th NERw . 3.03 30. Whn a Tnitn a_ dt____ r_________snt_ MI_____ ; mlth asso6ciated AC11ONP-E J [ecithin nne 5R tion shall be iaitigate to place the unit l -0T
- 1) n i&t I do'" not. 3 ac1my M-n i as applicable, 13j}S-thbdti fte limiting aComndeition --
Operationae me witoutrlance proithoe cotnaiu-ed NSR t mCiOtimn ts uonlesso fothr is e~pte.Tion e proftvbqision sh jjallrevsaeal iassae IndirodualtA OFBRATIONL (DSas required t op wit ACTION statements.L1 3.0.5 When a system, subsystem. train, component or device Is detrmne to be Inoperable solely because IsL emergency power source is inoperable, or solely because Its normal power source is inoperable, it imay be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergerncy power source is OPERADLE- and (2) all of its redundant system(s), subsystem(s), train(s), cotnponent(s) and dovict(s) are OPW.RALE. or likewise satisf the tequireifents of this specification. Unless both conditions (I) and (2) 'are satisfied, within 2 hoam action dlal be initiated topVac the unit in a MODE in which the applicable Limniting Condition for Operatkon does not apply by placing it as applicable in:
- 1. At leant HOT STANDBY wifthfinhe next 6 hours, 3s8.US 2.. Al least HOT SHUTDOWN within the following 6 hours, an
- 3. At leat COLD SHUTDOWN within the subsequent 24 hours.
This Spiicaition is cot applicable in MODES S or 6. 3.0.5 3.0.6 Equipment removed fromn service or declared inoperable to comply wihhATOet returned to servce uinder administrative controljsolely to perfonn testing required to demon OPERABILIT or the OPERABILIT of other mea~~t. Whs. Isanecetoto1 may be R 3.0.2 for the system returned to service under administrative contro to perform tge testing required toA8 demonstrate OPERABIURY.
~o Y COOK NUCLEAR PLANT-iNI I Page 314 0-1 AMOMENDMT 2 6 4 Q Page 1 ofl15 Attachment 1, Volume 17, Rev. 0, Page 40 of 471
Attachment 1, Volume 17, Rev. 0, Page 41 of 471 ITS Section 3.0 INSERT I Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6. If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated. INSERT 2 are not met, an associated ACTION is not provided, or if directed by the associated~ ACTIONS!,_the-unit shall be placed in a MODE or other specified condition in which the LCO is not applicable.A. O INSERT 3 in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required. LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4. INSERT 4 When an LCO is not met, entry into a MODE or other specified condition in th Applicability shall not be made e-xcept when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of tim4 T-his Specification shall not prevent changes in MODES----(A or other specified conditions in the Applicability that are required to complywt ACTIONSI or that are part of a shutdown of the ut Exceptions to this Specification are stated in the individual Specifications. LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1,2, 3, and 4.L. Insert Page 314 0-la Page 2 of 15 Attachment 1, Volume 17, Rev. 0, Page 41 of 471
Attachment 1, Volume 17, Rev. 0, Page 42 of 471 ITS Section 3.0 OINSERT 5 LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2. OINSERT 6 LCO 3.0.7 Test Exception LCO 3.1.8, "PHYSICS TESTS Exceptions - MODE 2," allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs isoptional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications. Insert Page 3/4 0-lb Page 3 of 15 Attachment 1, Volume 17, Rev. 0, Page 42 of 471
Attachment 1, Volume 17, Rev. 0, Page 43 of 471 ITS 3.8.1 ITS(I) 314 LIMKTIG CONDITONS FOR OPERATION AND)SURVEMIlANCE IIEQUI1EMEN'S 314.0 APPUCADILTM LimgTIN CONDMTON-F-lR OPERATION 3.0.1 Umixing Conditions for Operation and ACTION requirments, shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification, except as provided in Specification 3.0.6. 3.0.2 Adherence to the requiremets of the Limiting Condition for Operation and/or associated ACT1ON 'Within the specified time interval sall constitute compliance with the specification, except as provided in Specilicadion 3.0.6. In the event fte Lkmiting Condition for Operation is restored prior to expiration of the specified d=ieInterval, completion of the ACTION statemrent Is not required. 3.0.3 When a ijmiting Condition for Operation is not mnet. except as provided 'in the associated ACTION See r requvireents, within one hour motion shall be initiated to place the unit in a MODE in which the FSeto Specification does not apply by placing it, as applicable, in: 3.0 )
- 1. At least HOT STANDBY within th nex 6 hours,
- 2. At least:HOT SHUTDOWN within the following 6 hours, and
- 3. At leas COLD SHUTDOWN within the subsequent 24 hours.
Where corrective mecasure are completed that permit operation under the ACTION requirmiaents, the ACTION masy be taken in accordance with die specified time limits as measured froam the time of failure to rect the Limiting Condition for Operation. Exceptions to these requirements are stated In the Individual Specifications. 3.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACrION statements unless othierwise excepted. Thii provision shall not prevent passage throug OPERATIONAL MODES as require toc Il with ACTION statements. Required Actions 3.035 When a system, subsysterr. trin, comnponent or device is detemined to be Inoperable. solely because its A.2, B3.2, and CA1 emergency power sourc is inoperablo, or solely because Its normal power source is inoperable, it maey be 2coAtideaed HOTEAL forU wthin thp eofosaisfyin 6hhoquirrsandnso t plcbeUn odto forOpratonitprvied:(1 crrepodin nmia o emgncypDeclre sorequire fPERAturEs indprbe L2 ano citsreunantloasystmica blysein Ds),or6.~y opnt~)addvc~) mOE ,o qu0aipensti*rtemoe rm servieftor dhssecifired ionopera les t otomply dith os( n ACTONreuiementisfmyied(5 13.0.6 returne to seric' ude amnitatg e co tol asollmo perfr tesing r tocdmoitrat orprpseequired it OPERABUTY PERABLITY o the f othr equpmenLThis s an xcept oto urn o ropeimose Req0ire osiB See n .0. fOr teySTeMBrtre tohericeudrhne tdiins6di otrltoprfr thoutestn frequrosed ReqSectiotinnC demostrTe OP RABILthiY.3.0 COONULER OLDANr-N --- Pagehi houm1. A EN M T 6 eca rqurd eaurs npeagle.9of1 Attachment 1, Volume 17, Rev. 0, Page 43 of 471
Attachment 1, Volume 17, Rev. 0, Page 44 of 471 ITS Section 3.0 SR 3.0.1 4.0.1 byfineRw shall be dunnAthe MODES or otherAeonditiors InAprlicdkvarIdvdual tht 113 i CwD3o DODS ip on I nless COMM=wi stated in [a H SR30.2 .0.2 Each Sury Requirement shal be wormed wthln the specified i ntra INET8 A1 allowable ame not to exceed 25% of hde ed surveillane IntM.1l SR 3.0.1 4.0.3 IPerforman ofaSrelac ~qie~Within the specified time in sllConstitut coMPlianceL Wit fr:ihg Condition for Opraio ssociated ACTON' SR 3.0.3 If it is discovered that&aAveiiance was not PefrmedIfeaiyanete compliance with the requirement to declare dthe mitn rditionla gE not muetmabeGa Frqny from the ime of discovery, up to 24 hams or up to the limit of the rpcfiedl surv an 5isf ~ dl Y~i od is permitted~to allow perfomance of fth urINSERT SR 3.0.3 if tmai ellYit performed within the dely eiad, the rmting onition a Y~ prton must immediately be declared not met, and the alicahie ~N ~ is rd SR 3.0.3 Men he I51a I delay period and the Areun ce no the IT!nfij b wmust immediatey be declared riot moet, and the Applicable SR 3.0.1 Swrveillnt ulrnemnt do nobwveto be prormed oniL able ubnt SR 3.0.4 ntyit o N.,OEor ote lpEod j cdton'salno emdeuls their specifiedb MeISET1 Frequency- 4.0.5 Surveillance Requirements for Insrvice Inspection and testing of ASME Code, Class 1, 2, end 3 Code Class 1, 2 and 3 pumps and valves Ohal be performed in accordance with Section )a of the ASRM hBoler and Pressure Vessel1 Code and applicable. Addeiidgi as required by IO CM SO, Section SO.S5A. See ITSJ COOK NUCLEAR PLANT-UNIiT I Page 3/4 0-2 ADMENM TDI ,44 ,4Q, 263 Page 4 of 15 Attachment 1, Volume 17, Rev. 0, Page 44 of 471
Attachment 1, Volume 17, Rev. 0, Page 45 of 471 ITS Section 3.0 OINSERT 7 Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO.. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except. as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. INSERT 8 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 A1 times the interval specified in the Frequency,. as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. M If a Completion Time requires periodic performance on. a "once per. . ." basis, the above L. Frequency extension applies to each performance after the initial performance. Exceptions to this Specification are stated in the individual.Specifications. A1 O INSERT 9 A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk. impact shall be managed. O INSERT 10 in the Applicability of an LCO Insert Page 3/4 0-2a Page 5 of 15 Attachment 1, Volume 17, Rev. 0, Page 45 of 471
Attachment 1, Volume 17, Rev. 0, Page 46 of 471 ITS Section 3.0 INSERT 11 This provision shall not prevent entry into MODES or other specified conditions in t Applicability that are required to comply with ACTIONS[-or that are part of a.shutdownof2 the unit. SR 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1,2,3,and 4. Insert Page 3/4 0-2b Page 6 of 15 Attachment 1, Volume 17, Rev. 0, Page 46 of 471
Attachment 1, Volume 17, Rev. 0, Page 47 of 471 ITS (3) 5.5
~~~~~~~~~~~~~~~~~ITS V~ LIaMTNG CONDMTONS FOR OPERAT110N AND SURVMIlANCE REQUDIMENT 3/4.0 APPU.CAmllT .
4.0.1 Surveillance requirements, ahall be applicable dining dtheOPERATIONAL MODES or other conditions Specified for Individual Ldimiig Conditions for Opeation unless thewise State~d In an Individual Sureilance Requirement. See ITS section 3.0) 4.0.2 Bel Surveillance Requirement shall be performed within she specified time Interva with a maximum allowable extension not to exceed 25% of the specilled survillance IntevaL 4.0.3 Performance of a Surveillance Requlrem~enr itin. fthspecfied time Interval shl constitute compliance with OPERADLIT requiremnents for a Limiing Condition for Operation and associated ACTION sttemets unless oterwise required by the specification. If it isdiscovered that atsurveillance was riot performed idthin its specfie survillance Interval, the cnomplan with dhe requirement to declare the Limifti Condition for Operation not met may be delayed. fr Omth time oftdicovery, up to 24 bours or up to the liuit of the specified surveillance Interval, whichever is les. This delay period is permlttdut allow performance of the turveillanee. If the survelance is not performed withn the delay period, fthLimiting Condition for O.peration ms itmmediatelly be declaed not met, and the applicable ACrlON Toqulremens uiL be met. When the surveill~ancr. Is performed within the delay period and the surveillanne criteria are not mect, the ILinuting Condition for Operation must immediately be declared not mect, and the applicable ACTION requirements must be met. Svrveillnce requirements do not have,to be performed an inoperablt euipment. 4.04 Entry into an OPERATIONAL MODE or other specilled applicability conditon shall not be made unless the Survillnce Requiremnentqs) associated woith the Limaiting Condition for Operation have been pebrfomd wifthi the tated surveillane interval or as otherwise specified. 5.5.6 4.05 Surveillance Requirmnents for inservice I *sroFUtesting of AM oeC~ .2.a COOK NUCLEAR PLANT-UNUIT Page 3/4 0.2 AMENDWM ,1184,40,4Q, 263 Page 7 of 69 Attachment 1, Volume 17, Rev. 0, Page 47 of 471
, Volume 17, Rev. 0, Page 48 of 471
__ ~~~~~~~1D
~ ~ ~ ~~~~~~ITS Section 3.0 G COD NFORO [N SRELAC EURMN~
REQHMU
- b. Surveillance bntrvals specrioid In Section XI of the ASME Boller and, Pressure Vaasl Code amd applicable Addenda for the inservice Inspection and testing activities required by the ASME Boller and Pressure Vesse Code and applicable Addenida shall be applicable. as follows in these Technical Specifications:
ASbM Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for Inservice inspection and testing activities InservIce inspection and testing criteria________________ Weekly At least once per 7days Monthly Al least once per 31 days SeU Quarterly or every 3 months At least once per 92 Sees l5 Seianaly ofevery 6 months Atleastonce per 184 days Yeazlycrameually At leas one per 366 days C. The provisions of Specification 4A.2 ae applicable to. die above required frequences for performing inservice Inspection and testing activities. IL fedtcumac of (he above Inseric Inspecton, and tes*n activitiesshall be In & addtoto other specified, SurVeillnce Reuiemets.
- o. lfotbha In the ASME Boiler and Presur Vessel Code shall -be construed, to supersede the requiremets of any Tiechnical Sp~eCffcation.
COOK NUCLEAR PLANr4Nrr 1 P*Xa3M4S3 . MNMNIW0,4 2431 Page 7 of 15 , Volume 17, Rev. 0, Page 48 of 471
Attachment 1, Volume 17, Rev. 0, Page 49 of 471 ITS 5.5 ITS 314 LEhM1G COMMrONS FOR OPERATION AND RMVRUXAC1E QU1REME1? 314. APUCA33UM._Y SURVEILLANCE REQUIRMEtSZ 5.5.6.a b. Suv incebtervals specified in fecdo" ~ Sa7 MMrfrfn r die bm stng ativtes.Matvte rqie yd 5.5.6.d~~~~~~~ WPnsr Wshl eaplcbea flosI 4.0.6 Deleted" cm " COOK NUCLRapplicbeANTdVnd 1 fo Paology isAMEDEN*0,M23 ins~~ ~ ~ ~ ~ ~~~~ae f6 Attachment 1, Volume 17, Rev. 0, Page 49 of 471
Attachment 1, Volume 17, Rev. 0, Page 50 of 471 ITS Chapter 1.0 ITS (11 314 L~hffJlNG CONDITIONS FlOl OPEATION AND SURVEiLAN1CE REQtMEU(IN 314. 1.1 9kIN OTO SHUTOWN MARGIN - TAVO GR&AT= MIAEN20F Lwam- P0RLQZ~Ih= 3.1.1.1 Th SHUTDOWN MAROINuhzJbpegrwthinor qua to 1.3% Deft&k/it hZJ~~&~J~: MODES I20, 3, And4. See ITS1 With fthSHUTDOWN MARGIN les tha 1.3% De&t k/k. Immediat* lfntit and continu brntion atgeae doan at equal to 34 gpm Of Lwidouln condtainin puudamor upol to 6,550 pMu bom atr equivalmn umti fth require SHlUTDOWN MARGIN famatrd 4.1.1.1.1 Th SHUDOWN MARGIN udmU be deimbadtio be powte tha or opua to 1.3% Delta kIk 1.1 5. W~~~~~th.. ~~See Ot~~~~ft~~deI~~~tl~~a~~fMID~~~rahle ITS vim; 4 e atunarlppabe, fthabov require SUTDOWN MARGIN "hlbe-:eri.-. aooeptable wfic anhrme libwanae for-do hh woerh of d inmrahtle A.9
- b. When InMODS Ioc MODEB2 wft Neffgraw tham or mputo 1.O. stleaatoooepet 12bm Wor cIinS that comdo bhu witdrawa Iswidhn the lmits of Specfictson wafy 3.1.33.
. . ~~~~~~~~~~~
ITSI 3.1.6J c.: Whan In MODS 2 wbth Kef telouhn I.O. witi 4 hour ptla to achlevinS mawto ericalkty by verifyigt the6 prodiWctkW cotolrdalflilc position Is ithin fte limft dfSpxffcIIlW3on.1.3J.
- d. Pdw Wlnt4opmxutIaWW"SRATDTI1EMALpowEtaharaachfo~odzn" See ITS by commkdwalofofth & aaof sbeow,w tr bank at dem awole VA 31.
noSpedd Tog SeoeSjgelicdo.1 4i3~~~~~ Test - 3.l0.1~~~~~~~~~~~~~~ [seerrsj~~~~31. COOK NUCLEAR PLANT-UNIT 1 . hg. 314 14 AMENDMENT $4, U6. 34, 144 216 Page 16 of 35 Attachment 1, Volume 17, Rev. 0, Page 50 of 471
Attachment 1, Volume 17, Rev. 0, Page 51 of 471 ITS 3.1.1 ITS 314 LIWMiIG CONDMTONS FOR OPERITION AND SURVEILLANCE REQUIRMENT 314.1 REACTIvITY COWIROL SYSTEMS 314.1. MARGRZOCOTAV 1 il ~T CO M O OMTO within the limits specified in theCL LCQ3. 1.1 3.1.1.1 thi SHUTDOWN MARGIN dah bek w dior to 1.~3Dlt ACMOD 3,a o4 1itsk~c. w~hn . ACTION A tham or eulto44g of a sohtiam o6
-gnoV boaoicc te .
SR 3.1.1.1 4.1.1.1.1 The SHUTDOWN MARGIN shal be detbemhd to 'et [See ITs bimn~vbbet orumrlppebio, vce tepd SHUTDOWN MARGIN shal be 4fied See IT 12 houuuby IerffyWi that cotrol beak witlwdtuu Js withi the limits of Spwcificatlo 3.1.3.5. See irs~~~~~~~~ C. When Iia MODE 2 with IK!earnth an 1.0, withIn 4 hourm por to achevitig reacto crlticaliy by verifying hue the pniddcte citical comrual rod poshtlon Iswithin th limits Of the f 0~bl with the eBIkat the inSIvDM L
-see -To" ~ lmi. Seefca~f .. 35 COOK NUCLEAR PLANT-UNrr I Page 3I4 1.1 AMENDMZNT 74. 4U, 14$, 34,2716 Page 1 of 10 Attachment 1, Volume 17, Rev. 0, Page 51 of 471
Attachment 1, Volume 17, Rev. 0, Page 52 of 471 ITS 3.1.2 LMS~~~~~~I 314 LIMUlT1G CONDMIONS FOR OPERATON AMD SURVMULANC Ew IRIINWOr 314.1 REACTVrfY CONTROL SYSrEMS reqUTrDNSHUTCDOWN MARGNIsiord 4.L1.LI The SHUTDOWN MARCIN WWaI b 9este oemedoe than or eq to 1.3ua % Delt lk Se 3.1.1 Wm MUGN thes~uMON km m 1.3%Deb k, lm~b* WN mARI co hill bomlon9terif~ e tba atup to34 pmof haouib7verfytht s12d Smonrol banr OVAmwu Iophe whhln Umior Specifia umond mqWM MTDOWN ARGIN s3mm. See ITS 3.1.6 4.1.1.1.1M~~cu iLtyN byAvRiGINg tha the pdclemxd toca beul pwwtwor o Wtio 13 Deitlnta kitii
~ ~
d~~~~~~~~~~~ ~ ~~ ~~ ~ ~ ~ ~~~~See ITS Qw~mftteq~ft8HUM0WN WIAROYN d~beliSee ITS 3.1.6 burtionlb* of NWUWWNPage 1 of Attachment 1, Volume 17, Rev. 0, Page 52 of 471
Attachment 1, Volume 17, Rev. 0, Page 53 of 471 ITS 3.1.4 ITS(2 314 LIfMTNG CONDITIONS FOR OPERATION AND'SURVREiLANCE RQIEET 314.1. R9KACTVIT CONTROLSY M LEV 11INGCONITINQFR ZMAILQ 3.1.4.1 IU SHUTDOWN MARGIN shtll be greatee thno equ to 13*3 S Dela__ See FTS 3.1.1) IJchom: MODES1, 20,3, Ed 4. WI* ft SHUTDOWN MARGIN Ims dha 1.3% DebLt.k/, mmedlaay IudWs mad coimie bon"lo at grmater d=atoroqW to 34 gpm Of isL izuconetalnla 50Imur dmcc eqiad to 6,550 ppa bowom atequlvalem until fth requitd SHUTDwN MARGIN is auwied Required Action A.1.1 4.1.1.1.1 The SHUTDOWN MAROIN shl be delemhed to be greme tha or euAl to 1.3% Delta k/k: seeIUS
~ W-bsbov m~nd~ftn-bWNtMARGINihaldWb*4w~iiC4 buwvwsom Chapter 1.0
- b. Whim In MODE I orMODS 2 wkh uff eawartaan ccqual to 1.0, it Iter omc per 12 bouriby veri fig ht oomru bank withdraa Iswithindte limis of Spe~cifcai 3.1.3j.
See ITSI C.; Whim InMODE 2 wbth Mdf les don I.0. itbl 4 how priw to achievin momo 3.1.6J crklicaly by vafifin doi fte piedica rtcal" costel. rod poeltlo bawithn doe lmits Of Speclliatlon 3.1.33. ti. Pdltlha opaboire5%RATE DTERMALPOW aftareachfl~ie Se U by C=Wwlderl of tho bon ofge bdw ihd C baha ~ de SeeimTS lgIma imitd of kwafflcatla 3.1.35.311)
*so.Spcal -TetExceton 3.10.1. 3.1.1TS COOK NUCLEAR PLANT-UNIT I fts. 314 1.1 AbVZNbKMEN 14,.130. 148,.216 Page 6 of 14 Attachment 1, Volume 17, Rev. 0, Page 53 of 471
Attachment 1, Volume 17, Rev. 0, Page 54 of 471 ITS 3.1.6 ITS 314 LIWMING CONDMTONS FOR OPERATION AND SURVEELLANCE REQUIREj4MES 314.1 REAcTIvrry coNTRO sisTIm 314.1.1 W =RTIN coNTO AHUTOW? MARGIN - TAVO GREATERt DMA 200-F LahQam &QLEBhQLSee IS 3.1.1.1 Tbi SHUTDOWN MARGIN uhz be greater than or equal to 1.3% Dehta k/k. Ah1.LCARJLUM MODESI.,2s,3. and 4; With the SHUTDOWN MARGIN les tha 1.3S Delta Wk/klmmzediauly initiate and continu boratian at greaer than or equal to 34 gpm of asudom tinotalnlng Sreate thaor equal to 6,550 VMaboro or equivalent until the required SHUTDOWN MARGIN Esrestored. 14.1.1.1.1 The SHUTDOWN MAROINsh b. Geteaninetto be greaterOm or equal to 1.3%S Dulta.ik: L Wihbin am hou afte dcndan ofiam andi fma moos~ab. jSeeIT S] bwm iiff~e,
" o e-~m-reWNftMARGIN dMb nfe See ITS axptuhle with an lncmand aflowomn forthe withdran worth of die iznnvabla or Chapter I.J SR 3.1.6.2 b. When In MODE t orMODE 2 with. gaff greset. hancrequal to 1.0. as lenst once per 12 houruby erfying thut catmtro bank wlthdma is within the limits of Specil1aton 3.1.33.5 SR 3.1.6.1 C., Whon In MODS 2,with Keff Iess than 1.0, within 4 bour prio to achieving reactr critiaity by verifying thim th predicted critica contol roipostimoblwithin rb. fimits of Spvdlfcado 3.t.33.
- d. Pldaw UpuamdoabovaSS RAETEMALPOW~liatereoch (ml oad Se IT by comdwkntionf d fie--or of. bekow,wth hecaoetrobankstithe maximum eel hmgdtm limi of Spec~fict~ 3.1.33.5
*See Special -Tear Eception 3.IG0. 1. J~C COOK NUCLEAR PLANT-UNIT I Page 314 1-1 AMdENDMENT 74, 42O, 14,3j44,216 Page 3 of 7 Attachment 1, Volume 17, Rev. 0, Page 54 of 471
Attachment 1, Volume 17, Rev. 0, Page 55 of 471 ITS 3.1.1 ITS (I 3/4 [EidWUG COMMIONS FORC OPDAnCKP AlD SURVEULANCZ REQUIRW4TS 314.1 REC~rlvrcMqM O:sysrIIM SR3.i.1.i g ~~~~Wben bnMODES3~c4. at laitcrs -tpr4 C~M of ctt Molowafacwnr: I. S. - cancm~~~bc cm
- 7. Dcossal=y q=DE Aiv) 4.L1.LI 4. o cfbcwil wpv Wam. ibaliw db cwV dsvhao4e~rzi pe wM6n.uuCamlua %dab tok 1e.d ~ S ihav alPurDas(FD.Ti
- 7. ~Szam ip~wA %W 4mamfd r .4I ca ... 11o -Sf COOK NUCLEAR PLNUI I 1u*. 314 1-2 AM0S~ O 34.k230 Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 55 of 471
Attachment 1, Volume 17, Rev. 0, Page 56 of 471 ITS 3.1.2 3)4 L~hOTIG CONDITIONS FOR OPERATION AN4D SURVEnlLANCE REQUEREMMT 314.1 REACTIVIT CONTROL SYSTEMS
,SU'RVEILLANCE KEOUTREMENTS (Continum) e.When in MODES 3 'or 4, at least once per 24 hours by consideratio Of the following faCtors:.
I.Reactor coolant system boron concentration, 2.. Control rod position.
- 3. Reactor coolant SysteKma era tem [Sa rTS
- 4. Fuel burnup based on gross thermal energY generation, S. Xenon coneenain
- 6. Samarlum concntaton and.
SR 3.1.2.1 4.1.1.1;2 7ke overall core reaCtivtY balac shallbe etcoedvalues to demonstrate a e COOK NUCLEAR PLANT-UNM I Page 3/4 1-2 AM ENT 4N0, *48,230 bEND Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 56 of 471
Attachment 1, Volume 17, Rev. 0, Page 57 of 471 ITS Chapter 1.0 314 L&WrG CON0MONS FOR OPERtkION AMD S iLANCEREunIREmENs VUR 3141EA lyryCOtRL YTi 3.1.1.2 The SH(YFDOWN MARGIN WWaI be pstewr then or equal to 1.0w Delt k&l See ITS AM1LCABLUT MODES.3.1J ACM-Dx With die SHTUTDWN MARGIN hae die. l.O% Delta kk immediatly ledate and continue boration at greater tIm or equal to 34 pm of a soution contakiala pestr dhan or equal to 6,50 ppm bbcom or equivalent until the requfredsHUtDOWN MARGINIs retdomed 4.1.1.2 77wSHUTDOWNMAREN dul be de~mmia to begVwatedua orecquulto 1.0% Delta & S. c~mhol~m~e~dotect~olIOCM~aop~uble~o I £ andat See ITS 1.1 W na w f ole fa inoperale o IpersadlecautoLrimgmo3.1.4
.~~~I IL At lems ons pwr2d howr byooaeldersclom aftb foIKowkgaos
- 2. CQutrolutmd Pou1fic
- 3. Rbactorcolam system siorage tempeavzri
- 4. PMu bezmv baemW gpans hmulw emVygtamdon, rSee rrs1 L3.1.1J
- 6. XSenon cocqaftelona
-COOKNUCLEARPLANT-UNZT1I ag. 3/4 1-3 AMENDMNENT is0, 149,9% 230 Page 17 of 35 Attachment 1, Volume 17, Rev. 0, Page 57 of 471
Attachment 1, Volume 17, Rev. 0, Page 58 of 471 ITS 3.1.1 ITS 314 LIMIrNG CONDMTONS FOR OPERA ONANDSURVEILLANCE REQUIREMENS 314.1 BEACI3r CONTRL SYSTMm LCO 3.I1.1 3.1.1.2 The SHtTrDOWN MAROIN sha b iater tpor M ld o l. Defta ntithin lImi within 15 minutes L. ACTION A uicqrvtSSHUTDOWN MARGIN Is ftstored. SR 3.1.1.1 .4.1.1. The SHUTDOWN a m duAflbi dauzmhooto bcef" iud o lz : orwitrippabte, "i SHUTDOWN MARGIN shAll be WvIdd acceptaleb with an iflCsed ~ T SR 3.1.1.1 _ 3.
-COOK NUCLEAR~ PLANT-UTNIT I Page 314 1-3 AMENDMENT +.V, *48; M*230 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 58 of 471
Attachment 1, Volume 17, Rev. 0, Page 59 of 471 ITS 3.1.4 ITS (7 31 W41TM4CONDMONS FOR OPMRATON AMD SURVEILLANCE RQIEET S14.1 MXMWA SVI~ONT-RUOI SYS THA R EQAMS20 L~tfE DbLOEEFR OPRATHI 3.1.1.2 7U SHUTFDOWK MARONd~iall be gtr donthor equal to 1.0% Delta ki See UlS 3.1.1J APPEL1C&BD.. MODE S. WAu do. SHlMowN MARGIN 1e as I0% 1. Delta kkIrA mmediately initise and continue boraton at greter tha or equal to 34 pm of a solution continiaing greater than cc equal to 6,35 ppm bbcoa or equivalent untit the
*equSKEd8UZOWNMAROI1Nl retored
- 2. rod Conkol pouitiam, onolrodb mmvaleSe M 3.Atlo Rnorow2how by*savvslstadoertuof ao SeeoflSz 4.31.
- 2. Centol fcOdOcqtrlo 46 VWamvpmbconcmSnmadosmal e mrbn
.7. BoWSoNDxmly.
COOK NUCLEAR PLANT-UNIT 1 Page 314 1.3 AmENDMENT I-,0, 14*1 230 Page 7 of 14 Attachment 1, Volume 17, Rev. 0, Page 59 of 471
, Volume 17, Rev. 0, Page 60 of 471 ITS 3.1.1 Thin pals intnlfliti'any left t Ank.
C=o NUCLZaI MFli? NT 1 M 3/4 1.3. AKClDI(M i10.1*C, 148 Page 4 of 10 , Volume 17, Rev. 0, Page 60 of 471
, Volume 17, Rev. 0, Page 61 of 471 ITS 3.1.1 ThIs V'S. intenti@IIly left bl.axk.
cot VLC1.A.L *Uf MIT~1.1/i"1 2-3b Ajz~~nMMz 1u03Ze, 148 Page 5 of I0 , Volume 17, Rev. 0, Page 61 of 471
Attachment 1, Volume 17, Rev. 0, Page 62 of 471 CTS 3/4.1.1.3 3.1.1.3 flow rate of ueewot coo ea hn shall. be p ace than or squad to 2 Coolant ys boron cowcotration Losq na".* te tmsoe. actor C Ian:57t03 a ro~ucti InRactor I ALL NOOKS. With the owrate, of reactor ao through the reactor too en ystaon less tban 2000 *Luneiately sospen 1operactoim inwoLIDSn a reduction La boron Lmcrcou of the Ractr oLant System. 4.1I.L.S flew tat' of reco eetbthacu thM name Goelent &?Sta. shall be temndto be gretatr or oi4a to 2000 Du *thi on our prir to saret of amd a ot oncea per boreu" a T tion in the 2awter laa: Syseti boron Smo trce y ei Ve: A riVyfMAg at least one actot sooeant pmup Is in rion, or
- b. Verifying that at lea"ton OR3 pM'L Sii opera: onensplying greater than or equal t 2000 ps through the it tor clantf
- For @80 of tbis specific, ion. addition of water fr the 3115? does avc conat tu~edilution activiry' roviaefithe boiou coxncen aton in the 1115?
iLe jp aor than or equal co rho minimt.m required by speci icaton 3.2..2.11b.2 (HOD I. 2. 5, ,A a) or 3.1.2 7.b.2 (NODES 5 anld 6). I ID.- CMTCM 1 ~ 3/4 1.*'AIgr o 120 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 62 of 471
Attachment 1, Volume 17, Rev. 0, Page 63 of 471 ITS 3.1.3 HOW=RT~ ThMUTOR cogMCwI
&MZUNG CONDXT12i inX puVA'ION LCO 3.1.3 3.1.1.4 T mderator sa tesperatre coefficient fC)sbell be vithin the limits specified in the GMZ. 2be mazdama vxpr U.ait shell be Iwo thm or eqjual j to the limit sh'n Su Yigare 3.l2. -] .
APPUCABILITY:LLIai MOI3.ed2
- 03 i ACTION: A2
- a. Vith the HTC mote positive than the limi secifid gm the i~R-ACTION A ~ * £tablish aW Maintain control god vitbdraWal 14lim j it OE h .
ACTION B ~~~sufficient to restore lcnxu to vithin its lisit vithin 24 1nR~----f-A'vijthia the text 6 hours.. he
- 2. MA/inthe contro toi within the viedr41limits est lb~aed above Lii Subequent aes r~t eiftLos thatL.
tKChau been aeet d to within itL %i o the all z~.withdrawn condion 3.- lrepaeand submit & I" alptirt to th q.saLon prat to Spsecffiatf$ 6..2 within 10dsdeadribing the
~a~fthe measured ,the interim cnolrod vithdravalL.
the predictd aegcore, "1i5Ad necessary for r htrisn the positi TCowiinits for the all tImi t~.withdrawn eondi afn. ACTION C b. WMt the EITC more negative d=tha e Wh imit specified in the COLI, be In MOT S TDOIW within 12 hours, oe . Applicabilifty
- Wth -K raterthno w .
COOK HUCLIAZPIAI?-UIT 1 3/4 14 IJIDIKTO.10,101, 146 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 63 of 471
Attachment 1, Volume 17, Rev. 0, Page 64 of 471 ITS 3.1.3 ITS 4.1.1.4 rhs MC habol be dsteuLned to be wfthL& A Its lua iu egach 2s1 cycle as Lollms:upeA. a) 2be C sAll be swas=" an soupmrd to te 1Sat SR 3.1.3.1 Mepaitlei to the C=1 prior t* ozte peration aborwB o0f RATED THE.M1A' PC=', after eaCh fuel loaftr4. b) The K1TC shall be mamrnd at any 7A131W. t~within 7 EFPD after reachin% en equilibrium boron emesutsation of 100 pps. S 3.1.3.2 UsThimeasured value shell be comwaed to tbe, 00 pm sum~illsnce SR 3.1.3.2 ~lmit specified in the COIL in &be event thi mompaeo indicates that the WXC will be more reptive than the Lbt the KTC shall be remasured at least onwe per 14 SM durin5 h CMOKPUCULAIIAXT.WMTl ) /4 .sa hNM DKUTU0. fl, 146 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 64 of 471
0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~FC0 Figure 3.1.3-1 FIGURE 3.1-2'- Moderator Temperature Coefficient (MTc) IMTC~i 010 Ak/k/dgg.F 2 '. unac epto Oper, to 9.. ~0.50 0.00---
-0.50 - - ~
*0* -1.00 ---
cr ~~~~~~~Ace, itoW. Opera [on
-1.50 - --
-2.00-- - -
-300 -
2 0 ~~~10 20 30 40 50 60 70 80 90 100 4,
~~~~~~PERCENT RATED THERMAL POWEIR , Volume 17, Rev. 0, Page 65 of 471 Attachment 1, Volume 17, Rev. 0, Page 65 of 471 co P~~o (0
CD 0'
Attachment 1, Volume 17, Rev. 0, Page 66 of 471 ITS 3.4.2 ITS LCO be a.is wto g 2"wytes lowest eerwSao beg. vei-W. 3.4.2 (Tavg abal be P. c4T mtheastt58 5 Luei. h~G&1f.IU:MNde I and t*. ACTION A "ngrtsM t il-m~~~mitIneter rMO DE 2 with keff < 1.03 SR 3.4.2.1 4.1.1.5 the I&ACter Coolant Oastes ip~~a ?5 hl be 4stemaud t be 3 417: fa. qj;Is1 smants p t aeL aee wt
- b. £ .:.o per 30 vlnutv. a. the ueactor to cuItloal, the cwCoolsant System Ta P,less than 351.5 or 'herevsY L isImperable.
Applicability ovitb ,,af I .0. DC. V00K'UMT 311.1.6 Ar3MW3IRO.1Z6 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 66 of 471
, Volume 17, Rev. 0, Page 67 of 471 CTS 3/4.1.2.1 314 L~hdrrlN ONI NS FOR OPERATON SURtVEIflANCERE 3.1+/-23 As k minmuu one of the fol boron iz~jcton flow paths shall be- PEALE
- a. A flow path from the cacid tWks via a boric acdd tas pump mnlchrgigpUMP to the g~tacrC0,01Ant S if only the boric acid storg In Specification 3.t1 .7 Is OPERLABLE,mo
. 1he fHow path from the fengwater stoame tank vi gpump to the Reactor Coolant System If o!the aeuesn watn storage tak Seiiain 3.1 2.7b Is OPERABULE APPI ~~~MODES 5 and 6.
Wirah none theabve flow paths OPBRAB suspend adl operatior. Involving COEALMERA&TIONS or positivo react tc anuecepl: I) he"u or I~dovn of the reaect Coolant Vol provided, tha SHIFEOWN MARGIN ea to accommnodate the duan In tamperam Is mantained In with Specl~catlon 3.1.12 In cSpecificati02 of 3.9.1 In M B6.Caamdthehihqpar cooldown lesutdto SOoFor less in any period inMODE S. or 2) additi of water from the RWST. prvdd boron concennrtion In the RWSTUs tha or equal to dbe minimum uiOdbSpecitication 3.l+/-ThJ2. 4.1+/-1 At leas one of dhe abovere fl~owpazhs shall be demonstatzed PRBE S. At lead oaepec 7 by veifylztgthattdie to heaWmacontaining the nlow Pao* fzoa xboricmidunk to toe ritee amegrcaerVW or equal to630t4e lopah fromdhe boricacid tanks usd
- b. At leaw once per 1days by vei~ftg that each val (manual. power operate or automatic) In the path tmhaI not loced. sealed, tews secured in position, isin 1wc2Toc COOK UCLEAR PLANTANUN I Page 3/4 1.7 AMENDMENT *M. 16U2 , 30 Page I of 3 , Volume 17, Rev. 0, Page 67 of 471
, Volume 17, Rev. 0, Page 68 of 471 CTS 3/4.1.2.1 I.ICTIVTTy CN ROLsT¶EMS TUANELLE MmEuIFXEns_____
'Thia. page 1UtauticnAly lef bZlukR COOX NUCw+/-AJ PLAST -UNIT 3. 3/4 1-8 MM(DEN NO.15 Page 2 of 3 , Volume 17, Rev. 0, Page 68 of 471
, Volume 17, Rev. 0, Page 69 of 471 CTS 3/4.1.2.2 314 L1OTNDM TONS FOR OZAI AND SURVMilLNCE REQ
'314.1 E CONTROL STM 3.1.2.2 -hofthe folowing boro izaj onflow paths hai! be OPERAB The flow pubathm te adid twkvia aboft~al fpump ada aCharging pump to dhoeatr a Systm, andI The nlow path arm th o 1 war storag tank Visaa PUMP to the Reactor Coolant System.
MODES 1. 2, 3 and 4.
- a. Wilh th tlow path ftheboric adid tnks Ioperable, ve the Inoperable Jiom pub to OPERABLE sas tl 72 hours or be in at Ient H TADYand borated to
&SHUTDOWN MRIN equivalee to at leas IS at 200P1 within the neM 6 bors; etwore thlow to OPERABLE atalna wihi n 7 days aobe In COLD R.
SHUTDOWN withn a z 30 hours. b.. With tb Ra~w pah ftbesefbing water mozpgtank the flopazh mem=str so OPERABLE amsct one hour or be tast least STANDBY within OM nx 6 hours and ill COLD SHTONwithin sho 30 honm. 4.1.2.2 Each of the aboy, mqreqid paths tha be demnstrtex 0 L L. Al lugstowcepYu b verfytnghtshmet &fha mucoalnh~g the flow pah from do boric acddsank tot tooaregrnaewshanor
- b. A~l W once p3 dip by vdI~inthe eachnid e(amanuL power operated or wiustic~)in dhe path diat Is.not locked, sied, otherwie aecuresi In position.
- c. AtleataxamseI moVAtSdurlnsuhokmdmb ebaschwwmazAic valveln de flow pts o Ks correct position on inRf STscwniignal.
- d. .At Iestoue lmuhduringthusdown byve thatdhelpath required by OM
.. a delivers at leas 34 zups the fpcfctio Coao ytm COOKCLEARPLANT-UNTITI Page 314 1.9 ASSINDMEWT444,216 Page 1 of 4 , Volume 17, Rev. 0, Page 69 of 471 , Volume 17, Rev. 0, Page 70 of 471 CTS 3/4.1.2.2 THIS PACE INTENTIONALLY LEFT BLANK COOK NUCLEAR PLANT-UNIT I Pagp 3M41-10 AMEN4DMENTr 444, 216 Page 2 of 4 , Volume 17, Rev. 0, Page 70 of 471
Attachment 1, Volume 17, Rev. 0, Page 71 of 471 CTS 3/4.1.2.3 3/4 LIMITI]NG C DTONS FOR OPRATION SUIRVEILANCIE REQ O 314.1 REA CNRLSYSTEMS ARGNG ? - SHUDOW I MGC NDn ROPERATION 3.1.2.3p lmshe.4.12nO ,,,o4 3lato3...3b-
- a. Wion charging pumpInPtERAB useond alow opratioh irvoiing Cy ALTERT2ON orab pbosiieChreacivityo ahan exceth seaupportcodw nio 2 f the reamctoc coollant volumlroie accodacwitSpcfication 3 .1.1.2---rie wnMO ESUio Seficaion 2 .9.1 MOE6,adth on .
heatup or cooldown rateisr uceto 500 F or less in anyo - periodin MODE 5,or
- 2) addition of water from the WSprovided the boron cnta in the RWST is greater than or o the e id= re by SR cification3 27b.
- b. With more than one charging pump OPERABLE or with a safety iaection pump(s) OPERABLE when the temperature -ofany RCS cold leg is leas than or equal to 152PF, unles the reactor vessel I See rrS head is removed, remove the additional chargig pump(s) and the safety injecdion pump(s) motor I 3.4.12J circuit breakes from the electrical power circuit within one hour.
- d. dionto the above, wnSpcfton3.1.2.3.b is applicable and the equired flow path is available, retur the reurdfo ahto availale status within 7 dyor provide equivalent shtoncapabffity in Unit 2Han rF the required flow path to avail estatus within the nex 60 days, or have Unit 2mn O TANDBY within the next 12 an HOT SHUTDOWNL.
within the following 24 hus e ibe requirements of Specifc o30.4 are not applicable when. S fiain3.1.2.3.b applies. SREILLANCENT 4.1.2.3.1 'ieabove,required charging pump bedemonstrated OPERABLE b erfngthat the pump'sR. developed head at the teat flow isgreater than or equal to the re developed bead when tested pursuantto Speclfilcat S/.5 3.4.1i23 COON(NUCLEAR PLANT-ULr 1 Page 314 1-11 AMENDMENT 96, M~, IM, 46, 67, MO, 230 Page 1 Of 4 Attachment 1, Volume 17, Rev. 0, Page 71 of 471
Attachment 1, Volume 17, Rev. 0, Page 72 of 471 ITS 3.4.12 E_0 3/4 LRAMTNG CONDITONS FOR OPERATION AND SURVE111LANCE REQUIREAMM( 314.1 REACTWITfY CONTROL SYST7EMS 3.1.2.3~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~3/...1
- a. One charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE an capabe of bein powered from an OPERABLE emergency bus.
- b. One chargig flowpatb asociated. with support of Unit 2 shutdown fuwntions shall be available-'
APPLICABILTY Specification 3.1.2.3.L - MODES Sand 6 Speciication 3.1 .2.3.b. - At all times when Unit 2 is in MODES 1, 2, 3, or 4. A. with so charging pump OPERABLE, suspend all operations, involving CORE ALTERATIONS or positive reactivity changes except: 1) hecatup or cooldown, of the reactor coolant volume provided that SHUITDOWN MARGIN sufficient to accommodate the change in temperature Is maintained in
- accodance with Specification 3.1.1.2 -in MODES5 or Specification 3.9.1 in MODE 6, and the
- heaVu or cooldown rate is restricted to SOF or less in any one-hour period in MODES5, or ACTION A, b. With snore than one charging pump OPERABLE or with a safety~ o ups OPERABLE ACTION 8 EEthe temperature of any RCS cold legis 1e53thfor equIal toj!~~ .uness thereactor vessel Applicabilit y c is rx-emove the additional charging pump(s) and the safety injection ovedr~m oecrou.imeitl(' )
C. The provisions of Specification 3.0.3 are not applicable.
- d. hi addition to the above, when Specification 3.1.2..3.b is applicable and the required flow path is n:available, return the required flow path to available status within 7 days, or provide equivalent shtoncapability in Unit 2 and return. dhe required flow path to aval~able status within the nextSeCT 60 days, or have Unit 2 in HOT STANDBY within the next 12hours and HOT SHUJTDOWN SeT within the following 24 hours. 3/4.1.2.3)
C. The requirements of Specification 3.0.4 ar no applicable when Specification 3.1.2.3.b applies. SURVEILLANCE REOIRM ENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed bead at the test flow point Is greater tha or equal to the required developed head when LCO 3.4.12 'A maximum ofwcarf lea hl be OPE LE verth temperature of one or morm f h Applicability RScl legs is less than or equal to12 COOK NUCLEARMPANT-UNIT I Page 3/4 1-11 AMENDMENT 96,10, 13*, 164,17, 03, 230 Page 3 of 14 Attachment 1, Volume 17, Rev. 0, Page 72 of 471
Attachment 1, Volume 17, Rev. 0, Page 73 of 471 OTS 3/4.1.2.3 314.1 SYSTEM~~~~~~~~~~~~~~~~~~~~~~~~~~. CONTROL 4.1.2.3.2 Anl dhagin pumps and Whfey injecton pumps, excduding ib above required OPERABLE charglzg p~p sia be demons~mtd inoperble by Verifyin that the Moto circui breakers have See flS beenemoved from their elecuWa power supply circits at leas once per 1.2 hours, excpt whem: 3.4.12 J A. The reacto vesselW baIsrMoved, or
- b. The wmperacurofallfCS cold legi slgreadergm ll2P1.
4.1.2.4.3 ~line cross-tie valves Itoj t 2 will be cycled flltave a m pner. ISots 4.1..3.3~7 llo~ingcycling the valy 041i yified ve to be In thei ldt~ n. 1 COOK NUCLEAR PLANT-UNIT 1 Page 314 1-l1e AAENDNME 4)4, 167 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 73 of 471
Attachment 1, Volume 17, Rev. 0, Page 74 of 471 ITS 3.4.12 3/4 LIUMING CONDITONS FOR OPERATION AN) SURVEILLANCE REQUIREMENTS 314.1 REACTIVTY CONTROL SYSTEMS CHARGING PUMP:. SHTDW LIMITING COMMITON POQR OPERATIntcpalONineto it SR 3.4.12.1, 4.1.23.2 All chargin pumps and 9safy Injedon pumps, exdluding die abov required OPRAL SR 3.4.12.2 91g. PM adl be demonsturazdln~ nvMuckulrAM-bieenjSPed frmmtheir gpLA w M st"MO alou ethm ApplicabilIty b. The UcipezUw of all RCS cold legs Is peser 'F 4.1.2.3.3 (Cargiug KWn cros-11 valves to Unit 2 will be cycled full mstav leas oce per is omthdsj e FolloMin CYcliag, te Valves Will be verified to be in WUei closed po03ilon. 3/4.1.2.3J COOK NUCLEAR PLANT-UNI I Page 314 1.11. AbMNIDNENT 431.6167 Page 4 of 14 Attachment 1, Volume 17, Rev. 0, Page 74 of 471
Attachment 1, Volume 17, Rev. 0, Page 75 of 471 CTS 3/4.1.2.4 3/4 LIMITING Co TONS FOR OPERATION SURVEILANCERQ 3/4.1 RAON OLSYSTEMS IARGNG P - OPRTN DIN OEAIN 3.1.2.4 At eattwo chrgng pumps shall be PRBE APPLLQCABUf: MODESl1 ,23and 4. AMON~: With ony one Ing pump OPERABLE. astor leas two charging pumps to OP LEstatus withi 7W2 r be InOTSTANDBY within fthnex 6 thors Yo restore at leas two cbArgin to OPERABLE swausawihin the x48 hoursor be iriCOLD S W wirhnMetfollowinzg30b 4.1.2.4t least two charging pumps shall demonstred OPERABLE by tbMt the purmps eloped head at fthtest flow pntgreater tha or eclual to the developed, head when tdpursuaN to Specification 4.0.' COOK LEAR PLANT.UNIT 1. Pap 314 1.12 METU 4~203 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 75 of 471
Attachment 1, Volume 17, Rev. 0, Page 76 of 471 CTS 3/4.1.2.5 314 LIWMING NDITNS FOR OPERATIN SURVEMlLACE 1E 314.RA .CONTROL SYSIUMS BORICEm m 3.1.2.5 At om boric acid tansfer pminp be OPERABLE and capable of powered from an
- 0 ~~~emrgentvy bua if only the path thr=# the boric acdtransfer of sei&4wio
- 3. Ia I OPERABLE.
APIA13 MODESS5 nd 6. With no boic d taIf pump OPERABLE as to complete the flow path of iL3.1.2.1a, aDopxn Ausen kwinvn CORE ALEAINorpohveractivty chages except: ccooldown orea of fte reacor htvolume provided taWNMARGIN sufficient to zon i thechn In tempemmnr~ InccrdncwthS 3.1.12In MODE 5or pcf .9.1 inMODEE, and dot heani oodw rafte resriced to ln inswyon-haot perioIn MO 5, or 2) addition of Io water from th Sprvide the boron In the RWST Is gre dmatethno to fte minimm reurdby St liao3.1.2.7.b.2. 4.1.23S N additionalsurvellaie reqrientents than thos mvi~red by 4S..5 COOK PLANT-UMi 1 Page 314 1-13 ME~4W, 640, 230 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 76 of 471
Attachment 1, Volume 17, Rev. 0, Page 77 of 471 CTS 3/4.1.2.6 3.1.2. 4 At I eat On.* boric acid transf rpump in the baron injecto flow path required by g ecification 3.2.2.2., uhal be OPZRAJIZ and capable Q bein& povered frog &a01 I. mergency bus If the f ov path through the. bori aid. pump In Specification 31.2.22. to OPEDABI. APZLTC~ MODES 2.. 2, 3 end 4. Vith no barn acid transfesr pump OPE. AI re cstors at least on. rie acid transfer pmto OPElA3LE status ithi 72 hours or be in at leatsHOT STANDBY vittin the nzt 6 hours and borated to SEUDOVN MARGIN mquival. n to It akk at 200 F; reuto a at least one boric act transfer PUMP to OPEUM3Z status vithin the next 7 days r be in COLD SHUT'DOWN vi inthe -next 30 'hours. 81URVEV,-REOUTPIMENTS,~~~~~~~~~~~~~~~~~~~~~~~~~. 4.1.2.6 N1 additional. surveillence equirements other thane th a.required 'by Speciftcat on4.0.5. COlMU NU? IL=N 12 1 3/4 1.24 AUEKE 0w.14#, 164 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 77 of 471
, Volume 17, Rev. 0, Page 78 of 471 CTS 3/4.1.2.7 Xf4 LVAMiTN N ~FloNS~lERT AMDUVILNEZ 3.1.2.7 Asan iiaumm Om of"hfogl bomeid wwwalruorcsubelb LEM IL. Aboric " dtatue wkht
- 1. ~Awli bontod wavl*of S =ogal
- 2. Betwac 655 6,990 ppm of boron, and
- 3. Asinaimumiol Memprtmio(63*P.
- b. The rtfefuein Wwae teak wfdL
- 1. A hm~ borntsd watevehm. of 90O~OD0 es
- 2. Amiuimum ac cncoadon ofU40pp~m ad S. A toininuim uion ten etinoof0.
AEKA-A MODES andWA Wihb no witer iomic OPmRBL, all operation Involin COREATRAMN or posiltive rectiviy aen ezet1) heatup oatol oft raeao Coolan didme ha SHLUIDOWN MARGN atto accomko~dot h In tempertur is maitane In wth Specification 3.1.1.2Int DHor Speciilcauio3.9.lhu In 6,mWAdohehetupor cooldw arilcdto 50F orless In aNy o period in MODE S,aor 2) addWt of water from UrnRWST, prvdd boro concetration to the RW$TLx danor equal to tdo milalnm by Speciflcafioa3.1.2L7.b 4.1.2.7 The Above requhW bmrted uucuulemoiaeO LE:abo
- 1. Vryng bcewn comeewdonfof Owuwte.
- 2. Verfyn wuueikvslvlm ofdwtak
- 3. Verifying boric add skup tank ~ Wohd._en it Isdo acmeD
,b. Aezom per AlUs hom rsy werifngdiheRWST when f s the soureof CO NCLEAR PLAN FUNI 1 Pge V4 t145 AMENMZNT~A.*t*,.*6230 Page 1 of 2 , Volume 17, Rev. 0, Page 78 of 471 , Volume 17, Rev. 0, Page 79 of 471 CTS 3/4.1.2.8 3.1.2.8 of the foflowiM torad %wat uc ssha be OPERABLHA A bodr. add nouemp wth
- 1. AIIIII.R b barstwatcvolumtofSJW00l *
- 2. Etweam 6,550 6.99 ppm of boron, uid
- 3. AmiDniIBm=O tompmuuzuof63*
- b. The rfuelngwaters tn ih
- 1. Arninlnu vbmof 3l5SOMgpS~oof 26 0
- 2. BetwMe 12400 0 ppm of boron, and 3.A mh~ ~ - ezueruwoof 70'1' and a tata mOlutton tempffatuo .
AP" ~~MODW 1,2. 3 nd 4. IL WMt the bark WOd wobml restOre sswaut.O~pERA~p li stum iswkhin l Iren at lowzHOT8STAND dwohl hnext 6hom WAn buratetoaS MROUNequwvalatmoat ouu AJk at20OF.aswim th bas do stmgg to OPER"aJ. swu witin& amext? as or be in COD BIUJTDWK wihi 0un bohom.
- b. With doe reuin stora tank inop"rbl,0 restal tank to OPMUALE satus withl Gonehu r at kwu HOT STANDBY within neu 6 hours and In COLD) 4.1.2.3 Eablch b Iae wowmicas b*demooirateOSRAL~k Not uedwins harme wate Is 2 Into the RLCS to mseet W MARGIN reqtdmrments of MOPBS and4.
COOK ItPLANT-UNIT 1 PageV~4 1-16 AM NMENT 46, W.I~4 ~6 3 Page 1 of 4 , Volume 17, Rev. 0, Page 79 of 471
Attachment 1, Volume 17, Rev. 0, Page 80 of 471 CTS 3/4.1.2.8 REACTIVITY tONTR'OL SYSTEMS SLIRVE[LLAN REOUIREMENTS (Contin ed A. t least once per 7 days by: Verifyinig the boron concentration in each w ter source,
- Verifying the wate level of each water so Ce, and
- Verifying the bori acid storage system s ution temperature.
- b. At least once per 24 ho rs by verifying the AWS temperature.
- b. CRCO.NT1 / -7A detN. Ii I.~ ~~~ ~ ~ ~ ~ ~~~~~~~~ae2o Attachment 1, Volume 17, Rev. 0, Page 80 of 471
Attachment 1, Volume 17, Rev. 0, Page 81 of 471 ITS 3.1.4 ITS 3M. 1.3 KOVAILE COMTOL ASSEMKIES
=~TMN E CONDITION Pot PEATIo.
LCO 3.1.4 3.1.3.1. All full .length (shutdovn and control) rods shall be OPERIILE, with all Individual. indicated rod positions vithin the allowed rod misaliLgnment of their group Stop counter demand position as foloys:.
. for THflRAL POWER less than or equal to 851 of 1AWED mUKAL POMn, the allowed rod misalpigment Is *18 steps, and for IHUECL POWER greater than 851 of RATED THUEMA ?0MI the steps (or A2L equal to 101Z) to *:18 steps (for AnI greater or A CAMT H ODES 15kand (1 ACTION A a. Vith one or more full le~t rods Lnoverable ]due, to beiuig ablea requrament of Spec i-cation 3.1.1.1 Is satisfied vithuIn 1 o~ur and be in HOT STANDBY within 6 bolws. Add proposed Required Action AJ,1 ACTION D b. With more than one full. length rod1& c-rabje o m12saligned from the group stop counter demand position by more tbman a- weva rod misaligimiant. be In MOT STANDBY wIthin S bours.AdprosdRqreAcinD1.ad 1.
ACTION B c. With one full .t rodiftoo rala due to causx other addressedA ACTION a.M23 orl mlsal gnd from, Itsgrp t. cotmttr demand POS~tion toy m~et thAn the AlloWed rod isgoet lOP ERATION may continue prodded that within one houreth: PO
- 1. The oeted rod Is :estog to OPEZABLE ta WUhi the Abo ' aignaent require it.or TUDNAL level is reduqedA4 toaes than or equal 651 of RATED PO=E for rod mda Lgnmeats less t#or equal to *18 atps. or
- 2. IThe of&~eted rod A-4-eclae n h =oeal ITDOWMAIN( )
requirement of Specification 3.1.1.1 is satisfied. I WM OPERATION may then conti~nu provided that: fAdd propossed Required Action 8.1.2 L a) A reevaluation of roch ccdent alysis o 1 .1-14s performed vithin 5 days: this reevaluation shall confirm that the previousl analyzed results of these accidents remain valid for Za duration of operation under these conditions. and _*SuEAsclal Test~Mceptions 3.&24. and 3.10.4. COOK NUCLEAR PLANT - UNIT 1 3/4 1.19 AHE&DKEW No. 44. U4. "O. 193 Page 1 ofl14 Attachment 1, Volume 17, Rev. 0, Page 81 of 471
Attachment 1, Volume 17, Rev. 0, Page 82 of 471 ITS 3.1.4 ITS D ACTION B b) The SWTDWt t(&PIh! requirement of Specification 31. in determinud at least ones per 11 hours. and c) A power distribution map Ls obtained from the movable incore detectors and F0(Z) and 14a are verified to be vfthin their limits vithin 72 hours, and1. d) Either the TRD2(AL POWER level is reduced tolSs thai or e) toere eluder of the to ii he group with *inoperable rod a a aligned, to with the allowad rod sa~netof the parable rod vi one hour while itnngtheA. rod aequance and £inset onlimts as Spec f~d in the COLR; diTHERMA POM1 Ls. shall be restric adPursuant to 8 ciftcatiou 3.1.3. du~gsubsequent peration. SR 3.1.4.1 4.1.3.2.1 The position of each full length rod shall be determined to be SR 3.1.4.2 4.1.3.1.2 Each full length rod not fully inserted iza the core shall be determined to be OPERABI by movement of at least 8 steps in an~y one direction at least once per 92 days. 4.1.3.1.3 allowed Vod usisl enut for THUNVAL 10 greater than 851 of RADPOME shall be etermineid in conjimo on with theA. measre u ofAlL am defined Specification 4.2. .2. COOK NTMCLEAR& PLAN? USIT 1 3/4 1-19 AMENDAE1T 140. W. 4.4E i0%, 193 Page 2 of 14 Attachment 1, Volume 17, Rev. 0, Page 82 of 471
Attachment 1, Volume 17, Rev. 0, Page 83 of 471 ITS 3.1.4 ITS ~I IQ =rvr MorQo SYS'TMS tABL 3.1-4 ACZ 1?ALMAYS2S 3EQUflhZC EEE 'A1O Rod Cluster CeutroL As emly laarctiou Cbaractera ics Rod Cluster Control embly HiaLeraapuc Lose of Reactor Coo tfrom Sma'll Ruptured ftpes OrFromi Cracks In LargeL. ripa WALch Actuces a Emegency Core CaooLg stea S~uxle Rod Cluster Assembly Vlfthdmaal. A F'ul lover Ical l1aJor Reactor o Syntam ?Lp. Rptures (Los of Coal=AZL Mcdent) r tlajor seconda 3Syon Pip. R.uptu~re
&M%=ux of a Contr 1 Pd Drive Mecbanism Hous (Idd cluster control Assembly K2jectLou)
D. C. CQOK -UniT. 1. 3/4 1419. xD4~iO-12(v Page 3 of 14 Attachment 1, Volume 17, Rev. 0, Page 83 of 471
Attachment 1, Volume 17, Rev. 0, Page 84 of 471 ITS 3.1.4 ITS ROD MISALIGNMENT ABOVE 85% RTP ALLOWED FIGURE 83.1-4 Figure 3.1.4-1 STEPS 20-Is~~~~~ 16~: 1 2~~~~~9 0 ' 0 0 0 12 10 0 18- 11 a I~~~PI mnfetN.13 aNTI84119 OOO NULEA PLN ______________ ____________ I __Page_4_of_14 Attachment 1, Volume 17, Rev. 0, Page 84 of 471
Attachment 1, Volume 17, Rev. 0, Page 85 of 471 ITS 3.1.7 ITS ID POSITON IHDC&O a NK1 LMITIN COITIOtN FOR O~TO LCO 3.1.7 3.1.3.2 Al. shutdown and control, rod position indicater channels and the APPLIMA ODES I and 1. Hf: aL. VSith a mazim=i of cus, rod position. indicator chanueut 1per prou ACTION A inoparable either:
- 1. Determine the position of the non-indieating rod(s) indirmotl he ovbe rdeetsateast once per a hours a n oino h nn on.
Indicating rod vh~zh exceado 2 steps In ona direction since the last determination of the rod's position, or
- 2. Reduce TEMKAL POWER to less than 501 of RATED THERHAL POWJER.
vithin 8 hours..reult
- b. %FfthIaPAdem-ad position Ludicator ijJ ACTION C i!Ioperable eiter
- 1. Verify that all rod position indicators for the affected bank are OPEUILBL and that the most withdrawn rod and the least withdrawn rod of the bank eae within a uaxuma of the allowed rod v%.salipmnut of eAch other, at least once par a hours, ororealt
- 2. Reduce TUERMAL VOMMR to less than 6oX of RapE ThERML PowER, t~lhin. a hours.AdprpedCTOBL5 Adpoosed ACTIO .
4.1.3.2 Ea rod position Lndiat rchannel shall be da rained to be OPEALEb erifyir.S the demand uidon indication tye and the rod positio I iator chaninels age iT i the allowed ro misalignment at COOKC NUCLEAR PLANT - UNIT 1. 3/4 1.20 AANkDHENT No.-4I-~, 193 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 85 of 471
Attachment 1, Volume 17, Rev. 0, Page 86 of 471 ITS 3.1.4 ITS PoD DuRO ?Dn
?0t30 rW COWDITO 703 OPUATON SR 3.1.4.3 3.1.3.3 The 1nd"ViduaL full Is" mmert t c2or1) cod drop tuim from duAni Ahe f"u7 i,'Ld~rawu position I m-clfe d in te C*1I. shall be less thean or equaL to 2.4 asemi. from bOOISM10 Of decay Of atattmta!7 gripper coD "o1tage to. iaspot entry with: 0I A.vs PM-eaer thai or equal to a.nd lb. AII reactor coolamt 70ap operatlzg.
OM IIT NODES I AnD 2 With te time of any ftu ll 2 Vod determined exceed the abowa limit, aere the rod drop t o ithin the a ita prior toA. proc.. tcoMODE loi 2. SR 3.1.4.3 4. L.3.3 The rod dro elm of fuLL length rods shall be demonstrated thoush
- a. for all, gods fL~lUvIn each reO~wa of the reactor vessel head, b.1 fow CueLf ical fft Ividual, rods tol ay ma nuanc on or moi ctou to cme cantr ro Lrve systanL.
*Cci could affet eh ro time Of thou. colfie rodad C. At sact Oon 5moas (I~
COOK NUCLEAR VLA? - M=I 17 3/4 I-IL AMMMM3 NO. 7g; 1ZQ, 146 Page 5 of 14 Attachment 1, Volume 17, Rev. 0, Page 86 of 471
Attachment 1, Volume 17, Rev. 0, Page 87 of 471 ITS 3.1.5 ITS LCO
.5 3.1 in tTMe COLDO.
LCO
.1.5 3.1.3.4 All afrutdwra Tof shill be Uuicit impyhial insertion as specified A j APPL7CA!UI1TTV: HOD?! i'In1I ACTION A Vith lanGas sgdowi red Sziserttd beyn the Insertion limitI Applicability setifccion the1..L.. wIthin eLIMtlher S Note 1 thr SR 3.1.5.1 &.1.3.4 Zach shutdown rod shall be determined to be within the insertionI 11.5$ specified in the cola.:
- b. At least once per 12 hours thereaftnr.
I* Seea!,fcid Test' oP-tions 3.10 end 3.10.4. (il? COOK. UUCLUA PLOiT
- MIT 3. 3/4 1-22 AND== 1110420, 146 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 87 of 471
Attachment 1, Volume 17, Rev. 0, Page 88 of 471 ITS 3.1.6 ITS GI 209 Ob 282RTON LIK;T8 LIrUTINC CMIDTrON Mo OMATZON sequence, and overlap limits . LCO 3.11.6 3.1.3.5 The cov~ral bsWm shalfl be 1WSted In physical.ftmasrtioc as specifieG In the COIZ. APLTCAB3ThM: MODES A.d24 ACTION A Note Vth the control baniks inserted be~ond the Inertion Uaits, lexce~pt forl Applyicrveilanc a. cetis~ ouruant to Sfecificatlon 4....2itei Rsoethe control banks to wihi the Ulmt r:( A. 11ran2l
)
ACTION A o b edeTHERMAL POWER withn hos to less orequal to tefraction of RATED ?0V vicb La a d by theA. ACTION C C. be. it, H J within 6 hour.-mdne~opee SURV.EILLANCE. IRMLPTIS MD with k, < 1.0A. SR 3.1.6.2 *.l.1..5. The position of each control bank shall be detervin~d to be within
* 'LSeranalimtest ates t once3 got hors.,.jduiiit
.12 . Insva)
Applicability e With Feff greater than or equal. to 1.0. COOK NUCLEAR PLANT UWIT 1 3/4 123 AKDMKTP90120-Page 1 of 7 Attachment 1, Volume 17, Rev. 0, Page 88 of 471
Attachment 1, Volume 17, Rev. 0, Page 89 of 471 ITS 3.1.6 CDOr IMJCLLA1 PLN
'..& DWI7 1 3/4 1.24 A~)~
f46 Page 2 of 7 Attachment 1, Volume 17, Rev. 0, Page 89 of 471
Attachment 1, Volume 17, Rev. 0, Page 90 of 471 ITS 3.2.3 ITS hI~nNG CONDMTICI MR OUMON LCO 3.2.3.a 3.2.1 7be UW[Loated AXIA F=U IDX?7CS (AID) shall be maintained within the target bend about a target fluz difference. The target bund Iu specified 4&PPL1CA3<Y: MODE I above RDT4XL~ii ACTION:
- a. 111th the indicated AXIA FLU DIFFUEN1CE outalde of 'the target band about the target flux difference and with THUMAL POM:E ACTION AthnL lte a) EUther restore the indicated AID to Within the target ACTION B b) Reduzce THERIAL 10O113 toOF
- 2. hetween 50% and 10% or 0v9i ii uw1m~-x Less oRAE LCO 3.2.3,b -Ja) P011 OPExRAZO may continue provided:
- 1) The indicateG AID has not been outside of the target band fat more, than 1 howr penalty devisatIon ACTION C t~uouative, durin the previous 24 hours, and Adpooe
- 2) The Ir~t"eteO AnD to withain th. UnIits up*cifies tiII CniinCNtm.
the CoLLI Otberwise, reduce THERMAL POWER ro less than 50% of SLATED.THERNAL POWlER within 10 minutes LCO 3.2.3 Note 4 b) Surveillance testing of the lover Range Neutron Flux Channels say be performed pursuant. to Specification 4.3.1.1.1 provided the indicated AnD ia maintained within the limits specified In the COLR. A total of 16 hour. operattion may be acctumulated with the AID outside of the target bend during this testing without penalty deviation. S'ee !j!!!ETast !!2jp!!ii.0. (9 cm,"'r:.XAm~ ?!.ET ThT 1N& 3/4 2-1 Aj=.j- ~:::PI. 1l0, 14S Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 90 of 471
Attachment 1, Volume 17, Rev. 0, Page 91 of 471 ITS 3.2.3
- b. ?WMAN MM ll mtbe !!4nss""d bm~ M r .9 a AnL Ofthi vr La tons) *f to TUMML IW a do se S ated A vis" bi theart mi Amal Las) )a above has
- s. IWE~~shal Lu. AIe Umeae lot~ iStSAU OaI gtbani Ler bms he peawlt aLeu smduLses SR 3.2.3.1 4.1.I.1 lbs !LnGlatm6 hEl. FLU DIFFUENC shall be dstedrelas to be vithift its lim~ts dZate MU OPZDAOP bev ise of MMI MUMAL INu by:
- a. KMluutolag the tI~leated AnD fee each OPUAB.Z aswers. shannel:
sas legt s VAt oterIhu at. ea eAse pmer Alr te te AXILt Al m -to sham Kmtralum1 d rbeen Us lbso~i alesOfthe~p OG AX FL S riAL lhall fie ae bowseels: Is" swerwel 30 swgsah15mg ai COQM UC= 1AfT WIT.WIl /4 a.2 3KUTUO4140P hiB Page 2of 10 Attachment 1, Volume 17, Rev. 0, Page 91 of 471
Attachment 1, Volume 17, Rev. 0, Page 92 of 471 ITS 3.2.3 ITS LCO 32.3 . .1.2 The LaUciated APO shall be sonaidered outside of its target band Notel when at leant 2 of'4 or 2sof 30 ezcote ohamaIs Aae Uldic~tiug the LCO 3.2.3 to be outside the tat st band. Penalty rviation outside of the target Notes 2ansal b acuuae an basis of., LCO 3.2,3 a A-penalty deviation of one. minute for each one Uinute of P0OR Note 2 OMATlOlq outside of the target baud at ?HWW.. MMW lwvela equal to or above 50% of RATED THflNAL POVE.B and LCO 3.2.3 b. A penalty daviation of oneehalf ainute for each anm minute of POWM. Note 3 OPERATION outside* of the target band at TMWRIAL MMVE levels between 15% and 50% -of RA'flD THERMAL POUL.. SR 3.2.3.3 4.2.*1.3 The target axial flux difference of each OPEPALI excore, channel SR 3.2.3.2 4.21.14 The axial flux difference target band about tetarget axial CMO IVMARRAn -T 1Z~ 3/412.3 oy,~1t%. NW~U 146 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 92 of 471
Attachment 1, Volume 17, Rev. 0, Page 93 of 471 ITS 3.2.3 ITS
?Lpwe 3244 ttm2LouaLly deslted.
COO% OUMVLSAW UI-VW2 /4214 AUIMT go. di jfig. 146
- ~~Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 93 of 471
Attachment 1, Volume 17, Rev. 0, Page 94 of 471 ITS 3.2.1 ITS
)E&T ILU 110? CMI.FCTI~ Z LIMUTIG ggOND11ION la OPU101 F'PATI ewihnte iissecfe n h OR LCO 3.2.1 3.2.2 Fq(Z) dual2 lbtmitd by ~the to iq Wela1tionshIVS:
FC2) CTQOWJIKCZ) )J, o CMQI theP limit atA 2SBDMAL pOMUUpecif d inthe COLR o F C isthe meas~ured bat factor LUG) Ihne a 31 manufacturing tgL ane uncerTAinty a St measuremient VW*tiny o ICC Laithe normalized F C) as a function of ore he4'ht specified AfPPLCABILMl: MODE I Acrros.: ith FQCZ) enceedin its limit: a., Zeducs ?IEM HX I.O= at least to for each It F (Z) esceeds the limit proceed for up to a total of 72 hours; subsequent POVU OP'EIATION may proceed p.rovided the Overpower aX Trip S.tpoints; hve bean reduced at. ACTION A least 1% -for each It F (5) exceeds the, limit.
- b. Re ,. fv correct the cause of the out of limit condition prior to incroulaS THERMAL PO=E above the reduced limit required by a. above:
'THERMAL ?OVER may then -be increased provided Fr,(Z) Es demonstrated thouh nore- mapping to be vitbin its limit.'K COOKPI3CEAZPLANT UNIT I 3/4 2-5 AMWDKW NO., 120, ii 146 Page 1 ofl14 Attachment 1, Volume 17, Rev. 0, Page 94 of 471
Attachment 1, Volume 17, Rev. 0, Page 95 of 471 ITS 3.2.1 ITS 1.2.21. pvle"Lm eia L"flet.eu.0.4 t. appugabl. SR 3.2. 1.1 1.2 be 4stgem tm O be wthift LtU liit 1(2) 1Ah1l AbM~St Of 1ATED flIh&. PO. Mme:Ua to She 9011wiuw .eheol:
. con
- h. an Use L r21 ti /4tf. i m ~MD~i A. so-iaatIl Page 2 of 14 Attachment 1, Volume 17, Rev. 0, Page 95 of 471
Attachment 1, Volume 17, Rev. 0, Page 96 of 471 ITS 3.2.1 ITSEI1 ftis Mey +/-fttatismlly Lett bluik. mOOS WUxzA rimNT- WT[W 3/' 2-7 &iinin w. 7D.MZ. 120 Page 3 of 14 Attachment 1, Volume 17, Rev. 0, Page 96 of 471
Attachment 1, Volume 17, Rev. 0, Page 97 of 471 ITS 3.2.1 ITS Iftgwe 3.2.3 £atntui llMy Ie1.ued. CMo Nucus" Pun * =NIT 2 3/4 1.3 AUMNDU 10. U, fig. fulU 1406 Page 4 of 14 Attachment 1, Volume 17, Rev. 0, Page 97 of 471
Attachment 1, Volume 17, Rev. 0, Page 98 of 471 ITS 3.2.2 LT-S LT!ZSCONOITON 70 0?Aflov LCO 3.2,2 5.2.3 7 $hal be L~uital by th to ovizag r~tm~ vher~~tLathefraccouofI ?M 22AL l eftd n 173Is the power ta miltipiexLoT 7~ eIfted In he COLD. hAPlL2ICULZIT: HODZ I wihntelmisseiidAnteCL ACTION:
.. 3ftP*uL~~~
Nit Add propos~ed Condition ANt
- a. Reduee TIDNAL lOV to tons thia 50% of RATED INEZ=i ?OMWiRvthif Required Actions bowrs and reits* the love: IS!5S MsutTon 7lux-NII& 'frp Set Lats to A.1 and A.3 less than or equal to $55 of SA TD ?32)AL ?OMD within hours, Reqire AcionA.2 ACTION B -l ~
.4 ctio A.2~LfDemonstrate Requred -o ta yhu sthea St of XATED TWMIAL lOVE within the nezt x ( within its Uxmit within 14 howrs sfter exesedlur the ]limit hiforsibme TEDIAL ?OME a n to Required Action A.4 c. Monutifan corroct the cfoo h u-fU tcnilngirt coax UCLEA PUN aftWfl 1 Fg /4 2 Ar2T O.,
subn'"im POWM OMATZONmay LUT-40 -tmmj~ , 146 pr~wided that r., ta demarcatePage wiofi6 Attachment 1, Volume 17, Rev. 0, Page 98 of 471
Attachment 1, Volume 17, Rev. 0, Page 99 of 471 ITS 3.2.2 SR 3.2.2.1 '.21.3 Ona bal to 4atoized t be ith~Ls its 1 !!t by mit i
- 0. C. CON .. UM 3/4 2.10 AM== NO. l0sltO Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 99 of 471
Attachment 1, Volume 17, Rev. 0, Page 100 of 471 ITS 3.2.4 ITS ~I POWE D-ISTRICRUT-1IO LIMIT MMARAN POME TILT RATIO LIMITIIIG CONDITION FOR OPERATIO LCO 3.2.4 3.2.4 THE QUADRANT POWER TILT RATIO *hall, not exceed 1.02 APLMIIY MODE 2. ABOVE 50% OF RATED THERMAL P~w~)(7 ACTION A, a. With the QUADRAIIT POWER TILT RATIO determinead to exceed 1.02 but ACTION B 1.11 than or.equzal to 1. 09:I
- 1. Within 2 hours:,
b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER, for each 1%of Indicated QUADRANT POWER TILT RATIOimexcess
- 2. Verify tht the QUADRANT-P TILT RATIO iv i its limit within 4-hours after dxce in the limito c THERMAL ass~
lOER than 50% 'of T~)THERMAL -OEnext ihnthe 2 orand reduce the P0 Rang. Neutro Fl ihTrip set-ipoint to less than or eq 1 to 55% of RTDPOWER withi the next 4 houj. Adpooe
- 3. Iden ify, and correct th cuse of the out of limit condition Required Actions A.2, pri -to increasing TH POWER; subsequ* POWER OPERATION ACTIO AA BA6 n ab e50% of RATE POWER may proc.. provided that the URATPOWER TILT aA01 verified with its limit at least on eper hour for 12 h urs or until verifi dacceptable at 95%
or reator RATED P~ ACTION A, b. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to ACTION B misalignment of either a shutdown or control rod:
- 1. Reduce THERMAL POWER at least 3% from RATED THERMALL POWER for each 1% of indicated QUADRANr POWER TILT RATIO in excess of 1.0, within 10 *i eil Add proposed
~V~ri that the QUD
- 2. POWER TILT RAO0Ls within RqieAcionsA2 iW limit within 2 ousafter exc. ng the 1limit o0rj' A.3, A.4, A.5. A.6, and .
D. C.UNIT COOK 1 3f4 2-11. AMENMENT NO0465,120 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 100 of 471
Attachment 1, Volume 17, Rev. 0, Page 101 of 471 ITS 3.2.4 ITS ~1
'POMt IDIShh7'~l 14T LIKTIUC COWIOii FM O0flA'Tjgf (Can?.&MMd reduce IOMED to lo hn50%of PWR MIE within net2 hours an eu the oer eeitron Flux.
IU.5h psetpointu to hno *e qualtoS f RATED
?Wwithinte chus
- 3. Ideac f and correct the augo f the of IAt condition Du prio to incrasuing ?OU :ebarie- OWER IDTON ab 50% of RATED IW.may proca.. prv d that the L~OME TILT '10is verified nits Lisiit ateat onca lper hour or12 hours or ant verified accept~abl~e at95 or raster Rh UNLPOllE.
ACTION A, t. Vith the QUADRAMq PO=E TILT RATI determined to wiceed 1.09 du% to ACTION B causes other than the misalip:asac .tf either a shutdown or control rod: I1. Reduce oVE to luthan PEA 50 f AE TRHEAT POME withi hor M Idtdc Powe Kn nag Fux-lugh T:ripe tpoints ato less, ora equal to50ol TEDEMWAL LWRthin the naxt 4 Oate.opse
- 2. Ido if aid conean; cause& of teoto 'Limit condition Required Actions Al1, ptoto increaslaq PO=;ER: :s~iseq~ PM OPRTO A.2, A.3, AA4. A.5, L.
aba 500 oI "TED LVRmay proce 6provided that the A.,adCTOB POWE TITVs01 veii it its Iiuit at Ise once per hour f 12 hours or until erifled at 95% or tatr RATED TEMLLVR SR 3.2.4.1 4.2.4 Thek QtUAMRAT Poll TILT RATIO shall be detarnined to be vithin the limit above 500 of RWED THOYRAL POME by: a, calcl lk. -I-. d-amyswhen the amin MMRDL .
- b. Calcul n the rioat Ie n a per 12 hours dun stady state oeaonwhen theaar ioprb.
SR 3.2.4.2 c. Using the movable moonm detectors to datermine the QUADRANT POWE TIL RATIO at least once per 12 hours when one Power Ranja Chunal. is inoperable and THERMAL POVER. is greater than 75 percent of RATED THIAXAL POVEL D. C. COOK - VNIT 1 3/4 2.12 AMxDEnKM 110. lei. 120 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 101 of 471
Attachment 1, Volume 17, Rev. 0, Page 102 of 471 ITS 3.4.1 MTS 314 LIMITING CONDITIONS FOR OPERATION AN]) SURVEILLANCE REQUIREMENTS 314.2 POWER DISTRIBUTION LIMITS D2NB PARAMETERS LIMITING CONDMTON FOR-OPERA77ON LCO 3.4.1 3.2.5 The following D)NB related parmeters shall be maintained within the limits -shownOA Table 3.2-1:
- a. Reactor Coolant System T,,
- b. Pressurize Pressure C. Rcactr Coolant System Totit Flow Rate APPLICABILITY: MODE 1 ACTIM:
ACTION A -{~ With any of the above parameter exceeding its limit, restore the parameter to within its limit within2 hoorsor ACTION B --C reduce THERMAL POWER to less than (percent of RATED THERMAL POWER within the eII2f.{LI SURVEILLANCE REQUIREMENT - SR 3.4.1.1, SR 3.4.1.3 4.2.5.2 1 edicators used to dtmie alflow rate Sual b~eubfected to &9 NNEL CALIBRATION- LA-
-,a lastnnnr ffofl_
09 Add proposed SR 3.4.1.4 Note SR 3.4.1.4 4.2.5.3 TaCS total flow rate hallbe determined bya faf5 m sr hesemS at least OnceM1 per moth. 2:4 1ieab an -L COOK NUCLEAR PLANT-UNIT 1 Page 3/4 1-13 AMENDMENT .74,1201 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 102 of 471
Attachment 1, Volume 17, Rev. 0, Page 103 of 471 ITS 3.4.1 ITS 314 LuamTJG comnDoNS FOt oPERATioNl AND)sUvEHIANcE REQuIREMENT 314.2 POWER DIStmI[ON LOMI Dtff PARAMETERS r Reactor Cool=n System Tavg specifiediein T LCO 3.4.1 . PResanrize Preussra Reactor Cloolant System k 34,10O L Tots Flow Rate Adrlmi specifed LA.3 inCOLR Lfimt tot applica-ble dusing either a THERMAL POWER ramp Increws in ezoess of S percent RATED Applicabilifty THERMAL powER per minutor a THERMAL POWER ita Incmeas In mmes of 10 percent Note RATED) THERMAL POWElt. COOK NUCLEAR PLANTVNIT I Page 314 244 AMEMbMENT 94 4a0,426, M3, 214 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 103 of 471
Attachment 1, Volume 17, Rev. 0, Page 104 of 471 ITS 3.2.1
.3/4 LMmNG CONDMONS FOR OPERATIO AND SURVEILLANCE f"UnU1RMXN'1 314.2 POWER DIMTIBMfONLIMMl AI IWABLE POWE LVE APL MTN OCONTDMONFORMP2RATION.inteCL LCO 3.2.1 3.2.6bydeg moeqa AP~minvm Z fFq(Z)xV(Z)X Pi a CFQ is FQ limitat RATEDT TEMLOEspecifiedhInahe COLR.
- K(Z th rzorxa~ized F,(Z) se aimt fm coo heigh Wpcified fut C o F4(I the mqaaured hot channe factor a 3% mamdwturigto uctaintmd a max overZ ofa with evcoswe Note to 'Then eithe of the penalties, Pp. inhaflbe taken SR 3.2.1.2 F, -bumu &eda pemalty specified inthe COLR or, F, - 1.00 provded that Survel~lance Requireinent 4.2.6.2 is Rrisfied OMcper 7 ffctivw Full Power Days imtiltm sucessive maps indicae that fth cm OMrZ of -(Z Is not bcreing COOKNTUCLEARPLANT-UNITI Peae 314 2-15 AMENMMNTI42 6,iX42
, 30NC 251 Page 5 of 14 Attachment 1, Volume 17, Rev. 0, Page 104 of 471
Attachment 1, Volume 17, Rev. 0, Page 105 of 471 ITS 3.2.1 ITS (11 314 LIM1ITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ACTION B With APL"loss than THERMAL POWER reduce THERMAL POWER to AIPL or less of RATEDn hw I Trip Setpoints have been reduced the same percentage whiich blwR7D HRA QL~ FAdd propoed Required ActionBM3
.d ~~~~~~Add proposed ACTION CM.
SURVEILLAN4CE REOUTEMENTSA3 14.2.6.L 'Terovisionis o- ciip in40 entalcb SR 3.2.1.2 4.2.6.2 Ihlbe determ~ined,by mneasmrementlin cDniuriciion with the Taret flux differeigre-iid tre I&dm-41atiin1 above 15% of RATED THERMAL POWER, according to the following schedule:C B. 'Upon achieving equilibrium conditions afL-r exceeding by I10% or mzore of BATED THIERMAL ad
)
POWER, the THERMAL POWER at which was last determined .. or
- b. At least once per 31 effective fAl power days, whichever occ~m firstL I'-P9as- redefined bymLssurig th 4age:amflxdferne SR 3.2.1.2 'D)urng power escalation at the beginning of each cycle, the design target may be used umti a power-level for Note I extended opraio as been achieved.
COOK NUCLEAR PIANT-UNIT I Page 3/4 2-16 AMENDMENT .4,40, 251 Page 6 of 14 Attachment 1, Volume 17, Rev. 0, Page 105 of 471
Attachment 1, Volume 17, Rev. 0, Page 106 of 471 ITS 3.2.3 fiS (I 314 LIMITIG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUJIREMENTS 3/4.2 POWER DISTRUBUT[ON LIMITS LIMTING CONDI)MON OR OPERATION (Continued) ACTION With APL less than THERMAL POWER, reduce THERMIAL POWER to APL or less of RATED THERMAL POWER withi 15 minutes. Then reduce the Power Rmnge Neutron Flux-H1igh Trip Setpoints by the same percentage which APL is below RATED TBERMAL POWER within the next 4 hours; POWER OPERATION may Se T proceed for up to a total of 72 bours; subsequent POWER OPERATION mnay proceed provided the Overpower &T Se3I2S1 Trip Setpoints have been redced the same percentage which APL is below RATED THERMAL POWER. SURVEILLAECE Rg.EOTJIEMENTS 4.2.6.1 The provisions of Specification 4.0.4 are not applicable. 4.2.6.2 AFL &hall be determined by measurement in conjunction with the target flux difference and target band determination' above 15% of RATED THERMAL POWER, according to the following schedue: SR 3.2.3.2, a. Uipo , eving equilibrium condition after eedigby 10% or eof RATE]) TMERMAL SR 3.2.3.3 thPHEMLPOWEJWat which APt was last de or
- b. At least once per 31 effective fuill powed ro a--:
oc wi1thin 31 EFPD after each refueling APL can be redefinedby reinzasring the target axial fiux diference. I 3.See SR 3.2.3.3 .'During power escalation at the beginning of each cycle, the design target m~ay be used unti a power level for Note extended operation has been achieved. COOK NUCLEAR PLANT-UNIT I Page 3/4 2-16 AMENDMENT .4,420, 251 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 106 of 471
Attachment 1, Volume 17, Rev. 0, Page 107 of 471 ITS 3.3.1 3,4..- LMUrING.CONMMION FOR (6PEATIONAMD SRVEIlLANE REQUREMWENTS 314.3 M WMTRMENATON 3M4.3.1 REACTOR TRIP SYSTM ISTRUMENTATION LIMITING CONDITION FOR OPERATION LCO 3.3.1 3.3.1.1 As arn2inmilm dhereactor rp systemm utrumentationchaandel and interlocksof Table 3.3-1 phall be OPERABL.E.I APPULICABILT: As ahow InTable 3.3-1. ACTION A As shown InTable 3.3-1. Adr sdATOSNt T SR Table 4.3.1.1.1 Each reacwtorrIp system nsumna channe shall be demonstrated OPERABLE bythe 92 days on a Note vefrac f the CHANNEL q M CHANNEL CALIBRATION and CRSTAGGERED SR 3.3.1 .5 Th lgi for the Interlock shall be demonstate Orwto eualfco-r SR 3.3.1.13, SR 3,3.1.14, ERDEat least once per during CHANNEL, CALIBRATION tetqof each mbAwi SR 3.3.1.16 ected by interlock oprxin affi~1 SR 3.3.1.19 4.3.1.1.3 ThO REACTOR TMI SYSTEM RESPON.SE TIM inconsalb ffT SR3.3.1.19 NandctecoW U a hatfan cbnsene am At s lieo die flualgn:lpxdis Note of the channelP-0 be measured from detector Ltptor l of first electro cotco In chamne.
'COOK NUCLEA. PLANT-UNIT I Pare 314 3-1 AMENDR0 4W, M431.4442 Page 1 of 39 Attachment 1, Volume 17, Rev. 0, Page 107 of 471
Attachment 1, Volume 17, Rev. 0, Page 108 of 471 ITS 3.3.8 ITS 3/4 -* [JUM1 G.CONDMTONS FOR (OPERA11ON AND SMRVEilLANCE REQUMREMENTE 314.3 INSTRUMENTATION LCO 3.3,8 3.3.1-1 As a minimum ti rercrr trip sysomlntrm ntainrncsan ueohTable 3.3-1 phall Au sownIL~abY 3 s.3-1.abe .31 SR 3.3.8.1, 4.3.1.1.1 Each reactor trip system Instrtmentation channe shall be demonstrated OPERABLE jaite SR 3.3.8.2 efnu of the CHANNEL CREKCHANNEL CALJIBRATION Iand FUNMNATES e 92orth MODES and attefinpacz sownj~ i Taeee4ITS1 performed Urming t p geemj9 dys Itoa ko fnimddbdmsted3.3.1 4.3.1.1.3 REACTOR TRIP SYSTM, 'SOS TIME Of each ri bclnshall be to be within LI at leas once pec 18nmonths. atleasr innsallclude oam 1otcun Such tar boih logc Im ame twr at leas Onm mo r.ad ourneconed. per fauction such that all stested atleast onm eveay ?ftms1 otswhere NUs fth trotal mnuber of nnesla qmciftI=rarortrip % oashonIn te "Total Ieudfi No. of aiannel? columnTle3-.. Ncuta"4t a etoe pt f(MM snipe tietesig R~A"Mue time of AC'e fix signalpottionA4 of~g hnnl hil be measturd ;d~e-tector output or Inpu of f#4eokcomponenit Inchannel.
'COOKNUCLEAR [PLANT-UNIT I P'ate 3,4 3-1 AMENMtN M. M3444, 202 Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 108 of 471
Attachment 1, Volume 17, Rev. 0, Page 109 of 471 ITS 3.3.1 3)4 LIMIVMNG COkIDMOIM AMl OMMMTIO AMD SURVEMLANCZ 314.3 MMUENTMA17O - TbWu pqp lutcaniGM omIyft blank. COOX NUCLEAR PLANTUN1 I Fag 314 34 AMDMMNTV4 120 Page 2 of 39 Attachment 1, Volume 17, Rev. 0, Page 109 of 471
ITS
~Table 3.3.1 -1
- 11. Manual Reactor Trip2 1,2ad.2B 2.bF2. Pover Range, Neutron riwi1 4 In3 3. Power Range, Retron Flux, High Positive Rate 3.b 4. Paver Range9 Neutron Flux1 4 2,2D H~igh Negative Rate 4 5. Intermediate Range, 1 3EF Neutron n A9 5 6. Source Range, WeUtron Flux ______an A: Startup IL__2____ Nole 4 G,1, Q 1*
in 6 7. Overteuperature aT n 0n For Loop Operation 24
,~7 0. Overpower AT See ITS Four Loop Operation _______2_ _3 3.8 , Volume 17, Rev. 0, Page 110 of 471 Attachment 1, Volume 17, Rev. 0, Page 110 of 471 (D
o CA)
-h (C,
ITS C'
- 1. Manual Reactor Trip 2 1 2 1, 2 and
- 12
- 2. Paver Rang", Neutron Flu% 4 2 3 1, 2 and
- 2#
- 3. PoVer Pafl , Neutron Flux, 4 2 2 1,2 High .PosiIVe at See ITS a ~ ~ itv
~ ae3.3.1 4 .Paver Rang., Neutron Flux, 4 2 3 1, 2 2' High Negative Rat.
5 .Intermediate Range, 2 2an (S) LCO 3.3.8. 6. Source Range, Neutro Flux Applicabfiit, FAStrupaI#i - 4 and AcTION A S. ShutdownO2 2 3 4ad
~. 7. Overtesperatur. AT S. Overpower AT , Volume 17, Rev. 0, Page 111 of 471 Attachment 1, Volume 17, Rev. 0, Page 111 of 471 (0
-h0 ,
0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~0
ITS TAQD& .3-1(Continilue L Table 3.3.1 -1 nREAMR TRIP SYSTEM IMSTR-UMEIITATI01I TOTAL NO. CHANNWELS CHANNELS APPLICABLE in FUNCTIONIAL MIlT PCTIOEIODE OHAEELS DAI 8.a 8 9. -Pressurizer Pressure-Low 4 ,26 8.bs 10. Pressurizer Pressure--High 4 ,2 6 DAS 9 -4 ii. Pressurizer Water Level--High 3 2 127D 10 12. Lovs or Flow - -sin e p/loop loop In lo71 an opera- o a tin loop 1 10 13.' Loan of Piw- op 3/loo 2/loop n oIWD A Footote(e) (Ab~ove P-7adblw ) two oper-a o a ting loo Ia D 14~ 14. Steam Generator Water 3/loop 2/loop In lIL, 1 7 L.evel--Lww-Lw ny opera- eao.~A 15 15. Steian/Feedvater Flow 2/a -level 1/I -ovev lo-level 1, 2 7D
'Mismatch and Low Steama and conc ant and Generator Water Level 2/loopf w h 2/loo~p-flaw mismatc I 1loop-f mismatch or same loop Imimatch I o-ieve Bsas loop( )
a~~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ , Volume 17, Rev. 0, Page 112 of 471 Attachment 1, Volume 17, Rev. 0, Page 112 of 471 CD CO)
-h CA)C, Co -
ITS O ~~~TABLE 3.3-1 (Continued~) (Z Table 3.3.1-1 R_____RTRIPSYSTMINSTRUMENTATIO FUNCTIONAL F CHiANNELS TO M OPRBLE MODES ACTION 12 16. Undervoltage-Rheactor Coolant I/bus 2 d Pumps 13 17. Underfrecquency-Reactor A Coolant Pumps
- 18. Turbine Trip A 16.a A. Low Fluid Oil Pressure i I 6.b B. Turbine Stop Valve 4 Closure
~O:17 19. Safety Injcction Thput from 2 1,2 J. P ESF SkBiA 11 20. Reactor Coolant Pump Breaker Position Trip Footnote (e) Abovc p-7 I kr /breakerpr I IID 11 1 9, 21. Reactor Trip Breakers12 KP 20 5*
~~~~~~ ~ 14 BQ
~~~~~~~~~~~~~~3*,4, Z4 21 22. Automatic Trip Logic 212IJ 3~ 465w 14 B, Q , Volume 17, Rev. 0, Page 113 of 471 Attachment 1, Volume 17, Rev. 0, Page 113 of 471 (D
0 0
-h WA (0
Attachment 1, Volume 17, Rev. 0, Page 114 of 471 ITS 3.3.1 ITS Table 3.3.1-1 Lnotfully insere Footnote (a)
- iht e~ rr a reaers Imn the,:C ed s an Footnote (d) # g voltage to detior"may be dec-ce sed above P-6.
ACflONf STATEHMENS d rpsd~ql cinJ ACTION J ACTION I With the number of channla OPMMALE o lois than required by the Mi1nimum Channels OPERABLE nmcurembnt. ~ in HO0T STAM~BY within 6 ACTION D ~ gr~~wvr, one channel may be bypassed for up to orfor ACTION J Note -j~il ance testing per Specification 4.3.1:.1.1. ACTIONS C ACTION 2- With the number of OPERABLE channels one less than the' Total and D Number of Channels1 STARIUP andor POWER. OPERATION may proceed provided the following condititis are satisfied. Required Actions C. 1 a,. The inoperable cha~nnel in placed in tripped condition within and D.1 6 hours. ACTIONS C and D b. The Hinimum C33a etlB OPERAL% requirement is met bvvr Note the inoperable channel may be bypassed for up to hours for surveillance testing of the other chaxnzluaper Specification C. Either THERMAL POWER is raz-te o1n-ta TILT RATTO ia monitored at least once per 12 hours per
- 4 ~~~~~~~~~~~~~~~~~~~~~~~e~idd rpsdACTION P ACTION E ACTION 3 With the number of channalg O0RABL8 one leas tban required by the
.Minimum Channels OPERABLE requirement and with the THERMAL POWER.
D. C. COOX UNIT 314 3-..G110 I~~MINo. 4,4, 2S4 Page 6 of 39 Attachment 1, Volume 17, Rev. 0, Page 114 of 471
Attachment 1, Volume 17, Rev. 0, Page 115 of 471 (2~~~~j
~ITS 3.3.1 ITS 314 LIMITING CONDITIONS FOR OPERAX[¶ON AND SURVEILLANCE REQUIIREMENTS 314.3 INSTRUMENTATION, TABLE 3.3-1 (ContixmeA' Function 4 a. Bclo 6, restore the inoperab hne to OPERABLE ni prior to inreasing Applicability 1TRA DW h=tC:isait
- b. . Above P6 t below 5% of RATED POWER, restore the rable ACTION E hanloPR Lstv rtosues THR APOWERa 5% OfL.
Ien UGFE-5. WfRATED THERMA POWER. POWER'OPERATION mycnjm 4 ~~~~~~~~~~~~~~~~~~~~~dpooed ACTION F AC7ION 4 - vizzh the number of channels OPERABLE one less than required by the MnmmCanl
- OPERABLE reqluirement and with the THERMAL POWER levch:,M AdpoosdRqiedAtosIi ACTIONS G, I, Q dd proposed Required Action 0.1 for MODE 2 below P,6 anQ2foMOE3(, ()5)
A. Below P-6, Wtore the inoperable c Ieto OPERABLE prior to inceasing Function 5 Applicability b. Above P-6, operation may continue, ACTION 5 - With the number of channels OPERABLE one less than required by the Minimuim Channels OPERABLE requirement:
- a. Immediately suspend operations involving positive reactivity changes except Addition of water from the RWST, provided the boron concntration in the RWST is greater than the mi~nimumr required by Specification 3.1.2.8.b.2 (MODES 3 or 4) or 3.1.2.7.b.2 (MODE 5), and
- b. Verif compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applIcable, within I hour and at least once per 12 hours thiereafter, See ITS and ~~~~~~~~~~~~
C. Close the isolation valves for unborated water sources to the chemical and volume control system within I hour. In MODE 5, if the RWST boron concentration is less tha the reactor coolant system boron concentration and less than the boron concentration required by Specification 3.1.2.7.b.2, isolate the RWST fronm th reactor coolant system within I lhrnir-ACTION D ACTION 6- With the numiber of OPERABLE channels one less tha the ToWa Number of Channels, STARTUP and/or PQWER OPERATION may proceed provided die following conditions are satisfied: a.. Te inoperable channel isplacd in the triped conditionwi or ACTION D ACTION 7 - With the number of OPERABLE channecls one less tha the Tota Number of Channels, STARTUP COOK NUCLEAR PLANr-UMrT 1 Page 314 3-7 AMENDMENT A1, 230 jL. Page 7 of 39 Attachment 1, Volume 17, Rev. 0, Page 115 of 471
Attachment 1, Volume 17, Rev. 0, Page 116 of 471 ITS 3.3.8 ITS 314 LIMITNG CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENT 314.3 INSTRUMENTATION, TABLE 3.3-1 (Contintued
- a. Below P-6, restore the hnoerble chanel to OPERABLE stamus prior to Increasing THERMAL POWER above the P-6 Setpoint.
- b. -- Above P-6 but below 5% of RATED THERMAL POWER, restore he inopeable channel to OPERABLE staus prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER. See MTS 3.3.1J C. Above 5% of RATED THERMAL POWER, POWEROPERATION may continue.
ACTION 4 - With dhe nubber of channels OPERABLE wne less tha tequired by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: A. Below P46, restore die Inoperable channel to OPERABLE status prior to increasing THERMAL POWER above fthP-6 Setpoiut
- b. Above P-6, operation may continue, ACTION A ACniON5- With the number of channels OPERtABLE one less tha required by the Minimum Channels OPERABLE requiremnent: .4Add proposed Note I to Required AtonA.
- a. Immediately suspend operations involving positive reactivity changes except addition of to 2 water from the RWST provided the boron concentration in the RWST is geater thanfth~e oqult minfimum rqurd by S ecificationA.1.2.8.b.2 (MODES 3 or 4 or 3.1.2.7.b.2 required lmt L.
- b. Vew com liance wi~th sthe SHUTO N MARGIN ruiremnent$of S eificationl 13.1.1.10 3r.1.1.2, as a ial~ihnI hour and at least once per 12 hours drratr SR 3.1.1.1A.
and C. Close the isolation valves for unborated water sources so the ct andv corl e~fmjw Itn1hu. In MODE 5, if the RWST boron concentration is less than the reactor cpiatsystem boro concendirtoid ite-G te boon co ntration M--N1-4required limit ~ W SecfiaflM -12.7h-2.isolate the RWST crm, steMwithi I 'our. ACTION 6. With the number of OPERABLE channels one less tha the Total Number of Channels, STARTUP and/or PQWER OPERATION may proceed provided die following conditions are satisfied:
- a. Tbe inoperable channel Is placd in sbe tripped condition within I hour.
- b. The Minimum Channels OPERABLE requirement is met; however, the Inoperable channel mnay be bypassed for up to 2 hours for surveillance testing of the other channels SeU per Specification 4.3.1.1.1. 3ee3IT ACTION 7 - With the number of OPERABLE chanels one less tha the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided she Inoperable channtel Is placed In the triped condition within I hour.
COOX~NUCLAR PLANT-UNI 1 Pue 3/4 3-7 AMENDMENT 4, 230 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 116 of 471
Attachment 1, Volume 17, Rev. 0, Page 117 of 471 (~~~J~~~ ITS 3.3.1 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 3.3-1 (Continucd) ACTION 8 - (Deleted.) ACTION 9 - (Deleted.) ACTION 10 - (Deleted.)16 ACTION D ACTION 1I - With less than the Minimum Number of Channels OPERABLE, o eraton may continue provided
~B ~
ACTION ~ ~ ~ ~ 4[Adprpse CTO ACTION P Ebe in HOT STANDBY within the next 6 hu trta es ACTION Q ACTION M ACTION 13 - With one of the diverse trip features (Undervoltage or shunt trip attachment) inopeae, rsoei oOPERABLE status within 48 hour o~rdeclare the breaker inoperable and applyACIN1Th ACTION P sal not bebpsd while one of the dverse trip feature ainoperable excp o h t~~~~~beaker (tiMe required for erfb hin main-tenan-ceto resto)r-ethe breaker toOPERABLEstt. ACTION 14-F With thc number of OPERABLE channels one less than the Minimum Channels OPERABL ACTION B requirement, restore the inoperable channel to OPERABLE status within 48 hours oro e ACTION 0 reactf trip re ke w inthe neourH ACTION K ACIN1- With the number of OPERABLE Reactor Trip Breaker channels one less than required by the Minimum Channels OPERABLE requirement for reasons other than an inoperable diverse trip etrrestore the inoperable channel to OPERABLE status within -24 hors/or be in HOT ACTION P DY within the following 6 hours. Mne channel may be bypassed for up to 4 hours for ACTION K Note sveanetsigprScfcton4.3. 1.1.1, provided the other channel is OPERABLE. REACTOR TRIP SYSTEM INTERLOCKS Ipetri DESIGNATIO CONDITION AND SETPOINT Table 3.3.1-1 P-6 with 2 odiae Ran coetron P-.6 revents or efeats the anual Function 18.a xqs 'ta6x011am. COOK NUCLEAR PLANT-UNIT 1 Page 314 3-8 AMENDMENT 99,20,149, 277 Page 8 of 39 Attachment 1, Volume 17, Rev. 0, Page 117 of 471
Attachment 1, Volume 17, Rev. 0, Page 118 of 471 (2J~~~~~ ITS 3.3.1 ITS Table 3.3.1 -1 P7Wt f~fmRm ;d' - pva Functions8. greAtcrthnor equal. o I I S Ofofon., t Functio 18.d lAEDs THERAL 9%ofRAE blc :oe*ag l~~mtiw P gifit stage age 9 of 3 Attachment 1, Volume 17, Rev. 0, Page 118 of 471
Attachment 1, Volume 17, Rev. 0, Page 119 of 471 ITS 3.3.1 314 -. UffING CONDMOtGIOU OMMATON AMD SURVEU.LACI MEUUMEbW[ 314.3 BSWMFM~A~IMON Table dnentionally DdeleE COOK NUCLEAR ILANT-UNff I ftue 3143410 AMF4MEN K94*M M AM 202 Page l0oaf 39 Attachment 1, Volume 17, Rev. 0, Page 119 of 471
Attachment 1, Volume 17, Rev. 0, Page 120 of 471 (3) ~~~~~ITS 3.3.1 314 .LI&MING C ONDITONS FOR opER.ATON AND SURVIEHIANCF RE(~nUIRMflNT
/4i3 1NkRUMYENTA11ON TABLE 3.3-2 (Continued)
Table Intentionally Deleted COOK NUCLEAR PLANT-UNIT i Page 3/4 3-11 AMENDMENT 148. MS,202 Page 11 of 39 Attachment 1, Volume 17, Rev. 0, Page 120 of 471
Attachment 1, Volume 17, Rev. 0, Page 121 of 471 ITS 3.3.1 JTS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS Tbe3.a 3 .Poe1RneNuto NA 3.b4. Power Range. NeutronABLEN.A.
- 6. Range, Source Neutron NNEL 6,AN-EL 10 4 1 ()
M.13 SR 3.3.1.7~~~~~~~~~~~R .-11, R .11 7 8. Overpower~ U defvltag ri S-iN..4"5 g 11~~~~~. ProswierRang, euronvel- S-i 2-13,8 SA-3lO~ 2 FuHighPoiveRt 10 12. Lossofdite Rngw S-i SA-4 C. oKc RaCLeAR PLNet-UnI S1 g6Page143-12 MENDMENT7)9,13742, and1, 41,7 dpropo d~~ ~ ~ ~ ~ ~ Pae12of3 Attachment 1, Volume 17, Rev. 0, Page 121 of 471
Attachment 1, Volume 17, Rev. 0, Page 122 of 471 ITS 3.3.8 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUJIREMENMS 3143 INSTRUMENATION REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REUIREMENTSA. SR 3.3.8.1 SR 3.3.8.2 L MODE IN WHICH CHANNEL CHANNEL U NL SURVEILANCE EhUNCrlIQINAL UNII CHE ~ ALI~BAII SREQUIRED~i I. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. SJU(I)(0O) 1, 2, 3, 4', 5' B. Undervoltage Trip N.A.' N.A. SJU(l)(l) 1,2, 3' 4', 5' Function See UTS
- 2. Power Range, Neutron Flux S 1)(2,8), M(3,8), Q and SIU(I) 1,2 and'331 and Q(6,8)
- 3. Power Range, Neutron N.A. R(6) Q1,2 Flux, High Positive Rate
- 4. Power Range, Neutron N.A. R(6) Q 1,2 Flux, High Negative Rate
- 5. Intermediate Range, S R(6,8) SIU(17) 1,2, and' See FlS1 SR 3.3.8.1, Ntrr h,. 3.3.1 SR 3.3.8.2, 6. Source Range, Neutron 5 -1 2- 6,o4) M(14) andd Applicability Flux 2months L3
- 7. Overtemperature delta T S R(9) SA 1,2
- 8. Overpower delta T S R(9) SA 1, 2
- 9. Pressurizer Pressure -Low S R SA 1,2 SeeTUs
- 10. Pressurizer Pressure -High S R SA 1,2 3.3.1
- 11. Pressurizer Water Level -- S R SA 1,2 High
- 12. Loss of Flow-Single Loop S R(8) SA I COOK NUCLEAR PLANT-UNIT 1 Page 314 3-12 AMENDMENT 99, 420, 421,441,277 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 122 of 471
Attachment 1, Volume 17, Rev. 0, Page 123 of 471 ITS 3.3.1 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION Table 3.3.1 -1 TABLE-4.3-1 (Continued) REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS SR 33.1.1 SR 3.3.1.13 CHANNEL MODE IN WHICH CHANNEL CHANNEL FUCIN SURVEILLANCE FUNCTIONAL UNIT / CHECK CALIBRATION ______ILRE 10 13. Loss of Flowf ~ s-I -13NA.2onh 14 14. Steam Generator Water S- -13 SA.15 Level - Low-Low 15 15. Steam/Feedwater Flow S-1. -1 3 1 2 Mismatch and Low Steam dpooe oet R3311 Generator Water Level 12 16. Undervoltagce-Reactor N.A. 2 Coolant Pumps 13 17. Underfrequency-Reactor N.A. Coolant Pumps A~dd proposed SR 3.3.1.13 Add proposed Note to SR 3.3.1.18
- 18. Turbine Trip 16.a A. Low Fluid Oil Pressure N.A.
I16.b B. Turbine Stop Valve N.A. Closure A1 17 19. Safety Injection Input from N.A. NA. 6- Q (415) 1,2 ESP 11 20. Reactor Coolant Pump N.A. N.A. 19 21. Reactor Trip BreakerLi 19, 20 A. Shunt Trip Function N.A. N.A. 4- 2 Months (5345 19, 20 B. LUndervoltage Trip N.A. N.A. 4- 2 Months (5 1,2,3, 4. ,
~~
'Function ~ ~ ~ ~ ~ 1 L1 21 22. Automatic Trip Logic N.A N.A. Q(15)-5 1,2, 3', 4", 5' 19 23. Reactor Trip Bypass N.A. NA. 4- 2 Months (5)(12) 11 2.3' 4 5 Footnote (g) Breaker17 dSI0 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-13 AMENDMENT 199, 42, 44-1, 277 Page 13 of 39 Attachment 1, Volume 17, Rev. 0, Page 123 of 471
Attachment 1, Volume 17, Rev. 0, Page 124 of 471 ITS 3.3.1 ITS 3/4 LIMITING CONDiTIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION Table 3.3 1-1 I Wdfe react-or jls stem brea s closed adte control rod drive system capable of rod Footnote (a) wihryl SR 3.3.1.18 0) - Ifnot erormed in revious ~ays. SR 3.3.1.2 (2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent. SR 3.3.1.3 (3) - Compare incore to excore axial imbalance above 15% of RATED THERMAL POWER. Recalibrate if absolute difference greater than or equal to 3 percent. SR 3.3.1.17 (4) - Manual ESF functional input check every mots24onh SR 3.3.1.4 (5) - Each train tested at least every other 62 days. SR 3.3.1.9, SR 3.3.1.14 (6) - Neutron detectors may be excluded from CHANNEL CALIBRATION. Table 3.3.1.-1 Functionl 5 (7) - Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint. Applicability Footnote (d) Note 2tor SR 3.3.1.2 and (8) - The provisions of Specification 4.0.4 are not applicable. SR 3.3.1.3 SR 3.3.1.15 Note 2 (9) - The provisions of Specification 4.0.4 are not applicable orf (delt] et (1) - Te ANEL FUNCTIONAL shall independently verify $e OPERABILITY of the u rvtaeand shunt trip circuits rteManual Reactor Trip Fuct .The test shall also verify the PERABILITYof the Bypass B akrtrip circuit(s). L. Te,-HANNEL FUNCTIONAL 39T- shall independently verify e OPERABILITY of the
- ld'roltage and shunt trip attacj aents of the Reactor Trip Breakep tA, SR 3.3.1.4 (12) - l ca m Kual snt trip rior to placing breaker in service.
(13) - JAUJ~~~~~~~~~~~~matic L~~~~~~~~ddrvoi~~~.1 SR 3.3.1.10 Note 2 (14) - The provisions of Specification 4.0.4 are not applicable when leaving MODE 1. In such an event, the I ~~~calibration and/or functional test shall be performed within 24 hours -after leaving MODE 1. SR 3.3.1.5 (15) - Each train tested at least every other 92 days. SR 3.3.1.8 SR 33.1.10 (17) - If not performed in previous 184 days. COOK NUCLEAR PLANT-UNJIT I Page 3/4 3-14 AMENDMENT 99,U44M, 277 Page 14 of 39 Attachment 1, Volume 17, Rev. 0, Page 124 of 471
Attachment 1, Volume 17, Rev. 0, Page 125 of 471 ITS 3.3.8 ITS(I ) 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-1 (Continued)
- With the reactor trip system breakers closed and the control rod drive system capable of rod wvithdrawa1.
(1) - If not performed in previous 7 days. (2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent. See ITS 3.3.1 (3) - Compare incore to cxcorc axial imbalance above 15% of RATED THERMAL POWER. Recalibrate if absolute difference greater than or equal to 3 percent. (4) - Manual ESF functional input check every 18 months. (5) Each train tested at least every other 62 days. Note to SR 3.3.8.2 (6) - Neutron detectors may be excluded from CHANNEL CALIBRATION. (7) - Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint. (8) - The provisions of Specification 4.0.4 are not applicable. (9) - The provisions of Specification 4.0.4 are not applicable for f, (delta I) and f, (delta I) penalties, or for measurement of delta T. (See also Table 2.2- 1). (10) - The CHANNEL FUNCTONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s). See ITS 3.3.1J (11) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers. (12) - Local manual shunt trip prior to placing breaker in service. (13) - Automatic Undervoltage Trip. (14) - The provisions of Specification 4.0.4 are not applicable when leaving MODE 1. In such an event, the calibration and/or functional test shall be performed within 24 hours after leaving MODE I. (15) - Each train tested at least every other 92 days. (16) - Not Used. (17) - If not performed in previous 184 days. COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-14 AMENDMENT 99, 120,141, 277 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 125 of 471
Attachment 1, Volume 17, Rev. 0, Page 126 of 471 (III) 3.3.2
~~~~~~ITS 314. LEMTiG.CONDMrONS FOR OPERAnON AMD SURVEoLACE REQUIREwME S 314.3 INmRUIWMNATION I LCO 3.3,2 3.3.2.1 UeEgineered Safety PeamrurAcatlon System (ESFAS) lwanchannelsandlnteclaks APPU ~j ,: As shown InTable 3.3-3.
II~~kL Add ro os~~~~ed ACTIONSNt ACTIONS A L With an WSAS lnluew wi dis trip betpown less onmseratve dun th Vlu shon in through F ate Allowable Valucs aolumn of Table 3.3-4, declare the channel noperable and apply due applicable ACTION rcqtdenuh z of Table 3.3-3 untdil the etlrestored toOPERABLE stonu Jh heqrdpin *j~eqp atl with the Up value. I~ ACTION A b. With an EsFAS iwmtrmenaro wndie wnperablc, take the ACTION shown In Table 33-3. SR Table 4.3.2.1.1 Each WSAS histrummntadon channel shal be dezonastraWe OPERtABLE thef Note dhe CHIANNEL CHECK, CHANNEL CALMBRATIONFO CHNN~EL FUNCTIONAL an TRIP ACTUATING DEVICE OPERATIONAL TEST opetatim onsr the MODES and a t eL. frequencies shown in Table 4.3-2. SR 3.3.2.2 4.3.2.1.2 Ibe 1011 fo& r doe bmeuocks shl be demonstrate OPERABILE during due atomatlc loqj tesL The total intedock fuzcdo shal be dltmoasuaze OPERABLE at leasone per SR 3.3.2.10, mo &igCHANNEL CALIBRATION testing of each cbane affected by hItedock i..3 SR 3.3.2.12 SR 3.3.2.13 4.3.2.141 b NGNEE SAFETY FEATURES RESPONSE E mdn&elb LonaSTAGGERED TEST BASIS COOK NUCLER PIANT.UNff I Page314 345 AMENDMENT #0, 43&,44,4IU202. Page 1 of 51 Attachment 1, Volume 17, Rev. 0, Page 126 of 471
Attachment 1, Volume 17, Rev. 0, Page 127 of 471 ITS 3.3.5 314.. LJIMI1TING.CONDflMONS FOR OP1IRATION AND SURVEIANCE REQUMIEMbMl 314.3 INStRUMENATION LCO 3.3.5 3.3.2.1 The Eug neerad Safety Pcatur Actuaton. Syntel (ESFAS Seeueaatonchnnl APP~r.&VZM:' As shown In Table 3.3-3. A~~~~avlrbl CTO deNetofTbed3.-p3 until th-~--e hannel)IS NostoedtO I~ lls ACTION A a. Wi1th an EWAS Itrmcnat'don chmanne tInp eraobsle,ae h c maCtiON dhondinTbe 3.3-3.n i SR 3.3..1, 4.32.1.1 Ech SASlwal umnanchone shalle334 coltn bect hnnlhp adapyd SR3.3.5.3, TRappiPalACTUTN EIEOEAIONA TESm4of e333utilf operat iosresore theMODESI sanda h SRIO 3.3.5Wi4, arunce shownInsTrimnableh4-2. dhprbe ttdeA O wa nTbe333 SR 3.3.5.5 4.3-2.1.2 Tha logic (or the Interocks shall be deosrtdOPERABLE during the autmai atato logic teaL The total Interloc function shall be dftmoatmAte OPERABLE at leant ones per 18 See ITS months during CHANNEL CALIBRATION tuftin of each A, afnel d by jinfioc 3.3.2) 4.3.2.1.3 ENGINEERED SAFBTY RESPONSE TGEof ESAS fnction bahall be tobeWWhlnthe at least onepe IS moihs. test shall Woudeau leart one lgctrain soch thud both I rils ar tesed at lewam s 36 motsand odam nl . per function such thmal V owes pec PcJeduiast I montsgwhere N s fth soulmberofsedadi In a WAS ftiC m shown Inte ~rowa Nio. ot aainelid Colun of T& j.S-3. COOK NUCLEAR PLANT.UNfT 1 Page 314 3-15 AMNDOMEN 10, 43&, 444, W5,202. Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 127 of 471
Attachment 1, Volume 17, Rev. 0, Page 128 of 471 ITS 3.3.6 ITS 314.. L1M1TING.CONDMrONS FOR OPERATION AND SURVEIUJANCE REQUIREbMEITS 314.3 WSRUMENATION LIMTING CONDITION FOR OPERATION LCO 3.3.6 3.3.2.1 Ile Enginered Safety Feature Actuaton SYaSe(ESPAS)Imm dmctasonhande1itfiaiiiii See ITS hPUILUI: As shown InTable 3.3-3. droosed ACTIONSNt ACTIONS B and C a. With an WSAS i~atlaw mc channd trip sqotpi less conservtiv than dhe value shown fa the Allowable Values column of Table 3.34, declar the chanel finoperble and apply the applicable ACTION iqarmnent of Table 3.3-3 untiltechanne Isrestored to OPERAB.E mats Iwith mh-rpstp anU~dlalse *Ii-the E I-i value. ACTIONS B and C b. With an ESAS instrmmenaton channe noperable, tak the ACTION sho" in Table 3.3-3. SURVEILLANC R1EOMUwff.NT SR Table 4.3.2.1.1 Each ESFAS Intuetaincannel sall be deosrtdO~AL ! h PR"mo Note she CHANNEL CHECK, CHANNEL CALZBRTIONI,JH ~ U ONLTS TRIP ACTUATING DEVICE OPERATIONAL TEST opertions for the MODES and at the freuecies shown in Table 4.3-2. logic test. Tle tWta intiedock fUZmSIon shal be dtmotitrwod OPERABLE at least once per I8 See U months duuing CHANNEL CALTBRATION testing of each chane affected by ntrok3.3.2J 4.3.2.1GINEREDSAFET RESPONSE SAS fctionw shall be WIEo toe widhin do at l oce pec 18moah test dallln&,dat tent one logigtrin soh ha both taretsed at les
#=ran 6mnths ac an amA.
prfntombdig Ah U pIcasn onepr
- lu " Fete mouftewbere NIb 1*
of a~~h shoAS lfth 'Fotal No. ot 0ibwelCola= ofT 3. COOK NUCLEAR PLANT-UNIT 1 Page 314 3415 ANIENDIME 4004243, 444, 4U. 202 Page 1 of 29 Attachment 1, Volume 17, Rev. 0, Page 128 of 471
Attachment 1, Volume 17, Rev. 0, Page 129 of 471 ITS 3.3.2 ITS 314.. LORMING CONDITONS FOR OPERANION AND SURVEILLANCE RU mNT 314.3 INSIMtMRIX'ATXN Table 3.3.2-1 TM 1 ~~1.SAFETY INIBMrON, 1.b b. Automaic Acmuloz 2 1112,3,4 13 C,I 1.e.(2) Bte t
~~adg tine ine lne line 1A2135 COOK NUCLEAR flANT4.UNIT I Page 314 3-1w AbIEIDbMFT Pk I#, 153 Page 2 of 51 Attachment 1, Volume 17, Rev. 0, Page 129 of 471
Attachment 1, Volume 17, Rev. 0, Page 130 of 471 ITS C) 3.3.2
~~~~~~~~~~~~~~~~~ITS 314 LIWMiNG CONDITIONS FOR OPERATION AND SURVEILANCE REQUIREMENTS 314.3 INSTRUMENTATON Table 3.3.2-1 .TABLE 3.3-3 (Continued)
FUNCTIONAL UNIT OPERA9L MODEBS ACMON 1.e.(1) f Ste=m Line Pressure-COONULEA PLNT-NIT1 Page~o 2/ 3-17 AMENMEN 9 140SI 1 Page 3 of 51 Attachment 1, Volume 17, Rev. 0, Page 130 of 471
Attachment 1, Volume 17, Rev. 0, Page 131 of 471 ITS 3.3.2 ITS 314 LI&MING CONDMTONS FOR OPEATION AND)SRVERILANCE REQUIEMENTS 3143 INSMRUMIIEATION Table 3.3.2-1 TABLE 3.3-3 (Conftiued ENOMMERI SAFMT FEATURE ACTUATION SYSTEM l[NSTRMNTTN FUI4C13ONAL UNrITMOE ATO
- 2. CONTAINMENT SPRAY 2.a L MarnuallPndnlUt 2.b b. Antomatdc Acmsdan 2212.4 13CI 2.c C. COnwma~net 123 1 COOK NUCLEAR PLANT-VWIT1 Page 314 3418 AMENMENT to, 420,153 Page 4 of 51 Attachment 1, Volume 17, Rev. 0, Page 131 of 471
Attachment 1, Volume 17, Rev. 0, Page 132 of 471 ITS 3.3.2 ITS 3/4 LMIfiNG CONDMTONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3. INSTRUMENTATION Table 3.3,2-1 TABLE 3.3-3 (Continued) ISOLAT1ON
- a. Phase A" Isolation 3.a.41) 1) Manua ----- -Seeuctonal Unit 9 3.&43)2)FoSaey12 1234 13CI Injection Automatic Actuation Logic
- b. Phase 'EV solation 3.b.(1) 1) ManualSe uconlUi9-3.b.(2) 2) Automatic221234 13CI Actuation Logic 3.b.(3) 3) Containment4 A3 1236E Pressure - High-High
- c. Purge and Exhaust Isolation
- 1) Manual -------- See Functional Unit 9 --
- 2) Containment 3 1 2 1,2,3,4 17 See ITS Radioactivity-* 33.6 High Train AL (VRS 1101, ERS-1301, ERS 1305)
- 3) Containment 3 1 2 1,23,34 17 Radioactivity-*
High Train B (VRS 1201, ERS-1401. ERS-1405) Es specification only applies during PURGE. COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3.19 AmENDmENT94,niSS 279 Page 5 of 51 Attachment 1, Volume 17, Rev. 0, Page 132 of 471
Attachment 1, Volume 17, Rev. 0, Page 133 of 471 ITS 3.3.6 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3. INSTRUMENTATION Table 3.3.6-1 TABIL 3.3- (Coninued ENGNEEEDSAFETY FEATUJRE ACTVATION SYSTEM INSTRUMENTATON EUNC7lQNALUIM PRBL OES AIO
- 3. CONTAINMENT ISOLATION
- a. Phase "A" Isolation
- 1) manual --------- See Functional Unit 9
- 2) From Safety 2 1 2 1,2,3,4 13 -
Injection Automatic See ITS Actuation Logic 3.3.2J
- b. Phase "B" Isolation
- 1) Manual --------- ~~~~~See Functional Unit 9- -
- 2) Automatic 2 1 2 1,2,3,4 13 Actuation Logic
- 3) Containment 4 2 3 1,2,3 16 Pressure - High-
- c. Purge and Exhaust Isolation Function I 1) Manual -- -- - -- See Functional Unit 9--
Function 3 2) Containment 3 1 1,2,3,4 17 C HhTriRadioactivity-* 1101It S-Function 3 3) Containment 311,2,3,4 17 C Radioactivity-* High Train B 1201,yds- 2pr tanA. ER405) COOK NUCLEAR PLANT-UNIT 1 Page 14 3.19 AMENDMENT 94, 45, 279 Page 2 of 29 Attachment 1, Volume 17, Rev. 0, Page 133 of 471
Attachment 1, Volume 17, Rev. 0, Page 134 of 471 ITS 3.3.2 Table 3.3.2-1 TABLE 3.3.3 -(Cqitt~nuod) V!OINEEME SAFlTY FEATURE ACTUATION SYSTEM INSTRUENTATIOtj FUNCTIONAL UniT 0 HANOPERAB1LE -. tODES ACTIO A. STEAM LINE ISOLATION 4.a A. Manual........... hetFwcclnal 'Unit 9 . ... 4.b b. Automatic 2 1 2~Footnote (d) 1. 2,3 I.C, H
&caction Logic 4.c a. Containment Pressure 42 ,21E Add proposedL 4.e -d. Staaa Flov inf Two LFonote (d)
Steam Linua'-Migh FUr op2/teaml IL /a am cc 1. 2.130a I COQKNUCLEAZUET*WUI. ~ ~ I a3ny.1MlineI.9. n 5 2 eam Edd pr Pagep6oe5 Attachment 1, Volume 17, Rev. 0, Page 134 of 471
Attachment 1, Volume 17, Rev. 0, Page 135 of 471 ITS 3.3.2 ITS
.3)4 L~U1D'G CONDMZON FOROrnAU1ON MD MUVEULANCZ RQUARnOM 314.3 M~TtMEMMATION Table 3.3.2-1 TABLE 1.-4(C4afhiflem COINCIDENT WrM[Ad1rpoe 4.e .2 LW-4 COKULasti RAIFJf 1 3/4 3-21 PMml* re 3, U24 L1 ox-"
~ ~ Pge7of5 Attachment 1, Volume 17, Rev. 0, Page 135 of 471
Attachment 1, Volume 17, Rev. 0, Page 136 of 471 ITS 3.3.2 394 MUThING COMM~ONS IFOR OPERATION AMDSURVEMUANCK RREItmMMWd 3/4.3 ISRJErTo Table 3.3.2-1 g 3 A 6.e b. 4kVBusLcof r,2, II VokF pun,8w IA-L2 valve (Budi 6.d C- safctybnedwo 2 12 1.23 IS*B, H 6.g d.I d~d 2att 2 2 1.2 WB G
- 7. M m2 6.f~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.
6-c LSS OFPOW L~~~I " S. 4 kV Dw Eon of 3BSW lows 2121us 1,2.3.4 14' Vokge See ITS 3.3.5
- b. 4 kVfBus Demdud 3/Dim 2/Dam 21Bus 1.2.3.4 14' Woalt CrIA-TxinnD; (TIIA-Tain MIA-Tsie TLID-TndnA) 3;TIID- Z.T1ID-cooxKucWzARnAWT.NIT 1 Psp4 )1. AbMNi gDMU493q,f3 243 Ad rposed Function S6 La A.3 Page 8 of 51 Attachment 1, Volume 17, Rev. 0, Page 136 of 471
Attachment 1, Volume 17, Rev. 0, Page 137 of 471 ITS 3.3.5 M~ wdrINGCONMMONS FOR OM O MSVaMERQMMV
'FaALNOOP CANNIMi CANNHS APPCAEL5 p!TiPEffMAf NIT 3D.221E D)MABLE IMOD Ar"~
- 6. MMTR DRIME AUXILMAY FEEDWATIMRPIMIPS L &xzmOcowuaWata 354L m 213t GnL~~ llt(ktlL 1.2.3 14,
- b. 4kV~,Lmoso 3/Dug 2/Bus 2/Baa 1.2.3 14' pwStet 2lbua(TIA-.
-ThinA)
VudveActuation(Both 21buacas(IA 2ARITiUc See ITS
&TIID) 3.3.2)
- c. Safetl*adoin 2 1 2 1.2.3 lls*
Losuo LA" Feuewasw 2 2 2 1,2 l1I'
- 7. 'IURDINDRIVB AUXILIARY FEMWA~PMPS
.SftcaaGwmerbaWai 3/WmGCa. 2/BtaaGen 2/Sa.kGa 1.2,3 14*
Laval -towvLow uySO
- b. Hecarto~d "Pu~ 4-IBvs 2 3 1.2.3 19' LCO 3.3.5 8. WX3SSOFPOWER3 .
dAPPLICNABIIY 4.kV Bso[An of 3/Dus 2/B li123,4 114 'when associated" and AACTION ~~~~~Voltag 3DG Isrequired to M. be OPERABLE
- b. 4kV~usDe6Admd 3/u train .23.4 14' by LCO 3.8.2 WIMPag A-TWO IFt-iiD ( A-bin TI -balsA) ;TIA) A)I- .
CDOO N ZMU PAWFUVMf I P~4 aASMDMENT92",I5IS3 243 Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 137 of 471
Attachment 1, Volume 17, Rev. 0, Page 138 of 471 ITS 3.3.2
~~~~~~~~~~~~~~~~~~~IT 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION Table 3.3.2-1 ~~~~~~~~TABLE 3.3 (Continued~
ENGINEERED SAFETY FEATURE ACTUATON SYSTEM INSTRUMENTATIN FUNCTIOAL UNIT C ____MODS___ I
- 9. MANUAL lta a. Safety Injection (ECCS) 2 i /ri tan12 . 8B S.c Feedwater Isolation IRofctor See II 3.a.(3) Containment Isolation -
Exhaust Isolation 6.d Auxiliar Feedwater Pumps 2.a b. Containment Spy 1in /ta 1tai1,,3,4 18 B, I e 3.b.(1) ~~Containment tsolatin - 3.b.(1) P. R e T Containment Purge and .. 4.a d.St~~~Examust Isolation 2/ i( 1 s1 % petrn)Fooed
~~~~~c Containment Ioatirn -
7.a r Iftrain 1,2, 3,4 1 ,I L 7.c c. ~~~~Containment Pesurgean HigIT COO haUCLEA PslaNtiUnITI Pg / - MNMN L~ 2343 line
~ ~~ ~ ~ [Adof
~ ~ Pg 51p Attachment 1, Volume 17, Rev. 0, Page 138 of 471
Attachment 1, Volume 17, Rev. 0, Page 139 of 471 ITS 3.3.6 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION Table 3.3.6-1TAL333(Cniu ENGINEERED SAFETY FEATURE ACTUATION SYSTEM InSRUMENTATION FUNCTIONAL UNTPHAER2ABL MODES A
- 9. MANUAL
- a. Safety Injection (ECCS) 2/train l/train 2/train 1,2, 3,4 18 FeedwaterlIsolation Reactor Trip (SI)
Containment Isolation - Function 4 Cofitainnment Purge anSee3.3S2 Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System
- b. Conta, tpr lAran1am I1/ *n1.2,3,4 18 B Co nmet aion Function I Containment Purgean Exhaust Isolation C. Cont enlo o-hi /rain, 1
- 1,2,3,4 18 B Ase"""', 1 ~
Function I Containment Purge and Exhaust Isolation L.
- d. Steam Line Isolation 2/steam line (I 2/steam line 2/operating 1,2, 3 20 per train) (I per train) stam line (I per train)
- e. Containment Air 1/train 1/train. l/train 1,2, 3,4 18 Recirculation. Pan
- 10. CONTAINMENT AIR See ITS1 RECIRCULAMlN FAN 3.3.2)
- a. Manual --- -- --- See Functional Unit 9 Ib.Autornatkc Actuation Logic 2 1 2 1,2, 3 13
- c. Co2ntginment Pressure -High 3 2 2 1,2,3 14*
COOK NUCLEAR PLANT-UNIT I Page 314 3-21b AMENDMENT 453.234 Page 3 of 29 Attachment 1, Volume 17, Rev. 0, Page 139 of 471
Attachment 1, Volume 17, Rev. 0, Page 140 of 471 ITS 3.3.2 ITS Table 3.3.2-1 1 .3.; (Conttnudd 3xT Footnote (a) *Trip function may be bypassed in this KODE belov P-1. Footnote (b) 'Tcip function may be bypassed in this KODE below 1.12. ahcha (a) associated wiht ttective functions divd fromi the oult seervice Reactor Cd Lop shall be placed in etripped mode.
"iianuaU ri all bistablis hvud be automaticall ppda in the ev ntpressure in the assa lated active loop were leestnth press: e La the nactLVe looa for example, if loop I is heiative loop, then the bistalbles whic indicate low pressure in ops 2. 3. end reyetive to laooI should etripped.
ACTION B Note *Th provisions of Specification 3.0.4 are not applicable. ACTION C ACTION 13
- VLth the umbrof OPERABLC Charaels oni less then the Total ACTIONS H and I LbSItTFDOVN within'the follovin 30 hoar however# one ACTIONC~~~ote testing per Specification 4.3.2.1.1 oe ATO DNt ACTION D ACTION l'i - -th the uumbr of OPERABLE Channiel one lest than~ the Total j~,~,nop lab channel is placed in the etipped eanditian vichtnk LJ--j hour. Ad rpsdACTIONS G, H n .
ACTION 15
- th a channel associate with en. oprartint loop ino ereable, estore the inoperable a Ielto OPEIABLE status thn 2 husor be La ROT S within the follovig I oUral.
howeer,ne cannl sociated withi an operatin o a eA1 bypassed for up to 2 ousfor surveillance test per Ipecification 4.3.2. .1. ACTION E ACTION 16 -91th the numnber of OPW.AZLE channels ose teons ta the Total within 6 hours Li EMabot of Channels, operation may proceed provided the inoperable channel is placed in the bypassed conditionanth Kiniam Channels OPUMABL requirceent, is met: one additionalL. channel may be bypassed for up to !hours for surveillan~e4 tessting per Specification 4.3.2.1.L D. C. COOK
- UNIT I 3/4 3-22 AIMEDW1 go. 11,12a Page 10 of 51 Attachment 1, Volume 17, Rev. 0, Page 140 of 471
Attachment 1, Volume 17, Rev. 0, Page 141 of 471 ITS 3.3.5
,Trip function may be bypassed in this NODE below P-11.
"Trip function say be bypassed Ln this MODE below P.12.
'00The channel(s) associated with the protective functions derived from the out of seivice Reactor Coolant Loop shall be placed In the cripped made. See FrS e'"wsnually trip all btstablis which would be automatically tripped in332 the event pressure in the associated active loop var. less than che
,pressure in the inactive loop. For example. if loop I is the inictive loop, then the bistables which indicate low pressure in loops 2, S. end 4 relative to loop 1 should be tripped,
*The provisions of Specification 3.0.4 are not applicable.
ACTION 13 With the number of OPERAL9 Charnele ones less then the Total Number of Channels, be in HOT? STANDBY within 6. hours and in ACTION A ACTON 14 Wi~th the number of OEIABLIE Channels one lees than the TotaL in. ereble channel is placed in the tripped condition within 0 14 4 I ~~~~~~~~~~~~Add proposed ACTION B . ACTION 15 -With a channel associated with an. operating Loop inoperable, d proposedATOC restore the inoperable channel, to OPERABLE status within 2 hours or be in HOT SHUTDO= within the folloving 12 hours; however, one cannmel assooiated with an operating loop may beL4 bypassed for up to 2 hours for surveillance testing per SpeaLticatien d..3.*.l.l. see MTS L3.3.2) ACTION 16 *With the wimber of OPERABLE Channels one less than the Total Mimber of Channels, operation may proceed provided the inoperable chmanl is placed in the bypassed condition and the Klinimu Channels OPERABE requirement is met;, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. D. C. COOK - UNIT I .3/4 3.22 AIIMNDHCV 00.91.iZO Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 141 of 471
Attachment 1, Volume 17, Rev. 0, Page 142 of 471 ITS 3.3.2 ITS TAltz 5.3-) (Continued) ACTION 1i - with less than the tWaisa Chumnele OPERABLI, operation See ITS ear Gontiziua provided the coutaumaout purse aud exhaust 3.3.6 Yalvcasi mareintained Closed. ACTION 15 Vith the aiaber of OPflASL Channels one less than the ACTION B Total limber of Channels. resara, the Inoperable ACTIONS G, Hand I latH SMYwiti tO test5 us and OLa ACTION D ACTION 19 - With the numb.r of OPURASIX channels one. less than the OnRA.TION may Proceed provided the following conditions sre satisfied:
- a. The Inoperable channel io placed As th tipe condition vithin
- b. Tb.e K~nimm Channels OPADIZI requiremenut ts met; however, one additional channel may be bypassed for u to afor surv*illance testin~g per SpeciftcatLo ACTION 20
- ihthe aumber of OfPAUIchnnel one 1ess than the ACTION B Total. Umber of Channels, restore the inoperable 1to OIZEAEZ statue vithin 48 hours or declare ACTION J the assaciatad valve inoperable end take the ACTION COOK NUC= ZIK *~ VW1 2. 2/4 2-21 AMMOM NO. 00. W.~
153 Page 11 of 51 Attachment 1, Volume 17, Rev. 0, Page 142 of 471
Attachment 1, Volume 17, Rev. 0, Page 143 of 471 QII~~~~~~~ ~ITS 3.3.6 ITS twrmore Qj TL!S *S- (Continued)AdpoosdAIOA ACTION C A~CTINo u7 ih as than the linia Channels, OflZMLZ. operation may continue provYUSA the containeeit, purZ~6 and exhaiust valves are maintained closed. ACTION B cUOU13is With the mnber of OUASLZ Channels one laes then tits ACTIONB ?~~~otal. Wube: of Channels. restore the Io" rable ACTION C las RO TNBYwti the noext36hours
.. OL ACTION It V Wth the umber of CPDAILK chanels one less than the Total Rubs: of Channels, STAITUP and/or IOMu.
OSEUTZOI say proceed provided the following conditions are satisfied:
- a. The inoperable channel La placed in the tripped condition within 2 hour. See ITS
- h. TMe Miniwm ChanneLs OPfLBZ requirenent to met;3.2 howveer, one additional channel may be bypassed for up to 3 hom*& for sumvilance testing per Upeolfication ACTION 20 - With the number of OSPABIK channel. one less than the Total Paub.: of Channels. restore the inoperable chmanl to IOMABLZ statue within 48 hous or declare the aesociated valve Inoperable end take the LCTION required by Ipecificetica 3.7.1.5.
COOK NUMDLI M1M
- amI I 5/4 5.13 AISUNINT NO. 00. f0 153 Page 4 of 29 Attachment 1, Volume 17, Rev. 0, Page 143 of 471
Attachment 1, Volume 17, Rev. 0, Page 144 of 471 ITS 3.3.2 ITS Table 3.3-2-4 314 LIfMTIG CONMMTONS FOR OPERATION AND SURVEILLANCE REQuuIRmamT 8.b A~ddproposed P1 m!P lc B-C Of 4Lv. ICU 12 f5 W~~~~~~~~~age1y Attachment 1, Volume 17, Rev. 0, Page 144 of 471
Attachment 1, Volume 17, Rev. 0, Page 145 of 471 ITS 3.3.2 ITS 314 LL~fM1LJG COMM~rONS FOR OPERATION AND SVRVEMLANCE REQUME~~iTs 314.3 INSTRUMfENATION Table 3.3.2-1 ,- QM'IN-EERED SAFETY F AUEAWTrQN fiTEn 1SRM~NATION4 TRPLEUETPOI14jU 1.b b. A~~UNTIONai UNITato SitplcbETtJo AplicaBLE M I 1. SAFETY~g 1.17 MN1 1.e.(2 Bet. MWee ta Lines- SW t481.3unt 1.c C. Con~~teaine pressure- L hn reqa to 500L Palg reaue than or equal, to pi 1.e.(2) Betwee aSlne temlie uesu AddMr ed Footnote WcM COOK NUCLEAR PLAtUrUN I Pogp 314 3424 AMfflUD r 40i 44 M4U214 Page 13 of 51 Attachment 1, Volume 17, Rev. 0, Page 145 of 471
Attachment 1, Volume 17, Rev. 0, Page 146 of 471 ITS 3.3.2 ITS LOMMON CONDMTONS FOR OPERATIOM AIND SL1IVZU.LAaVCE REQMMLUN-S 314.3 LNSTRVUMENATION4 Table 3.3.2-1 TAKE 23,34 X ontIWJed' ENGINEERED SAFETY FE JURE ACTUATION SYSTEM INSTUMPN-TATION TR1,5iP ETIT FUN.CTONAL MUNITP&m L~MEL-VL
- 2. CONTAINMENT SPRAY I 2.a a. Mamwtitatlidtom - See Fucaioca 2.b b. Amrmadc Acwadoim Logic No Ap0llca Hot Applicab~e 2.c C. Comraiome Pressure- iha or ual to 2Z9 pg Lens thb or equal r~~ug/'
trigh-High.
- 3. C~ONTAINMENT ISOLATION
- a. Phase 'A' soluilon 3.a.(1) 1. Manual See FUwcrondlmUl9 3.a.(3) 2. From Safet Ipeetdon oAppNoApier AutoailcAsualo Logic
- b. Phase 'B' Isolation 3.b.(1) 1. Mmnualse uewlni 3.b.(2) 2. Autcnurc Actaulon 0 Notcal 3.b.(3) 3. Cornalnmecc Pmuss=- Ls ma qa COOK NUCLEAR PLANTUNX I Pape 314 325S AMZDbMEN 1153 Page 14 of 51 Attachment 1, Volume 17, Rev. 0, Page 146 of 471
Attachment 1, Volume 17, Rev. 0, Page 147 of 471 ITS 3.3.6 ITS 3,14 LLNMIT'G CONDMTONS FOR OFERATIO0N AND SLRVEMLLANCE RZQ1RML\TMS 314.3 L'NSTRhUMENTATION Table 3.3.6-1 TABLE 3.3-4 (Continiid) ENGIlVJEM=E SAFETY FEATUJRE ACTUATION SYSTE [NSTtMUENTArIO TRIP SETEOIhnT FUNCTIONAL ITUSdNNITLQALEVLE
- 2. CONTAINMENT SPRAY
- a. Manual Wndation - - - Sao FQ~ounctUnalit 9 - - - -
- b. Amtmatic Actuation Logic Not ApQJkIZI Not Applicable
- c. Containment Pressure- Less matano equal to 2.9 psil LMs duan at equal to 3 psig High-High
- 3. CONTAINMENT ISOLAITON
- a. Phase "Al Iolation I. Matnug e ucinl nt e T
- 2. From Safet Inection Ngot Applicable Not Applicable 3.3.2)
Automatic Actuadic Logic
- b. Thu*E'BIsolsaio
- 1. ManUal see Funcdionalunit 9
- 2. Automatic Actuation Not Applicable Notc Appicabls Logic
- 3. Contaimem Prusur-. Lensaibat equall to 2.9 psig Lisa tha or eqap to S pig High-Fgli Function I c. Putge and Eaxhants lactation I. Ma lSW FsmcdoAualduk9 COOKC NUCLEAR fLAW-f.Url I Pop.314 3.25 AMNDbMlNTi 151' Page 5 of 29 Attachment 1, Volume 17, Rev. 0, Page 147 of 471
Attachment 1, Volume 17, Rev. 0, Page 148 of 471 ITS 3.3.2 I/ LDMiIG COMM~~ONS FOR OEIATION.AN SURVR[LLANCERE mECF 3143 INSTU041MATION Table 3.3.2-1 AL . Conud-E1~{&Li~liuI . ATRIWABL V&LUM
- 2. Coiulaeineu Radio- See Table 3.3-6 NLot Applicable scdv4r-IlH& Tuhl A, See ITS (VIRS-E WI. ERS-iSOl. 3.3.6J
- 3. Conualmem Radio- SCO TabO 3.-" Not Applicable activity-High Thin B (VAS-1201, ERS1440I.
BRs-1405)
- 4. STRAM LOM ISOLATION 4.a see. uona,1w!
4.b b. Autmatic Amtazlou Lagic No plcbeNot ApplIdal 4.c C. Cczah=t i huacmui- fte ot to 2.9 L mv equzal topg 4.e d. ~~~szeaDiP in Two S(iam dUnaor to I.2 Ox Laadummaerqual o 1J6 4.e ~~Lb sh Co~deMi with ftm odIS 10 MG~r fromO lowma
;,-Lo~w-Law IM 16IW LS fthft At20% load la ro lom& ~~~~to 3.93 too Iba/b at 1005 Tgreat# or eUal9 T p,, rhu or eu 4.d e.Soem EJ= mpren-Lnrv 0" ib quito pug zif e elo 2 -j S. TURBINB TRIP AND FEEWATM ISOLATION EAdd propoe ot 5.b
- a. SteamGsgmgaWorw L4dwOflaino to7% Leamahofaral to6Gs Q%)M COOK NUCLEAR PEAmUNTAM 1. Pape 314 3-li AbMWNMEN~ K I4, 13,14 Page 15 of 51 Attachment 1, Volume 17, Rev. 0, Page 148 of 471
Attachment 1, Volume 17, Rev. 0, Page 149 of 471 ITS 3.3.6 ITS 314 LWAMG CONDMrON3 FOR OPERATIONAND SURVEILLACE REQUMEM 4FS 31431 IN~STWUA(EMF7ON Table 3.3,6-1 Function 3 2. ContzinntftRAdio See Table 3.36 NotA Function 3 3. *Coalmtsuz ado See Table 3.3- Ap I
- a. LMazma $0 Pimcdnal lnk 9
- b. Ammsomal Adauglo Losto Kuo ANotale? Applica C. Come~i Preur- Laes Ibaior equal to 2.9 pugS Lam ibm or equal idS pai
- d. Smin FlowltoTwoltaSMM Im aor quallro 1.42 x 06 Letdmn or equalto I.56x Lm-HlghColiddn with lbxih frm 0% load to 20% lWAd I06 ibm/r fro 0%5 1Wt Tzv9-LoqW- Linea from 142xY.06 lbs/bmg 20% boad Wmea fomm 20% tkad to 3.88a l0 lbshr at 1.56 : 1066lb;.ft as 20% load 100%l1104 to 3.93 10 bafbrat l00YSefl load.~~~~~L3.3.2J
~
T greSmaimw or equa T, resarmn orequal
- a. SW=a Llne Paema-Low Orator Om cc equal o 500 pug Gratew tha or equa to 480 Urnlam pramsnf pal mmamliePrA==
S.TURBKNB TRIP AND FEEDWATER ISOLATIONd A.saSm amtmWaar Lms bm atnqual to 67% of Lma taof *eqa to 68% of Levu-Hwmtb.g narow-fo ae surums Span mmow-mg curunaspa each aftam aftraeml each St"=gz COOK NUCLEAR PLANT-MU~ I. Page 3/4 3-26 AMEMMDMEN K4 42, 143 214 Page 6 of 29 Attachment 1, Volume 17, Rev. 0, Page 149 of 471
Attachment 1, Volume 17, Rev. 0, Page 150 of 471 ITS 3.3.2 ITS Table 3.3.2-1 314 314.3 L1fM~rG CorWWlONSFOR OPERA1ONAMD SU1RVEHLANCEREUEKT N hTM TAO
'AL934(ofmb 1
- 6. MaOTRDRIVENAUXIWRYL2 FEED WATEELPUMdPS .
- a. StcaGenrrWatcrLevel- tbomer to107% i Gaw tornor equalt 6.c ~~Law-Law 6.e b. 4 kv Bus Lou ufVoltaj 3286 itwit tudeay k 3245 vmlsnde3328 volt, wii tmed~ddsyof2*0O2 6.d C. SaL-yb~ecwdm Not lcb.Nothpplicabic
- 7. TUPLIMD~EDYWEAUXILMAY FEEDWATERPUMPS 6.c a. S1euCoeratNWrWLCatrv- dinnr to 17% Gmteraneer qato
- 6. b. ReacwoeluadPamtp~us dinr 2750 Oreater Giuo o~qmlt6 2725 S. LOSS OF POWERL
- a. 4 kvBus LomssefV0ltag 3286 v wksih atime delay of2 t 3245 voltsamd r3328 volts second. wihatimedulayof2*O.2 See ITS uccw~~~~~~~~~S ~~3.35 )
- b. 4 kvBusDcgmddVeltag 3959v0Web wadmaze delayof9 k 3910Ovoks and~4o00vofta ueeonduim a Stemgseneamtn withatinedecayd9*0OZ Viatcrhvs1lolowemrauafely seconds when uutem enctutor twecdmaumpspeam waft lcvl low-low or a afct COOK NUCL2.AR PLANT-UNrr 1 Pape 314 3-26a AMEDMET 414,M46 ,268 Page 16 of 51 Attachment 1, Volume 17, Rev. 0, Page 150 of 471
Attachment 1, Volume 17, Rev. 0, Page 151 of 471 ITS 3.3.5 ITS (1 314 LuiTnVG CO MN FO P 1O AND SURVEXUANCE REQU1REMKN'I 314.3 ISB~4NAI
- 6. MFOTODRDWEAUXILIARY FEEDWATEPUMPS
- a. StcamGa=ezuorWntcrLcvo1- Greaterdwnoreqiulto 1%of Gnaw Om or equal to 16% of LOW-LW IUT n nurw3vaS hamDdaPoa rSee rrS stamguorzoor each stemmgeaerator 3.3.2
- b. 4 kvBwa=oaaofbiha 32M volis wih atismedelay d2 M53AS ok esaz3328 vobs s"COuD& wiffatimdedlyof2*O2 WOD C. Saivwjecticm Not Applicable . NotApplicable d&Loms ofMaiaFeedwaterPumip NotApplicable Not AMplcable
- 7. TURBINE DRIVENAUXILI.MY FIMUWATERFUMPS a- Sb GMtrM~~~vj GreabcrUhuorequul to 17% of Greuterthmnor oqual to 16% of
- b. RearotorCoolamiPump~us Greatergwnorequal;750 Greater 9=atarcqualto 2725 Undervotag Voht-cachbuu Vohs-eacbus
- 5. LOSS OF POWER SR 3.3.5.5 a. 4kv~wLousofVoltze 328a ~b a me o2 a3245 volu and s3328 volt secomla wikadimdclayof2*0.2 9
SR 3.3.5.3 b. 4kv Bus Depaded~olh b9ye!~O k 39 1O vokand s4000 volts I second. ~masteanenemtiw witb it inideuy of 9+/-t025
~~~~~~ ~~~~seconds When a, seamgairtor iz~~~ signal w~-.atervel low-kvwor asaty COOICNUCLIAILPLANT-Ur(ff I Page 314 3-26a AM ONENDI T1B,4'3,268 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 151 of 471
Attachment 1, Volume 17, Rev. 0, Page 152 of 471 ITS 3.3.2 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 14.3 INSTRUMENTATION Table 3.3.2-1 FUNCTIONA1, UNT ISE0 ALOWABLE VALME
- 9. Manual 3 l.a a. Safety Injection (ECCS)NNA 5.c FeedwaterlIsolation A.NA IRctorI A.N.
3.a.(3) Containmient A. N.Aon. Phase "A' Containmnent Purge and N.A. N.A. See ITS Exhaust Isolation ________3.3.6 6.d Auilay edwtr A NA IEsential rvice N N.A.L..3 2.a b. Contanment Spray N. . .N'.A. 3.b.(1) Containment Isolation - I NNA e T pha~cf "R [e 3I3 Containment Purge and N.A. Exhaust Isolation 3.a.(1) ~~~c. Containment Isolation. N.A Phase "A! [ ontaiPntPre and .N..Seer [ ITS 4.a d. Steam Line Isolation NA l~~~~a~~e. Containmtent Air NA 7.a ~~~~~~Recirculation Fan
- 10. CONTAINMENT AIR RECIRCULATION PAN 7.a a. Manual .- - .See functional Unit 9 7.b b. Automatic Actuation Logic No~tpplicable Not Applicable 7.c c. Containment Pressure -HIh than oreC to 1.1 psi .. Less than or equal .2pg COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-26b AMENDMENT 463, 234 Page 17 of 51 Attachment 1, Volume 17, Rev. 0, Page 152 of 471
Attachment 1, Volume 17, Rev. 0, Page 153 of 471 ITS 3.3.6 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION Table 3.3.6-1 TABLE 3.3-4 (Conthiued) ENGINEERED sAFETY FEAuRE ACTuATION syTmm INSTRUMNAT R~IP SETPOINS EFUNQrINAL UBrt LOAL _ &
- 9. Manual
- a. Safety Injection (ECCS) N.A. N.A.
Feedwater Isolation N.A. N.A. jrSee UlS Reactor Trip (SI) N.A. N.A. 33.2 Containnent Isolation -N.A. N.A. - Function 4 Containment Purge and [ ----- N.A N------ Auxiliary Feedwater Pumps ervic Wamr ysseti N.A. N.N.A. N.A.Se j3.3.2 S
- b. Contai ntSr 4A NA.
con nt# tin- NA. Function I Containment Purge and NA. Exhaust Isolation C. Contai ot I-sol on - . . N.A. Function I Containmnent Purge and .. N.A. Exhaust Isolation L.
- d. Steam Line Isolation NA. NA.
- e. Containment Air N.A. NA.
Recirculation Fan
- 10. CONTAINMENT AIR~ See rTs RECICULATION PAN 3.3.2
- a. Manual --- --- See Functionall Unit 9
- b. Automatic Actuation Logic Not Applicable Not Applicable
- c. Containment Pressure - H1igh, Less than or equal to 1.1 psig Less than or equal to 1.2 psig COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-26b AMENDMENT 463,2341 Page 7 of 29 Attachment 1, Volume 17, Rev. 0, Page 153 of 471
Attachment 1, Volume 17, Rev. 0, Page 154 of 471 (71) 3.3.2
~~~~~~~ITS 314 .. LUhaMIG-CAMMONS IVOR opERATON AND SURVMHLANCE REQUMbMNTrS 314.3 RiSFEUMENTA11ON Table ntnonfyDeleted COO1 NUCLEAR I'LAKMFUl I Pap 3143427 AMFJNDMmrf 46,458,202 Page 18 of 51 Attachment 1, Volume 17, Rev. 0, Page 154 of 471
Attachment 1, Volume 17, Rev. 0, Page 155 of 471 C) 3.3.2
~~~~~~~~ITS 31M UMffiNG CXC*M1TONS FOR OPZA11ON AND SURVEULANCE IWQUMt1MDNTS 3MJ143NSMRUWA71ON TABLE 335-5 (Conamined
'Table ItnlnfyDelete COOK tIUCIZAR PLANMqUr I Pap 314 348 AMXN4DbMiT 9~ 4W 2
'Page 19 of 51 Attachment 1, Volume 17, Rev. 0, Page 155 of 471
Attachment 1, Volume 17, Rev. 0, Page 156 of 471 C) 3.3.2
~~~~~~~~ITS 314. LMWTIG COMMffONS FOR OMEATON MND SMJVEILANCE MEQU!RMMUT
.314.3 INS'IUMF2MATON TABLE 3.3-S (Contnudbj Table [talnlyDdelee COKNUCLEAR PLANT-UNiT I pose 31 3-29 AMENDMENT 48,42, &47 15,458,20 Page 20 of 51 Attachment 1, Volume 17, Rev. 0, Page 156 of 471
Attachment 1, Volume 17, Rev. 0, Page 157 of 471 ITS 3.3.2 3/4 1 L~ffMDG.COtIDMfONS FOR OPESA1ON AND SMVURVDLCE REQUIREMFHI' 3/4.3 MMWIUMdDIATON TJABLE 3.3-S (COiitiuedM Tablektztoal Deleted COOK NUCLEAR PLANT4JNar I Page 3/4 3-M AMMNDMENT 39459,A202 Page 21 of 51 Attachment 1, Volume 17, Rev. 0, Page 157 of 471
Attachment 1, Volume 17, Rev. 0, Page 158 of 471 ITS 3.3.2 ES-3/4 LIMITING CONDITIONS FOR OPERATION ANM SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-2 Table 3.3.2-1 ENGINEERE SAFETY FEATURE AC'IUATTON SYSTEM INTMETTO SRVELLANC REQUIREMENTS 1 SR SR 3.3+/-1 3..2.10 cjj~jq~ DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUN01ONALNIT' CHE CALIBRATION1 TE
- 1. SAFETY INJECT[ON,--
1~~~FT~~WATFP P1ThAP~~~~~~~~~ A~dd p.roosed SR 3.3.2.4 and SR 3.3.2.8M. laa. Manual Initiation --- See Feunctional Unit9 - 1.b b. Automatic Actuation L~ogic N.A. NA. Q(2)-2 NA ,., 1.C c. Containment Pressure- High s-I -10 SAgF5 N.A. 1.,3 1.d d. PressurizerPressure-Low S-I -10 SA-5 N.A. 1,2,3 1..2) - Differential Pressure Between S-I -10 SA-5 N.A. 1,2,3 Steam Uines--High 1..1) ( SteaLlnePresure-Low S-1 .10 SA-5 NA. 1,2,3
- 2. CONTAINMENTSPRAYSR3324adR3328 2.a a. Manual Initiation * - - e Functional Unit 9 2.b b. Automatic Actuation Logic NA. .A Q(2)-2 N.A. 1.2,3.4 2 c. Containment Pressure- High- 5-1 -10 5 5 NA ,,
COOK NUCLEAR PLANT-UNIT I Page 3/4 3.31 AMENDMENT 404Q,WMM44, 15,414,277 Page 22 of 51 Attachment 1, Volume 17, Rev. 0, Page 158 of 471
Attachment 1, Volume 17, Rev. 0, Page 159 of 471 ITS 3.3.2 ITS 3/4 LIMiTING CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-2 (Continued) Table 3.3.2-1 ENGINEERED SAFETY FEATUJRE ACPJA¶11N SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS SR3.3.2.1 SR 3.3.2.102-2 CHANNEL CHANNEL FCION OPERATIONAL SURVEILLANCE FUNCTIONAL UNr fl CALIBRATION RTEO
&UIRED
- 3. CONTAINMENT ISOLATION
- a. Phase AH Isolation Add proposed ~SRs 3.3.2.2, 3.3.2.4, and 3.3.2.8 o 3.a.(3) 2) From Safety Injection N.A. NA. Q(2) -3 N.A. 1.,.
Automatic Actuation Logic
- b. Phase'B"Isoladon prop'sed SR 3.3.2.4 and SR 3.3.2.8 r~~~~~~A'dd M.
3.b.(o) I) Manual ------------ SeeFunctional Unit9 - 3.b.(2) 2) Automatic Actuation N.A. N.A. Q(2)-2 N.A. 1,2,3.4 Logic 3.b.(3) 3) Containment Pressure- s-I -10 SA 5 N.A. 1,2,3 High-High
- c. Purge and Exhaust Isolation I) Manual -. - - - -See Functional Unit 9 -- - See ITS 3.3.8
- 29) Containment S R Q N.A. 1,2,3,4 Radioactvity.--igh COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-32 AMENDMENT 400,444,145, 48,277 Page 23 of 51 Attachment 1, Volume 17, Rev. 0, Page 159 of 471
Attachment 1, Volume 17, Rev. 0, Page 160 of 471 ITS 3.3.6 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION Table 3.3641 TABLE 4.3-2 (Continued) ENGINEERED SAFEY FEATURE ACTUATION SYSTEM INSTRUMENTATIION SURVEILLANCE REQUIREMENTS SR 3.3.6.1 SR 3.3.6.8 SR 3.3.6,6 TRIP ACTUATING MODES IN ICHA$NELI DEVICE WHICH CHANNEL CHANNEL IFNIOALI OPERATIONAL SURVEILLANCE EUCTONAL UNT CEK CALIBRATIONI TEST ~ REQUIRED
- 3. coNTAINMENT ISOLATION
- a. Phase"A" Isolation
- 1) Manual - - -See Functional Unit -----
- 2) From Safety Injection N.A. N.A. Q (2) NA 1,2,3,4 Automatic ActuationSeIT Logic 3.3.2
- b. PhaseS"B"Isolation I) Manual ----.------ --.-------- SeeFunctionalUnit9-----------
- 2) Automatic Actuation N.A. N.A. Q (2) N.A. 1,2,3,4 Logic
- 3) Containment Pressure--- S R SA (3) N.A. 1,2,3 High-High
- c. Purge and Exhaust IsolationM.
Function I I) Manual -- -- ---- See Functional Unit 9 Function 3 2) Containment 5 -1 6 N.A.1,34 Radioactivity--High
~~.-.- ~~Add proposed SRs 3.3.6.2, 3.3.6.3, and 3.3.6.4 for Functio2M2 COOK NUCLEAR PLANT-UNIT 1 Page 314 3-32 AMENDMENT 19I,44, 13, I3, 277 Page 8 of 29 Attachment 1, Volume 17, Rev. 0, Page 160 of 471
Attachment 1, Volume 17, Rev. 0, Page 161 of 471 ITS cii~~~~~~~ ~ITS 3.3.2 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION Table 3.3.2-1 TABLE 4.3-2 (Continwd ENGINEERED SAFMlY FEATUJRE AMMATON SYSTEM INSTRUMETT SURVERILANCE REQUIREMENTS SR 3.3,2.1 SR 3.3.2.10 d .NL DEVICE WHICH CHANNEL CHANNEL FUNCFIONAL OPERATIONAL SURVEILLANCE NCONLUNIT CHlEC C~ALIBEDLST . I QflE
- 4. ST"A LINE ISOLATION 4.a a. Manual -- ------ See Functional Unit 9 4,b b. Automatic Actuation Logic N.A. N.A. Q (2) -2 N.A. 1,2.3.
4.c c. Containment Pressure- High- 5-1 -10 SA .5 N.A. I,, d rpsdFont d High 4.e d. Steam Flow in Two Steam S-1 -10 SA-5 NA 12 Lines-High Coincident with C24months EAdd proposed Footnote ci) Tft-Low-Low 4.d c. SteamnLne Prcssure-Low S- 1 -10 SA-5 N.A. I .
- 5. TURBINE TRIPAND FE1EDWATER. ISOLATIONAdprosdFont()
5.b a. Stearn enerator Water S - -10 SA-5 N.A. 12 Level-Hi -Hi Add proposed SRs 3.3.2.2,3.3.2.4, and 3.3.2.8 for Function 5.e
- 6. MOTFOR DRIVEN AUXILIAR A-dd ;rorosed SR 3.3.2.9 for Function S71c FEEDWATER PUMPS 6.c ~~~~a.Ste=iuGenerator Water-1 S-5 NA1,3 6-c ~~~~~Level--Low-Low S 1 ANA 6.e b. 4 kv Bu3Loss ofVoltagc S- [-7 -& N.A. 1,2,3 6.d c. Safety Injection N-A. N 2 3 NA ,,
6.g d. Loss of MainFeed Pumps N.A. NAk -9 N.A. 1,2 COOK NUCLEAR PLANT-UNIT I Page 3/4 3-33 AMENDMENT 40, 420, 121, 144, 45, 214, 277 Page 24 of 51 Attachment 1, Volume 17, Rev. 0, Page 161 of 471
Attachment 1, Volume 17, Rev. 0, Page 162 of 471 ITS C) 3.3.2
~~~~~~~~~~~~~~~~~ITS 314 LIMITIG CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION I Table 3.3.2-1 TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRMW~TO CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTONALUN BA EQIE
- 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS 6.c a. Steam GeneratorWater S -1 -10 SA 5 N.A. 12 3 Level--Low-Low dprpsdNttoSL 6.f b. Reactor Coolant Pump Bus N.A. - 6 NA 1
-Undervoltage 184 days
- 8. LOSS OF POWER
- a. 4 kv Bus Loss of Voltage S R M N.A. t, 2,3,4 rseeITrs L3,3.5
- b. 4 kv Bus Degraded Voltage S R M N.A. 1,2,3,4 rAdd proposed SRs 3.3.2.2, 3.3.2.4, and 3.3.2.8 for Functo . .
COOK NUCLEAR PLANT-UNIT I Page 3/4 3-33a AMENDMENT400,4Z0,444, 43, 277 Page 25 of 51 Attachment 1, Volume 17, Rev. 0, Page 162 of 471
Attachment 1, Volume 17, Rev. 0, Page 163 of 471 ITS 3.3.5 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-2 (Continued) ENGINEERED SAFETY FEATUJREACrIUAT70N SYSTEM IN&T~RUMNATN SURVEILLANCE REQUIREMENTS SR 3.3.5.2, SR 3.3,5.4
'TIIP SR 3.3.5.3, ACTUATING MODES TN CHANNEL CHANNEL FU ONLOPERAniONAL SURVEHILANCE F(JNCTIONALUNT CHC CALIBRATION TST ,JI EQ!SI
- 7. TURBIE DRIVEN AUXILIARY 1FEEDWAIER PUMPS
- a. Steam Generator Water S R SA N.A. 1,2,3 See ITS)
Levell-Low-Low 3.3.2J
- b. Reactor Coolant Pump Bits NA. R M N.A. 1,2,3 Undervoltage LCO 3.3.5 and a vBsLs fVlae S- ,234'
.APPLICABILITY 4kussofltg S COOK NUCLEAR PLANT-UNIT I Page 314 3-33a AMENDMENT 400, 42, 444, 43, 277 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 163 of 471
Attachment 1, Volume 17, Rev. 0, Page 164 of 471 ITS 3.3.2 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION Table 3.3.2-1 TAB3LE 4.3-2 (Colitinued) ENGINEERED SAFET FEATURE ACTUATION` SYSTM INSTRUMENTATION SURVEILlANCE REQUIREMENT'S SR 3.3.2.10 CHANNEL DEVIC WHICH1 CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNcnIONAL UNfT CflC CAIRATMON 7
- 9. Manual 1.13 l.a a. Safety injection (ECCS) NA. N.A. N. 1,2,3,4 5.c FeedwaterhIolation24ots 3.a,(3) Containment Isolation-ContainmentPurge and ~~~~~~~~~~~~~~~~
ITS1 6.d Auxiliary Fcedwater 2.a b. Containment Spray N.A. N.A. NA. -9 1,2,3,4 See ITS 3.b.(1) Containment IsolatIon- 3.3.6J 3.a.(1) c. Containment Isolation- N.A. N.A. N.A. -9 12.3 4 ~ [See ITS3 PhaseW A3. i Exhaus1satio 9J 4.a d. Steam Uine Isolation N.A. N.A. 7.a e. Containment Air N.A. N.A. N.A. ~ 91234 Recirculation Pan
- 10. CONTAINMENT ATIR RECIRCULJATION FAN ti roposed SR 3.3.2.4 and SR 3.3.2.8 M6 lTa a. Manual -.--- ~See winctional Uni~
7,b b. Automatic Actuation Logic NA. N.A. Q[N -2 N.A. 1,2,3 7.c c. Contalnment Pressure -High SI -10 SA.3- NA. 1,2,3 COOK NUCLEAR PLANT-UN1T 1 Page 3/4 3-33b AMENDMENT 39,204, 234, 277 Page 26 of 51 Attachment 1, Volume 17, Rev. 0, Page 164 of 471
Attachment 1, Volume 17, Rev. 0, Page 165 of 471 ITS 3.3.6 ITS 314 LIMITING CONDMTONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION Table 3.3,6-1 TABLE 4.3-2 (Continued~ ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS SR 3.3,6.7 TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE EUNlQTIONLU~i CHl1F CAMIRATION TEST TIES~ REQUIRED
- 9. Manual LSafety Injection (ECCS) NA. N.A. N.A. R1,34 Feedwater Isolation ReactorTrip (SI)
Containment Isolation- re T Phase "A"SeIS Function 4 ~~~Containment Purge and L3.3.2J Exhaust Isolation Auxiliaxy Feedwater Pumps Essential Service Water I~qctem
- b. Contanntp NA. N.A. N.A. .7 1,2,3,4 CnintIs aton-Function I ConainmentPugan Exhaust Isolation C. Contai ant isodion- N.A. N.A. N.A. -7 1,2,3,4 Function I Containment Purge and Exhaust Isolation
- d. Steam Li.ne Isolation N.A. N.A. Q R 1,2,3
- e. ContainmnentAir N.A. N.A. N.A. R 1,2,3,4 Recirculation Fan
- 10. CONTAINMENTAIR See rrS, RECIRCULATION FAN3.2
- a. Manual - ------- See Functional Unit 9-
- b. Automatic Actuation Logic N.A. N.A. 0 (2) NA. 1,2,3
- c. Containment Pressure -High S R SA (3) N.A. 1,2,3 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33b AMENDMENT 39, 204,234, 277 Page 9 of 29 Attachment 1, Volume 17, Rev. 0, Page 165 of 471
Attachment 1, Volume 17, Rev. 0, Page 166 of 471 (131) 3.3.2
~~~~~~ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT 3/4.3 INSTRUMENTATION TABLE 4.3-2 (ContinueI TA13LE NOTATION SR3..2.2, (2) Dealhtraned gccanlsaleese tes vrohr2as SR 3.3.2.3, SR 3.3.2.5 (3) Thez include exercising the trarnmit sMI'ha1 O~MNKALTE ya igete cuiop r Note ie propnprate s0 of te tas r COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3.34 AMENDMENTS9,2304, 277 Page 27 of 51 Attachment 1, Volume 17, Rev. 0, Page 166 of 471
Attachment 1, Volume 17, Rev. 0, Page 167 of 471 ITS 3.3.3 ITS
- 34. 3.3 HON!TOTNC TJstML~a=IOy nlaDTa¶IO MOKITORtS2 JvSRUMMTATOW L!M!TI,.G CoN.DITTON. FOR OP!Ns-ATIOM LCO 3.3.3 3.3.3.1 -The cadatomnt onsruIntatinorin hannels shown En Table AppL.;AfLMIf: As shown In Table 3.3-6.
ACTION A, BC, b. itch one or more radtacLort monitoring thannelm inoperable, cake the E,and G ACTION shown in TabLe 3.3.6. ACTIONS Note I c. The provisions of Specifications 13f.OA Ad13.0.4 are not applicable. SURVETLYANICE R=M_4"MEN SR Table 4.3.3.L Each radiation monitoring inscrumencation chinnet shall be Note demonstrated OPEIALE by the Rerformance of the CHAYNEIrrL CHECK, CHASMEL CALI5EATIONI and 19MFRT~f& oeain uigtemdsada the frequencies shown in Table 4.3.3 D. C. COOK - UNIT I .3/4 3.35' AMESDI)XVT S-0. 60 Page 4 of 16 Attachment 1, Volume 17, Rev. 0, Page 167 of 471
Attachment 1, Volume 17, Rev. 0, Page 168 of 471 ITS 3.3.6 ITS 3/4.3.3 tMOMMIT9A G 1RsraMEtM-ATION LIMI~TING CONMDT:ON FOR 0ORA1,TtIO4_ LCO 3.3.6 3.3.3.1 -The radia:Lon uaonicartng Lnsrrumentatlon chanmels shown Li Table APLCBIIY As shown inTable 3.3-6. ACTION A a. 'WLth a,radiacion monitoring channel alaxftrip uat m exceeding ACTION C b. ULch one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.346. StREL= TJIaE REWREI(EMTS SR Table Note 4.3.3.L Each radiation monitoring Luscr'umentation chinnai shall be demonstrated OPERABLE by the performance of the CI{AYNE-L CHtECKC. CHtASSEL CALIBRATION and PU C7M operations dcring the modes and at the frequencies s cwviin T be 431
- b. C. COOK - MI I ,'4 3-35 A!'DM 1T 0o GO Page l0oaf 29 Attachment 1, Volume 17, Rev. 0, Page 168 of 471
Attachment 1, Volume 17, Rev. 0, Page 169 of 471 CTS 3/4.3.3.1 T-P-AvFOROP!3LA~~~~~~~~~~~~~~~~~~~tovA. 3331 m dtawithin 4 ours orndeclaruentati channel rabTb. shnwn 3.3- she bne ccMABE waiath e chatpeLa
&zarm/ntoring inoperableakte APPLI O sshown In Table 33.36.
C. provisions of Spec fLcations 3.0.3 and 3. .4 are not pplicable. 4.3.3.1 Each radiation monit ring instcrumentatlon CInnel shalt be D. C. COOK - UI~T 1. 3/4 3.35 AflUDESMMS !5, 60 Page 1 of 12 Attachment 1, Volume 17, Rev. 0, Page 169 of 471
Attachment 1, Volume 17, Rev. 0, Page 170 of 471 ITS 3.3.3 ITS Table 3.3.3-1 RADIATION MLONITORING INSTRUKENrATION (OPERABILITY DASES DISCUSSED IN BASES sEcTION 3/4 3.3.1) mINimum CHANNLS TI OPE&ATIO MODE/INSTRUKENT UE TPT AIO
- 1. Modes 1, 2, 3 A. Area Monitors 10 P:: 1 Taiente
'~~~L.Upe 1 /A it 54R/hr 21A See S 3.3.6 and
*(VR.S 1101/1201) / CTS 3/4.3.3.1 B. Process Monitors
- i. Particuxlate Channelt I N/A a 2.52 pCi 20 See ITS 3.3.6 and
* (ERS 1301/1401) rrS 3.4.15 J ii. Noble Gas Channer 1 N/A a 4.4xl0j.Oj 20 (EMS 1305/1405) C C. Noble Gas Effluent Monitors
- i. Unit Vent Effluent Monitors
- a. Lov Range (VES 1505) ---- eethe ODCH)-------
- b. Mid Range (VRS 1507) 1 N/A N/A 22B c.- High Range (VRS 1509) 1 N/A N/A 22B ii. Steam Generator PORV
- a. MRA 1601 (Loop 1) 1 N/A N/A 22B See
- b. MRA 1602 (Loop 4) 1 N/A N/A 223 CTS 3/4.3.3.1I
- c. HRA 1701.(Loop 2) 11 N/A N/A. 22B
- d. NRA 1702 (Loop 3) 1 V/lA 22B iii. Gland Steam Condenser Vent Monitor
- a. Low Range (SRA 1805) ....... (see the ODCH).------
iv. Steam Jet Air Ejector Vent Monitors
- a. Low Range (SR& 1905) ....... (see the ODCK).------
- b. Kid Range (SRA, 1907) 1 N/A NIL 223
- c. High Range (SEA 1909) 1 N/A N/A 223 COOK NUTCLEAR.PLANT -UNIT 1 3/4 3.36 AMENDMENT NO. 094,Z44, .189 Page 5 of 16 Attachment 1, Volume 17, Rev. 0, Page 170 of 471
Attachment 1, Volume 17, Rev. 0, Page 171 of 471 ITS 3.3.6 ITS Table 3.3.6-1TAL33-333 RADIATION-MONITORIING INMTUK{ERTATION topERATLITY BASES DISCUSSED IN BASES-SEC-TTON 3/4 331 MINIMUALOALVAUA7 CHANNELS AM I TPL AUA OPERATION MODE/IISTRUKENT EPT A IO
- 1. Modes 1, 2, 3 & 4 A. Area Monitors Function 3.c L. 12 rContaitmeti Eh L.J31... S/ee4 L.4 Li. Contaivnent High Range 2 IObR/hr 2AI (ees/ rTS' (VRA 1310/1410) 3.3.3 B. Process Monitors Function 3.b i. a culate Ch8a~Ce 1 /a 2.52 vCi 20 3
Function 3.a ii be Gas Channe H/A a 4.4x10O .1 20 C. Noble Gas Effluent Monitors L. Unit Vent Effluent Monitors
- a. Low Range (VRS 1505) -... ... (see the OD{)-------
- b. Kid Rage (VPRS 1507) 1 N/A H/A, 22B
- e. High Range (VRS 1509) 1 H/A H/A, 22B ii. Steam Generator PORV
- a. RA 1601 (Loop 1) I N/A H/A 22B
- b. KRA 1602 '(Loop 4) 1 H/A H/A 223
- c. HRA 1701.(Loop 2) I- H/A li/A 22B
- d. MRA 1702 (Loop 3) 1 F/A V/A, 22B iii. Gland Steam Condenser Vent Monitor I SeeCTS 3/4.3.3.1
- a. 1A Range (SEA 1805) ------- (see the ODCH) I-------
iv. Steam Jet Air Ejector Venc Monitors
- a. Low Lange (SRA, 1905) -....... (see the ODCH) .......
- b. Kid Range (SRA 1907) 1 N/A H;/A 22B
- c. High Range (SR& 1909) 1 . N/A, H/A 223 COOK NUCLEAR PLONT -UNIT 1 3/4 3-36 AMMMDENT HO. 494, Z44, 189 Page 11 of 29 Attachment 1, Volume 17, Rev. 0, Page 171 of 471
Attachment 1, Volume 17, Rev. 0, Page 172 of 471 CTS 3/4.3.3.1 TABLE 3.3-6 RADIATION MONITORING INSTSX1KENTATIP1 (OPERABIITY BESES DISCUSSED IN BASES SECTION 3/4 3.3.1) owmw ~ ALARM TI
- 1. Hlod 2.,2, 3&4 A A. Aea Honitors; 1.. Upper Contaimtent 1 K/A gc 54 mR/hr 21
______ *(VRS 1101/1201) Li. Contai~ment High ftange .2 10R./hr N/A 22A See iTS3 (VA111410)333 B. Process Monitors See ITS 3.3.6
- i. Particulate Cha~nnel 2I N/A a 2.52 pCi 20 and UTS
* (ELBS 1301/1401) 3.4.15 )
3 Li. Noble Gas Channel 1 N/A a 4.4X1- s&LC 20 (ER.S 130511405) c C. blaGasE eto ors:
* ~~~b.id ne(VRS 1507) 1 N/A N/A C., H., Range (V.S 15O9) 2.IK/ 2
- a. 1601 (Loop 1) 1 A2B
- c. 1701.(Loop 2) 11 N/A N/A 22B
- d. 1702 (Loop 3) 1 N/L N/A 22B iii. Gl~and/StemCondenser Ve onitorj I
*I a.A~~,vR~ange (SRA 1805 ..... (see .......-..... A.
COOK NUCLEAR. PLANT -UNIT 1. 3/4 3-36 AMENDMENT NO.- 04. 444, .189 Page 2 of 12 Attachment 1, Volume 17, Rev. 0, Page 172 of 471
Attachment 1, Volume 17, Rev. 0, Page 173 of 471 ITS 3.4.15 ITS R.DAINMONITORING INSTRWHE9TATION (opERAILIIY BASES DISCUSSED IN BASES SECTIONU 3/4- 3.3.1). MINIMUM' 33 CHANNELS i LAMI TR.IP OPERATION-MODE/INSTRUKENT IPER&BL SET O ACIONi See rTS 3.3.6I and CTS
- 1. Modes 1, 2, 3 & 4 3/4.3.3.1)
A.. Area Monitors See ITS 3.3.6 L. Upper Containment 1 N/A a 54 nE/hr 21 and CTS I ii. VELS 1fb1n201) Contaianaent High-R.ange (yEA 1310/1410) 2 10lO/hr N/A 22A Se 33 3r 3/4.3.3.1) B. Process Monitors SeT LCO 3.4.15.b L. Patculate Ch~a,,n 1 N/A 2.52 pCi 20 B, C,D, E LCO 3.4,15.c ii. a 1 A a 4.4xl104& 20B, C, D.E C. Roble Gas EffluenTt Monitor; L. Unit Vent Effluent Monitors
- a. Low Range (VRS 1505) ------- (see the ODCH)-......
- b. Kid Range (VRS 1507) 1 U/A N/A 22B
- c. High Range (VR.S 1509) 1 U/A U/A 22B Li. Steam Generator P0EV
- a. MA 1601 (Loop 1) 1 N/A N/A 22B 1602 (Loop 4) 1 N/A N/A 22B SeeCTS b.
c. MBA MMA 170l.(Loop 2) 1- N/A U/A& 22B J 3/4.3.3.1
- d. MBA 1702 (Loop 3) 1 11/A Uf/A 22B iii. Gland Steam Condenser Vent MonitorI
- a. Low Range (SRA, 1805) -..... (see the ODCM) -------
iv. Steam Jet Air Ejector Vent Monitors
- a. Low Range (SRA, 1905) -....... (see the 0OCM) -------
- b. Kid Range (SRA 1907) 1 N/A U/A 22B
- c. High Range (SRA 1909) 1 N/A U/A. 22B COOK NUCLEAR PLANIT -UNIT 1 3/4 3-36 AKEN1DUENT NO. P44 Z44, 189 Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 173 of 471
Attachment 1, Volume 17, Rev. 0, Page 174 of 471 ITS 3.3.6 ITS 3/4 LIMTIG CONDITONS FOR OPERATION AND SURVEILLACE REQUIREMENTS 3/43 INSTRUMENTATION Table 3.3.6-1 TBE336finiud OPERATION MODB/INTRUMENT OPERAB ~ I~l~ Footnote (a) 2. e6 assemblies w.4thin containment TS A. TrainA Fany2/3 22C 22 L ~~~3/4.3.3.1 Function 3.c i. Containment N/A :5 54 mRlhr Radiation Chane VR101 Footnote (b) Function 3.b ii. Particulate Channe\ NIs 2.52 pCi 3 Function 3.a i.eN/44Xl p~ B. TrainEB~ 22 C Function 3.c i. Containment AejN A 5 54 mR/hr Radiation Channel Footnote (b) Function 3.b ~I. Particulate Chnn I 2.52 l.Ci
-401 Function 3.a iiNbr-wCanf,,-54 fq
- 3. mode (j~
A. Spent Fuel Storage 1 15 mR~ir < 15nmR/hr 21 See CTS1 (RRC-330) 3/4.3.3.1 314.3.3.1] COOKNUCLEAR PLANT-UNIT 1 Page 3/4 3-36a AMENDMENT 94, 44, 49, 279 Page 12 of 29 Attachment 1, Volume 17, Rev. 0, Page 174 of 471
Attachment 1, Volume 17, Rev. 0, Page 175 of 471 CTS 3/4.3.3.1 314 L rI~iING CONDMTONS FOR OPERATION AND SURVERIANCE REQUIREMENTS 3/4,3 INSTRUMENTATION TABLE 3.3-6 (Continued) RADIATION MONITORINGINT ME ATN (OPERAIBILIT BASES DISCUSSED IN BASES SECTION 3/4 3.3.f UM CHAN~is ALARM rrL. OQPEA NMD/NT MNT OPERABL SETPO F-IPiNI ACIlQ
- 2. Mode 6 A. Train A any2/3 22 channels
- i. Containment Arcea N/A :5 54 mR/hr Radiation Channel (VRS-l1101)
See ITS ii. Particulate Channel* N/A < 2.52 IiCi 3.3.6 (ERS-1301) iii. Noble Gas Channel' N/A
- 4.4x107 3AG (ERS-1305) cc B. Train B any 2/3 22 channels
- i. Containment Arca+ N/A :5 54 mR/hr Radiation Channel (VRS-1201) ii. Particulate Channel+ N/A < 2.52 j+/-Ci (ERS-1401) nii. Noble Gas ChanneIr N/A !54.4x10-'sn~
(ERS-1405) c
- 3. Mode "
A. SeFlStorage 1 :l5 5mR/hr :s 5 mR/hr 21 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-36a AMENDMENT P4, 134,in3, 279 Page 3 of 12 Attachment 1, Volume 17, Rev. 0, Page 175 of 471
Attachment 1, Volume 17, Rev. 0, Page 176 of 471 ITS 3.3.3 AMIOH 20 - VLrch the w=ber of obmeals Olfl*Z Less thu an, q~~ad br theSe UM11m= Chmanul Oporabls e rufn eucMply vich the OtIO ITS 3.4.1 5 ekqufreitx of SpetcfLtatlom 3.4.5.2.L ACXOV IL - Vfth the umber of cba~ulz MEWIZ luss tbat tei*Lzed by the 1Uuu~ChistoeLs Operable tequ-razen-. pezim ames u-ways -of the r See aov~oed aue, irLeth poccbale inLtocftg £ns=auwcfou ar. toast CTS -314.3.3.1 cute pet day. A=QV 2 - Ltch the uubar of chamhaLs OPELUAZL Less then, raquixe4 by' the AGUOV 22C- ~ alsOpurable :qufrenents1 couply vLthb tha A~LOK See reurmnso po~cte.399 ThsA=1L I jqtc ITS 3.3.6 ACUI(12A. MUt tae utubet of 01IUA312 Me1.as Less than. reg1uiryd by the ACTIONS A and C 2.. atther restoa'ethe. Luapezabie C.auuL~s) to COZL*-t!aat Wi~thicnj~i1Lays of thea event, or .1
- 2. zpa: ama submft a. I 4tiu3 la to the Cc=&,.stmu r~ t ta ACTIONS B,E, and G De __ia~o
.. within 14 days fatseLzg the 'avan 5ut See ITS thes ACCLos :allian the cause Of the Lmo hmi~cy and the 56,)
ACTIONS Note 1 3. :ecbaic&L EptcUfLcaLanu Sactlx=2 [3~I .0.4 M1a: £ppUcabLo.M6 ACUZON 223 VLrch 'tie ui~ha of OPMU3Z Chaimel Less th= ac gtured tY the stf-mf=w Chazieu OEUBLET rairivstut. L. eGthS. rasence tha £vaieU~2 Cbha:mLc) to OflhJUr ita fWtlig 7 days of the sevet, or
- 1. pvcspine a" sasmit A specul lapote to the, ca.seLou. psu:== e Ipecifteca:mioa .9. vlubli 24 days fatUevLag the 4veamc .aoiUA~LugLCT343 r CSe .3/31]
the atclou Woen, the cause o~f tcha loopeabLUty ad the plans and schedule fattscx Ct iTU e sys73cen tO 02MIS~L sames.
- 2. Mm the even: of an acoidout Unooring cadclosigcal telesses ftntsia:k the pplcane aeto Of RMLCMdzIg the aleet appoptCLACS PmatneCes) v:LtW&r 72 bonts.
- 4. Tchnu~caL Specf-fLeaclam. Iectalus 3.O.3 and 3.0.4 lot ApLfxa'bt*.
Mir. NXC~t.ALmPW
- MIT I 3/I 5.2? A2tMEMT 90 M( XZ3Q SEB Page 6 of 16 Attachment 1, Volume 17, Rev. 0, Page 176 of 471
Attachment 1, Volume 17, Rev. 0, Page 177 of 471 ITS 3.3.6 ITS hIU.Z 3.3.1 C~suomud)
£CTUQE ZO - ftch the ubainb of chea02=WiT Less duma tequtize by th, See MS KLM anhiLi OpmbL& naquifr:t Ly wM Lthth AtK 3.4.15 coqulreamancs of SpeccLErcation 3.4.64.1 AC~XO11.- VLth thes tu~br f ohas=u1s 0!T-"B Lass them aq*eLM~ by therSeCT Xinza=a CbhenaeLs Opesb&%e c:auLeaea:. peaiicu am suz.&7 of the /,3 souxtored ae~s* Vick poxuble mfbmto?1u 9=c:nuaea~ul a: least mae* per da.
ACTION C ACTION 22
- fxh the aubar of chamels 0?fl2 t!Lu:tE eaZ~b h xtuSzi= cham4eL oiparbl re urueu 1. 'vih the AC?09 ACTION I2A. TLth the uwmbar of 0OPELZZ CL=&LS leu thea ~:ti~frd! by the Kw~qLu-uCbaiel1 OMA.L3I. zeqdxruitst:
- 1. aithex restare the LaspazbUe Chs=&I(a) to OPEWIS g u See UTS viddha 7 days of the ay=%, 3.3.
- 2. VC*un. aA su A+/-: 99 =ta an1 la=&-
D *ff~-1 dys £ollavtag the Ovenrs'G ~-L See rITS the actcLou takn mhuse of the £iopmUab ,-, aud the Iotazz 5.6 jmdxchadu~~~o fee raltg~~ft the ingym to OTEWU BuSet fl.
- 3. ?ecbhdcal Sptc1f1fL~tc&:oSietlou2 3.0.3 aud 3.0.4 Ko;r AppucbLe See3.3 L.. atthe: ireesars the Lwzocxhuhe 0heueLcq) to OmiJL! Suarus WUUthA 7 daTX of she eveut or
- 1. 'Pv14vwe aL . 9.1.
Auu~ 4 to t~he. Co=ULGL puiant to See CTS Lp~eLficaulo 4.g.1 vftkhliz days golso~at the even: .outt.Luft 3/4.3.3.1)
,the scuba taken,th ca&se ofthe 4b~puL~~ aah ~
azd schedale tor restovin thek systen to ORUULZZ Status. S2.?U the even: at enm acclant ft*vLrug uadL~oloSgfcsi t&Leasee Waaceau the pceplamaie afternata sathed of souiuo:1zs the approprLace paxametar~s) vbAtha7 boaxs.
- 4. 'fechbucaL 9pec*cfftcabo Seclons 3.0.3 Ltd 3.0.4 Not AppLfxcebLs.
COOK NUCALK3 TLAW?
- V=i 1. 3/4 3-37 AMMI:IZXT 10. U. ,
Jg io8 1 Page 13 of 29 Attachment 1, Volume 17, Rev. 0, Page 177 of 471
Attachment 1, Volume 17, Rev. 0, Page 178 of 471 CTS 3/4.3.3.1 ACTQIO 20 *VLnh the mbare of chxmneb OPEUAI Less tha taqatzad br the, See RS ULU1UM Chmanls Oper~able rsmfmetawomly VLth the &OL - 3A 15 raqwUsmemuts of Sw~e~ation 2.4.S.1.. AC=0O IL* t the tuber of Mh~E W=OU less tma'eani4 IT the
)Cua=Chszgne sjIlrnqfmr.psi~m U~Uo h _
sanftoved &-rea M=Ltovftg 1nmut l~oabl .at heast A=OV22 21 [ACUO( W%tthe uuer of chaselsOfl OhL USUlZess thm raqudn4 bythe ps-zable :eqadfrunts, comly vi.hthe re femnsof Speeiflcaton, 3.0.o This ACUOU ts tat Cequ.Lttd fAa"=Oi 6~~uUZi: tha parfo~.un= of cuntaLmeaut Lqr.Witad last viae Cast. f . f 3.3.6I Kr-.=Ft 22+/-.. Vuh the utimbe of OPEUA3Z Channels Less vthAs r'rijafrl by tEa I.. eIther restore the Lapeztlel Chz=eL(s) to OPIMIS stect= .. wi~h.~n 7 days of the "Mr., or
- 2. 'epqame edX3ms0=haLSu ad a=_'x=w_ -;t rseeITS
- 3. Tecbai~cal 9pec.fteatI~ou Scctlons 3.0.2 =An3.0.4 Not Appy~cabla. Se3ITS ACTIOH 223w Ich 'tug uiMhe of a ch-4~ Less thur -ad by the 02=11ILS a ruepixmuns.
- a. Vasco"~i2tha eca~l chaznelcs) o 03 TX ttU=
WLWhi 7 days of gimut or
- 2. purayrseM gA. uu: SpeIFLl epert to the. shoa p~suan: to_
Sp Meoalc lon .9. vlubia 1.4 days elt~o the even: .outdliuro the Agtus tsicen Cas of .tha anbd the plans
=S schedule sto g the spteen t0 eso IZStatis.
32 ftZ the eu:ent Anof &mn SMziI.g loic reeae IUtiate the PC menad alum"au etod £ aLtLuti the apprapr~act p a. ercs) within 71 bo~s
- 4. TecimlcalL Spe 'catestln 8ect~ons 3.0.3 5 2.0.4 Not IppIlcxbLe.
CQ0.Z UUCLKL ?LAf= U' I. 3/4 2.2? AEMUMI 10. UeUt,ril 1 Page 4 of 12 Attachment 1, Volume 17, Rev. 0, Page 178 of 471
Attachment 1, Volume 17, Rev. 0, Page 179 of 471 ITS 3.4.15 ITS UAlZ- 3.3.6 Nngmcid) ACTIONS AcTIOv l0 - vuch tke nuaber of climeae Oapimu Loss tha* npeqtd br tha B, C, D, E ULaLtizs Cham~els Opeaib r.emaet esupy wLth tha ACMUO
- a. :qu~mantmsc of spaCf ala3.4.&*..
I [ACTZOV 11 -TLt teke Uber at cia=AU~CI LIZ las thaft resudd by the
~ ~ Wnor h~l Otrbareqdfranese. patfo Lrm suzeys of he See CTS' 3/4.3.3.1 A==OI 22 - V~th the &=bare of chanuals OPEULIRLE Leas than tequfred by the.
UtULYM=vakpinnants Chz~ts Opax-abl comply v~ct tha AMOITSee ITSI rqafrazens of Sptdificatiou 3.6.9, Z* Th~U .LCTX Ls Doc VaqMILfed 3.3.6 d~~~~~~ftyLo~lg pafr:eao the aaptdlau cs CaSest.
~=Oat 11L- T out e O th nubro cause Q@~ Lhes 1~ptab=1e alzd th ln * .
Cba=4Ls QF1WLXzaqdxc~~~~~~~ts: See M~~Se T 1.eichn=r estare'the LuaperabL~e C.auaeL~s) to OfaJS_ t!aaeus 7daybofthsCaer or wit~h-la
- 1. peprn etA gautrle &-I aeet spea h, Coi~ifsamupaustSeCT SefLcacloa 6.Z 4 Up~ foQlUls;t the eveseAs L~~~ See3/.3..1 ek mtOU toen the Cause of Che Lop.r %Ut7ic ed the PLeAMa5 edsokeduie fr 9g.e
- estodv te yentoO.IZ tt
- 3. TechnicaL Specif-Lce~atl Saction 3.0.3 enA 2.0.4 Vat AppLic3b3e.
withiA of && *age 7 days 3 ofa1 Attachment 1, Volume 17, Rev. 0, Page 179 of 471
Attachment 1, Volume 17, Rev. 0, Page 180 of 471 ITS 5.6 ITS TAZL3034o~tu?20 LCUON 10 - Vtih the utbe: of chnaz.ls OMAh3XZ Limda: this duxd br the. rSefIT, M1L4- CbD.nnBlI Operable aed~ufm~it. aMVlY vwhk the LO!0L 3.4.15 [ :e~~caufremancs of Spaciflcutio 3.4.8.1. ACUOV -3 Vimth this umbe of dbanuals OrfLIX lass than :SpLxsd b the r. T Uniu=a ChiuzneLs Opsarble, rveftaL-srn. pedm auau.-Tar~s o09 theeeT amoutead areA vith poavbla muicoxrig Ism-gmazatimu at least LW4.3.3.1) GulA Vet d&y. LCTOV 22 -VWth the uu~ba: of c=Aels flEU.-tl Less then taqudxsd by eteerr MfUt.luz ChazizG3. Optcsable :eqdframnet, caep4y vith the L=ON eeR raqfxeans o Spr-fict~ 3...This iACzo ts Do e 3.3.6 ducls th po-Jl*x= ofoqarument Lutagmtad leak ract cast. ACUOt ilL.. Vfth thre atmbec of OIU.L3Z2 Cbssis Less this vaqL-a4 by th. MA=41iMU= taqdze"Uts: ~~~~~~~~~~~~See ITS 3,33 56.6 ~~~~the actLen ttliau. the cause of the LuopmrbLUt7 anS the l
- 3. ?.cba~czi Speci-fteztinu Sacd~ons 3.0.3 an4 3.0.4. Wa.; Apcab~e Se3.3S ACUOH I2w Wich Ome u~ex of OP.UIZ~ Cbweij Less d= az :zedk %y the BLndww m.auaets GTEWU LTdxauf2=atz.
Z 1.. afthar reascae tha £aexashl. ~mu1cv) to m l sunez "OL3 Vitts 7das of fte gvast" or
- 1. TV are amudmdt IL Spectal. 14"ert to the. Comlbsjum P=Arit co See CTS1 Specfktento S.0.1 vi.thft L4 days fo*Usv~u$ the eves ucitUnig the Actift takes, Ce ~as of 'th U. AbLUCy and the PLaSL L3/4.3.3.1 and scheduLe for vestoring tb.. mystam to GILZZ= stacus.
- 2. MmZ the evant of an acoddent SYlmiagv ca-if logfcs taleasee isULac th. ru6e =alt& method of mitcorda; the apptoprLace Pa-rnera:(e) vitWhA I2 hours.
- 4. Techufcal. Bpecifficadion WU=on 3.0.3 and 3.0.4 NoC A4p~cl~c~.
Coos NUCLEAL ILMJ
- TU I . 3/1 3.37 A2MDIET 10. 1%ICMI. 168 Page 7 of 16 Attachment 1, Volume 17, Rev. 0, Page 180 of 471
Attachment 1, Volume 17, Rev. 0, Page 181 of 471 ITS 3.3.3 Table 3.3.3-1 TALL a.3-3. RADIATION'MONITTOTING TINSTRUMlENTATION SURVETILLNERQIFET SR 3.3.3.1 SR 3.3.3.3 CHANNEL CHASME CHANNE FUNCTIONAL APPLICABLE. OPERATION MODEMISTRUTMENT CHC TI-TEflM MODESL.
- 1. Hodes 1, 2, 3I~
See A. Area Monitors . CTS 314.3.3.1 L. Upper Containment 3' R 1, 2, 3. 4. (VRS 1101/1201) 10 IOA /40, B. PoesMntr (ER.S 1301/1401) C. Noble Gas Effluent Monitors L. Unit Vent Effluent Monitors5e
- a. Low R~ange (VR.S 1505) -....... (see the ODCM) --------- ITS 3.4.15
- b. M~idP-Range (VES 1507) S . N/A, 1, 2,.3, 4
- c. High Range (VP.S 1509) S R. N/A 1. 2, 3. 4 ii. Steam Generator P0EV
- a. ERA1601 (Loop 1) S* 1 C.T 3,243,43S
- b. MS.& 1602 (Loop 4) S'P 1. 2, 3,;4 . cCS3/...
- c. MM 1701 (Loop 2) S' L q 1, 2, 3,.4
- d. MEA 1702.-(Loop 3) S*' R . q 1, 2,3, 4 iii.'Gland Steam Condenser Vent Monitor
- a. Low Range (SEA 1805) -....... (see the ODCK)--------
iv. Steam Jet Air Ejector Vent MonitorsI
- a. Low Range (SRA 1905) - -....... (see the 0DCM) --..
b..-Mid Range (SRA 1907) S, . Q 1.2. 3,4
- a. High'Range (SEA 1909) S' L. N/A 1, 2. 3, 4 COOK NUCLEAR PLANT WIT 1 3/4 3-38 AMENDMENT NO. Q4, 144, 4I", 189 Page 7 of 16 Attachment 1, Volume 17, Rev. 0, Page 181 of 471
Attachment 1, Volume 17, Rev. 0, Page 182 of 471 CTS 3/4.3.3.1 RADTATI0 ON ITORInL INSTRUMMNATION SUV 1REouITERETS
,lNE QFERATION /INSE CHANNEL FN ALAPPLICABLE' I3A1;MD
- 1. Nodes ,2, 3 &4 L A. Ar Monitors Upper Containment S* 3. 1, 2, 3, 4 (VPSIIQJ201 Li. Contamnnent High Range S R. 1, 2, 3, 4 See rrS
~~~~~~~~~~
131OZ1410) (VRA 1.. Particul~ate Chamnel 3.R Q 1, 2, 3, 4 rSeeITrs3 (EEL. 1301(L401 pl3.4.1. C. b.e a 1602 (Loop 4)
*Iil Gan yem Condenser,5 Ve....t(sN t......
- a. M~Range -(VSK 1807) (se e D )L.
C. Righ g (VSA 1909) 3. 1 2 CONCLa. PLAN UNITp 1 3-8 S/4 AE NN1O ~,44, 2,3, 15 S. I j, 2# 3; Pae 5 f 1 Attachment 1, Volume 17, Rev. 0, Page 182 of 471
Attachment 1, Volume 17, Rev. 0, Page 183 of 471 ITS 3.4.15 M_0 RADIATION HOWITORIN INSTRUMENTATION SURVEITlNC RQEMIT COA.3 SR3.4.'15.1 SR3.4.15,4 SR341 CHANNZL CHANNEL CTO APPLICABLE' OPERATION MODE/1NSTRUMEN A SOO OE
- 1. Modes 1, 2, 3 & 4 See CTS 314.3.3.1)
A. Area Monitors L. Upper Containment 5 . 1, 2, 3, 4 (VRS 1101/1201) i.Containment High Range S 8. 1, 2, 3, 4 [ser (VRA 1310/1410). LCO 3.~l5~bB. Process Monitors24mnhL. C. Noble Gas Effluent Monitors
- 1. Unit Vent Effluient Monitors
- a. Low Range (VRS 1505) .------- (see the 00CM) --------
- b. Kid Range (VRS 1507) S . N/A 1, 2,.3, 4
- c. High Range (VRS 1509) .S* 8.N/ 1, 2, 3. 4 ii. Steam Generator POEV
- a. MRA.1601 (1oop 1) 8Q 1, 2, 3,4
- b. MRA 1602 (Loop 4) S' L. Q 1, 2,3. 4 SeeCTS c.MRA 1701 (Loop 2) S* L8. 1, 2, 3,.4: 3/4.3.3.1)
- d. 12A 1702.( p3) S. R q 1,2, 3, 4 ill.'Gland Steam Condenser Vent Monitor
- a. Low Range (SRA 1805) ........ (see the ODCK)---------
iv. Steam Jet Air Ejector Vent Monitors. I
- a. Low Range (SRA 1905) -------- (see the ODCM)-........
b..-Kid Range (SRA 1907) S 8. 1, 2,3, 4
- c. High Range (SRA 1909) 5* 8. N/A 1, 2, 3, 4 COOK NUCL.EAR. PLANT .UNIT 1 3/4 3-38 AMENDMENT NO. 44, 14, 1U, 18 9 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 183 of 471
Attachment 1, Volume 17, Rev. 0, Page 184 of 471 ITS 3.3.6 ITS Table 3.3.6-1 .- IAL(Contimied) RADIATION HONTITORINC fINTRUKETATION SURVEILLANCE RMMURDMENTrS SR 3.3.6.1 SR I=.3.6.86. CHA1RNE CHASNE FU NLAPPLICABLE OPERTONMDE/INSTRUKENT CHC UU ATO MOE-
- 2. Mode 6 A. Trait A E]Font a Function 3.c L. Containment Area 1-p 8-liii 65 Radiation Channel During movement of irradiated 3.
Functon Li.Particulate Channel ~1inmen conta6 Function 3.a iii. Noble Gas Channel 1- 8 6 E. Train ~~~~~~~~~~~~~~~~~ ~Footnote (a) Function 3.c L. Containment Area 1 -6 Radiation Channel Function 3.b Li. Particulate Channel 1- 8-Function 3.a iii. Noble Gas Channel 1 .6[j
- 3. Kode
- Ak. Spent Fuel Storage Q 3/4.3.3.1 Vwit-h fuel in storage pool or building 3431 COOK NUCLEAR PLANT - UNIT 1 3/4 3-38a AMEHDHDI NO. 44, "4, U44. 189 Page 14 of 29 Attachment 1, Volume 17, Rev. 0, Page 184 of 471
Attachment 1, Volume 17, Rev. 0, Page 185 of 471 CTS 3/4.3.3.1 JULEL 4.3.3 Lqontinued) RADIATION MOSIT0RING INSrRTJMENTATION SURVEILUANCE REOUIREKEMT CBAN~NEL CHAN1NEL ONLAPPLICABLE Op ZN MODUINSIMM
-201L 31ST MODES~~~~~~~~~~~~~~~~A.
- 2. Modse 6 See ruS A. 'Train A 6 33.6 L. Containment Area Q Radiation Channel (VRS 1101)
See ITS] (ERonainen13 ra1. 3.3.6an (VRS1201)~~~~~~~~~~~~~~~~~~~~~F 341 Mi. Noble Gas Channel S. B..S .. 5 (ERS 1405)
- 3. kiode**~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~..
L. ContainentoAreae R.Q**L. Li. Particulate SPage*Channel ofL1 Attachment 1, Volume 17, Rev. 0, Page 185 of 471
Attachment 1, Volume 17, Rev. 0, Page 186 of 471 ITS 3.4.15 ETS TABLE 4.3-3 (Continued) RADIATION MONITORING NTRMUKEFTATION SURVEILtANCE RWMURVMENTS . SR 3.4.1 5.1 SR 3.4.15.4 SR.412CO CHANNEL CHANNEL OCTIO APPLICABLE OPRTION, MODE /INSTRUmi HEC GAL S MODES~ZL.
- 2. Maode6
*A. Train A, 6 SeT L. Containment Area. S S. Q. 3.3.6 Radiation Channel (VRS 1101)
LCO 3.4.1 5.b Li. Particulate Channel S LCO 3.4.15.c iii. Woble Gas CnelS. L. Containment Area S* R See ITS Radiation channel 3.3.6 (VRS 1201) S*~~~~~~~~~~~~~~~~~~~~. LCO 3.4.15.b ii. Particulate Channel LCO3.4.15.c iii. Nble Gas Channel A. Spent Fuel Storage S B. Q SeeCTS) (RRPC-330) 3/4.3.3.1)
** ith fuel in storage pool or buldi Se34e33C1 COOK NUCLEAR. PLANT -UNIT 1 3/4 3-38a AMENDMENT No. 04, Z4~4 444 189 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 186 of 471
Attachment 1, Volume 17, Rev. 0, Page 187 of 471 CTS 3/4.3.3.2 INSTRUMENT rO' MOVABLE INORE DETECTORS LIMITING NITION FOR OPERATION 3.3.3.2 he movable incore detect on system shall be *OP LEWith:
- a. At least 75% of the dete tar thimbles,
- b. A minimum of 2 detector thimbles per core quadran ,and
- c. Sufficient movable dete trs, drive, and readout uipment to map these thimbles.
APPLICAB LITY: When the movable i care detection system-is usd for:
- a. Recalibratlon of the a aI flu x difference detec ian systems
- b. Monitoring the QUAD POWER TILT RATIO, or
- c. Measurement of FTMand ~ Q(ZSL
.&H ~ L ACTION:R1 With th movable incore detectic system inoperable, do nt use the system for the above applicable monita Ing or calibration functi ins.The provisions of Spec fications 3.0.3 and 3.0 4 are not applicable.
SURVEI LANCE Rt IREMENTS 4.3.3 2The movable incore de ection system shall be d onstrated OPERALE by no altzing each detector a tput to be used during i s use when requi ed for:
- Recalibratlon of th excore axial flux diffe nce detection system, or
- Monitoring the QUAD NTPOWER TILT RATIO, or
- c. Measurement of FA nd FQ 5')
D. C COOK4UNIT I S/4 349 Aednent No. 25 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 187 of 471
Attachment 1, Volume 17, Rev. 0, Page 188 of 471 CTS 3/4.3.3.3 INSTRL)MEATO SEISMIC I TIMNAION LIMITING ONDITION FOR OPERATION 3.3.3.3 The seismic monitoring I strumentation shown inTa Is 3.3-7 shall be OPRBE. APPLICA LITY: At all times. ACTION: A. With the number of OP BLE seismic monitoring I struments, less than required by Table 3.34., restore the inoper ble instru-ment(s) to OPERABLE st tus within 3D days. b With one or more seis c monitoring instruments inoperable for more than 30 days. pr are and submit a Special Reort to the Coummission pursuat t Specification 6.9.2 with n the nexct 10 days outlining th Ca se of the malfunction and the plans for restoring the instrm nt(s) to OPERABLE status. The provisions of Spe ifications 3.0.3 and 3.0. are not applicable. SURVE LLANCE REQUIREMENTS 4.3. .3.1 Each of the above cisruic monitoring instrun nts shall be dem strated OPERABLE by the eromnce of'the CHANNEL CECK. CHANNEL ClRAION and CHANNEL FUNVT OMAL TEST operations at t t frequencies sh inTable 4.3-4.
- 43. .3.2 Each of the above cismic monitoring Inst nts actuated during a s ismic event shall be res ored to OPERABLE status a da CHANNEL CAL BRATION performed within 24 hours following the so snuic event. Data sha I be-retrieved from actu ted instruments and analy ed to determine the meitude of the vibratory g und motion. A Special R ort shall be pro-pa and submitted to the C itsion pursuant to Spe fication 6.g.2 within 10 ays describing the magni ude, frequency spectrum d resultant effect.
up nfacility features imPo ant to safety. 0.C. COOK-UNIT 1 314 3-40 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 188 of 471
Attachment 1, Volume 17, Rev. 0, Page 189 of 471 CTS 3/4.3.3.3 TABLJ 3.3.7 5EISMIC MOMIOR! G I?4STRUM4EVITATTON, MINIMUMJ~ MEASUREMENT INSTRUMENTS INSTP4F7 NTS AND SESOR LOCATIONS RANGE OPERARLE
- 1. 5-. OG MOTIC~.&TRIAXIAL AELEROGRAPHIS a Reactor Pit FLoor 0.1 g 1 b Top of Crane Wall O.d q I
- Free field 0.1 q I 2.EK RECORDING CCELEROGRAPIIS
- Containment Spring Li 0-2 g
- Diesel Generator Room Floor 0.2 g1 C. Spent Fuel Pool 0.2 g1 C. COOK-UNIT 1 3/4 3-41 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 189 of 471
Attachment 1, Volume 17, Rev. 0, Page 190 of 471 CTS 3/4.3.3.3 MIX 1u4 SES C Tn-ORuI INSMWHZNAT OlSa~LAC OIOMAL INUMM L CUQ-MLKWTIOI 5
- a. Rate or Pit Fnoor 1.T History Iecorder K3
- 2. LuaLcSiUe SA3.1
- b. Top f Craa. Wall
- 1. U.Hstory Rerorder II
- a. Fr. Field
- 1. asHistoly Recorde 5 f K
- 2. Laden Trigger t KA,
- 2. UfKK~OaCKfORlS
- a. aim~CSprang LUn K1
- b. i e.Generator loom floor 3. KA COOTNCLA PUNT - UNIT 1. 3/4.3.42 NO.J7,144 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 190 of 471
, Volume 17, Rev. 0, Page 191 of 471 CTS 3/4.3.3.4 Mr-rM~~::AL rNSTRL'MENTATION LU(IT G COMITT10 FOR OPEMAT!
3.3.3 4 The meteorological son toting Instrumentatton ch is shown In Table 3.36 ishall be OPEABLE. API I I-TY: At. all tLImeS. Vith the number of 0 E1S3e teaorlogical Wm rIng cbsMMels less than required b Table 3.3-8, suspend all rlease,of Saseous radioactive material from the vadvaste gait deot tanks until the inoperable channel(S ia restored to OVlA8LI tatus.
- b. WJith one or more re iired meteorological amoi ring channls inoperable for mere' than 7 days. prepare an a t a Special.
Report to the CoaiM sion pursuant to Specific ion 6.9.1 vL Wn the next 10 days ou lininS the cause of the function and the
-plans tat 'resta~xitt the thvrmb%(*) tosats C. The provisions of S scification~ss3,O.3 and 3. .4ar not L ILIAMC REOuIrEmnnfs
- 4. .3.4 lath cot t~he above sOTAologcal monUtongIM trunentation Cb nels shall be demonstra d OPZRABL by the perfe, e of the CHWUNL CH CC &and CHAKNEL CALUARATI operations at the treque ea shown in Table COOK VwN'I C.c 3/4 3.43 Page 1 of 6 , Volume 17, Rev. 0, Page 191 of 471
Attachment 1, Volume 17, Rev. 0, Page 192 of 471 CTS 3/4.3.3.4 LE 3.3,8 KETEOROLOGICA K ITORfNO INSTRUMNUTATION INSTRUMENT H1N1HUM KINlKM I~~sTRUMENT ~~~LOCA ION ACCURACY OPRAL
- 1. WIfND SP' Any 1/3 channels
- a. Prima at Backup IKetaotaogio~c Tower, Nominal Kiev. 10 m (1), c2)
- b. Prima Ktetorologtcal Towev. N sinal Elev. 60 m ULM,2
- 2. WMNDI CTION n 1./3 0 channels
- a. PrC or ~backup Hetsorololic Tower., Routual Kiev. 10 +/-
- b. P1 ry Mateozolosical Tower. oInal Kiev. 6O a +3
- 3. AIR? R TI B(for 60Oato 1 deltaT)R.
A. PC Cy Heteorolosical Tower, Nomi ali. 10 a 0.15 C
- b. PrC Myeteorological Tower. NomirAl Kiev. 60 a 0.150C (i) SVtar Lug speed of anmmter a U be $cI mph.
(2)+/-tIt or 0.5 mph, whichever i$ roster. (3) VIW delta T. nformation mailable, alps, thata, (a d deviation of the
'hot zontal. wind direction an teftivwd from erenypoedures) Lo to be used for
- 0. C:. U~NI of a3tai4 3." Amndmnt No. 127 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 192 of 471
Attachment 1, Volume 17, Rev. 0, Page 193 of 471 CTS 3/4.3.3.4 MiLt .3.-5 METMOLOC!CAL MONIT41 IR NSTRUMEN'TATlO SuRVEILIANCE UIKELRLE~NTS COMM ~~~~EL ________ tC ____~~~~C RATION 1.vIIISP ED
- a. fio b.. ie n&2 Eluv. 10. a Sl1Kav. 60uaI SA I
- 2. 'WIND 0 RlCTI§N
- a. gotal Elev. 10 a 0 S
- b. No bAl EloY. 60. 0
- 3. AIR T ERATURE! DELTA T a.N:nal Clv 1.0 a $A R
- b. N ztnal t1.v. 60.a 0 SA D. C. C - IUNT 1 3/4 3.45 Amen nt No. 127 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 193 of 471
Attachment 1, Volume 17, Rev. 0, Page 194 of 471 ITS 3.3.4 134 LDUMfIG CONDMONS FOR OPRAT1N AMDLRMVEHIANCEI EIXHEMEMT 314.3 RIMTUNMEaAn1ON L~fMCOMOFOR 1 LCO 3.3.4 3.3.35 The remote sulrtdown moioigIntuetzincanls LAho T .3- sha be, OPERABLE~wih vmfiout o~us WCon I APPUCABUM., MODES 1,2m-d 3. ACTIONS A and B L. With the nwnber of OPEIRADLE remote hutdown =onitorg channels les than requilred by Table 3.3-9, eliter restoe fte inoperable channel to OPERABLE status uddf 30 days, be InHOT SHUIDOWN within the next 12 hours. ACTIONS Note 1 b. The provisions of Specfidadon3.0.4 ame ot applicable. SR 3.3.4.1, 4j.3.3S Each remote shutdown monitoring Instrumnaton channel shall be demonstrated OPERABLE by SR 3.3.4.2 parforamace of the CEANNEL C~ECL and CHAX~NEL CALIBRAT1ON operations at the frequecides shown inTable 4.3-6. COOK(NUCLEAR PLANT-UNIT I Page /4 346 AMENDMENT 26; Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 194 of 471
TABLE 3. 9g REMOTE SHWJTOOWN MONITORING INSTRIMENTATION FWASUREPM ~CHANNELS INSTRUMENT LOAT ON RANGE OPERABLE
- 1. Reactor Tr pBreaker Hot Shutd Panel In OPEN-CLOSE 1/trip breaker Indicati tinit No. Control Room
- 2. Pressuri Pressure Hot Shut omPanel in 1700-2500 psig 1 Un It No. ? Control Room
- 3. PressurIze Level Hot Shu donPanel In 0-100% of ~
Unit No 2 Control Room Instrument s a
- 4. Steam ator Pressure Hot S tdown Panel in 0-1200 Psg 1/steam generator Unit .2 Control Roo
- 5. Stea Gnrtor Level Hot S tdown Panel In 0-lOMt wid range 1/steam generator unit .2 Control Room instrumient span , Volume 17, Rev. 0, Page 195 of 471 Attachment 1, Volume 17, Rev. 0, Page 195 of 471 (D
h ~~~~~~~~ 0)
Attachment 1, Volume 17, Rev. 0, Page 196 of 471 ITS 3.3.4 ITS
- 3. 101SIi.: ZaY.I L.1TRN 4.Ga~~~~SR3.3or1 Ste RL3l.4K
- 5. RSatO Geao ftuazer 24mnh Inacat~~~~~~~~~
COKUCA punT UN=IT 1. 3/4 3.48 AKNDKOH NOIO~iPI,1*44 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 196 of 471
Attachment 1, Volume 17, Rev. 0, Page 197 of 471 CTS 3/4.3.3.5.1 flPflI SEUTDOV INSTlUMRA O COND L12~TIG LO OR OPERATIO The Appe 41z ILremote shutdoin in truentation channels ah In Table 3.3-9A be 01 Evth an opposite unIt pove: supply available a~n wth read out capab2 ty at thes U! panels.. FPLICAB MODES 1. 2. and 3 ACTION A. U ithe number of OFERABL Ippendix R remota shutdavn Wri~tnL~g channel. La a than required by Table 3.3-9A., either restore the Ittopera~bLe ch~annel to 0 U2 status within 30 yor be La NOT IHMOV'N tWu the neat 11 bi a
- b. Vr the oppoaite unit pawve supply not available, revao the power eupply t, available status within days, or provide, fire va thas Ln the effected asccand cestore the Lnope abl channel to OPERABL tatus Withi:L thek net 6 days, or be La NOT STA I t~ihin the nezt1 hou &adSO? 5EUTDOV v hn the following 24 h 1.#
aeprovisions of Specific cdon 3.0.4 act not apple.~ La. suu~zzu E RIQ uUIREMT R.S 4.3.3.5.1 Each Appendix I remt a down monitoring instrize tation channel shall be deOnsetrst 4 OPERABLE by perfrac of the CUAHNL CRECK and AZELCALIU.A!?ION operattona at cha frequencica shn inTable 4.3-GA. D. C. K.UNIT 1 3/4 3-48a Amendment No. 131 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 197 of 471
fISSTIKI~~~~~~lNT ~LOCATION EAH2ff313
- 1. Steamr Ceneretror 1 UZI Cabinet I anE @400% wide wenge a" an oeh Ul end I ."MeI 181 Cabinet 4 instruMent saps cabinet for eme stem geertatec
- 2. steam Cenerutiwra 2 Ll aie n -01 lornea fl A
- 7. Reactor Ltot.4oopront*pa Colmt abne fe m stamtuGenertor WIp
- Cabinet 4 and 5th1" Vst AaTepeatres (ot LI! Cabinet 5 cablaetfo a steam SaftentoI COO NUCeaR lN UNIT 1 311.Cbloo 348 wWmend30ent No. 13 c a4 3 free 4 dabl~~~~~~~~~~~~~~~t for 64A~~~~~~C (0 -~~~~~~~~~~~~~~~
CD~~ ~ ~~S o"a-coat10P S aie a -0rO n40 4 Tespecetwe UM (Cotd) Cabinet S~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~T , Volume 17, Rev. 0, Page 198 of 471 Attachment 1, Volume 17, Rev. 0, Page 198 of 471
P.resur[zer Leve LSI Cabinet 3 0-lO0t of1 instrument spen
- 10. Reactor Coolant SYstem Preesure LSI Cabinet 3 0-3000 psigI
- 11. Ch-qrging Cross-flow B3tween Corridor 0.150 gU Units I Kiev. 5374 2 . Source Range neutron LTCbnt411xt p
CDOK NUCLEAR PLANT - UNIT £ 31'. 3-48c. , Volume 17, Rev. 0, Page 199 of 471 Attachment 1, Volume 17, Rev. 0, Page 199 of 471 C/) (D~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~(I (0 (D000
aid 3 3aw1 133 C~~I~wTAI 43-
- 3. Sloan Curioestlo I 351 Cabinet I mand and is Vresuur* 1~~53 Cabirnet 4
- 2. Steam Cnaatinrstu 2 LN 2A Ibne a" nep Mtel Mle. Su7*et
- 12. steamc Ieetw(-3 miangeeUure. 1.3 Cabtst A a"US
.OStealm Crem-Flew be...Unt 3. iuwtrimetemw4o sehMtIsad2 U urenac UIel
-~~~~~~~ 6 eemactoi coolanterwAO caamSL wt ii CainetaUg COW CD W(?'~~~~~~Tonjivatw UNT (lNot CabIva 3-a SWS D 3 0~~~~~~~7 ecltcoatl"LtCbnt4a 0~~~~~~~~~2144rt S Cbis p(od B. Cablaiet A "and ,
Reactor LSICoolant R~~~~~~~~~~~~0 , Volume 17, Rev. 0, Page 200 of 471 Attachment 1, Volume 17, Rev. 0, Page 200 of 471
Attachment 1, Volume 17, Rev. 0, Page 201 of 471 This page intentionally left-blank. D. C. COOK UNIT 1 3/4 3-~ tq w.T NO.E0a120 Attachment 1, Volume 17, Rev. 0, Page 201 of 471
Attachment 1, Volume 17, Rev. 0, Page 202 of 471 This page incentionally left blank. D. C. COOK UNThIT 3. 3/4 3-50 Ma~ENDKENT NO. 120 Attachment 1, Volume 17, Rev. 0, Page 202 of 471
Attachment 1, Volume 17, Rev. 0, Page 203 of 471 3/4 LMiTnh GCONDITIONS FOR OPERATIN AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMYENTATION Page Intentionally Deleted, COOK NUCLEAR PLANT-UNTT 1 Page 314 3-51 AMENDMENT P, 140, 208 Attachment 1, Volume 17, Rev. 0, Page 203 of 471
Attachment 1, Volume 17, Rev. 0, Page 204 of 471 3/4 LEYM[TNG CONDITONS FOR OPERATIN AND SUIkVEILLANCE REQUIREMENTS 3/4.3 INSTRU"MENTATIN, Page Intentionally Deleted COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-52 AMENDMENT 29,140, 208 Attachment 1, Volume 17, Rev. 0, Page 204 of 471
Attachment 1, Volume 17, Rev. 0, Page 205 of 471 314 LIvMiNG CONDITIONS FOR OPERATION AND SUAWEELLANCE REQUIREMENTS 3/4.3 INSTRUM*ENTAT1ON TABLE 3.3-1 Table Intentionally Deleted COOK NUCLEAR PLANT-UNIT 1 Page 314 3-53 AMENDMENT;*4~,14US, 208 Attachment 1, Volume 17, Rev. 0, Page 205 of 471
Attachment 1, Volume 17, Rev. 0, Page 206 of 471 ITS 3.3.3 ITS(I) 314 LUUTIG CONDMTONS FOR OPEATION AMDSRVEMAMCEEQMU EMO [s 3)4.3 ]INSI1UMEIATIoN LIMTING CONDITI[ON FOR OPFERATION LCO 3.3,3 3.3.3.8 The post-accident monktorhiq Wmnsuentation chwnnls shown in Table 3.3.41 shall, be OPERABLE. A jjJ : MODES 1. 2, mnd 3.poeAC AMON~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~. ACTIONS A and C ft. With the nmunber of OPERABLE post-acciden monitorla chmnnls less than required by TWA. 3.3-tL(emce Item 8), elthe restore: die !cable chande to OPERABLE status within3 ACTIONS B, E, Fand G ore - 0'H d ooedR le Ato ACTION A b. With gme vamber of OPELABLE post-acc~ient monitorig dihnnel one less nam recTired byM. Table 3.3-11, item B,Refueftn Water Storage Tank Wote Level L I. Either restorc Mhein Iblchannel to OPERABLE statu WUthn ab iat ACTION B -Lews HOT SHUTDOWN withi, Ow next 12 hours. anddooedR ie cto . . Add proposed ACT rCad Fct.o uiON ACTIONS Note I C. The provisiouns of Specification 3.0.4 are not applicable. SR Table Note 4.3.3.8 Each poet-accident monitoring intuetaincmnel shall be demonstrated OPERABLE by performance Of the CHANNEL CHECK antl CHANNEL CALIBRATION operation at the frequencies show inTable 4.3-7. COOK NUCLEAR PLANT4JNIT 1 Poge 3)4 3-54 ADMEK) 49,1U,I" 232 Page 1 ofl16 Attachment 1, Volume 17, Rev. 0, Page 206 of 471
ITS Table 3.3.3-1 UTTOUNG
=.Accrpmr IN MmKtNIH19 8 IL. Goutaiumant true2.
3 21, seact.: CooaUsOtetIsoqeraeure- T~ (VI". Range) 2 4 3. Reactor Coolant Inlet Ieus ac li"T (11dm Raws~) 2 5 4. Reastot Coolant ?esr~d a 2 12 S. Presaaurier Vats: UnIL 2 2, 6. Stem LinA rreasur. 2 Oea.Geerto 22 7. Steam GIOeneater Water Ll-vl Nact leaPI Whofses CeamratorM. 24 5. lefOGeUO V~ar. StrmTn Uste: leTGl 2 Q
- 19. !O.~~~~~~~~~~~~~~~Id
~temConersacr*
25 11. BaetacS c~oolat ys~t"mSboln KergiU NOUlto: Lf"l 15,6,1,185. nera rassoueaCor-- IAt zOwXccupee 6 15. lealvo: C olant I InyEuakm men Upatas~ tba fe4dvAGr Slavdate ob2.ulOuttrofa3 161,81*0 LWMW omt, oLge Poe-tinnPlmilmal pe tre ave . 4LWa,)CelDOUSO 6260 Reactor c"Md propsedFuntions 9 13 14, 2t21 23,26,271an12 (27n CD LVI 19!~~~~~~~~~ese N.) CI)~~~~1 o~ ~~~ .cnsmn-ae Footnote l~ml (d Manuals screw .im Owwrtm be. uwA guar s a substitte foc the am auxiliar , Volume 17, Rev. 0, Page 207 of 471 Attachment 1, Volume 17, Rev. 0, Page 207 of 471
- 0) lwmecme Iomt 03~~'edte
Attachment 1, Volume 17, Rev. 0, Page 208 of 471 ITS 3.3.3 ITS D Table 3.3,3-1 SR 3.3.3.1 SR 3,3~3.3 3 a. R&aser coolant outlet ?eupratura. 4 ,. MOWi~ C..laht Zwl1. Teupereture. 5 4. UiW4Coolan U r-id isg 12 S. ftiasssiat VateI lays) 2 6. Items U"n Pressure 22 7. Iteas @emiestev VAter Lmwl.Iarrow 3Ange 24 1 Mvt I 19 lOAM"amly FedAaer now MA2 onh . 25 U1.11aacTs CeesAs SYSteM NUObeeeft 6 ~~12. Pa:.esla Xsasure trachiMUMSysNe CUeats tcheasellw ~~ai 7 lI.Cento 24 monthsLeel 16,1617,1'1H1mov %%memilpes tCaen theresesples) mN ue e ein 6 16.eacte Cooan tWwI~ry rvctxsystlm eeev siueettylLA i"~3.~ ~ ~ ~ ~ ~ ~ ~ ~~~ae f1 Attachment 1, Volume 17, Rev. 0, Page 208 of 471
Attachment 1, Volume 17, Rev. 0, Page 209 of 471 CTS 3/4.3.3.9 3.3.3.9
- explosive gSU monito nginstrumentation c UshowIn Lin Table 3.3. shall, be OPERA7U vi tbair alarmtrip satpo st to no ensue h the limits of Specif tin3.11.2.1 are not a eded.
6zptl~ As shown Lu Table .3-12.
. ith an explosive gas taring intrumentatio hanneil alarm/trip setpolut Ie conservative than the apecification, dealara Ihna inoperable taethe ACTION shown in Table 3.3-12.
- b. pth lass than the . number of explosive ax Umontoring instrumentation chann OPIMALEW take the AC O~Shown in Table 3.3-12. Restore th parable instruueutatio to OPERABIS status within 30 days. If unsuccessful,eprep; and submit a SPECIA REPORXT to the asion purtuant to S iftc~atiou 6.9.1 to explain why this arabilfty was not cor eted In a timely R manner.
- c. The provisions of Spa i Latos 3.0.3 and 3.0 4 are not applicable.
4.3.3.9 Each explosive gsm taring instrumentation W be Ishl demons ated OPERALS bygato eof the CLARMNECHE ,CiNE CALIER ION, .and analog MUNC=0WAL TEST at the rquencies; shown in Tablo 4. 348. COOK c~PLANT-UNIITlI 3/4 3-57 M NO.69"I54",189 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 209 of 471
Attachment 1, Volume 17, Rev. 0, Page 210 of 471 CTS 3/4.3.3.9 Is
- 1. Waste Gas Holdup System Explosiv Gas Koixitoring
- a. Hydrau enMonitor 12* 3 b., Oxyg Moniitor 224 (QC- 400, QC4370) a ts~~~~~~~~~~~~~~~~~~~~.
Action 23 Wth the nuwber of IhesOPERABLE less than equired by the Minimum Channels OP . requirement, operati of this system may continue for up to 14 days, provided grab amie are taken and analyzed every '12ors Action 24 With the number of c el OPERABLE one less, required by the Kiniuma Channels0eRAL requirement, ope atiou of this system nay continua f up to 30 days. With2 channels Inoperable, operation f this system nay can ufor up to 30 4ays, provided grab a pies are taken and a azd every 12 hours.
**Dur. vaste gas holdup syst aoperation.
I£h~ ate gas holdup system explosive gas monitoni system may be mop rable for up to 160 Gasan a one-time basis £r t~he purpose of
*rep acing one oxygen nonito During this time, gr samples for oxy en are to be taken and nayed'every 12 hours.
COOK CLA.PLANT -WUIT 1 3/4 3-58 ANUMMS0T 0.04 49 V4. 189 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 210 of 471
Attachment 1, Volume 17, Rev. 0, Page 211 of 471 CTS 3/4.3.3.9
- 1. Vaste G s Holdup System kploS GaCasMouitorint system IS. By MonKnitor D K Q(1 *
- b. an Monitor D Q(2) *
(Q 1400, QC-370") (1) The CAUEMUTIO1 bals Incle the us* of a 4asa samples con: annnominal:
- a. Ylum percent hydra n balance nitrogen.
b*our Volume percent hydr enbalance nitrogen. (2) The CAELCALIMRTION 1includ, the use of a Ib .4 as samples Coll aignominal:
- a. volume percent oxyg n balance nitrogen.an
- b. Fo volume percent ozy egbalance nitrogen.
- inz waste gas holdup Sy tuoperation.
asa surveillances are t required during the 16 -day period in Leh this monitor is be replaced. COOK CEA PUIT - MUNT 1 3/4 3-59 AMIZWHNT NO. 944 138. 16, 169 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 211 of 471
Attachment 1, Volume 17, Rev. 0, Page 212 of 471 ITS 3.4.4 ITS 3 /4.4 R1EACTOR CO22LiI sysT( 3L4.4 2.1 tRACTOR 22216ar LOOPS AND COOLANTr CIRCULATION STARTUP AND PMM~ OPEIATIONI LIMITr110 CONDITION FOR OPUPATION LCO 3.4.4 3.4.1.1 All reactor coolant loops shall beLupeto. APPLICABILITY: MOVRS I and 2 A. ACTION: ACTION A 'With lose than the aboVe ~*~r idrseocoat loops La operation, be in at learnt HOT STANDBY VLCh~nLQhoir SURVEILLANCE UMI~fRLIME SR 3.4.4.1 4.4.1.1 The above reouired TrActor coolant loops shall b6 v'ertifmd to be in operation sn'croulatIfig reactor clAt:aclealsernce oar 12 hours.LA D. C. COO.K UNIT 1 3/4 4.1 Amendment No. 76 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 212 of 471
Attachment 1, Volume 17, Rev. 0, Page 213 of 471 ITS 3.4.5 ITS iD HOITSTAf ND!I O 1IOKRTO LCO 3.4.5 3.4.1.2 a. The reactor coolant loops listed below sball, be OPEABLE and in opetation as) required by items b. o., and 6: SC?00 a ts, associated maenerator actr tn cooln
- 2. 1A to Coolat lop2adits associate stam;nerator eatot cooatp ,L.
3.. eta: Coolant Loop 3and its seasoci detem gUAnrator reactor coolant
- 4. atrcleant 4 and its 4Osaso edsteam genetito tOCo cooln Pump.
- b. At tose: tw of the above coolant 1oops shall be OPERASLE and
- c. apaleae of eodfwtheaboeoo tc salle.lAI*n
- 4. At 1. t three of the a! coolant loops Il be OPEWJLE end operation Aboe.2 (Slar to T hia .
Sp 4fiction 3.3.2.1I abe 3.3-3 for itrumentation nts. - TUZ Y-ZZT NODEI 3 LCO 3.45
- Al ractor cooMant pmps a b de rited for up to I. hour provided (l Note ~ no operatins are permtte that wud cas iaiton f-he oacr coolant
- items b ron coo~crftcton**. end (2) acre outlet temperature La maintained a least 10'F below saturation temperature. Ad roposed LCO Note part c
**For pUrpo 5 of this specifics adtion of vater am the R.WST does not conscti tea dilution activ pr dad the boron cccntration in the RWST is eaterdthan or equal etemn~ required specification D. C. COOK - UNIT 1 3/4 442 AMKMM? iso.7 120 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 213 of 471
Attachment 1, Volume 17, Rev. 0, Page 214 of 471 ITS 3.4.5 ITS zqzaCTft COLN ACTION A a~~. V7Leh etaxthan the oe reqoira reactorcoolantb loops~ Required immediately 2 s0ui Cth require to loops P*L st addusedRui ActioLns. n ACTION D b. ULth noratrcoat opL prtoan. 'loops roIl~ Required Vi~~h~a Add propospd RequireAddActionsed.SR a.d.5.3-NOT aprco,- b lhass uhae toa ube OfRA operpetin 7 layt by0o Ziia~t ca~sc bralw a~p~.d abovd rniaed paequre number of cap c~zcq1I~t~nztiico: ootnt a tu o nceapaer oolant Sysa C.:, ACTION D
- do.j~oe ofchino raecfctr doola lddopion operacter rouspend allTdo not co tica era dltions aLc. ptved cthe i baron COUCancr i1of
[la a nteL3 a~SA~sgreterthan toratua the reqinmmrqredeolntlo b o opercicton.
- 0. C.WIT
- COOK 1 ---/- 4.2* . propse FAeqiEDfre Acton7,
;M~~rTTAMZ &M=C=S ed SR 3.4.5 Page32NofE Attachment 1, Volume 17, Rev. 0, Page 214 of 471
Attachment 1, Volume 17, Rev. 0, Page 215 of 471 ITS 3.4.6 ITS 3/4 LIdMTIG COMMITONS FOR OPERATION AND SURVEILLANCE REQUMIEMENTS 314A REACTOR COOLANT SYSEM LIMITNG COMMITON FOR OPERATION LCO 3.4.6 3.4.1.3 a. Te coolan loops, listed below shall be OPERABLE and in operation as required by items b and c: I. Reactor Cooban Loop I its associated stam. sen rnd reato coolant PUMP.,
- 2. Reactor Coolant Loop 2 its assciate steam ad rtactor coolant u
- 3. Reactor Coolant Lopand its associated steam reator coolant setrand pump.*
- 4. Reactor Coolwan 4 and Its associated adeam g rand reactor coolant pump.*
Residual Heatx East. Residual Heat alWest, LCO3..6 hour*. per8 h.oAnt lem woo thesialboea caoolawlshll be OPRBL rn at e remlove frm COOK NUCLEAR PL~fl~.UNIT I Page314 43am poitionTo b83W,-V rod12 C. dwabov A!5'~hrv recwpwlao o tw aw be sd In"of Page 4i Attachment 1, Volume 17, Rev. 0, Page 215 of 471
Attachment 1, Volume 17, Rev. 0, Page 216 of 471 ITS 3.4.6 ITS 314 LIMITING CONDITONS FOR OPERATION ANT) SURVEILLANCE REQUIREMENTS 314.4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATIN(Continued) ACTION: rcinA2Nt ACTIONS A and B a. Wit catathabvreuedcoolant loops OPERABLE, immediately iiit crrec-tiv e action to return the required loops to OPERABLE s ats as soon as possible: L be in COLD SHIUTDOWN withinLMours-
- b. W thanthe numbe of opleat coolantloops reqir44 Add aosed ro ResuoredAtn .2ad32 ACTION B C. With no coolant loo In operation, suspend l operations v mgw ar du i n o concentration of the Reactor Coolant Syte n"and Immediately initiate corrective L.
action to return the required coolant loop to operaton. SURVEILLANCE REOQUtIEMgNTS 1441.3.1 A 6 required residual beat wflo~)shall be dzrieP ABEperSpcfaioj SR 3.4.6.3 4.4. 1.3.2 The required reactor coolant pump(s), lif not inov- ronShall be determined to be OPERABLE onceg 7 days byven jni correct breakcer aliounen ndicndated pwer availabil SR 3.4.6.2 4.4.1.3.3. The Vired steam enerator(s) shall be determined OPERABLE by ve*iyi4 secondary side level SR 3.4.6.1 4.4.1.3.4 At least one coolant loop shall be verified to be inoperationland cirecul reactor coolan aleast L. once per 12 hours. Forurpof hisspeIfcaion adi of water frin th WST not constituteaI diuin vt rvdd the boon netrto in the RWSTi e than or equal to theL2 mlii requlrebyspecificadi .I2.8.b.2.I COOK NUCLEAR PLANT-UNIT I Page 314 4-3a AMENDMENT i, MO, 224 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 216 of 471
Attachment 1, Volume 17, Rev. 0, Page 217 of 471 ITS 3.4.7 MTS 314 LIMITIG CONMMTONS FOR OPERATION AMD SURVEILANCE REQUUUEMENTS 314.4 REACTOR COOLANT SYSTEUM COD -SHUTDOWN - LOP FLE LIM I~NG COM~MON FORt OPERATION~ LCO 3.4.7 3A.IA At leas one midnal begt removal (RUR loopt shl be OPMWALE and Inoperatiou, and either:
- a. One aditional RHIR loop sh" be OPEWALE*, orh o fte -ue
- b. The secondar sde wame leftl of at least two steam genermors sh" be rgreteff _Um- to APPLICABUlLII MODE 5 with reactor coolant loops fraled.***
ACTIONS a. Withoane of fte 1R11 loops biopetable ind with less thanto required steagenrator water level, A and B Immedatey initiate corrective actionto return the Inoperable RHR loop to OPERABLE status or ACTION C b. With no RHR loyIn ow ndsuapradans nvolvi a eductionlIn bo-ron - SR 3,4.7,2 4.4.1.4.1 The secondary ide water leve of at leaM two Wtem genrators wben reqired salbe determined 4.4.1.4.2 At least onm RHR loop shal be detemined to be Inoperatdon [and circla reiacto cools at SR 3.4.7.1 lIast o=c per 12 bouts.AdprosdS3473 LCO 3.4.7 PhETwolcuedo ~ ~ brsocnrro LCO 3.4.7 on AM lopwyb oeal for up to 2 hoar for murve~lflot tstins provided uli other Note 2 RHlI loop Is OPERALE ond Is "peaimuk A reactor coolant pump shall ntA be #tartedwith one or Uore of the Reactor Coolant System cold leg tempeastures lkw tha or equal to 152F unless (I) the pressurizer water volume ls~Se T less.than 62 %of spa or (2 the secondary ova lemperstm of each stam generator Is less 3.4.12 then ao ac fTe atr oln System cold leg tempmeLer Operabift of a nfe!or 5Ep!pwsoure be Ic. ttFor OflIs sedfai of Water from the o coniurte a WCT pro~e th --I 1 IL !in theW s than oreopal totb L by qw~~fi .l.io b.2. Adroposed LCO 3.4.7 Note 3 COOK NUCLEARt PLANT-UNI 1 hgse 3/4 4-3b AMENMENT 224 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 217 of 471
Attachment 1, Volume 17, Rev. 0, Page 218 of 471 ITS 3.4.12 MTS 314 LImrIG coNDmoNs FOR OPRATIoN AND suRtvEu mNC EQUIRMENTs 314.4 REACTOR COOLANT SYSTEM MOM -SHUTDOWN - WO ILEMD-LIMTING CONMMON FOR OPERATION~ 3A.1A At kWas on resitual hMa removal (RHI loopt shal be, OPERALE add Inopmntoun, and eiter.
- a. One addtional RHR loop sallU be OPERADLE**, ot
- b. The secondary ade wame levtl of at leas two steaw Sgeneam shal be gretertam or equal to 76% of wide rapge nstrmen apan.
Maz iLUX:. MODES5 with reactor coolant loops fifled.000 AMfOj See UTS
- a. e of the RIMl loops inoperabe and wih less Owan th requIted mtem generator water level, onh Immnedlately initiate corrective action to return the Inoperable RHR loo to OPERABLE statu or restore tde required steam generato wame level as soon as possible.
- b. With w~ RUR loop In opeation, suspend all operations Involving a reduction In boron concentration of the Reactor Coolant System and Imzaediaey Iitiate corrective action to retur die required RHiR loo to operaton.
4.4.1.4.1 The secondary sde water level of at least two smem gcenertor when required shal be determined to be widthi limts 91:least oam per 12 hours. 4.4.1.4.2 At leas one RHR loop shal be determined to be inoperatio and circuatigg reactor coolant at least onc per 12 hoors. The RHR pump may be deenergized for up to I hour provided: (I) no operatonsar permitted thot would cause dilution of ihe Reactor Coolant System boron coracmnntiontt mad (2) com mulct tempervture is mainaine at least 10"F below saturation temperature. One RHR hoop may be InoperaWl for up to 2 hour for surveilum~ tesftin provided Ib ado=e fullosOPERARLE andl i opeatin. LCO 3.4.12.c Areactor coolant pum* shl no% be stred with one or more of the Reactor Coolant system cold leg temperaure les than or equall to 152'P unless (I) the psesuriner water volume is less. than 62% of span or (2)the secondary water temperatur of eac mtem rIs less; tThe normal or eunmerec power source may be Inoperable. SeM tt For purposes of tbis specification, addtio of water from.the ftWST does moonstitut a 3 J4 dilution activiy provided the boron cowmentralo inthe RWST Is greater than or equal to the minairmm required by specifiation. 3.LI.7.b2.. COOK NUCZLEA PLANVrUNIT I Poge 3/4 4-31bAU M~ 2 Page 5 of 14 Attachment 1, Volume 17, Rev. 0, Page 218 of 471
Attachment 1, Volume 17, Rev. 0, Page 219 of 471 ITS 3.4.8 314 LICMrNG CONDMTONS FOR OPERATION AND SURVELACE, RE'QUIREMENTS 314A REACTOR COOLANT. SYSTEM l-IMMTNO CONDMTON FOR OPEATION LCO 3.4.8 3A4.1.5 At least two residual beat removal CRIHR) loopst shall be OPERABLE40 and at leaut one RHR 1o6l *bafl be in operutlon.* AP~tAJ~JjJY: MODE S with reato coolan loops not tlled. ACTION A a. Wihb less Omathe above required RHR loop. OPERABLE, Immediately inifital corrective sactonM. SR3.4.8.14A~l. toleast one l loop ed shlloeonwmltoOPRBLE Ittu oeastion spub ACTION B b. noc prH 12 1~~~last inhour nAs.eton uoli O-t-o nb LCO3.4.8 TbeIWR bdeenerlzefor tolburpz (lE=Dmlosre td . Note I ~~~~~causenti orteator mianS e-m coamentiutltftaecowi cton oet LCO.4. ** ne HI lop Ay b Ioopral for upnton2husf.sreuns etgpoie te No34.. te A.. H loo one RERAL anloop lberatictrmn. dt e1 prlni imhlw&w lcut om power2sourc a eIn.rbe Note 1 1~ tFor of Mueld cause aa of wtRa=Coanter rom thaWd o Contitut diutle t~acslv Isproldcddibor atl10tblow mntheSion te~thano popos LC.34 1 pwvkW the on In b6eRWST d= Pageui1 of 3 Attachment 1, Volume 17, Rev. 0, Page 219 of 471
Attachment 1, Volume 17, Rev. 0, Page 220 of 471 ITS 3.4.1 0 ITS 314A4 REACTOR COOLNTSYSTEM-: SAFETY VALVES - SHIFTDOWX?4-. UMIM~NG CONDMTON FOR OPEATION LCO 3.4,10 3.4.2 "Aminimum of prssrie coeafety valve shall be OPERABLE with a lit setting of,2485 PSIG APPLICABIUTY MO0DES 40 ACTIONS WERE no p code saecty valve OPERABLE: A and B [d rp
- a. lmnedatel supend allUert involvin positive reactivty. es except additon of water ATO from the RWST, provide th o ocnrto nteR greater than the minimumn xeqire bySpcifcaton3. .. b.2 -(MObDE 4) or 3.1.2.7. (MODE 5). -and paice an OPERABLE RHR loop inoprtr nthe thAdd propooo b Immeiatelyrecder AlU eyI~eto up nalln' bu necaring pump inoprale by SURVEILANCE REQUIREMENTS SR 3.4.1 0.1 44.2 pres cd safety valve shal bed osrd OPERABLE prersS cilance Requirecmet4.4.3.
Ad proposed SR 3.4.10.1 1~~i~~iT~orrespondt pbltcntinofthe.vaval~ ~ praigtemperature( " ) SR 3.4.1 0.1 'Th presswi~zer cesafey,valve' shall6beria o h nih aue+% hnver. tond outside the +1
-COOXCNUCLARPLANT-UNIT 1. Page 3/4 4-4 AMMNMENT634!0, 214, 230, 272.:
Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 220 of 471
Attachment 1, Volume 17, Rev. 0, Page 221 of 471 ITS 3.4.10 ETS 314 LIMiTNG CONDITIONS FOR. OPFERATION AND SURVEELLANCIE REUIRMENTS 314.4 REACTOR COOLANT SYSTEM: SAFETY VALVES -OPERATING LIMMTNG CONDITON FOR OPERATION . K LCO 3.4,1 0 3.4.3 All pressurizer code safety valves WmHa be OPERABLE with a lift setting of 248S PSIGt 3 %.YV
-APPLICABILIT: 'MODES 1,2 and 3.-
ACTION:Aplcblt D ACTION A W'ilh nepsuiercode safet valve Inopemme elther'restore the Inrbevalve to OPRBEstatus within ACTION B Imnts e a sh n Q { any RCS cold loop temperature 266- F . Ad proposed Required Action B 1 ddsecond Eartof conditlonBa SURVEILLANCE, REQUIREMENTS . SR 3.4.1 0.1 4.4.3 No srefiance ote tanamuretosepre Speclficatioa4O5
~Ue ift etwressueipd npn o~l1n codiiosfth alve at -intwhfe SR 3.4.10.1 lbTe"prsurzt ety V hal WMe rstd tvau 1wbNeveir folnd oulete+1 COOK NUCLEAR. PLANT-UNyr I Page 3/4 4-5 AMENDMENT M. 364, ~4.272 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 221 of 471
Attachment 1, Volume 17, Rev. 0, Page 222 of 471 ITS 3.4.9 314 LiMMMIG COND ONS FOIROVERATON AID SIflVIILIMACE UQU[WE~nT 314A IMACTOR COOLANT SYSTEM LnMiNG CONDiTIN FOROPIERATION LCO 3.4.9 3.4A The pressurim~abal be OPERABLE with a water v ls than or equal to 92% of spoz and two vains opueaters Oht lh tapadof ea t me hnor equal to 151)kW. (N
~~MODES
~~~ 1.2 n 3.
ACTION B Wihte*s~ie ~pzb j an Inoperable hWl of p atsvi=izer eatr either restore the M. ACTION C SHTDW11tn 2bours. ACTION A b, WithOle ET be inat leastEHO SHITIDOcid SR 3.4.9.1 4AA.1 The pres detrined to be withiits mits at leatonceper 12 hour. thoin~aalb ) SR 3.4.9.2 4AA.2 Ike pres detnsal be demonstrated OPERABLE at least oawe per Months by cnergizig tbc raquired capacity of heaters in cac h ain. COOK NIAIEAR PLANT-UNIT I Paoe 3/4 4-6 ADMMEN140,U4, 246 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 222 of 471
Attachment 1, Volume 17, Rev. 0, Page 223 of 471 ITS 3.4.13 ITS 314 J~MI1G COMMT1ONS FOR OPMAUON AND SURVEILaNCE )WQUMREME~n 314.4 -REACTOR COOLANT SYSTEM Adrposed ACTION B (Condition third part) VMt ame ar stemc~rca Inpeule. dos bnpembl geertms &pdw ift M.2, SR 3.4.13.2 4Asiom&.U se ra bimbe OflRABLE by of dA. follWleg 4.43.1 mmomO mraosame! ad bg2cW neo - ilac sxam geamr ba! dMto &m&e OPERABLE &dur scdownm by wdcimg Ead bupetig at le artdie mnimm of semm enemomaspcfidI Table 4A-1. 4A.5.2 Se=m frtMr TvWb Uame! Selcedon and baueto - The -dam gratar Utubmlnnm= sampl size, Inpenkm. ts&a!caulfkac6ados adIb correpondin sedn requiredvUal be as speciie InTabl 4A-L The InsmeekW e of mtem pw mawrtbes shal be perfwnnd at die frsiualesd tpecifid Ia Spewffcabon 4A.3. and dke Imacted Wmbe dwal be vudfled accep able per ate acpab eak of kwe~fcadwm 4A5A. The tubet ele fa each I ImnairiceInpecic. amBa! lude tas eK3%of da tta u of tubes bai swm pnummnw dke babe selcte for thes Izipeals aba be osradaa oelctd bea ean*
- a. Wher eLqaezkc insimils ph= with sbmil waon obmulsy Indicate dalW muea so be bupecWeOf ihuatIcastrn o~frIm hopecdtda ba e fimdn~ jgcWW uv See rSJ
- b. lb m fistsmple of tuba aelcted for each luervi lupectionubeqtum f doe I. All Otbe that prsvim*~ bad delctble %,af penmnulm (greaterthaateqWa so 205) dhthahv wte hm phu~ed.
This a WYi
- r~ Pwbileptformlngca b Iu Umiftin COORNUCIZAR PUNTAUMlI hpe 31 444-7 6,053 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 223 of 471
Attachment 1, Volume 17, Rev. 0, Page 224 of 471 ITS C~~~~~~~~~~~~~~
~~~~ITS 5.5 314 LWT1MG CONDM2ONS FOR OPMATXON AND SWEEIIILANC Q JR W 3/4.4 REACTORt COOUr SYSIEM 3A.5 Each m pmew drbalbe OPERABLE.
MODES
~~~~~~~~~~~~~~~~~~3.4.
A~~~J~~~h~~~D.DX: 1. 2.3MODESI,2Zand4.' andC 13J .
~~~~~~~~~~~~~~~
ITS Wbk am cr "u It= sozmmod lncqierabl reamee dar inaperabe genwszo*~) a OPERAL#E m pio t bMOIsfn TA, above 2007. 4.4J5.0 Inch -mm Spopxmi ar1 be demoommaed OPERABLE by Perfomaunce of fte Mfowlzg mvnewmed Iaserviee Izarpecdmionprmpm and die rernuemmof lpeifiesdan 4.0J. 5.5.7 4AJ.~~~ 9resm&-eam= Sinkl Seleton and Inanctio - Exit *am gSxraur salbe deletmndw 5.5.7 4AJS. fpm ftMmw Tube Sauke SeJjan sd Imetwom - The m grsur atbemnm sAq6ibm. s kaIpecdom ftes ub amilea on.ad doecwuepaoda seacin weqdred dhall be as
.pewle hi Tabl 4A-L. Th kwimsrk Impnd. of susa gnrtwontubes sha be Performed at die freqjmuud specilied In Speedfidado 4.4J. ad de sIall be verlfied f 6criKze dietbe lwkof 443H~lln 4JA be Uubseicted for CKl 5.5.7.a busrvinelIspcimm swbhal Icldealea3Sof Un wm ubm of tubes In all su Senerszws die-babesseclod for Omes Impactidogssh be selected uaandam N basis except 5.5.7.a.1 a. Tram lIA mU Phluvf Udif111du 5 dmeiny 11fisa aclu ddal aesto be b~Impctd, heat kWt0%of lbe tau besnpecd shal be frum thwmies cia1 m.
5.5.7.a.2 L ru~~~~~~ sutample of ad s elcoed for oakh bmvk he Impc (subequam to der 5.5.7a.2 ~~~~puweierhpe d~afbeah mg wom-r buigvak 5.5.7.a.2.a) ~~~~~~1. All odbesdipm fyhddtctbkwlpeonm 20%) dathaave nx beat pluged. (puater dam requid to ThMSpeeleaicanw doesno apl In b Mode 4 WbAil pertftmlagcrvic dushiq as lon as Imitin Ccowmliii for Opuradam for Spodfiullods, 3A.3 an malmaind (3A.Se4131T COOK NUCLEAR 1U2IT4J14 I Pap3144-7 sANUM Mri a0 n, IM 23 Page 9 Of 69 Attachment 1, Volume 17, Rev. 0, Page 224 of 471
Attachment 1, Volume 17, Rev. 0, Page 225 of 471 ITS 0 5.5
~~~~~~~~~ITS IN4 LUhM1NG COMM1ONSVFOR OPE~n1ON AMD RVEMIAMCE QmhOII 5.5.7.a.2.b) 2. raw In 6mabm experlpe loa h od poludal probkew.
5.5.7.a,2.c) 3. A ab Impenda (pVsm= IDSPeCiICaso 4AJ5A.LS) dal be pedore an acxt sekecld o6be If my ueleted tubs dmsma permit lbs pasag of dos e*d CMrz probe fbr aat be hspsduibs abai be nmeded and ta soa jcm be ahal be sekectd am! sabjected ioanAb kwtoan 5.5-7.a.3 L TMlbtube adce dieasm aid tkd -ml (if mok by Tabl 4A42) diwio auh WwI.Iw bx=W mvbe o~cod so apaidalk tbe opeedco provwde 5.5.7.a.3la) I. lbs tubes waelced for doeasapWe laclide tub. gaas dine a=s of at nibs
- uwhw nb. uflphcwerwwe pmvsnwlibu 5.5.7.a.3.b) 2. Tat dice puim ofdd Mmbe bdecluu.Icl wum Iipedecdcmewe 5.5.7.b The saft of eack am*Imp l cdm iidw be bealWe lw cm ofdoe Mwftfoh din calegwie C4 Lm tm SSl cfdiwiWbsWmup amdusdpmWudduib amigouf e Inspected an* cdw mdef C.? Ouorm mwb, tbu.%am =amdgm lof de wW tba~p amur hdnfcit -or btwee SI and 1011 of dieo Wum tb~enseted wt degra~de C43 MamuduanlOSlt dd~dmds paimt edudiepa o rs mdum IS ofOmInspe=W Wmbemsdeeibdv Page 10 of 69 Attachment 1, Volume 17, Rev. 0, Page 225 of 471
Attachment 1, Volume 17, Rev. 0, Page 226 of 471 ITS (I ) 5.5
~~~~~~~~~~~~~~~~~ITS M1 Lfl&flG CONDM~OMS MM OPMM1OX AM D8UVEULANC33QfZ ~ l SM4A- EA-CTOkCOOLANTSYSW4 5.5.7.b Nwr in asl laspcims peem3l &ad mtA= atc s1gftca (rmr gm or equa io 10%) ilarbr wal pmeuraona u be kdcubid In6e aboaf Pgecaamr awatio 557c ~~~4A.53 rgmW-Theabov rquhzdi~redineelcslpcana ta uurtrcbssal
~
5.5.7,c ~ ~ ~ a Te iluve *It inowt iossalbpecftim datr6efcieFaRIwrMnsba.ii 5.5.7.c.1 A. Mmh hmaaethsape WdaI cbegym I medr 90ait A Poew Mcom Sbseut Within 4 kacia add be perkrmeda htuv*a(l Im h 12 sw aew fn 24 calmada nmozfz namo afte doe previow Icqusad. If two coincumdv laqiect av fowing serie OWaNe AVT I esmm orUI wo eouadveai uedn deonmmmtupreviosly obsrved degradadon barn mtcontinue nod to admidhi deguldsbu 3mccwreCd dom lampedaoa latuva say be nmtede
*io, i mu atomper4O momft 5.5.7.c.2 b. f t Io mI Vwa fam Su midkxc~m f "4.
rA40 uiont berlsft Wll kCalegoy C-3, tt lupecim ficoquu~ dnis be bat&Wse to ashue me pe 20 moc&. Mme bmma In hpeedon knqamc dhul mp*~ui di mne beq bepectious msds toe athen ci B-opeclftadm 4AJ3a fthlmatWa MW bhm b emadd lo a 5.5.7.c.3 C~~. Ad~dwd auLsshdldoM booeue IpedmAi be ~;farynd an ech amrn g h ina 5.5.7.c.3~ ~ d= M t M n~ h~~df *O InTabl 4A-2 dafit ft shtdwaiabeqt
,msowoufflaeMowing coadhko:
5.5.7.c.3.a) j* ftw~~ tubes leags (not bd lo~~tb ozgladg rot bobe0"4odu sdee wh)aecusm off Hudtlm ad Speelinuom MAL6 5.5.7.c.3.b) 2. A U1210occmegueaeerthma OPraUlft ashflibquab. 5.5.7 c.3.c) 3. A Ion-ofcoalm sdcald ef gachdom of doe engluev ftgmbl. 5.5.7.c.3.d) 4. A mob a go atrime wawe doebreak COOKNUcIZAII ANr4INIT hps 3/4 4-tAM fr off W6oa238 Page 11 of 69 Attachment 1, Volume 17, Rev. 0, Page 226 of 471
Attachment 1, Volume 17, Rev. 0, Page 227 of 471 ITS 5.5 ITS 31/4 WLff WA CONDMfONM FOR OPERATON amD 8URvzLANCEEQUIREMMM 3144 REAMrOJ COOLAN En'=W 5.5.7.d 4A.5A 5.5.7.d.1 L MAse i d Vndflcint 5.5.7,d.l.a) I. l~ Umum a exeptoe to to dbimmaia, fhibb or camcmofr ca nbs ftcm th roquke by hbulamdwrwlngs or ved&==ti. Eftmymurn usuIbns Irdicatlo bel 201 of dx nowbal the n~ wall dkmau, it deWesale MAY be Comidered as 5.5.7.d.l.b) 2. n piningea Mevkne-bduoed Pr "I i, wattag. Wmar F guimi ~hosi cccw~AV uldw stdde r ofa Ube. 5.5.7.d.1.c) 2. as peft d Sur Omoruipialki20% ofthBxindwa I U*dmm Calldby ~depsn. 5.5.7 d.1.d) 4. mom de.azaos ofd rOmbe Iat thiahu uffhebd cc nmsed by 5.5.7.d.1.e)
- Aub 5.5.7.d.l.f) 6. ZEudut -o dwiempubdhon dept at or bepeed w4ZIh fte tube dog be I removfed tram scrvku Any uith whch, Wim robe wail depudstim equdmchfbb ofd40 puesmw t x ooracinoind NW W beilbupbd peixr dthcb nmbftdo mum girS s mwvlc.
5.5.7.d.l.g) 7. IN41tdwrildo icoaslheofawblk luIurumofaualm a ubatlp Oigb so uffec mhamxcull bur* la de MMof ain Opemi Dauis bnhquab. a Ilanof-. Coohat lackldm, of satam IHo at 6hedwla obmbukua pecifiedIn4A.S.S. abowe. 5.5.7.d.lth) 3. duw fi ecadkllm of t ixmum enrta ube ban ft palm ofemjy COOK!NU AR PLAWAr4IN £ t 4*10 3S24 ANNM k4~ 238 Page 12 of 69 Attachment 1, Volume 17, Rev. 0, Page 227 of 471
Attachment 1, Volume 17, Rev. 0, Page 228 of 471 ITS C) 5.5
~~~~~~~~~~~~~~~~~~IT
$14 UVMMMlCONDMION FMR 6PEAZON AMD SURVANCEREQUMRVMM
$14.4 REACTOR COOLAmSYFMM 5.5.7.d.2 b. Tb. Want prmm "hlte deumlned OPMUMJE uber coazpkwedng cirpodig Acdooa
=z OtWuubn AUnzbu exaeingmth plugin limi and all cbes c=uunin cbro*ghwau Cracks) nqmdredby Tajdc4A-COOK NUCLMA YLAMrUNN I Pap 514 4411 APD Mr8.f6 JK Ml%§KI5U 238 Page 13 of 69 Attachment 1, Volume 17, Rev. 0, Page 228 of 471
Attachment 1, Volume 17, Rev. 0, Page 229 of 471 ITS 5.6 ITS 314 LVhUTKG CONDMTONS FOR OFPATIOR AND ZWVEULANCERQm 4I IL44 MEACTOR COOLANfTSYJ 5.6.7 4A.SS S. Fdaow4b each Iinfvkc iupecdon Of U= som zabcbs%. fte nmber of amie plused Ineach uma $ameno fhal be repaWrte otoe Coemnmbft wkhthn 15 days. J
- b. VA empl ewmcs of die mm Ig nivbs hnerict L=B allm be bxdude
- 1. NHmacrmdcfa of Wnbubpeed.
- 2. Locadoinsdpercew, of waI4dckhi~hu muafor ce ~ch an Ipmpefcdaa ndcaof coafuted lo detemIne ci tt of atu dep~adoadou am!cecfti meaune take fo prev COOKNECLEARWLANTUUNT lag 314 412 Ai0MMNM U. I64, Mt 4S ammms238 Page 8 of 16 Attachment 1, Volume 17, Rev. 0, Page 229 of 471
Attachment 1, Volume 17, Rev. 0, Page 230 of 471 ITS 5.5 ITS Table 5.5,7-1
=MfIIG HWMB! OF STEA GENERATORS TO BE rNSPECTED- DURING INSERVICE. INSPECTION Preservice rnspection .yet No. of Steam Generators per Unit Four
*First Inservice Inspection Two Second & Substquent Inservice Inspections one Table Notation:
Table 5.5.7-1 1* The Lnservice inspection may te limited to on. steam generator on a Footnote (a) rotating schedule encompassing 3 N%of the tubes (where N is the number of steam generator's in the plant) if the results of the first or previous inspections indicate that all steam generators are performing in a likce mariner. Note that under soae circumstances, the operating conditions in one, or mare steam generators may be found to be more severe tban those in other steam generators. Under such circumstances the sample sequence shall be modified to Inspect the most severe conditions.
- 2. The third and fourth steam generators not inspected during the first Table 5.5.7-1 inservite inspection shall be Inspected during this second and third Footnote (a) ins pections, respectively. The fourth and subsequent inspections shall follow the instructions described in 1 above.
COOK NUCLE&AR PLABM UNIT 1 3/4 4-.13 AMMNP2MM NO. I" 16 6 Page 14 of 69 Attachment 1, Volume 17, Rev. 0, Page 230 of 471
, Volume 17, Rev. 0, Page 231 of 471 ITS 5.5 1 -4AM M sif"3 1 .N5X~tL~rM Pa
'4 ~~~~~~~~15 Paej5of6 , Volume 17, Rev. 0, Page 231 of 471
Attachment 1, Volume 17, Rev. 0, Page 232 of 471 ITS 3.4.15 ITS 314 LEMING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314A REACTOR COOLANT SYSTEM 314A.4, REACTOR COOLANT SYSTEM LEAKAGE LEAKAGRE DE1=1TON SYSTEMS LCO 3.4,15 3.4.6.1 'Me following Rector Coolant System leakage detection systems sllbe OPERABLE: LCO 3.4.15.b AL One of thie containment atmosphere paricuatemonitorn channels LI-1131or R-9 LCO 3.4.1 5.a b. The containmen SUMP an flow monitoring se n . LCO 3,4.15.c C. Esther toe containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring chanels PRy305 ar [0 . APPLICABLfl: MODES 1,2,3and 4.L. AddprooseACIONSNtL5 ACTIONSA, 8 euired ActinA.1 dd Rropos~~~~~~ed C,and D f 11~ saternOPERABLEAd proposed Required L Required Actions pvddgrab samples of fth containment atmospher ame obtained and analyzed at least once per B.1 .1 and CA1 ie e aseous arair particulate radioct requ monit&~ channels am lno c; otewie aa ACTION E latHTSTANDBY within the aem 6 hours and Iin COLD SHUTDOW within the,following 30 hmnr. 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by: SR 3.4.15.1, a. onametatmosphere particulate and gsueous (if being used)- mon0iton sytemn-. O SR 3.4.15.2, fomneOf CHANNEL CHECK CHANNEL CALIBRATI0Nand SR 3.4.15.4 FIx OA thde frequencies specified In Table 4.3-3.A2 SR 3.4.15.3 b. CztinetSUMP e lwmntrn -proanefCHNE CALIBRATION atlesocepr2L6 SR 3.4.15.5 C. Cotainment hunmidity moitrif being used) -performance of CHANNEL CALI WATION at leas once pr2 COOK NUICLEAR PLANT-UNIT 1 Page 314 4-15 AMENDMENT MO.A44,166 I Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 232 of 471
Attachment 1, Volume 17, Rev. 0, Page 233 of 471 C) 3.4.13
~~~~~~~ITS 314 LIMITING CONDMTONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.4 REACTOR COOLANT SYSTEM UOPERTIONAL LEAKAGE LIMIMNG CONDMON FOR OPEERAIO-N LCO 3.4.13 3.4.6.2 Reactor Coolazit System leakage shall be Limited to:
- a. No PRESSURE BOUNDARY LEAKAGE.
- b. ~ NDETFIDLEAKAGE, C. 600 galons per day total. pdimay-to-secondary leakage through all steam generators and 150 gallons per day through any one steam generator.
- d. 100GPM MDENTIFIED LEAKAGE from the Reactor Coolant system, 1
- e. seal line resismance than or & to 2.27E-1 ft/ pM and, SeerTs]
- f. The leakage f'Om uReachR tor Coolant SyStemi PressurIsolation VAlve specdfied in Table 3A See IT"S
"'albe limledto 0.5gpm per nominal inch of valveslz up to amaximumof 5gpm,Sta 3..1 Reactor Coolant System average pressur withIn 20 psi of the nominal funl pressur value. I341 APPIJMALiTY: MODES 1, 2, 3and 4.*
ACTION D a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours ACTION C ~~~PRESSURE BOUNDARY LEAKAGE, reduce the IL ecrate to within limits within4ho r ACTION D be In at least HOT STANDBY within the one 6 hours and to COLD SHUTDOWN within the C. With any reactor coolant system pressure Isolation valve(s) leakag greater than the above limit, declare the leaking valve inoperable and Isolate the high pressure portion of the affected system from the low presure portion by fthuse of &combination of at leas two closed valves, oam of - which may be tie OPERABLE check valve and the other a cdosed dea d motor opdrx See rrS valve. Verify the Isolated condition of the dosed de-energized motor operated valve at least once )4 per 24 hourz, or be In as [ecm HOT STANDBY wdihin the mnex 6 hours and In COLD SHU1TDOWN within die following 30 hours.
- Specification 3..6.2.e Isapplicable with avernge pressur within 20 psi of the nominal full Press=revalue See rrS 3.5.5 COOK NUCLEARt LANT.UN1 1 Page 314 4-16 AMENDMPENr 44, 166, 4=, 483 XWO Orer-ddAted .ApPl20 If8l Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 233 of 471
Attachment 1, Volume 17, Rev. 0, Page 234 of 471 ITS 3.4.14 ITS 3/4 LMUNG CONDMTONS FOR OPERAITON AND SURVEILLANCE REQUIREMENS 314.4 REACTOR COOLANTf SYSEM OPERATIONAL LEAKAGE LIMM~NG CONDIMON FOR OPERATIO 3.4.6.2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE, See ITS
- b. 1 GPM UNIDENTIFIED LEAKAGE, 3.413J C. 600 gallons per day total prdmnzy-wosecodazy leakage through all steam generators and 150 gallons per day through any one steam genera=o, See ITS
- d. 10 GPM IDENTIFIED LEAKAGE from the Reacor Coolant Syste. 3.5.5J 1e. Seal line resistance ireare than or etulto 2.27E1-1 fr/m and, LCO ..- F~j~
3.4.14 The leakage fiomeach Reactor CoolanzSystefa Pressure isoltionVdls 40 SR 3.4.14.1 1Mb im 1ite o05pKmiperun linho valve f iize p to' iaxlmama of 5 ion#lat a~. . Reactor Coolant System average pressure thdin 20 psi oftbong lfull valure APPLIC [BLT: MODES 1, 2,3 and~ See ITS Ad p oosed ACTION S N t 2A4
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at leat HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hour.
- b. With any Reactor Coolan System leakage greater than any one of the above limits, exilding See MTS PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours or 3.4.13) be Inat least HOT STANDBY within the next 6 hours an In COLD SHUTDOWN within the followingj 30 hour.M1 C. Writh any rexor coolan systm pressure Isolation valve(s) leakae greater than the above lIm Ad rpsdRequired declare the leaking valve inoperable and Isolate tde high pressure portion of the affected syte Acin land A.2 Note ACTION A fro the low pressur portion by the use of a.combinadico of at leas two dlosed valves, one of which may be fte OPERABLE check valve mand the other a closed d-enaerie motoc operated ACTION B S WN iwihin~ the followIng 30 hours.
- Specification 3.4.6.2e is applicable with average pressure within 20 psi of the nominal fullI pressure value. See ITS COOK NUCLEARl PANT.UMr 1 Page 314 4416 AMNDMENT 4(4, 14w, 13, US, 2WO crdcr dted -Apra W0L";
21S Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 234 of 471
Attachment 1, Volume 17, Rev. 0, Page 235 of 471 ITS 3.5.5 ITS 314 LIWMlNG CONDMIONS FOR OPERATIONI AND SURVEiLANCE REQUIREMENTS 314.4 REACTrOR COOLANT SYSTEM QEMLATIONAL LEAKAGE LIMITING CONPMTON FOR OPERATIO 3.4.6.2 Reactor Coolant System leakage shall be Limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. 1 GPM UNDETIIE LEKGE See fls3 C. 600 gallons per day total prlmasy-o-aecndary leakage through All steam generators and IS0 gallons. per day through any one steam geneato,I
- d. 100GPM IDENTEFIED LEAKAGE fr-om the Reactor Coolant Systeml,
- e. Sea ltine resistace greater than or equa to 2.27E-1 fktgpm~and,
- f. The leakage from eachi Reactor Coolant.Syucte. Presslue Isolation Velvts specified tnTable 3.-
shilbliite so0. gp pe noina Ich of valve siz up to a maximum of 5 gpmn Ata r Reactor Coolant System average pressur withi 20 psi of ffie nominal ful pressure value. LJA1 APPLIABILIII: MODES 1, 2, 3T.'( ) A=ONQ,:
- a. With any PRESSURE BOUNDARY LEAKAGE, be inat least HOTr STANDBY withi 6 hours See rls and in COLD SHUTDOWN within the followin 30 hour. 341 ACTION A b wd M P E~m ACTION B he in atleanHOTSTANDBlY wltln theziez6 hoursndlnln ER OD C. With any reactor coolan system pressur Isolation valve(s) leakage greater than she above limt, declare fthleaking valve Inoperable and Isolate the hig pressure portion of the affected system from the low pressur portion by the use of a combination, of sit least two cdosed valves, one ofSerr which may be the OPERABLE check valve and the other a closed de-energized motor operated 3.4.14 valve. Verify the Isolated,condition of the dosed di-energized motor operated valve at least onc per 24 houws, or be In at least HOT STANDBY wihin thie next 6 hour and In COLD SHUTDOWN withn die following 30 hours.
SR 3.5.5.1 Specification 3.4.6.2.e Isapplicable wi av ep essure do h nmna ai Note 0 COOK NUCLEAR WLANTAUNIT Page 314 4-16 AMIENDMENT 46243, .643, 1.8 2WO 215 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 235 of 471
Attachment 1, Volume 17, Rev. 0, Page 236 of 471 ITS 3.4.13 ITS 4.4.6.2.1 Rsector Coolant System leakesges .afle be demonstrated to be within each of tbe above Unmits by:
- a. totingthe cota /t osxet particlt doatvy
,, o at least ocpe .2hours.L1
- b. Eutrnthe aM netz M pat least once IeI1hours.
- c. Deter4minan the seal im. reuiatmne at least owce per 31 days when the average pressurixer pressure Ls within 20 jpsI of tsc zomnual full pressure value. The see. lUna tesisuanc measured durngth SUrM'Ll2amsc out be greater than or equal to 2.27 -14 LIgp~ The meal line reuistam*,s 1Rni La determined from the following
'LL-2. 31. (?CP -,I See ITS share: PGO m charging pimp header pressure, psig3.5 P.1- 2212 psig (low pressure operation) 2251 psig (high pressure operation) 2 Iji - co"Werl~on factor (12 UVWfr /(62.3 llb/fth Q - the total se4l Wnectxin fLOW. arn The prowisons of Specification 4.0.4 are not applicable for enczy into -MODES- 3 and4 4.
SR 3.4.13.1 d. Perforimane of a Reactor Coolant System watsr imnozy balance at least once per 72 hours dutizg steady state operation, and x tdornig the T iaoff ayr.tleast onwe per 184ka*ln~ 4.4.6.2.2 Zath reactor coolant system pressure isolation valve specified LnJ I See UrS Table 3.4-0 shell be demonstrated OPEURI pursuant to Specification 4.0.5. 341 MUKWAWT 5;0. 144&r "sr 14, 188 MmO WCLIA M1M VW? 1 3/4 4-17 O'+/-se "lds 41LI acraeir Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 236 of 471
Attachment 1, Volume 17, Rev. 0, Page 237 of 471 ITS 3.4.14 ITS 4.4.6.2.1 Useator Coolant System. 1ekagqs aball be demonstrated to be Within each of tbe above Unmits by: See ITS 3.4.13 aL. MonlitorIng dhe cotiet amospherepatclerdictit
- b. Monitopri the ctaintmet muap Invetory and discharge at Least
- 5 m pr 2 ohsoaueatrneser.
- 4. Dtenddngtba ealIfnarvastane a leat ae pe 31days when the average prossurixer pressure is within 20 jpsi of Xts nominal full presenre velv. The. smee line, veuistance Mmeasud duigthe surveillarms east be.Sroater than or equal to 2.27 Z-1 ft/pa.The seal line resistance. 2 SL. ia determined from the following 3.S - 2.311("cp1 "I See ITS vhsrez Pcgp ca arglag pmip headier pressurie, ps4 .55 PSI 2112 Paig (low pressure operation) 2261 psi4 (high pressure operation) 2.31 - couvetslon factor (12 In/ft)X/(62.3 lb/ft 3 j Q - the total. Sel InjectiiWn flow. anm The provision, of SpecIfication 4.0.4 are not applicable for entry ino W-D 3 wide4.
- 4. erforance of a Reactor Coolant Sysnem water Inventozy balance at least onwe Ver 72 bouts duting steady state operation, and ISee IrS 3,4.13
- e. 310okitorin the reactor he". flange leakoff system at least once per 24 bours ------
Tb .40 halbdeosatdOUM prsattSeifcto40.. dd proposed SR 3.4.14.1 4.4.6.2.2 3wh roator coolauat sm La ti SR 3.4.14.1 L3 64 Amom=~l N0. "Gar r 4;, l8a COOK NWCL3AR PLANT - UIMT 1 3/4 4-1i euesi Ldev .rf. 10. M Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 237 of 471
Attachment 1, Volume 17, Rev. 0, Page 238 of 471 ITS 3.5.5 ETS 4.4.6.2.1 Raincto? Coolant System. loakops shall be dmmonttated to be within each of the above Uuits by,.
- a. moitoring the couafust atmacpbere particulate rniioativ:Lc I ~~~See US moni~tor at least owce per 3. hous. y341
- b. Moioigthe conaimet wsm izuentay and discharga at Least SR 3.5.5.1 c. Dotenqminn the geal line resuisance at leastionc vr 31dawe Not to R5.5.5.1,o4ODE S nd .
d eftheazceof a leater Conlan: Syste L wate ofveucialnce at heas oncsuepe 72ho, din s Usted rmstame, moration du See rr
- a. lio laorng mth bcor hat tlan oeleqalo sytem.2 a: latonepr341J I Tbl3.-0seal llne "be OIRL Rdemonstrata~eduma:t pcfrocatio 4OJ oweGPPae o Attachment 1, Volume 17, Rev. 0, Page 238 of 471
Attachment 1, Volume 17, Rev. 0, Page 239 of 471 ITS 3.4.13 LiTs REACTOR-COOLAFT SYSTD4 ZUMB~ E'ISOIATIONVLE valve MeLeakage' Uuabe: (Am.) Iunction (a) pa) _____________________________________ ~~~SeeITS 3.4 .14J 5141701.2 10 ECC8 to Reactor Coolant Loop 02 Cold Log S RH 133 8 M toReactor Coolant Loop .2 Cold Xeg 4 SI.17OL3 10 ECCS to Rmactor Coolant Loop 03 Cold lag S RH 134 6 RHR to Reactor Coolant Loop.03 Cold Lot 4 (a) MLnLiza t*st dLfferential Presit=, Aall no be b.low 250 paid. ISee ITS 3.4.14 AMMEMDMU "sr*3
*4 188 COOK IMCLEAR PlAN - UNIT 1 3/4 4.17* 0:1., dalelA;:L2 20. lo!&
Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 239 of 471
Attachment 1, Volume 17, Rev. 0, Page 240 of 471 ITS 3.4.14 ITS UAT TSOLATION VALVT~~~~~~~~~~~A. alve Salve 9 SX.170L2 10 aCc to Rmactor Cool Loop 02 Cold Lm, S RH 133 8 RRR to RSactor Ioo 0op2coldLUsg SI.1701L3 10 ECCS to Reactor o Loop 03 Cold lag RH 134 6 R3 to Reactor CooD Loop. 03 Cold Let COOK )JUCLEAR PLAN - UNIT 1 3/14 4.17s of"* 46Me &1*6& So. 19o1. Page 3 of 8 Attachment 1, Volume 17, Rev. 0, Page 240 of 471
Attachment 1, Volume 17, Rev. 0, Page 241 of 471 ITS 3.4.13 ITS This page intentionally left blank. COOK NUCLEhAR PLANT UNIT 1. 3/4 4-17b Amendzuent No. IS88 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 241 of 471
Attachment 1, Volume 17, Rev. 0, Page 242 of 471 CTS 3/4.4.7 -314 LMTNCONDITONS FIOR opRTIn AND SURVEIfLLACERE 314A MlEA COOLANTSYSTEM 3.4.7 The tr Coolan Sys=e cbemznrsy shall maintained wit dinte llmhs inTable 3.4-1.
- a. Wzh amyone or more chemistr toexes" ofhatedytc but within its Transientl~mktrestore toc Steady =Ub iit Iotbnt 24 houretbein at leas HOT STANDBY within tect6 boum and InC0LD SHUDO Within the foumoing
- b. Wihmyocmormore chemistr~y In xoeasofits Transientm 1 beinat least HOT STANDBY withi 6 hours and CL SH DO Nwithin the f 30 hous.
Wihcoocetrtioc of either chloride fluoride inthe ReactorColn Inexcess of Its Steady StteLM t for mor than 24 hem or In of Its Tuaulska imtrdc pesuir presur to ICL p If iapplicable, andl perform anlssto determin die efet of out-of-limlt conidition on she bnieriity of the Reactor aniSytem determine gma bhe Coolant system rean efrcontinud opertion prior to hicreaslg the presurizer above 500 p*l or prior to 4A.47 Reactor Coolant System chemist be determined tobe withi fte iby anyalyss of thos p ters at the frequencie specfied Tbe4.4-3. Performance of hils fs not rcquired reactor Isdefueled with notf circulation.
~D4NUC1EAt PIrrMuM 1 CO Fag 314 4-15 AN ~ E 3 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 242 of 471
Attachment 1, Volume 17, Rev. 0, Page 243 of 471 CTS 3/4.4.7 314A RECIOLANTUI 1 ag 34 1'23 TARJ 3.4-1~Pge2 f Attachment 1, Volume 17, Rev. 0, Page 243 of 471
, Volume 17, Rev. 0, Page 244 of 471 CTS 3/4.4.7 D3SSO4
- = OLONT YSE COOK PLN~4JHE I-SR Page 3144-2 OMREM*EM23 SAMP11B PaeA3ofD , Volume 17, Rev. 0, Page 244 of 471
Attachment 1, Volume 17, Rev. 0, Page 245 of 471 ITS 3.4.16 ITS 1iREACTOR COOUM~ SYTCH 3/4.4.8 SPECIFIC ACTIVtWI LIMIINC CONDITION FOR, OPERTION LCO 3.4.16 3.4.6 The apecific activity~of the reactor coolant shall 'be ILsiced to: SR 3.4.16.2 S. Less than or equal to 1 sicroCuris per grm DOSE EUVALEN 1-1-31, and SR 3.4.16.1 b. Loes than or equal to iooii microCuries per gram of gross radioactivity. APPLICARILT: MODES it 2, R..4 MODES 1, 2 and 3* Adrpoe Condition A No-te-
- a. With the specific activity of the reactor coolant greater than ACTION A I microCurte per &ram DOS& EQVIVALENT 1.31 for more than 43 hours durnt one continuous t~ius interval o *aceedi4g the lImit line ACTION B shovn on figure 3.4-1. be In HOMSTAJISY withTSV less than 5SoOF Lilthin 6 hours.a ACTION B b. Withi the specific activity of the. geector coolant greater than l004( aictoCuries per gram,. be in NOT STANDBY vith T loesthan 500 F within 6 bourn. V ACTION A a. With the specific activity of the reactor coolant greater than I requirements of item a of Table 6.. ithe specific act r .
SURLVEILLANCE RUIR1mENS SR 3.4.16.1, 4.4.1 The specific activity of the reactor coolant shall be detemined to be SR 3..16.2 vlthin the limits by peformance of the sampling and analysis program of SR 3.4.16.3 Table 4.4.4. APPLICABILITY *With T greater than or equal to 5000?. COOK NVCLZAR?LAXT - UNIT 1 3/4 421 Acindrent no. 142 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 245 of 471
Attachment 1, Volume 17, Rev. 0, Page 246 of 471 ITS 3.4.16 ITS This Vae. la:.atloal~ly 1.ft blmak. COOK WLCULIA
?UMT - MIT1 1 3/4 4-21 umnftot No. 142 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 246 of 471
ITS TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACITIVITY. SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMEN MNJ MODES IN WHfICH SAMPLE _AlD ANALYSIS FREQUENCY AND ANLYSIS REQIRED L SR 3.4.161 1. Gross Activity Determination 13iitie1Ri 7 days with a I
- 2.
SR 3A416.2 2. Isotopic AaelvSIS lirDS IVA- 1---- Iper 14 dgays LENT 1-131 Concentration SR 3.4.16.3 3. Ridiochemical for f Determination I per 6 months* w ooelNtet R341.
- 4. isotopic Analysis tor odine a) Once per 4 hours. 2 [T Required Including 1-131, 33 n -135 wm-b .i Action Al -~ 3 n ciiyecesi EQUIVALENT 1-131 SR 3.4.16.2 b) One sample between .2 2 A 6 hours following a THERMAL POWER L change exceeding 15 percent of the RATED THERMAL co POWER within a one CD hour period.
CA) , Volume 17, Rev. 0, Page 247 of 471 Attachment 1, Volume 17, Rev. 0, Page 247 of 471 0 the seific actiy
~~~~~~~~~~~~UntI primrretedwhiit, %7 co 3.4.16.3
~~~~SR *Samuple to be taken after a minimumm of 2 EFPID and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours or longer.
0/)
Attachment 1, Volume 17, Rev. 0, Page 248 of 471 ITS 3.4.16
~
ITS ~ ~ I L II I I
~25 Figure 3.4,16-1 OPEFRAT1ON 15 ACCEPTABL S~~~~~
OPERATNOFRTDTENAPWA
>~~~~~PIU~3-DOEEUVLN -3 rmr oln pcfcAtvt mtVu Per~~~tit ofO RATED THERMAL POWERwrhtePmayContScic Actvity >11.OpCilgram Dose Equivalent 1-131 D.C. COOK -UNIT 1 3/4 4-24 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 248 of 471
Attachment 1, Volume 17, Rev. 0, Page 249 of 471 ITS 3.4.3 ITS LCO 3.4.3 3.'*9 .1 The Iaacear Coolant systac C cep cA a resslur'iei tSUempoar,= and 1hdrestatc Ctea vth
- a. A umauium beactup of 600F Lu any one,hour? period.
- b. A uaxlnsw cooldom o.1 000? to any one hour period. end C. A ws~aimu teapsratuta lehan$ of S? el Lan AMVon huitr puried.
during byduoscaCic testing oporations above sysana desip prescure. APELIWAITLfly At all tinee.' Addroposed Conditions A and C NoteIA. IJLth any of the above Uinlis exceededte m.weado ACTIONS A aeasure to vtthine. the lilut wvticd oto*tl A. f YE~c JA
~
andC ~ ~ ~ ~ rea~e of Wleactor Coolant S tm eecltam r Coolant 5suta.nae aeceptable for conttnued. operatos : I at leau:10 LI? Ad proposed ACTION B STANDS? v~tchin the nxt, S hours AnM reduce the I TagadpreSture to lssa Required ACTION 8 ~tha 20?aud SOD psi&. resp~etively. within t follo *n 30 bouts. fe Actions A.2 and M C.2 Completion
- a Tpec al ext EcepLon_1.10. 3 COW~C ,C LEANTL UN11T 1 3/A64.25 h~iN.17 Page 1 of 9 Attachment 1, Volume 17, Rev. 0, Page 249 of 471
Attachment 1, Volume 17, Rev. 0, Page 250 of 471 ITS 3.4.3 ITS REAMTR COOLANT SYSTE SURVUtLLMC MIUIRU4VITS SR 3.4.3.1 . a. The Reactor Coolant SYStem tomprature and pressure shall be detti'mined to be within the limits at least once per 3o minutes during system heatup, cooldown., end inservice leak and hydro. static testing operatlons.
- c. The/eactor vessel maearia irradiation survaillae iD htl 0sh~b removed end etx~am ned, to determine chapge in MartlA6 pw 6prties, at the into als shown in Table 4.4.5
- ults thse examinations s all be used to updto FfgurA .4.2 and D.C. COOK.- UNIT 1 314 4426 Page 2 of 9 Attachment 1, Volume 17, Rev. 0, Page 250 of 471
Attachment 1, Volume 17, Rev. 0, Page 251 of 471 ITS 3.4.3 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM ReactorCooleant S estemHauLimit atos[itot ri-sfrntum ttoi;r 2000
- operationabl fo 32EFP ofperatitnon ateril Heatup R l 135I20,C .1/ 10 17til50 --T 6--- De F 0 Deg. esaF/3HrFYCriticality Dg.
200
~
a- ~ ~ i LakTs ii Heatup Rate Li itibasedto CCrtiali 2750 60De.t/ Lmi 100 5 0 5 0 5 0 5 0 5 0 5 E~~~~~~vrg eco oln ytmTmeaue(e.F 1260~~~~~~~IUR .. RECO OLN YTE RSUE-TMERTR IISVRU 0 600 FH AECIIAIYLMT O.U II N EKTS II COKNCERPATUITIPg / -7 AENMN0 ~ 3 7 Criticality Page 3asof 9 Attachment 1, Volume 17, Rev. 0, Page 251 of 471
Attachment 1, Volume 17, Rev. 0, Page 252 of 471 ITS 3.4.3 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM F~~~~~gure 3.4.3-2oe T047., u .1%,N -0.0 Unacceptable 2000 Operation~t~o~ 1760 I ! ~* E~~~~~~~~~~~~~~ 12* C~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~"1 o i Soo ldw Rt 100~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 0 50 100 150 200 250 300 350 400 450 500 550 Average Reactor Coolant System Temperature (Deg. F) FIGURE 3.4-3 REACTOR COOLANT SYSTEM PRESSURE - TEMPERATURE LIMITS VERSUS COOLDOWN RATES COOK NUCLEAR PLANT-UNIT I Page 3/4 4.28 AMENDMENT 9S, 467, a~a 278 Page 4 of 9 Attachment 1, Volume 17, Rev. 0, Page 252 of 471
TAKlE 4.4-- 0 VESSEL MATERIAL
~~~~~~~rEACIOR IRRADITlNit____
SPECIMEN REMOVAL INTERVAL Capsule~ V, Iiy
*0 ~ Casl Y5M 0~~~~~~ , Volume 17, Rev. 0, Page 253 of 471 Attachment 1, Volume 17, Rev. 0, Page 253 of 471
(.0
Attachment 1, Volume 17, Rev. 0, Page 254 of 471 CTS 314.4.9.2 A. Amaximum heatup of 10O' inany one hour period,
- b. A maximum cooldown of 2 *Finmay ome hour period And
- c. A maximum spray water rature differential of O4F.
APPLICA ILITY: At all times. With th pressurizer temnperatur imits inexcess of any ofth above fimits, restore the temperature within the limits within 30 minutes; Perfo naayi odtrin he effects of the out-Of- mit condition on the racture toughness proper ies of the pressurizer; de emine that the p uize rmisacceptab e for'continued operation rbe inat lestO STAeNrDBYewmitahsin the nex 6 hours and reduce the Pauie pressu eto less than 500 psig wthin the following 3D hou S. 4.4. 9 2Tbe Pressurizer teiler tures, shall be determined tobe within the I iits at least once per minutes during System he& up or cool-down. The spray water tempera re differential shall be etermined to be wi bin the limit at least ce per 12 hours during au liary spray oper tion. 1D.. COOK UNIT 1 314 4.30 Amndment No. 23 Page I of 2 Attachment 1, Volume 17, Rev. 0, Page 254 of 471
Attachment 1, Volume 17, Rev. 0, Page 255 of 471 ITS 3.4.12 ITS LuimsTIN coND~Qn4 En OPERATION LCO 3.4.12.d 3.4.9.3 At Ias one of die fol~owin~ overpreswr proftection system shal be LCO 3.4.12.d.1 A. Two powe oprated relief valves (PORVs) with a lift sening of less Omaor eqWa to 435 ptig, Pr LCO 3.4.12.d.2 b. one power operated relief valve (PORV) with afift scowr~ of leas shinor equal LCO 3.4,12,d.3 j s Vened through a 2-square-Inch or larger y ri~qj w-ffeb Ad poosed LCO Note 2 AdrosdACT
- a. WithoamoftwIORVslrqed b ebma aret Wmdie ORV otRliR ACTION F safey Valve required by item b above inoerbl, eit1her restore the Inoperable ACTION G~~~~~~~~~~MMofI Rz- et ACTION G SR3.4.12.5 C. - Waith d1WRCSvetd eem ATOa orbtiniabole veify~lthe pahayr RVt ACTION G b. bone peRV Wi~~~thas 31day when the pafthwyI rddb valve s)nthat 1, lftosdseald, or otherwisof suedo hCid.. opepoiin ! otherwise,1 veriy h
- d. In a xthe,eithrWthe PORV, ot RRsaft orav as) RCSPveVar usWed hmidetham C m tnl SpoeclR shlbepprd kmnd tr the doys%mltepthas pu ovidad bo a 6.9.1swith~ 30Ls dayke. sIeraleportaaind sudsehirdo open psito:oti eiyd e 6f the POKVS WA~Pae 1ofl Attachment 1, Volume 17, Rev. 0, Page 255 of 471
Attachment 1, Volume 17, Rev. 0, Page 256 of 471 ITS 3.4.12 ITS SUMVEILLANCE REOUIREMEMT 4.4.9.3.1 Each PORV shall be demonstrated OPE LALE by d rposed SR 3.4.12.8 Note SR 3.4.12.8 Perfomwi3ce of a CHANNEL FUNCTIONAL TEST on dhe PORV aczuazlon days thereafter when the PORV required OPERABLE. SR 3.4.12.9 b oWnl fCLRTO n1ePR cao hne SR 3.4.12.6 C. Verifysn the PORV isolation valve IsoMe at leas once per 72 hours when the PORV Isbeing used for overprssure protection. C. Determining the enerency airkunk OPERABLE by verifying: SR 3.4.12.7 1. A!lat bw cm per 31 days. ar wek pressure Sreate than or equal to 900
- 2. Air pm sur neezoOPERABLE b rraneof a:
FU(/~7ONALTEST at esoneer31 days. CHANNL CHANL ASATO t least eerImots
.4A.9.3.2 The RHR WMez valve Shall be demonsuraed OPERABLE by:
SR 3.4.12.4 a. Verifyig tha the RHR System suction is allgru to dhe RCS loop widi the valves to theflow padopen atleast oncprl12houirswhen doRHRtsafety COOK NUCLEAR PLANT- UNIT 1 314 4-32 AMENDMENT No. S3, ZU.176 Page 2 of 14 Attachment 1, Volume 17, Rev. 0, Page 256 of 471
Attachment 1, Volume 17, Rev. 0, Page 257 of 471 CTS 3/4.4.1 0.1 314 L GCONDITONS FOR O ONAND SURVEILLANCE QIEET 314.4A E COOLANT SSE 3.4.10.1 The structural integrity of the Code Class 1, 2 and 3 cmomsshall be maintained in accordance with Specification 4D.101. PPLICABIL ALL MODES
- a. With the structural integrt of yASME Code Class I cop ~)not conforming to the above requirements, restore the rctu integrity of the affeteco ens) to within its limit or isolate the affected compo ts prior to increasing the Reco atSystem temperature more than S0'F above the miiuntemperature required by NDT ertos
- b. With the structural Inerity aany ASME Code Class 2 compo ns)not conforming to the above requirements, retre the tuctural Integrity of the affected netsto within Its limit or isolate the affected compo I(s) prior to increasing the R CoatSystem temperature above 2001F.
c.. With the structural integriy any ASME Code Class 3 e ens)not conforming to the above retpulrwznets, restore hsrcua integrity of the afce moens)to within its limit or isolate the affected eapnn~}from se-vice.
- d. The prov~~om 3.0.4 Ilre of BatSpecificad applicable.S COOK LA PLANT-UNrT I page 314 4-33 AMENDMENT 09,117 Page I of 3 Attachment 1, Volume 17, Rev. 0, Page 257 of 471
Attachment 1, Volume 17, Rev. 0, Page 258 of 471 ITS 5.5 ITS 3/4 LWIMIIG CONDITONS IFOR OPERATI[ON AND SURVEHLL1'CE REQUIIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.0IQsTRucuRAL liNTEGRITY See CTS ASME CODE CLASS 1.2 and 3 COMPONENTS 13/4.4,10.1) LIMITNG CONDMTON FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1,2 and 3 components shall, be maintained in accordance with Specification 4.4. 10. 1, AE&MaM~fl ALL MODES ACTION: L With the structural, integrity of any ASME Code Class 1 component(s) aot conforming to the above requirements, restore the structural integrity of the affected component(s) to within Its limit or isolate the affectd component(s) prior to increasing the Reactor Coolant System temperaure more than 50OF above the minimum temperature required by NDT consideratdons.
- b. Writh the structural integrity of any ASMdE Code Class 2 component(s) not conforming to the above requiremnents, restore the structural Integrity of the affected component(s) to within Its limit or Isolate die affected component(s) prior to Increasing the Reacto Coolan System temperature above 2001F.
C. rith the structura.itegrity ofany ASMECode Class 3 ompon ts) not conformilngro the
- d. The provisions of Specification 3.0.4 are not applicable.
5.5.5 4.4.10.1 In ad4rnto the a of caln4.0.5 each reactor coolant pump flywheel al COOKNUCL teAR yhe oth 1iceo onLANTiUfrr Pag er3/ 4.33 rasufceeaito A mENDMeNT part21 eprovsions fSR 30Pagen 3of3 16 69 Attachment 1, Volume 17, Rev. 0, Page 258 of 471
Attachment 1, Volume 17, Rev. 0, Page 259 of 471 CTS 3/4.4.1 0.1 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM This page intentionally left blank. COOK NUCLEAR PLANT-UNIT I Page 314 4-34 AMENDMENT 98 Page 2.of 3 Attachment 1, Volume 17, Rev. 0, Page 259 of 471
Attachment 1, Volume 17, Rev. 0, Page 260 of 471 ITS 3.4.11 ITS 314 LUM71TIN( COMMrrONS FOR OPERATIN AND)SURVEILLANCE REUIREbMETS 3/4.4 REACTOR COOLANT SYSEM4 RELIEF VALVES - OPERATIN LIIIG COMDITON FOR OPERATION LCO 3.4.11 3A.11 Threepower operaedrelief valves (POR Vs)and teir associatedblock valves shllbe OPERABLE. APPUCABILITY: MODEIS 1, 2, sand 3. ACTIONApsd ATIN CKNSNt 1 1 ~ ~ ~ ullcq ACTION H houtrs-&f napnd HO STDOWN owng 6 hlous. Lihisdie waoitd lc ACTION B fron the lock val thrwise be n at least wIs,, be HOT STANDBY within t amdI benxe6hw ACTION H HOT an i SHUTDOWN withintthefoolowipg hours. 6 ACTION ~~~b With ton PORV!9 raopeWE55ohmbi xesEaI55 ihnIb~ RequIred Acin 9.had .a(ouhe blok valvs (RatM sumato sthe m soIciPted blo OvEalvean reaove pwetinr Required DfromtheAction oursWe, ot-rwi OeI t es HOTAB SADYwithin die ex6 hours o and inHO ACTION H ScHUTheOWNowithi6 ours. owm 6hor. Reqire Acion 8 an 1.2 Wifomthoe block valvpige' attn n fteIoerable within PMt PMEsai ACTION C SHUTDtOiWN e ORwing nins cotrlem.yewr . ACTION H cm_ beYR lo ACTIONS nd G -r---C E Wbhtworthreebokmvale i 6RAREo tbokVle Required ActionsC.1 n . .-- fi oavlelnb ei H OTrSTherYwenianif 5Lebi vus-n OS C RequIred Acio AC.nth Required ActionG.1~~~~~~~~~~~~~ird ctn . Required El -. Actio tlockEBL Withvanes V tatus wih theoowur I 95ti etwhe In~HOTvSTADB ACTION H wti h et6husadI HOT SHUTDOWN within the followiqg6 hours. (~~OOK 'LANT-UNFF NUCLEAR1' Page 314 4uire AfoE`1aME .1NDMNote ~0 7 ACTINS Wth woandG o fte blck al b=,M rmyttms fATIMRe~Pag~e 1o Attachment 1, Volume 17, Rev. 0, Page 260 of 471
Attachment 1, Volume 17, Rev. 0, Page 261 of 471 ITS 3.4.11 MS_ 3/4 LIMING CONDITIONS F OR OPERATION AND SURVEILLANICE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEm LIMITING CONDMTON FOR OPERATION (Continued)annocpbl ACTIONS Fand H - t~fJ With PORVs and block valves not nthe sa ieh cOao 0 Required Actions B.1 and13.2 1buletrtevvS0 P Required Action C.1 control in each rapctive line~. pp y meporonas o XC Tc or a abve. aeang ACTIONS F and H ATOA fQE sWmpdate for two or three liinesuavailab ACTIONS Note 2 h. The provisions of Specificatin 3.0.4 are not Applicable. 4.4.11.1 (nsad&'ion to the red1ru~ent of SPtfcto 405 c ORV shal be demonstrated (j OPERA~BLE:
- a. At I olnce per 31 days by pao of a CHANNEL PUN A ET xldn Z SR 3.4.11.2 b. At least once per mon-ths by operating the PORV Chzough one complete cycle of full travel during MODES 3 or 4, aM SR 3.4.11.3 C. At least once per mwonths by operating sloleod air control valves andi check valves In PORV control systems thtough one complete cycle of full travel. aEd SR 3.4.1 1.1 4.4.1.12 Each block valve &haI,be demoenstrated OPERABLE at leas once per 92 days by operating the valve through one comvlete cvclqjof fif trael unles the block valvo Is dlosed in artder to meet the requirmets of ~C dI lnbe o pecification 3A. LI.
4.4.11.3 Deleted. COOIC NUCLEAR PLANT-UNIT I Page 3/4 -4 AMENM ENT 144, 44, 476, 211 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 261 of 471
, Volume 17, Rev. 0, Page 262 of 471 CTS 3/4.4.12.1 WsatINW op"Ind weI la 8egiS., PV"V~ S CuesIs De csat shall be M12A MAu closed.
So is boch DE ihe least Vessel %00M ,.st patiosLaeperble, ad at UeSSR @se of the lie. us, staern sPsMI wet tha C13IMZZ Case Spesit~atleu 3.4.1.3 eperaties, is wool to 2a SOTv 4mny mostimmo jprwtded the iamoreabie vat paths a maktalaed eased With Powe remwe1 She valve astuac srs a5 GmU the rmtw17 Operated valise. Is elboth spesabhie wst thai restore at least eNW of the tUnt he "it pa: wtbia 36 days sr "essel be ia 3V? Mna? wich 4 boueers lauCmL witbis h b.. Wish both of the tea Vessel head Vast pt aNW betheofhe fresswleer steam cap "Mwet peths lapwbl s~ asitela the Inoperable gest Pats losb" with Pontr rIny 4 fig the valve actmtews of all of a rsately operated val, a In all 61 the inoperable "eat PAth restore sago of h as Irhle feat pathe frm either the laces9 fm esl head useS rorc a Presewlaer #te$* spass, visbla 73 boars of be Is U6Z IAIDI! his 41bees aid in coil sanui witbia 4;cuilsvla 36 hhu.
- a. The pmvaLos at :I Ustbaatm 1.0. ae not apl~eable.
C. ~~~~~~~3f4 4-37 hMauhto 9g Page 1 of 4 , Volume 17, Rev. 0, Page 262 of 471
Attachment 1, Volume 17, Rev. 0, Page 263 of 471 CTS 314.4.12.1 3/4 LTMJThINGC M~I'ONS FOR OPERATION fDSURVEILLANCE REU i ET 4.4.12.1 BO Reactor Vessel head vent paths shl be demonstrated OPERAB -at least once per.
- 1. Verifying the common manual slation valve in.the Reactor vessel dvent is sealed in the'open position.
- 2. Cycling each of the remotely predvalves in each path through at least one complete cycle of fall travel from the trtRoom while in Modes 5 or 6.
- 3. Verifying flow through bohof the Reactor Vessel head vent ptsduring venting operation, while in ModsS 6.
COOK NUC R PLANT-UNIT 1 Pae344-38 AMENDMENTg96 243 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 263 of 471
, Volume 17, Rev. 0, Page 264 of 471 CTS 3/4.4.12.2 ting of aw* tt y pesatd vallm La :e.pmondr fom
- a. Lab be bu@te ~ss a man=saed we aekeeab JOBSoIt.2, 3, ab 4~o 7* a4ytpisWhR
£L atik pofL4Os TMe Lam $tm l space. e~ eatu Iqae I*se Lab p the: :inyed the valels atat of A1l t e -.
mte1~ gewste ral .14. oila tbs kepe* u. At pat-.;
- 5OU0U is the 1.1 20 bows.
. tbbto~th QC tasP tui nraemva "at b..esd bel&ato th. Rsee eastVessL ae vast pathis f =0peRabTA -fgktbs AmkprAzale vast pat'. lased with pm:e v frig the velve astmet~ft of Al ind eMcl. atewated'wA a Wa ll of tbs Laqierable omt Paes zeetwemiseq.tbs a~em. sh Exm either the leat tvslel bke$ wee,~f : am-1relwa:
ovgea" vbia 72bors :be' s X2'3?h5! iabo s CUD Azmouu wishis. folmvift 30 bow... a* 2he Fovishlow of 0 ISSUcfaI 3.0.4 awe set mppljcbls. D. CO co KiIU J. 4-3. '*4 98 Page 1 of 4 , Volume 17, Rev. 0, Page 264 of 471
Attachment 1, Volume 17, Rev. 0, Page 265 of 471 CTS 3/4.4.12.2 214 LUTN oN~Ol1o~l~ AMBMVZMIM1CB AIM ~~~Pzqutdb mtem sPec v ath shaU be desnumufaad LBat lowm o=c per I Vcx1oIng fth ciownw Isoatloi yah In dw mtumn spum veaL is 4Cyclin Cub oclb %a perawe web"e in each PM&i linesal n mzJ eycle of full tiy! w m Cotu Rooum while In Modes 56 Vard4gflowsd throgh 1 of ame Pesswiw steam sp4"vn pals dmrin veerin ocpntiak *WhelIn~ m ar6. Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 265 of 471
Attachment 1, Volume 17, Rev. 0, Page 266 of 471 ITS 3.5.1 ITS 314 LIMING CONDMIONSFOR OFERATONAND SURVEUNCEREQURtEWNI 31445 EbRGENCY CORE COOLUING SYEMS(ECCS) LWMING CONDMTON FOR OPERATION LCO 3.5.1 33.2 y5.1acmuao shall be OPERABLE with: SR 3.5.1.1 L. Theisolation Valveopcm SR 3.5.1.2 b. A contained borated water Volume of between 921 And 971 cubic feet SR 3.5.1.4 C. A boron concentration between 2400 ppm and 26D0 ppm, and SR 3.5.1.3 d. A nitrogen cover-prssure of between 585 and 658 pdg. hJAPP LAB: MODES 1,2and . ACTION A a. -W~ith oe accmultwor inoperable, due to boron m taon, nta wii limits, restore boron ntao to Within BiMWtwithin 72 hours r be -inat least Mdode S within the cmx 6 hours' ACTION C atdrdueractor coolant system pressur to less tha or equal to 1000 pslS within the following ACTION B b. .... J--ith one accumtulator inoperable for reasons other ecncnraion not within fizulits. Lwoh acumulato to OPERABLE saums within ar be In at leas Mode 3 within the ACTION C mmx6 hours adruce reactor coolant system presure to lesthan or equal to 1000 psi *if Adoosed ACTION D j 435.1 Each accumulator shal be demonstratedl OPERABLE: R. At lcwtowe per 12 bourby. SR 3.5.1.2 1. Verifyin the contained borated water volume and nitrogen cover-pressure in Mhetanks, SR 3.5.1.3an SR 3.5.1.1 .2.. VUWrlfyitat each accuzoulator isolationVal Isopen Applicability 'kpa Colanm System Pressure above 1000X p.1g. COOKNUCLZARPLANT-LMI1 lag 3145 AMN MW6 44 237 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 266 of 471
Attachment 1, Volume 17, Rev. 0, Page 267 of 471 ITS 3.5.1 ITS 314 LIMTNGCONDMTONSFOR OfRATJONAND SMVURYIL CEREUmMENTS 314.5 EMERGENCY CORLE CGOOLNG SYSWWMS (ECCS SURLVEILLANCE REOUIREMENTS (Contlnued) SR 3.5.1.4 b. At kess once per 31 days and, for the affecte accumulator*),!wjhl 6 hours after each solution [ f vohume Incms of greater tha or equal to Liiof 1iia1diu Idts no the result of addition ftom did retfaeling water storage tnk by veifyin the boron concentration of the accuulator solution. SR 3.5.1.5 C. At least once per 31 days when the RCS pressure Isabove 2000 pinr, by verifyin ftat power is removed from each accumulator Isolation valve operator. coOKNuCLEAR PLANT-UNIT I 1-sp 34 542 AmmIbn:NT4eq, .4.,e4, 237 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 267 of 471
Attachment 1, Volume 17, Rev. 0, Page 268 of 471 ITS 3.5.2 ITS Ec= SUSSvSTIMS - sgoof
.621TING CIO?~ITTOR.FMR0 M-TfAIMN LCO 3.5.2 W ulb- W
* .0a 0Pa tLraitfa1 i : al ,qvP
*.Af cp. flow p& pable e. 3kt ml'of u~
M-A wtmi a rnt a u nkan1Sa iyrdtrticl -&I1 adE
- transf as s4oclui -.he C~&tlr *~ 4uHi clr;.
ruen~ Ca~l_. MhansOgl ratn. APUMIA3lTYT~: MM 'I, Z aiid 3. ACTION A ~ csg~yt2t ic U~Ia nea1p-ACTIONB Xi% u OFM?.IM-9 WU= tzShift 7Z howa si't In HoT VVrr C..cKWnZ v(I - the E I 4 I nsne i.E Re , SPgei1 r cam~~~nt SY~~t" oft Attachment 1, Volume 17, Rev. 0, Page 268 of 471
Attachment 1, Volume 17, Rev. 0, Page 269 of 471 ITS 3.5.2 ITS DIERGENCY CORE CCOL&ING Says TELs SURVILLANCE REOUZREMEURT3 SR 3.5.2.1 4.5.2 Each ECCS 9UbSYstfF shAll be dewostratad OPERABLE: A. At least once uer 12 hours by ver'ftying that thes following valves au's in the indicated-oositions with the cenwo1. power locked out. Valve Numlber Valve Furictibn Vatve Position
- a. 1140-390 . a. AWVTto'RHR a. Open
- b. IJJ'0-315. b. Low head St b. Closed to Htot Log C.
- c. 0-325 c. Low head St c. Closed to Hot Log
- 4. Th04B d. Mini flow lfine d. Doen e8. 114046 *. Mini flow InMe e. Opeii
- f. 114-251 f . St Suction 7. open SR 3.5.2.2 b. At least onice pe 31,days byverifying that each valve (manual,
- power' operated or automatic) In the flow path that is Fiat locke",
sealed, or' otherwise secured in position, Is in its correct post tion. C. By a visual-inswetion whiih Verifies that detris soIos (rags trash, clothing, e )i present int ontainment which could be teansporta to the contafint .mp and Cause ros tion of the pump vfs Iinspectfoet Shal Wtoris. during LC performed: nitions. This (~ I. 1cr all accessble rate of the contal ntprior to establishing Coo'! Hu ITKMT
-? a 2 Of the areas 0t ted within cantr nt at the Completion of each Contal nt entry when CoTA NTLGRZY is IN establifshed.l
'Yjive siust change poslw~td uring the SWit fo njlnI a Valve loa oile LOCA. 54rfoinat O.C. COOK L'UNIT I .3/4 1.4 AW566At No- 98 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 269 of 471
Attachment 1, Volume 17, Rev. 0, Page 270 of 471 ITS 3.4.14 3/4 LIMITING CONDITIONS FOR OPERATION AND, SURVEILLANCE REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) SURVEILLANCE REQUIREMENTS (Conti nued) SR 3.4,14.2 d. At least once per 5months by:
- 1. Verifying the automatic interlock action to prevent opening of the suction of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
- 2. A visual inspection of the containment sump and verifyin that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
- e. At least once per 18 mnonths by:
I1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal. See UTS
- 2. Verifying that each of the following pumps start automatically upon receipt of a Safety 3.5.2 Injection signal:
a) Centrifugal charging pump b) Safety injection pump c) Residual heat removal pump
- f. By veri~fyig that each of the following pumps' developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to specification 4.0.5.
- 1. Centrifugal charging pumps
- 2. Safety injection pumps
- 3. Residual heat removal pumps
- g. By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
- 1. Within 4 hours following completion of each valve stroking operation or maintenance on fth valve when the ECCS subsystems are reuie tob 3PRABLE.
COOK NUCLEAR PLANT-UNIT I Page 314 5-5 AMENDMENT 407,4*36, 444,4+48, 464, WG3, 249, 275 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 270 of 471
Attachment 1, Volume 17, Rev. 0, Page 271 of 471 ITS 3.5.2 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) SURVEILLANCE REQUIREMENTS(Cnnu)
- d. At least once per mnh y j
- 1. Verifying the automnatic interlock action to prevent opening of the suctionl of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
LSee ITS 3.4.14 SR 3.5.2.7 2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion. C. At least once per motsby: tha inot locked, sealed, or SR 3.5.2.4 1. Verifying that each automatic valve in the flow path acuts to its correct position on a SR 3.5.2.5 2. Verifying that each of the o umnps start autornaticl nreceipt of a R E SR 3.5.2.3 f. By verifying that each of the o pms' developed head at the test flow point i rae 1.7 than or equal to the required deeoped hawentested pursuant to specification 4.0.5. Centrif acaring u s
- 3. ResdIa heat re~vIPUMPS SR 3.5.2.6 g. By verifling the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
(valve when the ECCS su~~esare required to be OPIBE COOK NUCLEAR PLANT-UNIT 1 Page 314 5-5 AMENDMENT 4W, 4-26, 4-44, 448, 464, , 249, 275 Page 3 of 8 Attachment 1, Volume 17, Rev. 0, Page 271 of 471
Attachment 1, Volume 17, Rev. 0, Page 272 of 471 ITS 3.5.2 ITS 314 LIdiTING CONMMTONS FOR OPERATION AND SURVERILMC REQUIRUMMS
-314.5 EMEGENCY CORE COOLING SYSTEMS (ECCS)
S1JRVELLANCE RMTRE~ EMMMT (Confinuod) . SR 3.5.2.6 2. At nc e 24s IflWitin ,~I 0ef Valve Number Valve NuMIer
- 1. 1-S1-141 LI 1. 141I-121 N
- 2. I141-141 1-2 2. 1414-21 $
- 3. 141I-141 1.3
- 4. 141-141 LA4 IL. perorming a flow bdalac=et E subsystemn that a~ehe sudw followbg cspeio!modificaions to meo er flow hratrscsadthe following flow C Boron Injection SystemSfeyJjcl ysm Sile PUmp inl Lop 1Boron Ii~jection Fow Looplm nd 4Cold Leg 117.5 gpm Plow2300gpm Loop 2 Bo=nrjctlm Flow Lov 2mnd 3ColdLet, 117.5gp Flow k3O00gPM Loop S Boroin Injecton Flow **Combined Loop 1, 3 mad4 Cold Leg 117.5 gpai Flow (simgle pump) lathan or equal to 640 gpm. Tota SS( Pump) nlow, Inuding Loop 4 Boron h1jeet~w Flow mildilw, shlli t e 675 gpm, unless the 117.5 gpm yppis speclflallytulfeto a blgbaflow up to am-Axlu-of ()Ogp.
*The flow in,each Samo hijectinm (El) r souIdbe adjusted to prvide 1I .5pm (nominal) flow in enoh loop. Ud these cond~tons thm Is zer o and SO gpm plus of 5 gpm simulated RCP seal
-ktbI fow.
The actual ineach DI line may deviate ame nominal so long as: a) differencebetween the hihest lowest flow ls 25 Wpm or lessi. b) talflow to the four branch doso exceed 470 gpm.
) minIMum flow (towa flow) gfsth three mos conservaive flow) brnch lines must not be I1 thm 300 Spm d) chargIng pump dilschre (2.31 x Pd/Qd2) must not be ea tha 4.73E-3 f/V&m and mms begeter thn.27E-3 (P lts the pump disharg prm at rMMut Qd is the total pump COOK NUCLEAR PLANTUNVW I Pops 3145 AWEDO)MPIW PS, 4I, 229 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 272 of 471
Attachment 1, Volume 17, Rev. 0, Page 273 of 471 ITS 3.4.12 ITS EM1MED- LOU MOLMl ELSMhI reel $nuSSYTVS Trav C 3!CF 3.5.3 As & mnimusm, one ICCS subsystem comprissd of the following shall be OPUMALE A. One OflUALZ centrifulal, chaging p'mp,,
- b. Ona, OUANU rasidual heat removal beat exohaziger. See ITS)
- c. One OMUALS resiftal, heat removal, Itmp. and353
- d. LnII 0111A3 flow path capable of taking suctiau fro. the refueling Vatsr storage tax* 'upon WeAS manually realigned and trarisfernrtg atictian to the containment sump during the Recirculutioa phase of
- a. Vitch ro KCCS subsystme CIDAIL becamse of the Inoperability Of either the centrifugal charging pimp, or the flow path frau the refueling vacaer storage tank, restore at least one £CC subsystem ca OflIALE stoatu within I hour or be LaflCOLD MD whn the "SeeITS next 10 bouts. 3.5.3
- b. With no V=C subsyscem, OPEA111E because of the traperabil-iy of either the residual heat resioval best exchanger or reasddual heat removal pimp, restore at least one 9CCS subsystem to O?7A1MX status or am~naizcan the Sesacar coolant Systea Tavg lees than 350 F by one oil a mteratheart nemvl. mdmhos-.
ACTION A, a. Uith more tdan cagg mpOPIULSL or with a safety ACTION 8 La oeteft-omm a OPAL the toevatmrats of cay =3S cold log 6 L3 Appliabi lily P(s) mA the safet injection s) et roun e r era17
-* h: 1 e-~
mtIn m e2iactuated and inj Ones water Lnat Seehe subsitted to the Cemoission pursuant to Specification 6.9.2 vitbinSeIT 90 daye describing the atircwsamanca of th. actuation and the total 3.5 .3 ancqmialtad actuarion ovolas to data. LCO 3.4.12.a eLmaximu, f a centrifugal charging pump shall be OFEWAIS a:d both safet ineWon amoshall-be imarable 16nvr the eamr of OAt Applicabilityor ar of the ICS cold legs ts less than or eulc II
'COOK VUCLUIA PLILJT WIMT I 3f4 5.7 AMC=~1. .16 .
Adpoosed LCO 3.4.12 Note I L Page 6 of 14 Attachment 1, Volume 17, Rev. 0, Page 273 of 471
Attachment 1, Volume 17, Rev. 0, Page 274 of 471 ITS 3.5.3 ITS Icel MM=TTE'.
- Twn-< 350o LCO 3.5.3 L?!M!TWO COM~IT1OR 70 OpD.ATl1t 3.5.3 As a minimuu, owi £CC$ subsystem C riced of the olloving shall be M 3e
- d. An OPEWALK o path aps o~f taking tion trom the efueling vaterst aeo t Wkuon be inai.a It- Liped xAndcc far::ng suction to
- containmev sump during recirculat. phSO Of operation.
AFLCAtLITY: MODE A. ACTION C ~ gga cari ACTION A mPt-!~r'h lea s ooazte Sytm jca aeot.sall ons ,.$'Sparsy an suL thedt thesColsi h ursatt C 5pcZc~o 4.9.2widhi y I0Munacrlestin ath leapstaumm~ of itytheaedom to OtE totLL. umuated orenAIAtuaeo Rc~lstor dooanta.Isste Sse 5 mma Wit more thentruam charging pump 07AAbeoOALtEa safety safty mjetio papath shafe.ty injoperabl *eneuewr he qracut rs o oer 3.4.123 ormoe f the leg is les ha o thecol ineqcltO 5? ULast PLAZI RoV~ SystemTa. I' 57 t sall DIU andU16 20 thedescribing 4 tn**&Of tPagehe oft4 Attachment 1, Volume 17, Rev. 0, Page 274 of 471
Attachment 1, Volume 17, Rev. 0, Page 275 of 471 ITS 3.4.12 ITS MUM NOLUM m oUflAa per dw applUeabL. [See ITS 4I'5. T MO susyste sU&U~ b dmmtattac 3,5.3 ISuiwwsmlin MtUI?.mInts of 453.2 SR 3.4.12.1, 9*orbroftUSclISLals hofme o Applicability am cmO NUCLIa ?LUM . UNA1/ 5.6 MaXAI0 F9, Page 7 of 14 Attachment 1, Volume 17, Rev. 0, Page 275 of 471
Attachment 1, Volume 17, Rev. 0, Page 276 of 471 ITS 3.5.3 ITS
&S ICCS ~euh SR3.5.3.1 .5.S.Itern shafl. be cad the app2R 3.5.. a p~ine 4.5.5.2 ll chazl~g arni decy b~ot~s~ pis. ezoejt the modiidb teNt) requtred p~~. aball be dem eba~~~iagOFRAILK ~ ~ SRc3a5o23, SR 3b5.2b6 4-.31 llsrgin Vd~ a nd1s pe osct~ih eastey r~s aCScol 1h5 abv LAP between 152 f =Wi 200 F.
COOK MUCLUIAM 111 UIT 1/4 gm 5.3 ANIh1E? 0. ZF
- ~~~1674 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 276 of 471
Attachment 1, Volume 17, Rev. 0, Page 277 of 471 ITS 3.5.4 ITS 314 LIMITIG CONDITONS FOR OPERATION AND SURVEILLMICE, REQUIREMENTS 314.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) LCO 3.5,4 3.5.5 The reiling wazer soage tank (RWST) shall be OPEWIABE widu-SR 3.5.4.2 A. A ainimum contalined volume of 375,500 gallons of borated water. SR 3.5.4.3 b. Betwwea2400mnd 2600 ppmn of boron, and SR 3.5.4.1 C. A minimurm water temperature of 70"P and amaximum water temperatur of t0DIF. ACTION B -{Tt h euln ae trg akiooal.restoetetn to OPERABLE staws within I liourlor be- in at ACTION C Ii~ O TNB ihn6husmdi ODSHUTDOWN within the Followng 30 hours. 4.5.5 Tbe RWST shall be demnodstatedl OPERABLE;
- a. At lenstonce per 7daysbr SR 3.5.4.2 1. Verifyin the contnaind borated water level in the tank~and SR 3.5.4.3 2. Verifying the boron concentration of the water.
SR 3.5.4.1 h. At leant oce per 24 hours by veriyng th RWSTtlempershmr. COOK NUCLEARIPLANeUMIT Page -1451 AhME MENTS444,U24, 234 Page I of 2 Attachment 1, Volume 17, Rev. 0, Page 277 of 471
Attachment 1, Volume 17, Rev. 0, Page 278 of 471 ITS 3.6.1 ITS 314 LVAnIWG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUREMENTS-314.6 CONTAIMENT SYSTMIS 3/4.6.1 PR-MARY CONTANMEN'T LCO 3.6.1 3.6.1.1 primary b M LAE LMUMl: MODES l.2.3 and 4. ACTION A piay CONTar ~ ~ ~ RM & B L T 0et- w~ti ane hour or be' ACTION B O..{j At least NOT ~ t~ et6 hoursand in C DSHTONwithin dhe followbng 30 hours. SURVEMiZZEQQEE IOERABILITY L M myasz 31 days bym-
- 1. All pemetralons =o capable of beig closed by OPERABLE contanent auoaicsolation valves md required to bt closed durinS accident conditions arm dosed by valves, blid flanges, or deactivated xweonatc valves securd In See rTSJ ihei positions. ecept for vaushar dwei open nufte admhnisratve control as 36 pemndby Specification 3.6.3.1, ad
*Excpt valves, blind fiazkges, and deactivate ,tmatic Valves whichar located insde the contami nmetad.
locked, sealed or otherwise secutred Inthe dosed padomiza These penetraions shal be verified dosed See ITS during ewch COLD SHUTDOWN except tat such verificedaon need not be performed more often tda once per 3,6.3 92 days. COOS NUCLEAR PLANT-UNI1T 1 Page 314 6-1 AMENDUME pg, 60, 181 Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 278 of 471
Attachment 1, Volume 17, Rev. 0, Page 279 of 471 ITS 3.6.3 ITS 314 L!MIT1NG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUflEMDWMrS 314.6 CONTAINMENT SUSTMS-S14.6.1 P-=Any COAIMN LIMITIN CONDMTON FOR OPERATIOl L3.6.1 3 3.6.1.1 PrimarY CONTAINENT INTEGRITY ShWl be lrind ALCAEIIJLHMX MODES 1, 2,3 and 4. RequiredActions L M least ~~~~ ~ ~ ~~ ~ Ib~LAddproed prequired ACTIONonste2sn C2, 3,1 A.2 .2,1. nd Al pACrtic oN ca dose andOPERABLE ctAi, B. and noCokd SRIO 3.6.3.3 OTSADY knftC ~m i ow .. SReqie 3.6.3.2,~tsI n ndSs3... ad36.. SR 3.6.3.3,Kmd sldn"aeo SR 3.6.3.3 fdanges, cloesed byvVlvebind or r oated Insmaid deactivatdatmtcvle hc thles conraiinca a ecrd SR 3.6.a3ke.se2d rotewsescue iiedse osto. k esveri fle ose shalv 3T1ese [oieruhoc SR3.6.3i.e3c ODSLTDW xcp htsuhvrfcainne nrb eromdmreotntanoc e
- P~~~~~~. AUcjdayhKa.oe adseld COOKINUCLEARPage 314 6-1
&.NT~~iNIT AMENDMENT PS, ISOee181 b.
dA echconahentWrloc y al* i ina~~a=wih Te Pagem 4fof610 Attachment 1, Volume 17, Rev. 0, Page 279 of 471
Attachment 1, Volume 17, Rev. 0, Page 280 of 471 ITS 3.6.1 ITS 3/4 LIMITIG CONDMTONS FOR OPERATION AND SURVEIULANCE9REQUJJI3MENT 314.6 CONTARMNME SYSTEMS Lflvffrnmo CONDION FOR OBK'O LCO 3.6,1 3.6.12 Conitainmentlek rates sballibelmieto
- a. An overall integrated leakage, rate of~ L1, 0.25 percent by weight of the contanment air per 24 hours at P,, 12.0psig, and See flS b.
I A combined lealmge rate -of&0.60 1, for ill penetrations and valves subject to Types B and C tests wheuapresquized to P.. - 4 5, J Tyes Ctests too 0.60 Lprior to as the Reactor Coolant aoe20*7 SR 3.6.1.1 4.6.12 Perform lekaerate t aciv4ordance withlI CFR 5OAppendix JOption B, excepts hsi Seef Notes: Se ots 1 A one-time exception to the requirement to perform post-modification Type A testing is allowed for the
&team.generators and associated pi;ing, as components of the conitainment barrier. For this case, ASME Section Ileak testin will be used to verify the leak tightness of the repaired. or modified portions of the containment barrier. Entry into MODES 3 and 4 following the extended outage that commenced in 1997 See ITS may be made to performthis testing.55 J 2 The Type A testing frequenc specified. in NEI 94-0 1, Rtevision 0, Paragraph 9.2.3, as '...at least once per 10 years based on acceptable perfbreaance histor 3 ' is modified to be '...at least once per 1S years based on acceptable perfomance history." TIs&Change applies only to the interval following the Type A test performed in October 3992.
COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-2 AMENDMIENTS, 460, W, 496, 209,U4, 274 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 280 of 471
Attachment 1, Volume 17, Rev. 0, Page 281 of 471 ITS 5.5 ITS 3/ LiMIrEING CONDMONS FOR OPER~ATON AMD SURVEHIANCE REQTJIRmEN'Im 314.6 CONTAINfMEN SYSITEMS __ See ITS CONTAINMENTLEAKAGE 3.6.1 LIMITING CONDMTON FOR OPERATION Add proposed ITS 5.5.14 and 3.6.1.2 Containmnent leakage, rates shal be limited to. . 5.5.14.a 5.5.14.b, 5.5.14.c, a Anoveral integrated leakage rate of~ L:,, 0.25 percent by weight of the conaimntA. 6.5.14,d.1 per 24 howr at P. 12.0 psig, and 5.5.14.d.1 b. A conibined lealage rate of &0.60 I. for all penetratiom and valves subject to Types BL. and C tests when pressurized to P,. A?~~LL~~flI: MODES 1,2,3 and 4. 361 5.5.14.d.1 combined, leakage rate for all penetration and valves subject to Types B and C test exceeding 0.,60 L..re-store the SURVEMLLANCE, IEURMNs 5.5.14.e 4.6.1.2 Perform leakage rate testing int Accordance withi 10 CFR 50 Appendix I Option B, except as niodifled byNRC-approved exemzptions, and RegulatoryGuide 1.163, dated September 1995. See Notes Iland 2.I
- a. Each. coutanmntai lock shall'be verified to be in complianc with the Reqryireroents of [S. ITS I Specification3.6.1.3. 3.6.1
-'Mprovisions o ,4 caon. oap 5.5.14,a.2 I A one-time exception to die requirement to perform post-modification Type A testing is allowed for the Steam generators and associated piping as components of the contemnent barrier. For ths cas;, ASME Section M leak testing will be used to verify the leak tightness of the, repaired or modified portions of the containment barrier. Entry into MODES 3 and 4 following the extended outage that commenced in 1997 may be made to perform. his testing.
5.5.14.a.1 2 The Type A testing ftequency specified in NEI 94-01, Revision 0, Paragraph 9.2.3, as "...zt least once per 10 years based on acceptable performance history' ismodified to be "...at least once per 15 years based on acceptable performance history."' This change applies onl to the interval following the Type A test performed, in October 1992. COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-2 AWMENDENTAI 160, UM,496, 09, 48, 274 Page 17 of 69 Attachment 1, Volume 17, Rev. 0, Page 281 of 471
Attachment 1, Volume 17, Rev. 0, Page 282 of 471 ITS 3.6.1 ITS 314 LLM1TING CONDITONS FOR OPERATION AND SUREILLANCE REQLULREMLNTS 314.6 CONTADINMNT SYSEMUS Thi page Imenuoufly left blank. COOK NUYCLEAR PLANT-UN IT Pape 3/4 6-3 AfMENMENT 4UO, 137 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 282 of 471
Attachment 1, Volume 17, Rev. 0, Page 283 of 471 ITS 3.6.2 ITS(II 3/4 LLbITIG CONMMTONS FOR OPERATION AND SURVEILLANCE REQUMIREENTS 314.6 CONTAMINMNT SYSTMIS CONTAINMENT AIR LOKS LiMITMNG CONDMTOD1 FOQR QMEATION LCO 3.6.2 3.6.1.3 Each coataimmnt air lock shall be OPERABLEw L. Both doors closed except when the used for normal transt entryad xtA. through the conmainme=,4n air lock door shad be dosed, and Ib. An oVeral aklocklabagemmof90.05 at P.12 psig See ITS 5.5
~ZEIJ~~L~:
MODES 1,Z,3 and 4. Add prposed ACTIONS Note 1 [Add proposed ACTIONS AKAdpooe.ATOSNt and B Ad rposed ACTIONS Note3 ACTION C fWith mair lock go ~rable~restore ih air lock to OPERABLEatazawlhn 24 hours rbein atleIstHOT ACTION D -[STrANDBY within the next 6 bours and LnCOLD SHUTDOWN within the Molowing' 30 hus . Adproposed Required ActionsC. SURVEILLANE REOU~tEMLNTS and C2 4.6.1.3 conmainment air lock shall be demonstrated OPERABLE:M1 SR3.6.2.1 a. ~~Inaccordance withl0CF5O onflun g azo Guide 1163 Idated §emnbe 19951 andSer5. SR 3.6.2.2 b. It At lenst ocper mofthsb vatuyft Containment Leake (~~~the Mm onlty ow oriu. j oRate Testino ProgramA. o can bpenee at adr _ _ _ _ __ _ _ _ _ _ _ Adproposed SR 3.6.2.1 Note I Adproposed SR 3.6.2.1 Note 2A. COOK NUCLEAR PLANT-UNT 1 Page 3/4 64 AMENDMEa Wk 209 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 283 of 471
Attachment 1, Volume 17, Rev. 0, Page 284 of 471 C) 5.5
~~~~~~~~ITS ITS 314 LL1ITING CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENS 314.6 CONTAIN-MENT SYSTMIS See ITS)
CONTAINMENT AMR LOCKS L3.6.2J LIMITNO CONDMON FOR OPERATION 3.6.1.3 Each cornalnmmn air lock shall be OPERABLE With: L. Both doors closed except when Ome air lock isbeing wsed for nouzhrmansmit entuy anid exit thrugh the containmen, mathnr least oce air locck door shel be dosed, and 5.5.14.d.2.a), b. An ovcrall air lock leakage rate of £ 0.05 1.a at Fa, 12 pxsl. 5.5.14.b APPLHIhBJHlf: MODES1, 2.3 aWd4. A=l~j rSee ITS Wichua air lock Inoperable, restore dhe air lock to OPERABLE tatuns within 24 hours or be in at least HOT 3.6.2 STANDBY within the next 6hours amd in COLD SHUTFDOWN within the following 30 hours. SUVE"MEREQUIRMENT 4.6.1.3 Each containment air lock shall be demonstraMe OPERA3LE. 5.5.14.a L En accordane it 10 CFR 50 Appamftl I Optdon B and Regubaoty Guide 1.163, dated September 1995, and
- b. At Ica onceper 6 monoshby vcri~lorithat only onedoor Incach air lo*cm abe opened See ITS.
- b. ataime. I3.6.2)
COOK NUCLEAR PLANT-U IT1 Pge 3/4 64 ASM bENDE40, 209 Page 18 of 69 Attachment 1, Volume 17, Rev. 0, Page 284 of 471
Attachment 1, Volume 17, Rev. 0, Page 285 of 471 ITS 3.6.2 ITS ~I 3/4 LMUTING CONDITIONS FOR OPERATION AND SURVE11LANCE REQU[RENMNEIFS 3/4.6 CONTAINMIEN SYSTEMS This Page hzmdonafy Loft Blank COON NUCLEAR PLANT.UMr 1" Page 314 68AMENMMNT 46, 209 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 285 of 471
Attachment 1, Volume 17, Rev. 0, Page 286 of 471 ITS 3.6.4 ITS(I 3/4 LEMffIG CONDITONS FOR OPERATION AND SURVEUIANCE REQUIRMENTS 3/4.6 CONTAINUME.SYSTIEMS L-IMITING ONIINFOR OQENATIN LCO 3.6.4 3.6.1.4 Primary coutaiment Internal presur shal be mnarntakind between -1.5 and +0.3 psig. M&WARNIM~I: MODEIS1, 2,3and 4.
&CfLQN:
A-,wVidi the cotanzalnnet lntema presur outside of the limits above, restore the Internal pressure to within the lmt ACIO ACTIONA LWMthpII bourfor be In Usleast HOT STANDBY within the nam 6 howr and in COLD SHUTDOWN within the ACTION B -- fbllowing ~30 hours. SUREMLLANCE R SR 3.6.4.1 4.6.1.4 The primary conmalnment antena pressre shal be determined to within dhe limits at least oc per 12 hours. COOKC NUCLEAR PLANT4ffif IT Pag 3146-Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 286 of 471
Attachment 1, Volume 17, Rev. 0, Page 287 of 471 ITS 3.6.5 ITS ~I CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITrNG CONDITION FOR OPERATION. LCO 3.6.5 3.6.1.5 Primary containment average air temperature shall be maintained:
- a. between 60 and 1006F inthe containment upper compartment, and
- b. between 60 and 120*F in the containment lower comoartment.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: ACTION A r~~W-ith the containment average air temperature not conforming to the above Lliimits, restore the air temiperature to within the limits within 8 hours ______________ or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN ACTION B wŽithin the following 30 hours. SURVEILLANCE REQUIREMENTS SR 3.6.5.1 4.6.1.5.1 The ri arv cotiment upper mrenaverag air tern-following oca on~~Pae 1of Attachment 1, Volume 17, Rev. 0, Page 287 of 471
Attachment 1, Volume 17, Rev. 0, Page 288 of 471 ITS 3.6.5 ITS ~I CONTAINMENT SYSTEMS SURVEILLAIME REflUIREI¶ETS (Continued) SR 3.6.5.2 LOCakti
- a. LV No nal Elev. 624 1 0-1/2" A.
- b. LVoinal Elev. 6 0n C. Nominal Elev. 6266M SR 3.6.5.1, 4.6.1 .5.3 The primary containment average air temperatures shall be SR 3.6.5.2 determined at least once per 24 hours.
- 0. C. COOK-UNIT 1 3/4 6-8 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 288 of 471
Attachment 1, Volume 17, Rev. 0, Page 289 of 471 ITS 3.6.1 ITS 314 LI9M1TG CONDM~ONS FOR OPERATION AND SURVEILLANCE REQUIREMVENTS 314.6 CONTAE4MEN SYSTEMS CONTAWNMENT STRUCT AL INTEGRITY LIMITING CONDrTION FOR OPERATION LCO 3.6.1 3.6.1.6 The st~ruual intcgrity of the co inmient shall be maintaind at a level consistent with the APPJ~LCAILIfl: MODES 1,2, 3and 4. Add proposed ACTIONS A and BA. With dhe Integritqd of the contaimen miconforming to the above ire oe tbhe srcramla Integrity to " te limits prior to inbes h Reactor Coolant Systee fp a bo.ve 200 F. SR 3.6.1.1 4.6.1.6 The struchtua intemt of the contakupme stn==ur and sdteelne shall. be detemined In COOK NUCLEAR PbLANT.UMr I Page 314649 AMMINMEf 45W 209 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 289 of 471
Attachment 1, Volume 17, Rev. 0, Page 290 of 471 ITS 3.6.3 ITS 3/4 LIMITING CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM L1MD NG CONDITION FOR OPERATION cnsiderations for personnel entry, and for surveillance testing and maintenance activities. No SR 3.6.3.1 more tha one purge supply path and one purge exhaust path shall be open at a tirne. APPLICABITU : MODES 1, 2, 3, and 4.AdprosdCTOSNt2 a1. With one containment purge supply and/r one exhaust Isolation valve inoerable, isolate the affected penetration b~z use of at least on ~~ai alve secured in the cdosed position, and, within I2,11ours, either ACTION A '-etmteizprl a
- 2) Deactivate the automatic valve secured Inthe closed position.
- b. I Uperafion-f&~ fthe continue imtiiprfonice of fh~efiR7 ou'iRR vave testip-rovi'ded ( I that the automatic valve secured In the closed position is verified to be deactivated ini the ACTION D c. Otherwise, be in atleast HOT STANDBY wlthln the next 6hou=nandIn COLD SHUTDOWN within the (ollowing 30 hours.
I Al-~ The nRovsiona~-6 Specfication 3&a-Air not anliabe. ( . SURVEILLANCE RAQUIREMENTS COOK NUCLEAR PLANT-UNIT 1 Page 314 6-9a AMENDMENT, WP,209 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 290 of 471
Attachment 1, Volume 17, Rev. 0, Page 291 of 471 ITS 3.6.6 ITS(I 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS 314.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING COND)ITION FOR OPERATION LCO 3.6.6 3.6.2.1 TWinpedt containment spray systems shall be OPERABLE wihec pysystem capable_ APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: ACTION A Wihoecnanetsrysystem inoperable, restore the inoperable s ra system to OPERABLE status within 72 ACTION th nx4 ours obe in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE: SR 3.6.6.1I a. At least once per 31 days by verifyig that each valve (manual, power operated or SR 3.6.6.2 b. By verifying that each containment spray pump's developed head at the test flow point is actualer pstion on eqal Coterqirent dessuelope gheahig teste pusuganttSeiicto S36.. Add proposed Noe 2.0 Vrf.gta5ahspa.upsat uonaialo a ntP ue- 3 L. toSR 3.6.6.43 es inl SR 3.6.6.5 . At Veastyonce pera1 ears buto ani valvr orte flowpahatte test echorrect tu . COOK NUCLEAR PLANT-UNIT I Page 3/4 6-10 AMENDMENT 4.07,444.4.83, 20, 275 Page 1 of 3 Attachment 1, Volume 17, Rev. 0, Page 291 of 471
, Volume 17, Rev. 0, Page 292 of 471 ITS 3.6.6 This page intemt~ocal1y left blznk-. *D. C. COOK UtIT I. 3/4 6-11m~mntN.9 Page 2 of 3 , Volume 17, Rev. 0, Page 292 of 471
Attachment 1, Volume 17, Rev. 0, Page 293 of 471 ITS 3.6.7 ITS(I
.314 LInMING COMMITONS FOR OPERATON AND SURVEILLANCE REQUIRMM N'I LCO 3.6.7 3.6.2. De quiy additive system "hlbe OPMLABLE with:
SR 3.6.7.2, a: Aapiy addfitietank c Mnlngavrounebetwee4000 and 4600glons ofbetween30 SR 3.6.7.3 and 34 ctby wdsNsOHasohnzom, and AUCAEMJA ~X.- MODES li.23 azd 4. ACTION A {Wd ytw kesry ab1C restmr fte migm to opmRADLE mmo WIN i2 hw!-icr miiv in St leas ACTION B - ~ ShNBwthn orOW xi hmIrtm y:gqttenxt4 b in SIYID~k4within the following 30 boums 4.622 The spay additive *yiemsal bc, desmontrted OPERABLE-SR 3.6.7.1 AL At least ooce per 31 days by verfying that each valve (manua, powft operaed or maukmtic) in tew lbw path tat s not lokemd scaed, or atherise aecured in position, is
'b. Ail eWa= neper 6mmfthsby.
SR 3.6.7.2 1. Ved~ngihesohfitionvc1 ficthe ank and SR 3.6.7.3 2. Verifying the c=ionftemc d XOH 0lI nt COOK NUCLZARtPLANT-UNIl1 ag 3/4 6-12 AMNDMMENTI44 25 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 293 of 471
Attachment 1, Volume 17, Rev. 0, Page 294 of 471 ITS 3.6.7 SR 3.6.7.4NAIMET YSEM SR 3.6.7.5 di. At least once per 5 years by verifying the flow rate from the spray additive tankc line1. COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-13 AMENDMENT 407,444, 464,N~O, 275 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 294 of 471
Attachment 1, Volume 17, Rev. 0, Page 295 of 471 ITS 3.6.3 ITS CONT3 ONjX ?KNE SOLfjXSVAVE LIMITING -CONDITIO ]FOR OERATION LCO3.63 6.T~iliachconitainment isolation valve shall be OUERABE otimu ug SR3.6.3.2under administrative control./ The ACTION Sta met of T/S 3/ .3.1 not ACINd app ica tth cnalent purge supply anexh~aust Lsolatovae. TheA. ACtIONS Unmiting onito o ration and its as eLated ACTION s te ntfor these NoteI ~valves le ne ial S ecifcation .6 .2..?. Vith ont. or zore of te containmenc isolation valve(s) inoperable. either: a&. Restetathe inoperable v e
!~Ls) to OPERABLE xtgt1wi'thin 4 hours, orA ACTION A, b. Isolate each affected ptnetratiou withinW4, ours by use of at least one ACTION B, deactivated automatic valve secured in the isolation position, or I hour fr MI I A ~~~~~~~~~~~~~~~~~~
B
- c. Isolate each affected penetration within 4bours by use of at 7 or o least one closed. manual valve or blind flange. or ONrfoC ACTI2 .
ACTION D ~ L S=UD0t; within the following 30 hours. 4.6.3.1.1 Containment isolatio ,valve shall be demonstra %d OPEPABLE prior I to returni~th Valve to servc atrmaintenance, repai replacement work L' ' is parfor ~othe valve or its psotiated actuator. co tAor power circuit by perfowu$c of a cycling tezzt~ verification of isol La*tie.I COOK VJUCLEAR PLANT - NIT 1. 3/4 6.14 AMENDMENT NO. g5, 4 181 Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 295 of 471
Attachment 1, Volume 17, Rev. 0, Page 296 of 471 ITS 3.6.3 ITS(S) 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILL.ANCE REQUIREMENTS 314.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Cotud)2 SR 3.6.3.5 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE at least once per mnh 4.6..1.3 SR3.6..4 a. IonAM, of-, timte pweboeatdeicaaiAet each otaiwlisolation isolation valvesalbepsto COOK NUCLEARPLaNt-uNIte I p Pagetio /o615AENMETtio44n6.8
- b. VerifIAX-seB~ontakinent islation est s48al, 2ac pPages2tofn1 to isolation actuates Attachment 1, Volume 17, Rev. 0, Page 296 of 471
Attachment 1, Volume 17, Rev. 0, Page 297 of 471 ITS 3.9.3 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued 4.6.3.1.2 Each containmient isolation valve shall be detnoustrated OPERABLE at least once per 18 mnh CUTS ee 3.6.3 by:
- a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates Coits isolation position.
- b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve SR 3.9.3.2 C. Verifyn that on a Containment Prge and Ehust isolation si each Pur eand Exhaust valve actuates to its isolation position.aculosilte CSee MrSj 4.6.3.1.3 The isolation time of each power opexrate or aut-omatr contaiW -n sltinvlesal 3.6.3 Jdetermnined to be within its lirnit when tested pursuant to Specification 4.0.5.
COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-15 AMENDMENT 407, 444, 464,468, 4-84, 275 Page 3 of 8 Attachment 1, Volume 17, Rev. 0, Page 297 of 471
Attachment 1, Volume 17, Rev. 0, Page 298 of 471 ITS 3.6.3 Pages 3/4 6-1.7 throug~h 3/4 6-22 deleted cox =CLL&R PUST CO .Un t. 1 3/' 6.16 Mom=EJ~ NO. w I a Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 298 of 471
Attachment 1, Volume 17, Rev. 0, Page 299 of 471 ITS 3.3.3 ETS
/.64COMIMSZDL GU COMRfOXs zLmTN colmmov TM~ OMTZCOI Table 3.3.3-1 3.6.4.1 Nwo containment hydrogen analyzers shali be OPERALE.
Function II APMCASILTs HOOK 1 fii~i2 3pse C
~
ACTION B ~ ~ CTON ACTION D b. With bote hydrogen analysis devices inoperable, restore ath
!peasbt one ana~ysts device to oIEtA=L sa&tuq w'ithin 72 hourejor be -in at ACTIONS E and F I-least HOT STANDBY within the next 6 hour
.sUR ~ ~ 1th~ ~~and CE HULA! n MODE4 SR 3.3.3.2 4.6.4.1 Each hydroenaayiedvcsal em sttd OPERABLE at'L1 least once pox 92 d jAys TAGz fiZ5 peGrfozzing a CHAN=E CALIBMIU usW a our percent ad9teen YeaetmA=
Womin hydrogen, gs,r bal ncc nitroven.I D. C. COOK - UNIT 2 3/4 ki,23 Aftne-- No. 196 Page 8 of 16 Attachment 1, Volume 17, Rev. 0, Page 299 of 471
Attachment 1, Volume 17, Rev. 0, Page 300 of 471 __ QI~~~~~~~~~~~~~~
~~ITS 3.6.8 314 LiMITIG CONDMTON FOR OPERATION AND SURVEILLANCIE REQUnREMM4T TV MMCON AINMENT SYSmgtTEMS c.
LCO 3.6.8 3.6.4.2 ig ;-ainment ntfg bydowerecomblner systens sbanl be OPERaB . AP2TCE LI MODFES l an 2. ACTION A wihoahydrogen recombiner SYste inoperable, westore the Inoperable system to OPERALE status W1Whi 30 ACTION C dS~~~r be in at lkam HOT STANDBY within die uxct Ebows. 4.6A.2 Eah bydrp teomb imm. sysoah be temoenstrtd OPERABlLE: SR 3.6.8.1 A. At leas owce M on1'=ths bf vedfg dudin arecomnble Mtern functiona test ta
- b. At Icatonceer thb SR 3.6.8.2 2. Veriffin throug A visua examinaton OmaOmerIs no evidence of abnorma SR 3.6.8.1 3. Verfitdrit a recombiner "tem fiunctona set thatte teslaL SR 3.6.8.3 4. Verifying dbe integrt of allbeete clectical circults by Eormin actinut COOK NUCLE KAR LATUMI PpSM 6.24 AMEDMENTIUM3 242 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 300 of 471
Attachment 1, Volume 17, Rev. 0, Page 301 of 471 ITS 3.6.9 3M4 LIMrgG CONDrmOS FO)ROPERATION AND SURVEIULANCE REOU[RMENTS 3J4.6 bONTAVMENT8YSTp4S LCO 3.6.9 3.6A.3 .4 Both trains of the Distributed Ignition System shall be OPERABLE.1Adscn ar fLO"S] ACTION A A. Restore the inoperable train to OPERtABLE staus within 7days, or L ~~~ ~~~~b. Perform irvliNce -ufrment 4.6.4.3& once 7eday an the OPERABLE train t . ACTION B -- With no OPMLABLE hydrogen Ignter In one containznent region, restor out hydrogen inite hinthe affected ACTION C c~~~ontanmnregion to OPERABLE MtMu within 7 dansfor bcinHOTrsTAND)BY within 6hours. 4.6.4.3 Earch train of the Distributed Igntion System sabal be demonstrated OPERABLE: SR 3.6.9.1 a. Owce perg Mka *'zingthe supply brkeak and verifftn that at leas 3403LA SR 3.6.9.2 b, Once par byverifyin at least Inlidoo gie sOEAL ned Containmuntr~go&. SR 3.6.9.3 C. OMMtsyeiyn tetr lsu ac gie aliu 1700F. COOoK NCLEAR PLANT.UIftr 1 3/v 46.25 AmE)mpl T2AZ Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 301 of 471
Attachment 1, Volume 17, Rev. 0, Page 302 of 471 ITS 3.6.11 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS 3/4.6.5 ICE CONDE1ASER ICE BED LIMITING CONDITION FOR OPERATION LCO 3.6.11 3.6.5.1 The ice bed shall be OPERABLE with: Add proposed boron concentration upper limit SR 3.6.11.6 a. The stored ice having borenG1c~g fa est10 pf9ebrn SR 3.6.11.4 b. Flow channels through the ice condenser, SR 3.6.1 1.1 C. A maximum ice bed temperature of: 270F,
~:
*.. .. b~skes~cpe~inmg least 1144 ibsf ienofcycle", an SR 3.6.11,2 APPLICABILITY: MODES 1,2,3 and 4.
ACTION: ACTION A Wihteieme nprble. restore the ice bed to OPERABLE status within 48 hoursfo-r be n at least HOT ACTION B LSADYwti h et6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
- a. At least once per 12 hoursb usin tee-deMemteratu ntr-ing steto verify SR 3.6.1 1.1 that the maximum ice bed temperature is< 271F.
- b. At least once per otsb: 5 o R361.
Add proposed SR SR 3.6.11.6 .,3.6.11.6 Note 1. Chemical anal~yses which verify that at leastf 9 representative samples of stored Ii hv~e a boron concentration of at least 1800 Rp te eOVIM onhlrm SR3.6.112 ~~~2. Weighing aprsentative sample _0at least 144 ice as e n v each ice ase otains at It14 b fieedo-yl) g The tM Add proposed total mass and zone require-m-e-nts`L.1 COOK NUCLEAR PLANT-UNIT I Page 3/4 6-26 AMENDMENT 83,480,2320,334, 280 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 302 of 471
Attachment 1, Volume 17, Rev. 0, Page 303 of 471 ITS 3.6.11 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAIMENT SYSTEMS SURVEILLANCE RBUIREMNENTS (Contimued Add proposed total mass and zone requiremet ~ SR 3.6.11.2shlbecn iefrom the 20 addtoa bas ets adthbiceatasket rhalcn notees than 1I 4ounds/basket (end- fcIata 95% levelfcofdn. SR 3.6.11.3 The ice con ser shall also be subvided into 3 groups of askets, as follows: A-dd Group I - l~sI through 8, Group, - bays 9 through 16, 9fd Group 3 -bays 17 proposed throg 4.The minimum avae ice weight of the/sample, baskets from 4-Ice mass L Raillos1, 2, 4, 6, 8 anOf9 in each group shalVnot be less than 1144 requirement Poud/akt(end-of-cycle) Ata a 95%level of confd6. SR 3.6.11.2 The minim total ice condenser ip~weight at a 95% ofvconfidence shall be calcufe using all ice basjt weights- determined uig this weighing prourn'adshall not he less 2,222,000 onds (epdo-cce). SR 3.6.11.4 3. Vci ing by a visual insection of at le two flow passaepre cnesr acumulation of Ice on bay, that the Accumulation of frost or ic on theo structural members intemieiate eck. and on flow passag between ice bakt dpslatce comprising Rlow channels iframS isr cte to a nominal thickne of 3/5 inches. If on asaeper through the ice bed is bay is foun to have an accumulation o frost or ice greaiter thn i hcns, a
- 5 15% blockage of the representa ve sample of 20 additional owpassages from the bay shall beL.
total flow area for each visually ted. If these addition flow passages are fou acceptable, the
,safety analysis section surveill c program may proceed nsidering the single de aunique aiecy C. At I o6nce per 11 months byvzfig ya visual inspcinahice condenser bay.
that le accurmulation of frs rc ntelower inle pnlhsport structures andL4 ngs-vanes is restricted toa mnltikesof 3/8 inh.A cumulation of frost fice greater than this tjksssevdence. of abofa erdton of the ice (ondenser.I SR 3.6.11,5 d. At least once er40 months by lifting visually inspecting the aesble portions of at least two i sesfrom each 13 ofe ie condenser and yeni ing that the ice baskets are firee detrimental structural er cracks, corrosion o te damage. The ice baskets al be raised at least 12 ftfor this inspection. Add proposed ice basket wear/damage requireet . COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-27 AMENDMENT 408, 431,438,444,330, 234 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 303 of 471
Attachment 1, Volume 17, Rev. 0, Page 304 of 471 CTS 3/4.6.5.2 314 Lhifl CONDMTONS FOR OEA O AND SURtVEILANCE QUIREMENFS 314.6 COTSYSFM S ICE BM L RE HQIOING rFIING 0oNE -PRTO 3.6.5.2 ice bed temperatur monito ystmhall beOPERABLE with zlent 2 OPERABLE RTD la the icc bed at edeva 652' 2-1/4', 672' 5-1/4' and 69 '2-114' for each one third f iece condense. AHCABI MODES 1.,2,3 Ld4.
- a. With th eIe bed, moitoring system Ioperable. OE OPERATION may cotnefor up to 30 provided:
- 1. The ice Iowar isat doors, ntmeideck doos., and top deck doorsrc x .
- 2. The los meam ice bed temperature was 20' and stedy;, and
- 3. Toe Ice coolin systm IsOPERAB wihat least:
A) 210EAL air hosding Onda, b) 20 LE gycolclrculadg ,and c) 30 mRDErfrigec at nit; othewise, be In a O SADBwihn6. and In COLD SHUTDOWN within tie flong0 hours.
- b. With the ice bed z-oaitorig syste u.ad with dhe ice oofldens coolin sytem Mt doe inninumm coMponents PE.AIF1rqirement of a.3 above POWER OPRT ON an donine for to 6 days provided &ci. ce coqmpartmmtlo doors Intenidlafte deck I ,and top dock doors re closed and dhe last mean icebed utgeaittewam 1'Puad steady;otherwisebe in at leas HOT &T 1YWihn dhe neot 6 hours In COLD SHUTDOWN 'wihin the mdowimgs Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 304 of 471
, Volume 17, Rev. 0, Page 305 of 471 CTS 3/4.6.5.2 ent-az4MirI 314 II*"
Page 2 of 4 , Volume 17, Rev. 0, Page 305 of 471
Attachment 1, Volume 17, Rev. 0, Page 306 of 471 ITS 3.6.12 ITS(3 CONTAINMENT SYSTEMS ICE CONDENSER DOORS LIMITING CONDITION FOR OPERATION LCO 3.6,12 3.6.5.3 The ice condenser ileat doors, intermediate deck doors, and top deck doors shall be closed and OPERABLE. APPLICABSILITY: MODES 1, 2, 3 and Ad rpse CINSNt ACTION: Vith one or were ice condenser-doors open or otherwise inoperable, POWJER ACTION B OPERATION may conttinues for up to 14 days provided the Lce bed temperature thn o eqal o 2 F~'otervserestore the doors to x Mantanedles ACTION C 11heir closed positions or OPERALE etatus (as applicable) within 4S hours ACTION D fr be in at least HOT STANDBY within the next 6 hours and in COLW SHUTDOWN 1y-ithin the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.5.3.1 Inlet Doors - Ice condenser inlet doors shall be:
~nce Ar~~~~~~~~ pr 12hursL.
SR 3.6.12.1 a. cotag y mraaAand determined closedlby m. co ~ 03 tiftor ste and
- b. Demonstrated OPERABLE dur! sbh don at least once per 18 months by: "I, SR 3.6.12.5 1. Verifying that the torque required to initially open each door in less than or equal to 675 inch pounds.
SR 3.6.12.4 2. Ve~rifying that opening of each door is not impaired by Lce. fotc or debris. Peomatorque test SR 3.6.12.6 1. Te 1 ech oneo of the dorh e gta toru requre oopen each oo s 1Ss than 195 inch-Po when the dois40 degrees open. is torque is definea the L.
*dor opnng torque* aid is I to the nominal ocr torque plusa ritional torque compo et.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-30 A.M].NDHENT NO.rn0, IN, 144 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 306 of 471
Attachment 1, Volume 17, Rev. 0, Page 307 of 471 ITS 3.6.12 ITS &I
- 4. at eachb of the 4.00* 4 veirfywu that,1 o rquequired I to be ach de:fosr cIan l La g reas:tear thpoiMda Whenr
- dcis " 40 depe o~mu. tis~torru L efined as the 4@d"40114 torque* stiL equal to the 0 or ~qeL.
aftu a fricutiua tor sosponent. S. Cal tesio of the h.L tottmofa do tested ina cc ordancs with 3 and
- hy. Uk aln ted frIctMIonl torque t
Ube loes tunz of qals4O &&th. 4.t54.3. znasauedate Deck Doors
- Lach lee cndnswer iaseorediate deck dooI chall be:
SR 3.6.12.2 a. Verified clouud and that openInS Of each door La not Impaired by Lee, fross of dabrLs by 6, 'isual inspection at Least oace pot 7 daYe. and SR 3.6.12.7 b. Da0fstotaraed OPllASLK At Reast once pet II months by visual~ly verIfying no structural detertoratton, by verifying free powsment of Ch. vdaclt&Ctoe C andVail As t Lea, tfar o" requal. a lite wit tahe p t lcabt Adjacesont wa Lebeha oVeWa.
- 3. Adjaenss Crnatne uVail . Lea than Or equal.
- 4. Pa4L 4vLth Door Adjacent. Less than or equal to to .u*Lnmnr. V&IL 21.0 tbs.
COOK IMCLhI rLOPA M UNIU 1 3/4 5.31 AMMMM~I 10. 0I.138 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 307 of 471
Attachment 1, Volume 17, Rev. 0, Page 308 of 471 ITS 3.6.12 ITS CONTAINMENT S15TLS SURVEILLANCE HgEAOURE1TS (Continued) SR 3.6.12,3 4.6.5.3.3 Top Deck Does
- Each fee condenser top dock door shall be detmtredclosed and OPERILE at least once per 92 days by visually
- a. That the doors are in place,, and
- b. That no condensation, frost, Or ice has fam~ed on the doors or blankets which would restrict their lifting and opening if required.
- 0. C. COOK-UNIT 1 314 '-3 Amendment No. 83 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 308 of 471
Attachment 1, Volume 17, Rev. 0, Page 309 of 471 CTS 3/4.6.5.4 COITAWIMEM YSTEMS LNLT DOOR ~SITION I4ONITORINO SYST LIHITING CAoITION FOR OPERATION 3.6.5.4 The lale door position mon toring system shall be PEPRAZE. APPLICAB1LI KODES 1, 2, 3 and4, ACTION: With the I et door position mouLt ring system inoperable.PW. OPERATION may Couti for up to 1.4 days. pr dad the iLeo bed temp. atur. monitoring syutom is aiBL nd the maxi. ico bed temperature is eas than or equal to 2 F when monitored at I1. conce per 4 hours; o isye., restore Cho inlot or position monitcrin system to OPUAILZ sta vithin 48 hours or b in at least HOT S within the next6 h. sand inCOLD SHUTDOWN vthin the following; 0oUrs. S1JRVzLL I RUTRIKENTS 4.6.5.4 inlet door position nioring system shall b determined OPEAL
- a. Prformifng. a CEANNEL C at least once per I. hours, R
- b. Performing a CH4ANNEL CONAL TEST at least ae per IS months.
C. Vrifying chat the son tornsyt crely etsth sttsof *cact inlet ras the oorrioentl indircatesoth COOK. CLA ?ZAMI UNIT I 3/4 6-33 A#DMCM 00-47.244 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 309 of 471
Attachment 1, Volume 17, Rev. 0, Page 310 of 471 ITS 3.6.13 ITS D COTAX!MW=I SYSTEMS LIMIZTING CONDITION FOR OPERTTON LCO 3.6.13, 3-G. e ersormal accss doors end equipment hatches betvsen tbe SR 3.6.13.1 rconta~i~untss upper and lover c uarmaets shell, be 01UABLI and closed. MZLZPULUfl: WgOES l,2,S3arM&. Ad rposed Condito ANt Vth W11rsonel access door or. 41t more o one orl m 3.6.13 Note. ACTION A *rr plgora tramias *DM anid? grea~ter 2 0F, Westorste door or hatch to CUAUBIt status or to1:E closed position (as applicle) Iv olr be in at least 90' SUMYI vithin the neat d houra and in ACTION C COLD NTIVOU within the fol~lewing 30 hours. SR 3.6.13. 1, 4,6.5.5.1 The personnel access&doors end equipment bathe~s betveen the con. SR 3.6.13.3 ca~ament's uppr end lower compartmnts shaLl be determined closed by a viusjl inspection prier to incireasing the Router Coolant Systeam? above 200 r and after each perliouml transit entry when the Reactor coodIt~ System 'A! isa boe200I SR 3,6.13.2 4.6.5.5.1 The personnel access doors and equipomnt hatches between the containment's upper and lever compartosts shall be dettulmind OPRUMLE by vsisually Inspecting the seals end sealing surfaces of these penetrations anid verifying no detrimental aisalguwnts, crecke or defects in the sealing surfaces. or &pparsnt deterioration of the seal materiel:
- a. Prior to final closure of the penetration each time it has been opened, and
- b. at least once per 10 years for penetrations containing seals f'abricated from resilient materials.[
COOK SUCLIAZ PLUXT
- MT? 1 3/4 6.34 win-MIT 80 W;0.144 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 310 of 471
Attachment 1, Volume 17, Rev. 0, Page 311 of 471 ITS 3.6.1 0 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS CONTAINMENTIR RC L &CLT-IONSYSEMS L4MITNG CONDITION FOR OPERA O LCO 3.6.1 0 3.6.5.6 Two[j~ ~ ~containxncnt air recirculation systems shall be OPERABLE. APPLICABILITY: MODES 1,2,3 and 4. ACrION: ACTION A Wihoecn ain t air recirculation system inoperable, restore the inoperable system to OPERABLE status witin 2 hursorbe in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the ACTION Bfolwg30hus SURVEILLANCE REQUIREMENTS 4.6.5.6 Each onametirrecirculation sysem shall be demonstrated OPERABLE at least once per 3 months on JSA~1;D -r-ASSby. eactual or simulatedL2 SR 3.6.10,1, a. Verifying that the return air fan starts on an signal After a 1.20t 12 seconds SR 3.6.10.4 delay, the motor oprated valve in the sucti nwr ac..tualtmpfl compartment opens Q n- terturn adthe return air fan operates for'at least 15 minutes (applicable inMODES 1,2., and 3 ny, o iulated signalL. SR 3.6.10.2 b. Verifying that with the return air fan discharge backdraft damper locked closed and the fan motor energized, the static pressure between the fan discharge and the backdraft damperns k 4.0 inches, water gauge, SR 3.6.10.3 C. Verifyig that with the fan off, the return air fan damnper opens when a force of~ 11 lbs. is
- applied to the counterweight, and COOK NUCLEAR PLANT-UNIT I Page 314 6-35 AMENDMENT 80, 234 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 311 of 471
Attachment 1, Volume 17, Rev. 0, Page 312 of 471 ITS 3.6.14 ITS j1141IKtt CONITHOI FMR OPERTIOM LCO 3.6.14 3.6.5.7 The ice condenser floor drains Shall be OPERAILIE. APPICAILIYf : MODES 1, 2,3 and 4. ACTION: ACTIONS A and C 1f1th the condenser floor dr nifloPerable,'rst te floor drain toOEA sttspro o esng eco lnthSsemtn mratu abe 0F SURVEILLANCE REOUJZREMENTS SR 3.6.14.3 4.6.5.7 Each ice condenser floor dra is 1!l be demnstrated OPEAL At least once per 18 months 1drAz~~nby:
- a. Verifying that valve gate,opening isnot impaired by Ice, frost or debris,
- b. Verifying that the valve seat Is not daimaed.
- c. Verifying that the valve gate opens when a force of ,~100 lbs is applied, and
- d. Verifying that the drain line from thle ice condenser floor to the contaliwent lowe compartwet Is unmrestricted.
D. C. COOK-UNIT 1 3/4 6.36 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 312 of 471
Attachment 1, Volume 17, Rev. 0, Page 313 of 471 ITS 3.6.14 ITS CONTAfINMEN SYSTE.MS REFUELING CANAL DRAINS LUN4TING CONDITION FOR OPERTION LCO 3.6.14 3... euln aa rains shall be OPERABLE. APPLICAB!L.!-Y: NOCE$ 1t 2, 3 and 4. ACTION: ACTIONS B and C with a ref inq canal drain i ruble, restore the Ain to OPERABLE Status por to-increasing th setor Coolant y tetmperature above 200SF. !!l~ SURVEILLANCE REOUIREMENTS SR 3.6.14.2 4.6.1.8 Eachirefueling canal drain shall be doonstrated .OPERABLE Prior to increasing the Reactor Coolant Systm temperature above 200,F after each partial or complete filling of the canal with water by verifying that the blind flange is ruwoved from the drain lint and that the drain is not obstructed by debris. AdR 3,6.14.1
- 0. C. COOK-UJNIT 1 3/4 5-37 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 313 of 471
Attachment 1, Volume 17, Rev. 0, Page 314 of 471 ITS 3.6.13 ITS COlqTAIkttZ' sysTEKs LiKITII CoKD!To2 mFormOPrATog LCO 3.6.13 3.6.S. 9 Ih iie are etsalb ~MU--
&MTON: JAdd proposed ACTIONS Band CA ACTIONS B and C Vwchthe A battior seal Lypotable. restor.te ea to OPIASLE pt o r to increalns atactoz Coolat Syasprarxro abov 200 F.
4.6.5.0 TMu dividar batrrLer Real. shall be detembine OPZASLZ at least once par months I uriff agusk~fow by: 2 SR 3.6.13.4 a. amnvtii tWo ivIlder beatLer coal. test coupons aid VerifYLUE Chat the physical properties of the test osupons are within theL. acceptable can&e of Values shom Jis USble 2.6-2. SR 3.6.13.5 b. Tilualmly inspecting at least 95 perosne of the Real's entire leaph eA-.
- 1. Voritying chat the seal anmdseal.ssw~ia bolts are ptoperly Installed, S"d
- 2. Verifying chat the seal aterial showe no vis.ual evidence of detarioration due to boles. rtutureu. chemical attack, abrasion. radaiacon dimege at ebanges In physical COOK NXUCLWA PLOTl
- VW? 1 /4 6431 AXMXDWr NDO4,l44 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 314 of 471
ITS QIVII)ER BARRIER SFAL Tensi le Hate i Eopato SR 3.6.13.4 [frill,~k 30071 120 psi JOOZ (4-
*Eqiial de~~s "en at least the qufenents discussed in QuaestJln5i911 of the Plantis I'SA(II( , Volume 17, Rev. 0, Page 315 of 471 Attachment 1, Volume 17, Rev. 0, Page 315 of 471 CD 0
CA) ~~~~~~
-h 0 0)
Attachment 1, Volume 17, Rev. 0, Page 316 of 471 C) 3.7.1
~~~~~~~~ITS 314 LEWITING CONDMTONS FOR OPERATION AND SURVEULANCE REQUIREtMLNT 3/4.7 PLANT SYSTEMS 3/4.7.1i nuRB= cycLE LIMITIN CONDMTON FOR OPMRA10N LCO 3.7.1 3.7.1.1 All main steam line code safety valves asoclazed cute withCd gam~r salbe OPERABLE.
AEELLABLff: MODES 1,2 and 3.ACIN ACTIONA ~~~~~~~~withone or mo mnszuW cd af V* L.2~Lgo-A ACTIONA =v crocced =~~~videdgmcw 0PEL& ina o e Powter Range Neuton Flux High Setpoint trip is reducedpeA. ACTION B b. L-able 3.7; erise la HOT STANDBY within die *= 6 hocrs and coM2!y with aonsaeet.AdproedRequired ih2o 3gatrc~-i an ~d~ Action Al oi i
-CM.1p3 ACTION A on, Ind with one or mormain teasn line aola safety valves associared wilt a gin I Inperamay pncc ET~ . Av.3~
ACTION B are jpmrwisc, be in,HOT SHVTDOWN ~1 C. Th 10ov 3..4
.o iZtf-fp r
SR 3.7.1.1 4.7.1.1 Each main stem line code safey valve sbal be demonstrated OPMWALE. in aordance with Spec~aifaon 4.0.5 and widt lift seconp as shown in Table 4.7-1. Mme safety valve shall be reset to the nominal value +/-t1I% wheceve found oumsid-di :th *1% toernce. The ptovislou of Specificadon 4.0.4 ane uo aplitablet for Cury into MODE 3. COOK NUCLEAR PLANT-UNIT I Page 3/47-1 AMNMN 4a U4M W. IS310 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 316 of 471
Attachment 1, Volume 17, Rev. 0, Page 317 of 471 ITS 3.7.1 ITS 314 LIMITING CONDITIONS FOR OPERATON.A.NDWURY9ILLANE IEQUIREMENTS 314.7 PLANT SYSTEMS Table 3,7.1-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWERFR-ANGE NEUTR L~ HIGH SETPOINT WITH ftOPERABLE STEAM LINE SAFET VALVES IURING 4_1G OPERATION iiINumber off operable Safety Valme on Maximum Allowable Power mv7 n Any Operating Stearn GeneratorI i (Percent of RATED THERMAL POWER) COOKC NUCLEAR PLANT-UNIT I Page 3/4 7-2 AMENDMENT 2-4O, 273 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 317 of 471
Attachment 1, Volume 17, Rev. 0, Page 318 of 471 ITS 3.7.1 ITS This page tunmcnciamay lFeft bLsxik. lD. C. COOK ~UT I 3/4 743 Amte~rn{, ::o. 12 Page 3 of 8 Attachment 1, Volume 17, Rev. 0, Page 318 of 471
Attachment 1, Volume 17, Rev. 0, Page 319 of 471 ITS 3.7.1 ITS Table 3.7.1-2 Z~L.. VALVE NUMBER +/- ITABLEO A. 2=
*, SV.IA 1065~zpugm a b' P45 ~~~~1065 PAS 1 2 -L.
- b. SV2A 1075 psi$ 1.6 2 2
- a. IV25 1073 putg 16I
- e. PV-3 1085 puS.g 1 I COO IIUCLEAR MMB? UNIT 1, 3/4. 7-4 £~m~Etm No. &
U, 182 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 319 of 471
Attachment 1, Volume 17, Rev. 0, Page 320 of 471 ITS 3.7.5 ITS (I 3/ LIOMING CONDMTONS FOR OflRATION AND SURVEILLANCE REQUIREMENTS AUXIIUARY PEEWkTER SYSTEM LDMINO CONDITIO FOR OPERAI&ON 3.7.1.2 LCO 3.7.5 a. Auxillr feedW pumps l~~~~~~~~~~enaror ociateod fo risL
- 1. TwM drvnaxiay we pump, eahcap of being powered j
.pant emeren~y and
- 2. tamtabndrvn feedwate pup lf being pweredLA remanOPERAELB 1system.
A!PUCAB.LrrY: Spcffon 3.1.1.2.a - MODES 1,2, 3. ACTION B
~ C ACTION ~ ~ ~L mthenet6hour OEAndLnHO suTmWNwihi ICe O TNYwti ACTION C a 6 hours and InHOT SHUTDOWN withinf~daiem
*-Add proposed Required Action D INt ACTION D C. Wvith thre mauxiia feedwate IcnAi Initiate corr salonactio to restore at leant one auxiliary toOPERABLE statua as soon as When specificauio/.7.1.2.b Isapplicable:
W'itliofo to Unit 2avullable, reun at toeflow path to availmbe wlha7dya, or provide eahuownc= pabilkyin UnkZ2 and atleast one Amopath to aviab wih nthee 60 days.. orhnv Un4 nHOT STANPBY within the 12 hours and HOT HUD wthnthe fol~owuiqg 24 hours. ThE reurnsOf Spec~imfiaion 3.0.4 are t pplicable. COOK NUCLEAR PLANT-UNIT i Pge 314 7-5 AENMENT P3, 430, 436,43.168 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 320 of 471
Attachment 1, Volume 17, Rev. 0, Page 321 of 471 ITS 3.7.5 ITS 314 LIMITING CONDITONS FOR OPERATION AND SURVEILLANCE REQUIREMENT 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5 by: SR 3.7.5.2 a. Verifying that each motor driven auxiliary feedwater pump's developed head at the test Add proposed SR 3.7.5.2 b. Verifyring that the turbine driven auxiliary feedwater pump's developed head at the tes Speification 4.0.4 ~ caule f rye into MODE 3. maulndcerorad SR 3.7.5.1 C. Verifying at least once per 31 days that each lnon-Wo-maH av in the flow pa hti not locked, sealed, or otherwise secured in position is in its correct position. L.6 ~~~~~~~~~~~~~and ilnboth-steam supply tiow paths to tihe steam turb'ne drivenur SR 3.7.5.1 d. Verifying at least once per 31 days that each automatic valve in the flow path is in theM2 tat Ianot ~ L.7 correct iositio e~ne~ver Me water system i's paced ia fuxiary mtccorlo ifapable of being when above 1006 RATED THERMAL gOWER This requirement is not applicable for manually realigned to the In poiton those portions of the auxiliary feedwater system being used intermittently to maintain APW/mode of operation steam generator water level. . Add proposd SR __ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ ____ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ SR 3.7.5.3 3... Note _ e. Verfigalatoc U oth htec uoai avin the flow path actuates to its conrect psitionuUpnreceip tof thea#ropriaten n-ic dee r et ea52 fe actuatio Adproposed SR test signal.Mlggn432r 3.7.5.4 Note 2 SR 3.7.5.4 f. Verifying at least once per mnh eahauxili feedwater vuml starts as [Add proposed SR designed automatically upon receipt of the appropriat:Estre 13.7.5.4 Note I actuatots inl uriao culo
.4 ~ ~ ~ ~ ~~~ddpooed SR 3.7.5.1 and SR 3.7.5.2 for MODE 4 requiremn COOK NUCLEAR PLANT-UNITr1 Page 31 7.6 AMENDMENT400,44, 444,464, U03,2M,30,2WS, 279 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 321 of 471
Attachment 1, Volume 17, Rev. 0, Page 322 of 471 ITS 3.7.6 ITS PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATIONi LCO 3.7.6 271.3 The eondensate stor*age tank (CST) shall he PEALwth a mininii 3- . SR 3.7.6.1 - f contained volume of M w allons of water. wtout reliance o ta FWith the condenste storage tak inie abg withi 4 ur ihr: generator for heat removal ACTION A AS&th-.CTko-fb NOS ACTION B Lnthiln jx ous12r 2 ACTION A as a baCkUp SUPPlY 0 M)- And generator for heat removal ACTION BMOE3whi SURVEILLANCE REQUIREMENTS SR 3.7.6.1 4.7.!1.3.1 The condensat storaea tank shall be daimon'strated OPERABLE at Required Action A.1 and 4.7.1.3.2 Thesu fial eice Wat ste shall be demnnstrat OPERABLE second Completion Time 9ta-m etieW D..COOK-UNIT 1 3/4 7-7 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 322 of 471
Attachment 1, Volume 17, Rev. 0, Page 323 of 471 ITS 3.7.17 ITS~ PLANT SYSTEMS CT! VITY LIMITING CONDITION FOR OPERATION LCO 3.7.17 3.7.1.4 The specific activity of the secondary coolant system shall be 0.10 11CI/gram DOSE EQUIVALENT 1-131. APLICABILITY: MODES 1, 2, 3, and 4. TION: ACTION A ith the specific activity of the secondary coolant system
- l. 0.10 ui~C/
ram DOSE EQUIVALENT 1-131, be In at least HOT STANDBY within 6 hours nd in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENT SR 3.7.17,1 4.7.1.4 The specific-activity of the secondary coolant system shall be ~( I D.C. COOK-UNIT 1 3/4 7-8 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 323 of 471
Attachment 1, Volume 17, Rev. 0, Page 324 of 471 ITS 3.7.17 ITS TABLE 4.7-2 suCOgigm COOAN SYSTEM SPECIFIC AC'?!VT IMNPE AMU MT313~I PRLGRAM TYPE OF x2A1UEMU4 MINIIMUM
- 1. Gross Acttvity Daetamination 3tines per 7 days wi th 4 MAXima tine of 72L.
mmw beteen uwmles SR 3.7.17.1 EQIAEN. 31C~enrto Sr r* s act Ity Qj 4eemnation ind ticaes Ioine cancent ationa Aloablelimit. below 10,0Pagfea2aofo4 Attachment 1, Volume 17, Rev. 0, Page 324 of 471
Attachment 1, Volume 17, Rev. 0, Page 325 of 471 ITS 3.7.2 ITS Gi UTM STrOz VALVES MEAo LCO 3.7.2 3.7.1.5 Zach ocean generator' vato e YIshall be 0tOA51.! h~~I~alL I~ MO!YS 1, I and S., exetwen all SGSVs arecoe NODE I. with am geoneVrator stop valve LooperableI b. ACTION A of MAT say tXS r~le the inopezable valve L~s restored to 0?UASLE Itas vilz bomws; -o ela reduce. power to loss than ACTION B to3p~n zI TI S O Vi~thi the nert 6 MODES 2 tonorore octam genrator stop valves inoperable. close the ACTION C &A3 inoperable valve(s) vithia 6 hours avid verify the Iop~rable valves area closed at least once pr 7 .f rWise be In ot least NO0DE ACTION D I&Vt~j1 aur wt the mi nat least MODE 3 within the first IThe pwitons of B gfc-ation 3.0.4 aa6t Mlicabl j? SR 3.7.2.1 4...51 Ech stea generator stop valve fttL d--sllb-ii'rtd OM~ABZ by veifylng- full Closure seconds when tased pusat 6ih~ to Specification 4.0.5. SR 3.7.2.1 4.7..5.2. TMe provisions of Spocification 4.0.4 use not applicable for entry Note into MODE 3. 4.7.1.5.3 a6 provisions of SPec DeiU4.0.4 aze not Ucable for entr A. COOK EUCLAR. VUflT MNT' 1 3/4 7.10 AMMMM~ Io* 420, 4,. 4,64. 185 Page I of 5 Attachment 1, Volume 17, Rev. 0, Page 325 of 471
, Volume 17, Rev. 0, Page 326 of 471 ITS 3.7.2 hIs past intentionally left blank.
C. COOK-UNIT 1 3/4 7-i1 Amendment Pwo.36 Page 2 of 5 , Volume 17, Rev. 0, Page 326 of 471
, Volume 17, Rev. 0, Page 327 of 471 ITS 3.7.2 his page inte1ntio~r'ly left blank.
0, C. COOK-UNIT 1 3/4 7-12 Amendment No. 36 Page 3 of 5 , Volume 17, Rev. 0, Page 327 of 471
, Volume 17, Rev. 0, Page 328 of 471 ITS 3.7.2 This page intentiOnallY left blank.
3/4 7-13 Amendment No. 3
- 0. C. C00K-U!flIT 1 Page 4 of 5 , Volume 17, Rev. 0, Page 328 of 471
, Volume 17, Rev. 0, Page 329 of 471 CTS 3/4.7.2 PLANT SYSTOI the steam g nerators shall be 3, 7 'Fwhen the pressure o either coolant inthe stel generator is-- 200. p 1g.
APPLICA8111I At all times. With the uirements of the abov specification not &aiIsfied:
- a. euce the steam gene tor pressure of the ap licable side to 200 psig within 30 m flutes, and
- b. erform an analysis to determine the effect the overpres-urization on the stru tural integrity of th steam generator.
termine that the Ste generator remains a~ceptable, for ontinued operation p or to increasing its peratures above SURVEILLA CE REggIREMEI4TS D.C. O0K-UNIT 1 3/4 7.14 Page 1 of 2 , Volume 17, Rev. 0, Page 329 of 471
Attachment 1, Volume 17, Rev. 0, Page 330 of 471 ITS 3.7.7 ITSGI 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 LCO 3.7.7 a. At least two d ndncmoetcooling water loops shall be OPERABLE. APPLICABILITY: Specification 3.7.3.1La - MODES 1, 2, 3 and 4. 1&cifi& n3.7.3. Lb -At a]
- when Unit 2is~ a D-ESi1 23or.( )
ACTION: When Specification 3.7.3. La is applicable: Adr sdR ie cinA1Nt ACTION A With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within L72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the ACTION 8 olwn 30 hours. When Specificat 3.7.3,1.b is applicable: With no fi hto Unit 2 available, return a atone flow path to available sts within 7 days, or provide equivalent stwncapability in Unit 2 and ernat least one flow path to avable status within the next 6011 days, or e nt2in HOT STANDBY wi the next 12 hours and HOT S DONwithin the following 24 hours. erequirements of Specification 3 .4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE: SR3.7.7.1 ~~a. Atleast once per 31 days by verifying; that each valye (manua, power operated or SR3.7.7.1 ~~~~~automaticiservicing safety related equipment that is not locked, sealed, or otherwise A3 Uintheflow-ath - ;w securd in poition, is in its correct position. SR 3.7.7.2 b. At least once per[ ~otsb e ~ ta ahautomatic va seA2a i~e Isnosald, r lhevse securedInctalo loke,
- c. Ay-verifying pump D~ormnance Pursuant pt pecification 4.0.5. L.
COOK NUCLEAR PLANT-UNIT I Page 3/4 7-15 AMENDMENT 407, 4-34, 444, 464, 275 W Page 1 of 3 Attachment 1, Volume 17, Rev. 0, Page 330 of 471
Attachment 1, Volume 17, Rev. 0, Page 331 of 471 ITS 3.7.7 ITS This Paz intentiaona1ly left blanik. D. C. COOK UNIT L 314 7-1.6 amendment No. 98 Page 2 of 3 Attachment 1, Volume 17, Rev. 0, Page 331 of 471
Attachment 1, Volume 17, Rev. 0, Page 332 of 471 ITS 3.7.8 ITS 3/4 UIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITNG CONDITION FOR OPERATION LCO 3.7.8 3.7.4.1 a. At [east two Inde -denhlessential service water loops shall be OPERABLE.. b. I At yei one essential service wtilwathi associated wih~~~tof Unit 2 shutdown
~diitions shall be available.2tt Qii)r APPLICABILITY: Specification 3.7.4.1La - Either Unit in MODES 1, 2, 3, and 4.
[Specificudof[3.7.4. Lb - At alAh1Iks when Unit 2 is i-ODES 1. 2 r4 ACTION:
- a. When Unit I s in MODES 1, 2, 3, and 4:
ACTION A ACTION B {Iwithin With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status 72 hours o-r e in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. Wha.nit 2is j!jODEStt,,3and 4 Unit 2 LCO 1. With any Unit 1 essential service water pump not OPERABLE, Iwi on orclose at Note and least one crosstie valve on the associated header or have Unit 2 enter ACTION a for Unit 2 ACTION A Specification 3.7.4.1 for the Unit 2 essential service water pump sharing the same header with the inoperable Unit I essential service water pump.
- 2. With no etal service water flow p available in support of Ur 2 shutdown fuinctions, SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:
dproosed SR 3.7.8.1 Nt . SR 3.7.8.1 ~~~~a.At latonce per 31 days by verifying that each valve (manual, wer oerated or automatid Iservicin safet ated e inmen that is not locked, sealed, or otherwise fin the flow path scrdi position, is in its correct positio 24 L. A3 SR 3.7.8.2 b. At least once vemnth ibyening that on each itef n fin the flow path reae imncutsto its correct psition. etsga.L. . 4that are not locked, sealed, or otherwiae secured in ostiton IC -erifyig pump ~F rman~ce pursun to cification 4.0..ata
~d.c tie ccledfrom the conrlom COOK NUCLEAR PLANT-UNIT 1 Page 3/4 7-17 AMENDMENT 40q. 4-3, 444,464, 2-53, 275 Page 1 of 3 Attachment 1, Volume 17, Rev. 0, Page 332 of 471
Attachment 1, Volume 17, Rev. 0, Page 333 of 471 ITS 3.7.8 ITS This pxie Lacemclonally lef blazk D. C. COOK - ON . 3/& 7-18 sqo. 98 Page 2 of 3 Attachment 1, Volume 17, Rev. 0, Page 333 of 471
Attachment 1, Volume 17, Rev. 0, Page 334 of 471 ITS 3.3.7 ITS 314 LIMITING CONDrTIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3(4.7 PLANT SYSTEMS 314.7.5 CONTROL ROOM VENTILATION SYSTEM CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION LCO 3.3.7 3.7.5.1 The control room emergency ventilation system (CREVS) shall be OPERABLE with: APPLICBILITY MwoDE 1,de,3de4prsuiand on thens moemntd firdae fesebis MODESLIC 2,B3LITdY: , ,3 4 n jIj [OE terovmn ofirdodefulasebis ACTION A a. With one pressurization train inoperable, the inoperable raalint0 T2CAUR ]~ 7 days For be in at least HOT STANDBY within the next 6 hours and in COLD w~myithin ACTION C SHUTDOWN within the following 30 hours. 4 AdpooedCTOB
- b. With the filter unit inoperable, restore the filter unit to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
C. With two CREVS pressurization train inoperable due to an inoperable control room envelope/pressure boundary, restore the control room. envelope/pressure boundary to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLE) SHUTDOWN within the following 30 hours. During the movement of Irradiated fuel assemblies:
- d. With one pressurization train inoperable, restore the inoperable pressurization train to OPERABLE statuis within 7 days, or initiate and maintain operation of the remaining OPERABLE train in the pressurization/clearnup alignment. rS rrs C. With any of the following: (1) both pressurization trains inoperable; (2) the filter unit inoperable; or (3) the control room envelope/pressure boundary inoperable, immediately suspend all operations involving the movement of irradiated fuel assemblies.
- f. 'Ike provisions of Specification 3.0.4 are not applicable to movement of irradiated fuel assemblies.
COOK NUCLEAR PLANT-UNIT I Page 3/4 7-19 AMENDMENT 459,24, 276 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 334 of 471
Attachment 1, Volume 17, Rev. 0, Page 335 of 471 ITS 3.7.1 0 MTS 347(i 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.7.5 CONTROL ROOM VENTIL-ATION SYSTEM CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION_ Ei) rtflIs LCO 3.71 0 3.7.5.1 Wcntolrom erg~ y ventilation system (CR~EVS)Llhal be OPERABLE go: _ __ __ _ _ _ __ __ _ _ _ __ __ _ ~~~~~~~~~~~~
- a. /rolndeen4/t Presurizti/itrains, and
- b. On chrcadrbrHP itrunit.
----- NOTE---- - -__
The control room envelope/pressure boundary many be opened intemitently under adunnistative control. APPLICABILITY: MODES 1, 2,3, 4, and kuigthe mnovement of irradiated fuel assbi ACTION: MODES 1, 2, 3, and 4: ACTION A a. r-With one pressurization train Inoperable, restore the inoperable train to OPERABLE status L- within 7dayso ein at least HOT STANDBY within the next 6hours and in COLD ACTION D -+ UTDOWN within the following 30 hours. ACTION C b- Lwith the flIter unit inoperable, restore the filter unit to OPERABLE status within 24 hours ACTION D r-or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN Lwithin the following 30 hours. C. With two CREVS pressurzton train inoperable due to an inoperable control romm ACTION B envelope/pressure boundary, restore the control roomn envelope/pressure boundary to OPERABLE status within 24 hours orb in at least HOT STANDBY within the next 6 ACTION D hours ~~~~and in COLD SHUITDOWN within the following 30 hours. Durin the moemnent of irradiated fuel assenilies ACTION A . ~~~~~~With one pressurization train inoperable, restore the inoperable pressurization train to OPERABLE status within 7 days o initiate and mnaintain operation of the remiainingA3 ACTION E KP-E-RABLE train in the presurizationlcleantip aio dpooe eurdAto ACTION F e. ,follown e~~~--- (I pressurization trains inoperable; (P!he filter L. suspend all operations involving the movement of irradiated fuel assemlies. COOK NUCLEAR PLANT-UNIT I Page 314 7-19 AMENDMENT 4-59, FR, 276 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 335 of 471
Attachment 1, Volume 17, Rev. 0, Page 336 of 471 ITS 3.7.1 0 ITS (I 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.5.1 'The control room.emergency ventilation system shall be demonstrated OPERABLE: SR 3.7.10.1 b. At least once r das ~ a DTEuua~~ h At least once per 19 monthfs or (1) aHEr any structural mainteanc on te HEPA bMter or charcoal adsorber housings, or (2) followIng painting, fire or chemical release In any ventilation zone communicating with the system, by:
- 1. Verifying that the charcoal adsorbers remove P_ 99% 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 6000 cfmn 10%.
- 2. Verifying that the HEPA filter banks remove299% of the DOP when they arc tested in-place in accordance with ANSI N510-1975 while operating th See MlS ventilation system at a flow rate of 6000 cfm +/- 10%. 55
- 3. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less tihan or equal to 1.0% radioactive methyl iodide when the sample is tested in accordance with ASIM D3803-1999, 300 C, 95% R.H7 The carbon samples not obtained from test canisters shall be prepared by either:
a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample from an adsorber tray, mnixing the adsorbent thoroughly, and obtaining samples at least two Inches in diameter and with a 1ength cqual to the thiclness of the bed.
- 4. Verifying a system nlow rate of 6000 cfin +/- 10% during system operation when tested in accordance with ANSI NS510-1975.
COOK NUCLEAR PLANT-UNIT 1 Page 3/4 7-20 AMENDMENT 4$9, 271 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 336 of 471
Attachment 1, Volume 17, Rev. 0, Page 337 of 471 ITS 5.5 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 4.7.5.1 ibe control room emergency ventilation system shall be demonstrated OPERABLE:
- a. Deleted See ITS 3.7.10J
- b. At least once per 31 days on a STAGGERED TEST BASIS by initiating flow through d HEPA filter and charcal adsorber train and verifying ftht the train operates for at least 1 minutes.
5.59 C. At least once per torlatrns trlmieacothHPfilter or charcoal adsorber housings, or (2) following painti , fire or chemnical release in any ventillation zone coonmunlcating with the s"tmyWhile Itis Inoprtonta 5.5.9.b I. Verifying that die charcoal adsorbers; rernove > 99% of a halogenated filter bank or charcoal hydrocarbo refrigerant test gas when they are tested in-place in accordance with aPdsorber capability ANSI N510-1975 while operating die ventilation system at a flow rate of 6000 cfm +/- 10%. 5.5.9.a 2. Vetifylng that die HEPA filter banks remove k 99% of die DOP when they are tested in-place In accordance with ANSI N5IO-1975 while operating the ventilation system at a flow rate of 6000 cfmn +/- 10%. .5.5.9.c 3 eiynl-en'Idqlfe'M ta aoaoyaayi facro samnple fromn either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less than or equal to 1.0% radioactive methyl lodide when the sample is tested In accordance with ASTM D3803-1989, 300C, 95% R.H-. The carbon samples not obtained from tOs canisters shall be prepared by either. 5.5.9.c.1 a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at Ieast two inches in diameter and with a length equal to die thickness of the bed, or 5.5.9.c.2 b) Emptyin a longitudinal. samnple fromn an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. 5.5.9.a, 4. Verifying a system flow rate of 6000 cfmu
- 10% during system operation when 5.5.9.b tested in accordance with ANSI N510-1975.
COOK NUCLEAR PLANT-UNIT I Page 3/4 7-20 AMENDMENT 4-59, 271 Page 19 of 69 Attachment 1, Volume 17, Rev. 0, Page 337 of 471
Attachment 1, Volume 17, Rev. 0, Page 338 of 471 ITS 3.7.1 0 ITS (3 314 LIUMING COMM~fONS FOR OIERA1ON AMDSURVEMLMACRE QUIRMEVIES
- d. AM ervery 720 hours of charcoal adsober FVRafon bY eit-her
- 1. Verifyirg vithIn 31 days aOne rmoal that a laboratoy anaysis of a carbo SUAnieobrd fromateatcnistershbow a peaettion of lessOtonr equal to .
1.0% for radiactive methyl Iodide wben the sample Istested In accordance, with ASTM D3803-1989 30~cq 959%fLU or See ITS
- 2. Vedfyizng wIthin 31 days afte remiaval tha a laharatmy analysis of ot least two ~ 5.5 J cezbon samples shows a penetration of Iess tha or equal to 1.0% for radioactive.
methyl Iodide when tho sarmples ami weotd inuacrdalca with ASTM D3803989, 30PC. 95% RLH; and the amples DOppared by eithcr a) Emptying one entir bed from a removed adiorber ftay. mixing fth adsorbent tboroughly end obtalinrg sampies at loas two Inches In
* ~~~~disawanae ad wdih.a lesth equal to tbothlckness of the bedor
- b) Emptyig a lxohgtdlna sample fwa3 an Wsdsrbe tray. mixin the adsrbent tbauugly and obtaining samples at leas two Inches In duamneterandA th alength equal to fththickness of the bed.
Subsquent to Teinstaling the adsorber tray wed for obtainng fthcarbo sample, sstmaballbe donutmmiteOPfRAEl by also. doth a) Verifyingd that thchrcoal JAdsoitcs rmve k 99% Of 4 balogenated hydrocarbon refrigerean test gas.whan they awe tested In-plac in accordance with ANSI N510-1975 while operatig the ventilation system at a nowrat ofW 6000 vIn 10%. and b) Vemiyin that the HEMP fiter banks remove ?. 99% of thme DOP when
- the~dy =r tested in-plac in accodanc with ANSI NSIO.1975 Whie opeatingoth ventilatio system ata lowrata GfGOOcfin* 10%.
COOK NUCLEAR PLANT-U1iT I Page 314 7-21 A&MENMENT 257 Page 3 of 8 Attachment 1, Volume 17, Rev. 0, Page 338 of 471
Attachment 1, Volume 17, Rev. 0, Page 339 of 471 ITS 5.5 ITS 3/4 LMWTIG COMM~ONS FOR oPERATON AND SURVEMLACE REQuUIRmEN Md.7 PLAI'?SYSTM S
~ ~
5.5.9 ~ ~ ~~ . Afterevezy720hoiisof charcoal adsorber operatioby eithr. 5.5.9.c albrwy o mm sample abtained from a test caitrshows APeneftraion of Ies thnA or equal to 1.0% for &awdiatvemethy iodide when the saple Istested In accardance with ASTM D3803-19S9,300C.95% REH or 5.5.9-c aflQ; 1 zi-aMu m nbboatkttw cabon samples show a penetration of les than or equal to 10 for gadioactie methyl Iodide when the samples ame tested Inaccordance with ASMA D3803-1989. 30'C95%RE; and the samples ameprepared by either 5.5.9.c. a) EnM*Sn one entre bed from. a removed &atsrbor ftqay mt*5n the adsorbent thorughy, and obtaining umples at leag two IndhuieIn
- diarneter~and with a letgth equal to the thiknessof fte bed or 5.5.9.c.2 b) Bmptying a longitUdnal sample frn an adawrbe tray. mizing tho adsorbent thoroughl, an obtainin samples at luag two inches in disnaerandwith alnh Woo l to the thicknes of dosbed.
Subse orisaln h tray used for olbtann Catbon sample,
- the sbfbedeosraeOby 01so:
a) aifring that thtdc a % a balogenated ubrsrmov rfrigran tet gs when they ydroarbn tested In-place In L accordanlce with ANISI 10 11975 hle teVentilation system atatlowrate of 6000, *h0%.and b) Verilftndiatth AC iler banks remove 2 %ofthe DOP when
- ar tested they~~f i accordmncec wit hipt I SIO.1975 while cpeeatingthe ven nsytemataflowrata OOcfMtl%
COOKNUCLEARPLANT-INUIT Pagel314 7-21 AMENM ENqT 257 Page 20 of 69 Attachment 1, Volume 17, Rev. 0, Page 339 of 471
Attachment 1, Volume 17, Rev. 0, Page 340 of 471 ITS 3.3.7 ITS 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIR~EMENTS 314.7 PLANT SYSTEMS SURVEILLANCE REUIREMENTS (Continued) SR 3.3.7.1 e. At least once peem-onths by., SR3.3.7.1 2. ~~~~~. Ve thatrssr VeriIfyinga dop acrossnhecomioneSi HEPfrom tnis antharcoale See ITS Table 3.3.7.1 Function I2yr autaDom-aticll opeae in0 e~pu oresu C0 .31 Lau SR 3.3.7.1 [. Verifyig that onaatinm t h systemSeIT L automatically operatesli die pressurizatinc eanu mo71.
- 3. Ver~fing tha the system maintains the control room envelope/pr=sur boundary I 1 at a positive pressure of greater than or equtal to 1/16 inch W. O. relative to 'he Se IS outside atmosphere at a systm flow rate of 600 cfin plus or minus 10%, with a L3.7 .10 makceup air flow rate of < 1000cdin.
- f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater tha or equal to 99% of the DOP when they are tested hi-place In accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfraplus or minus 10%.
- g. After each complete or partial replacement of a charcoal adsorbe-r bank by verifying that L eT fthcharcoal adsober remove greter than or equal to 99% of athaogenated.hydrocarbon refrigerant test gas when they are tested In-place in accordance with ANSI NSIO-1975 wvh1Ie operating the ventilation systemn at a flow rate of 60300 cfsn plus or minum 10%.
COOK NUCLEAR PLANT-UNIT I Page 314 7-22 AMENDMENT 4OM,444. 24,271 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 340 of 471
Attachment 1, Volume 17, Rev. 0, Page 341 of 471 ITS 3.7.1 0 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) SR 3.7.10.3, e. At least once per mnh y SR 3.7.10.4_________________________ _____
- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal Iadsorber banks Is less than 6 Inches Water Gauge while operating the ventilation systerm at a flow rate of 6000 cfm plus or minus 10%.
--------- an acta or SR3.7.10.3 Add proposed Notea to SR 3.7.10.3 SR3.7.10.3 t2. a. Verifying that ona ietln
~~~~~~~~~automatically ifl operates in te tresu zfncl J
Mg& rh.stm
- b. Verifying thaton a Safet numnit thsyte automnatically operateslin te re en SR 3.7.10.4 3. Verifying that the system maintains the control room envelope/pressure boundary at a positive pressure of greater than or equal to 1116 inch W. G. relative to outside atmosphere at Sinow ea c useor minus *withoa miakeup airtflow rate of < 1000 cfni. on STAGGERED TEST BASIS .
- f. Afte each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place hinaccordance with ANSI N510-1975 while operating the ventilation system at aSe flow rate of 6000 cfm plus or minus 10%. - r
- g. After each complete or partial replacement of a charcoal sdsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place In accordance with ANSI N510-1975 while operatingt the ventilation system at a flow rate of 6000 cfm plus or minus 10%.
COOK NUCLEAR PLANT-UNIT I Page 3/4 7-22 AMENDMENT 407, 444, U8I,271 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 341 of 471
Attachment 1, Volume 17, Rev. 0, Page 342 of 471 ITS 5.5 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)L3 5,5*9 e. At least once De nh y 5.5.9. 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 Inches Water Gauge while operating the ventilation systcem at a flow rate of 6000 cfin plus or minus 10%.
- 2. A. Verifyin that on a Safety Injection Signal from Unit 1, the sysftem automatically operates in the pressurization/cleanup mode.SeIT337
- b. Verifying that on a Safety Injection Signal from Unit 2,tesytm and automatically operates in the pressurization/cleanup mnode, ITS 3.7,10
- 3. Vrfigddtesse anan h oto omevlptrsucbudr ata positive pressure of greater than or equal to 1/16 inch W. 0. relative to th See ITS "
outside atmosphere at asytenm flow rate of 6000 efin plus or minus 10%, with a 3.7.10 5.5.9 ......~~~>-tif~er each complt orpartial replacement of a HEPA filter banlcb eiyikta h
~ ~ ~ ~ ~ ~ ~ HPAfilter banks remove greater than or equal to 99% of the DOP when they are tested 5.5-9-a 5.5.9.a In-place ~~~~~in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 efin plus or minus 10%.
5.5.9 g.. hreach complete or partial replacement of a charcoal adsoqrberbank by' verifying that
~~~ chacoa asrbers remove greater tha or equal to 99% of &fa t~~~he baogZenatehyrcbo 5.5.9-b refrigerant lest gas when they are tested In-place In accordance with ANSI N510-197S while operating the ventilation system at a flow rate of 6000 cfm plus or minus. 10%.
COOK NUCLEAR PLANT-UNIT I Page 3/4 7-22 AMENDMENT JOa, .144, U81271 Page 21 of 69 Attachment 1, Volume 17, Rev. 0, Page 342 of 471
Attachment 1, Volume 17, Rev. 0, Page 343 of 471 ITS 3.7.11 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS CONTROL ROOM AIR CONDITIONING SYSTEM LIMITING CONDITION FOR OPERATION tra ns LCO 3.7.11 3.7.5.2 coto omarconditioning system CASsall beOPRAL APPLICABILITY: MODES 1, 2, 3, and 4. Du rgnoeent of irmadiated fuel asemlsL1 ACTION: ACTION A With one system inoperable, restore the Inoperable system to OPERABLE status within IT-tiiig a 301 or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 ACTION B hours. CINSA n 4Md)rpoe SURVEILLANCE REQUIREMENTS Ad poosed ACTIC)N EA2 SR 3.7.1 1.1 4.7.5.2 The control room air conditioning syste shall be demonstrated OPERABLE at least once per 12 hours by verifying that the control rca air temperature Is less than or equal to COOK NUCLEAR PLANT-UNIT I Page 3/4 7-22a AMENDMN27 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 343 of 471
Attachment 1, Volume 17, Rev. 0, Page 344 of 471 ITS 3.7.12 ITS tTWTTI~~ COW~T?~OW 701 OdPLCO Not ACTION A WLth as USF ventilation system mxhaust ait filt.:er trumclqoperable. restate 11the iunaerable, train to O1'UALZ utatua vlchin 7 dayslat be La at lee*L.XoT ACTION C STMB within the paxt 6 hours sad in COLD SHUTDOW within thes Alo~wUn la 4.7.6.1 Itach Ui von acl,6aiasyatee exhaust afr titter crala shlLbeL. demlustatraed O79uIALZ SR ~ ~~ ~ 3.7.12.1 ~ ~ ~ ~ ~ ~ ~ ~~~~~poe S .71.
- b. At Least ams, per 15 montihm or (l) after any stmuocil maintenance, an the HIFA filter or charosl aduorher ousinps, air (2) following VaintingS fire or 'abou~eal. release 1A amy ventilatiou sone caamiecaing vith the goyec, by:
2.. Deleted.
- 2. Weitfing that the charcoal adetanbr nwes a. Its ef SeT halouated bydrocarbos refnigerauttst~ gas See ITheyaI costed Laplace to accordance with AMNSI351904 YUIl& j 55
.p"eclug cbe vwnctartu eyeva. en a CLivw ro of 55.000 ots
- 3. Verify"4 that the HEFA 911ter beakrese aits of tdo Dop Wozn. choyasrse oted in-pluse in a"cordanse with ANSI X510.1.510 v4iil operating the ventilation system at a flow ctic, of 23.000 of.l ' 205.
D. C.COOK UNIT L 3/4 7.23 1111110-s124 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 344 of 471
Attachment 1, Volume 17, Rev. 0, Page 345 of 471 ITS 5.5 ITS 3.1.6.. 'Two Ind~pondat lit vmnt~latLan system exhaust air filter train& See ITS MflZ~U~~: HODU 1. 2. 3 avA 4. 3.7.12J MLth one 157 veuttlattou system exhaust alr fittet tultu' Lippewable. restate the tnoparehbe xraia to OM=IL status vitbin 7 days or be La at lsau. loT STAIMlY within the muxt 4 hours and In COLD SKUDIMW within the fotlievng la bout.. 4.7.6.1 lath Ur vsatilatLon system exhaust at: filter tcia sWaL be demetratad OIISAILZ See FTS
- a. At least ouco per 31 days an a ITA0GflZ TIST DAST by Lintateta. 3.7.12 from the centrol room. flew tbzouh the BUlA filter an ohatoai 5.5.9 en theUaro trinA -andevowtyr thasal at porte(2 for tleast turaihinau 5.5.9b 2.
AxL u ytq169Uthe-asor chat i. afereb waminve a Mintonce, ako caca oil Ulor ha A r carcol aarbo holap or adeorbr capbilit 5.5.9.8
- pa
- 3. vealgfyirg tatrehouBlca r heleseWak ventiaton~I.o taie, 0 whenicdo withastheasted npaeby eurdneudaA 3143
- 1. Dist". oprainn ir ttof1500 operation thatta
~.
- 0. OOK operaingthe2atla /a 7yte.13 fo ratse61 23,W.12 Page 22 Of 69 Attachment 1, Volume 17, Rev. 0, Page 345 of 471
Attachment 1, Volume 17, Rev. 0, Page 346 of 471 ITS 3.7.12 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEZIANCE REQUIREMENTS 314.7 PLANT SYSTEMS SIRVETLoLANCE REOUIREM5MT (Continued)
- 4. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less than or equal to 5% for radioactive methyl iodide when the. sample is tested ini accordance with ASTM D3803-1989, 301CC1 95% R.H., and k 45.5 fpm face velocity. The carbon samples not obtained from test canisters shall be prepared by either.
a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample firom an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also verifying that the charcoal ad~orbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI NS510-1 980 while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 10%.
- 5. Verifying a system flow rate of 25,000 cfmn plus or minus 10% during system operation when tested inaccordance with ANSI NS1IO-1980.
C. After every 720 hours of charcoal adsorber operation by either:
- 1. Verifying withi'n 31 days after removal that a laboratory analysis of a carbon SeK sample obtained from a test canister shows a penetration of less than or equal to SeeIT 5% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 309C, 95 %R.E, and _>45.5 fpm, face velocity; or
- 2. Verifying within 31 days after removal that laboratory analyses of at least two carbon samples shows a penetration of less than or equal to 5% for radioactive methyl iodide when the samples are tested in accordance with AST1M D3803-1989, 30-CC 95% R.H., and 2: 45.5 fpm face velocity and the samples are prepared by either.
a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inche's in diameter and with a length equal to the thickness of the bed, or COOK NUCLEAR PLANT-UNIT 1 Page 314 7-24 AMENDMENT 424, iU6,25 Page 2 of 6 Attachment 1, Volume 17, Rev. 0, Page 346 of 471
Attachment 1, Volume 17, Rev. 0, Page 347 of 471 ITS 5.5 ITS 314 LIMITING CONDITONS FOR OPERATION AND SURVEILANCE REQUIREMENTS 314.7 PIANT SYSTEMS SURVEULANCE REQUIRMENT (Continued) 5.5.9,c 4. Verifyin l~ithth 31 dt~s afereeimoa.aH abrtr analysis of a carbon. 5.5.9.c ~~~~~~~~sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbcrs shows a penetration of less than or equal to 5% for radioactive methyl iodide when the sample is tested in accor~dance with ASTM D3803-1989, 30C1C, 95% R.H., and ?. 45.5 fpm face velocity. The carbon samples not obtained from test canisters shall be prepared by eithier 5.5.9.c.1 ~~~~~~~a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equa to tehikssof the beor 5.5.9.c.2 b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. Subsequent oreinstalling tedsrrtayused for obt ing the carbon sampletestm shall be deosae PRBEby veiyn htthe charcoal lsresremove gra~ta requal to 99 of-a--ao-ena-- hydrocazo refrigerant test ga e hyaetested in-pl6 nacrac witL4 ANSI N 0180 while opeai te etlton system afortef 25,000 efinpl omns10%. 5.5.9.a, S. Verifying a system flow rate of 25,000 cfin plus or minus 10% during system 5.5.9.b operation when tested Inaccordance, with ANSI N510-1980. 5.5.9 C. After every 720 hours of charcoal adsorber operation by either. 5.5.9,c 1 eiyn~i~n3 esata aoaoyaayi o U sample obtained from a test canister shows a penetration of less than or equal to 5% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 30CC, 95% R.H., and Ž>45.5 Ifpm face velocity, or 5.5.9.c ~~~ ~~~~~2. Verifyini w in 31 Ws after rtr ss Cmvla ofae carbon samples shows a penetration of less than or equal to 5% for radioaciv methyl iodide when the samples are tested in accordance with ASTM D83 1989, 30CC, 95% RJ., and a 45.5 fpmn face velocity and thesapear prepared by either. 5.5.9.c. a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or COOK NUCLEAR PLANT-UNIT 1 Page 3/47.24 AMENDMENT 44, 456,257 Page 23 of 69 Attachment 1, Volume 17, Rev. 0, Page 347 of 471
Attachment 1, Volume 17, Rev. 0, Page 348 of 471 ITS 3.7.12
'SRVEIjLLACE REWIIERUTS (Concinued) b) Emptying a longitudinal sample from gn adsarber tray mixing- the adsorbent thoroughly. 'and obtaining uampi least two inches in diamter an with a length equal the thickness of the bed.
Subsequent to reinstalling the adsorber tray used for obtain-SerJ ing the carbon sample, the system shall be demonstrated OPEMMLE by also verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerint test gas when they axe tested in-place in accordance vith ANSZ N510-1980 wahile operating the ventilation system at a flow rate of 25,000 efm plus or minus 10%: SR 3.7.12.3 d. At least once per 0 mna'ths by:Q)
- 1. Verifying that the pressure drop across the combined IMEPA [See [T~S filters and charcoal adsorher banks Ls less than 6 Inches i .
Va~ter Gauge while operating the ventilation system at -a flow rate of 25,000 cfm plus or sinus 101.
- 2. Deleted.
Ii~~~i~~k actual or simulated actuation si nal SR 3.7.12.3 3. Verifying that the standbtyiJ iltarts automatically on a A cunte neent Pressu-e-High-Rih gnal end aracta tsa
.exhaust flow through C filters and charcoal adsorber banksa gn a Co~i cPmsr~~g. hSi~gnzl.
- a. After each complete or partial replacement of HEPA filter band by verifying that the HEPA filter banks remove greater than or equal to 99% of the DO? when they are tested in-place in accordance with ANSI See ITS V5lO-1980 while operating the ventilation system at a flow rate of 5.5 25,000 cfm plus ot tinus 10%.
- f. After each complete or partial. replacement of a charcoal adcarber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are-testead in-place in ac-cordancek with ANSI N510.-1980 sohile operating the ventilation system at a flow rate of 25,000 efm plus or sinus 10%.
COOK. 4UCLEAEL pLANT UNIT 1 3/4 7-25 AHENDMENT NO. Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 348 of 471
Attachment 1, Volume 17, Rev. 0, Page 349 of 471 (3) 5.5
~~~~~~~~ITS ITS
*PrAIIT SYSTH SUVEIUlANCE REQUIREENS (Conti~nued) 5.5.9.c.2 .b) Emptying a longitudinal sampLe 'from aIn adsorber tray.
mixing the adsorbent thoroughly. and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. Subsequsx to reinstalling th dsorber try u~dfor obtain-ing the n sample, the ,tytce shall be deintrated ar OPEIAB4 byalso varifying that tha. chsacoal a&srbors remove groatsVta or equal to ~9% of a halogenate~ yrcro . rafri ~attest gas whoe they are tsted 1$place in aceoyanc with AN£NS -1950 AhL oaing ae the ventilation ya ata flowrat 2500
. ls snslI 5.5.9 d. At least once par Iiiuh y 6.5.9,d 1.. Verifying that thes pressure drop across the combined REPA filters and chaircoal adsorber banks is less than 6 inches Water Gauge while operating the ventilation system at a flow rate of 25,000 cfm plus or minus 101I.
- 2. Deleted.
S. verifying that the standby fan starts automatically on a Contaitnent; Pressure.-High.High Signal and directs its See ITS
.exhaust flow through the, HEPA filters and charcoal adsorbe 3.7.12 banks onAL Containment Pressure--High-High Signal.
559 ~~~~~~~~a each complete or partial replacemen f HEPA filter -band by vrzzying toat Whe UFvA 11iter -bankx remove. greater than or equal to 5.5.9.a 99% of the IDOP when they are tested in-place in accordance with ANSI X510.L980 while operating the ventilation system at a flow rate of 25 000 cfm plus or minus 10%. 5.5.9 .... .. fer each complete or partial replacement offa charcoal adsorber back [by verifying that the char-coal adsothers remiov greater than or -equal 5.5.9.b to 299 of a balogenated hydrocarbon refrigerant test gas when they are - Zested Lu-plAce In accordance vith ANSI1 N510-1980 while operating the aet!atiacn system at a flow rate of 25,000 cfm plus or minus 10%. COOK.NUCLEAR PLANT - UIT 1 3/4 7-25 AME.NODENT No. ,7% Page 24 of 69 Attachment 1, Volume 17, Rev. 0, Page 349 of 471
Attachment 1, Volume 17, Rev. 0, Page 350 of 471 CTS 3/4.7.7 A LUMM4CONDMONSFOROIVW. ANDStMVEUJANCE 3/4.7 PLANTSTSTEMS 3/4.7.7 S CONTAMINAM LR4 EQB O-UM&= 3.7.7.1 iealed awce conWft flux material eldw tri excess of microcmies of beta gamma emIuIAS uuwW 3 ancrocwies of a1pba emitft dWI be fift of adcrocurits of removable A At all Each $ease $oine I movable conumbaft In excess of aboim limim shall be Immedialely wabdmvl:iro Use a&.
- 1. Mer ..- A.-A re1wred. of
- 2. Disposedof -- -wkh
- b. Mit pwvhim of Spec 3.0.3 and 3.0.4 am not applkab S RBQMRMNTS 4.7.7.1.1 Teu Reauktaym - Each suM dM be wMed for leskap and!
S. 'Me licensee, or
- b. Odw persons spec authorIzed by tk Commiub State.
Thettumedkoddallbans unddvby of 8%lean 0.0c cr per UU&- 4.7.7.1.2 TeS EMMMdM - Pich sealed source " be tested at descr9bed below. SOUMS In Rse IOU=" am Balm nmdmh subkgW le gm At lean cm six mowbs fbr all sealed wmn radloacdVematerials. COOX =MPLANTtMI Pop 314 746 MEMD=ff 2351 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 350 of 471
Attachment 1, Volume 17, Rev. 0, Page 351 of 471 CTS 3/4.7.7
.3/4 LIMITL CONDJITIONS FOR OPER N AND SURVEILLAINCEREQ MNTS
.3.14.7. PLANT YTM SURVEILLANCR URMNTSContine
- 1. With ahalf-llfegr aer than30 days (excluidingHydrog 3), and
- 2. .In any form other gas.
- b. Stored source not in use - Eachealed source and fission dete rshall be tested prior to I use or transfer to another icensec unless tested within the p~re ious, six months. Seale~d sources and fission detect ritransferred without a certificate iatn the last test date I shall be tested~irior to be'g placed into use.
C. Stru ore - &a.'l se aAstartup source and fussion detect rshall be tested within 31 days prior to being SUNJte to core flux and following re or maintenance to the source. 4.7.7.1.3 Reot A Special Report shall prepared and submitted to the Co ission on an annual basis if sealed source or fission detecto leakage tests reveal the presence f :0.005 microcuries or removable contamination. COOK CERPLANT-UNIT I Page 314 7-27 AMENDMENT,91 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 351 of 471
Attachment 1, Volume 17, Rev. 0, Page 352 of 471 CTS 3/4.7.8 3.7.8.1 Al safety-related snubber snall b-a OMUABLE. AZPLIGAB IODES 1, 2, 3 and 4 (HODES 5 and 6 for sn- ars located on systems req ired OPERABLE in those OES). WJith onesor more snubbers inoperab a. within 72 hours nrepi e or restore the Lnoperabl nbar(s) to OPERABLE tatus and perform an en inering evaluatio: per Specif cation 4.7.8.1.c an the sported component or clare the supported yeten inoperable and is low the apipropriat. ACT ONstatement for that syste 4.7.8.1 E ch snubber shall be de ostrated OPERABLE by p fomance-of the following uganted Inservica ins ection program and the equirements of Specifica on4.0.5.
- a. Visual Insections Snubbers are categoi ad as inaccessible or a cessible during reactor operation. ch of these categories inaccessible and accessible) may be i apcted independently a ording to the schedule determined y Table 3.7-4. The via I1inspection interval for each a of snubber shall be d ermined based upon the criteria provide in Table 3.7-4 and the first inspection interval determined ing this criteria shal be based upon the previous inspection ntrval as established y the requirements in effect before Ame nt No. 17
- b. 3~ulIseto iei Visual inspection. hail verify (1) that th re are no visible indications of dama a or impaired OPERABILI , (2) attachments to the foundation or s porting structure are acr,and (3)in those locations whe a snubber fovesment can a manually induced without disconnecti the snubber, that t~he snubber has freedota of I
movement and is no frozen up. Snubbers wh h appear inoperable as a result of vies inspections shall be lassified as unacceptable and m ybe reclassified as ac ptable for the purpose of establishing th next visual inspection intrval, providing that (1) the cause of the rejection is cla ly established and remedied for that articular snubber and f r other snubbers that may be generically susceptible; and (2) th affected snubber is COOKC LEAR PLANT -UNIT 1 3/4 7-28NO 1" ",I ,V Page 1 oflO0 Attachment 1, Volume 17, Rev. 0, Page 352 of 471
, Volume 17, Rev. 0, Page 353 of 471 CTS 3/4.7.8 decimenty toestefd Am fouedoprtondvitho and cpabled s pber.f Spcntinued o4ration c. bel jnustif 4,tesnb s tell to elane IoprI end he aCT fluid tsora shallb At least onceop 2r onsmurng ydrutvLa e settv aemplaed(4 of the toe fof dehterminif snher Inspectionte plat sall be frevtiew lyateste eiher ineplrac or andbe dacceptnc rtedrojsi fy cific ration 4.7 th~ an additoableU ofthat. typ coftSnuber shLlob functionally tins ed. nub abaelre dssezaried unap e seetead thorMO fuctqioltetg shall b includethe variousa4om igraiongsbutdopaaing a romentsand th range of1k oiz and aecta of eachbtypo ot lzbeast of the use thenfhallon tbre f ca gorieste: ihrI l~ ri ec tes. Srr cnubber.ihnfe doeshaoy eostphentvlve, pumpt ac.a tncbecr.ithrina of fe sitheio dischage1f aan sdtcafety onubbert thapae iof ifibed1 as fuectinally tixicattd. moe Tnlddi he representative saaaseeced.* ucto* stn hl Incladdiie the t
v earou suample. snubers tin h failed andth praneviofusfzctinald hl be retete dungthnetet period.If a spreta be asnubeensi Itle plc of. ah faldsnubber, i ther ot zthve faipled sallbe(i i s reaifred the fosauvinghr. ols
*~ rmanen o The!f erpti n~ from funtonal reactifor iendivdule a .r Snbeswtin theectgr a es grate bywteqimn Iso onl if a i conditionsat ithe thecoletion ofe tshergr biato orfaty a Val-Lofvalve~~~Pge o 1 , Volume 17, Rev. 0, Page 353 of 471
Attachment 1, Volume 17, Rev. 0, Page 354 of 471 CTS 3/4.7.8 forith somober Ls) fom auopenablae.anSengieebevl vatioush beIef caued on tanfe orntdsich arefsuote byIh snubbers)at the pu Thoseo this eigeatiogshallbe tof etherif the c~pon sta poted b tesnubbers no were4 runyafcted by thFor asbbrsubber.s the eabltyo an onde tor *thuatiothe l supported componet em tapblof metingth designed service. d.. The hydraulic nuabber tIon test shafl Var that:
- 1. Metivation (rest? action) Is acivdwthin the specified range o velocty or accalerati in both tension and coinpresuion.
- 2. Snubber bleed, o rlease rate, where to reise within the specified range compression or tensioL For snubbers
- specifically r ed to not displace. umda continuousu load, the ability of snubber to withstad 10 d ithout displacemeants be verified.
A recard of the Sermi life of each snuber date at which the designated service IL aecsand the Lusteatn and mane anc records hihthe desipiated as c life is buxed shall be maintained a required by Specificsti 6.10.2. Concurentwith the f rt Iansrice viesua otion and at leasnt once per le amoth's reftrthe Installatio and mainteanmce records for al ani *reatd nbers Shall revieved to verify that: the L£udktcaede! so Ue has =o: been sedad or vill. not be exceeded -prior to ouxt scheduled snubber srielife reviev. If the Indicated sari life will Us exceeded pr or to the next scheduled snubber us cclife review, the ber service hie shall be reevaluated or th snubber shall be replac orrconditioned so as..to extend its us 6 lifa beyond the dote f the next schediuled service 1Sf a reve.This reevaluation, repi emeant or reconditioning shell be indicated in the reco a. COOK PLANT - MIT 1 3/4 7.30 AIMDMHENT NO. Q4" 173 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 354 of 471
Attachment 1, Volume 17, Rev. 0, Page 355 of 471 CTS 3/4.7.8 NMOER OF CC MM3L1RIJJS Population column A Colums B column C or Cateory Extend Into .1 peat Interv'al R~educe Interval (Notes-4 and 5', (Notes A and iA 0 0~~~ 2.00 0 14 1SO 0 38 200 2 5 13 300 5 12 25 400 3 1 36 Note 1: The next visual Inspec onInterval for a snubber opulation or category size shall be rateried based upon the rvoainspection iutsrv4l auid the tumber =fuacceptable snubbers o'dGuritg that interval. Snubbers a be categorized, bhsed u their accessibilicy
-during power operation, as, accessible or Imaccern. hi. These categories may be ezami ed separately or jointly. However, the icmnaee must make and cumant that decision beE re any inspection and shall use that dAcisic s the basis upon Which determine the next note 2: Interpolation botween o lation or category sixa and the number 9f umnueeptabls snubber.s apermissible. Use next ower Lnteger for the value ofl the lisit for Clumas A, B, or C ifta integer includes a fractional value of oceptable snubbers as dat rand by Interpolation.
COOK PU.EATlA-EUNIT 3/4 741 AMENDMCEN t4. A tM, 173 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 355 of 471
Attachment 1, Volume 17, Rev. 0, Page 356 of 471 CTS 3/4.7.8 Note 3: If the nmb~r of unaccepte a snubbers is equal to a less than the or Ln Column A. the no inspection interval may astwice the pv~~iou nterval but not rater than 48 months. neote 4: the muaber of ~maccep I. snubbers is equal to rloee than the r in Column I but getsr than the number in Cl A. the next etion interval thall a the some as the prei interval. Note 5: I thenuber of vmaccep 1. msubbers in equalo greater than
-entbet in Column C. next inspaction inteo oh-all be two-irds of the previous ine~a.However, if the erof eceptable &nubbr is es than the nm~ber inC but greater anthe number in Coum 3, the next Interao h be reduced rtlrronally by, Intepon stion, that Lo, the pteyous*interval shall
*reduced by a factor t is one-third of the ra Lo of the ftronce between the or of unacceptable sna ers found during
- previous interval, the number in Column S the difference in o numbers in Columns C.
Note 6: a provieions of Specif Caia 4.0.2 are applic la for all ispection intervals up aand Including 48 won COOK~ NU PLANT MNT 1 3/4 7-32 AHENDMEYT N, 173 Page 5 of 10 Attachment 1, Volume 17, Rev. 0, Page 356 of 471
Attachment 1, Volume 17, Rev. 0, Page 357 of 471 ITS 3.8.1 MTS 3/.t.CMR!AL tJSYTS 3/4.8.1 A.C.SORE UIXGCon-mTom MOR OQflATI LCO 3.8.1 3.S. 1.1 As a minim=m, the fofloving A.C ice] pwavr sources shall be OPERAILE:
- a. TV*obcircui c ts between the offoite transmission network and the onsite Class It distribution system, and
- b. Two IxwDeptate gd jzdeafsndent di...]. generators, each vith: A.
SR 3.8.1.4 -A.~ I yfue tan containing a %LnIvAn of ialifful
- 2. Asepaate ualstorap ysem containing a i'=indicated Volume See MTS 3.8.3
.of" .00-0 "alions of fuel, andpoeLC3
- 3. 1A #4 arate fal ewtafifr, y~imlC )
APWLIg&IL1=: MODES 1,2. 3and 4. ACTIONA fueperable, demonstrate the OP ITSBACTIONothed fremanit 2A.C suc M.st ACTIONFAoCTIiN: 30ohours
- b. Vth andiesfel gnrauto of the above required A.C. electrical power sources ACTION A inoperable, demonstrate the OPU.&BTh1 of theresia A.C. offsite sources yL2 ACTION B'byperforming Suv'veillance, Requirement 4.8.1.L~a Within hour I and atles ACTION F STANDBY~i within the nolt 6 0hoursan At O SZoW r a urs ore Completion Time bTaa sepa dsesel betfeen rate disels bueqsh beteenUnis red li and1. See lource COO nopeErable~demUnstrate 3/e 8.1=Y f h ADHfffeN NOurc4$s by, ACTIO S prforlng urvellanc Reqiremnt 48.1..1.a ithi I hur ad atl183 sine heeafer er8 b-ndLf x he"*&I uiraor ecmeLuPwagle 1o Attachment 1, Volume 17, Rev. 0, Page 357 of 471
Attachment 1, Volume 17, Rev. 0, Page 358 of 471 ITS 3.8.3 ITS ~I 3/4.8 tLECTRCAL MMVR SM=S 3 /4, .81 A.-C -SOURCES
~ ~
OPERATrNG ~ ~ ~ ~ Ad proposed C .. .
==IQXN 2=1D!TTO MR~OPEM=TO 3.8.1.2 As a ,41 the LoU wigA . eolectrical pover a as
§~Msb~all be 0?MALEJ See ITS
- a. Two physfcally indepenideut circuits between the offaitce transiission network 3.8.1 and the onsite Class 1.6 distribution system, and
- b. Two separate and indepenidsut diesel generators, each with:
1.. A separate day fuel tank containing a ainimnis of 70 gallons of fuel. A SR 3.8.3.1 2. A Iji fuel storage systam* containing a aicisums indicated vol=WA See rrS] AL. Vi~th an offslte circuit of the above required A.G. electrical power sources inoperable, demonstrate thes OPERARILTY of the rezmaining A.C. offsite, source
'by perforuing Survilance R.equireaent 4.8.1~.1.a-8 within I hour and 'at least once per S hours thereafter; restore at least two oftsite circuits -and tv, diesel generators to OPERALZ status within 72 hours; or be in at. 1eaut See ITS1 SOT STAN=E within the next 6 hours and ia COW SW OW Vit'hin the 3.8.1 folLowing 30 hours. -
- b. Vith a diesel pgenrator of the a.bove required A.C. electrical power sources inoperable, demonstrate the OPU.&B1LTY of the A.C. offsite sources by perorming Surveillance Requirement 4.8.1.1.l.a within 1 hour and at least once per 8 houzs thereafter; and if th~e diesel ;mnerazro becam. inmpora~b1 due to any cause other than an inoperable support system, an independently I testable coupwuant. or proplmanead preutven e mantnac or testing.
deomontrate. the OUABLZ'Y of the raiigODLEdiesel generator by performinij Surveillance Requirement 48. &...4within S hours, unless the absence of any potential coma sode -failure for the Temfainin diexel generator is demonstrated; restore diesel generators to OPEWALE status within 72 bout or. be in at least ROT STANBY3 within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.*At the u~mber of failures for the inoperable, dieael indicated in Table 4.841 perform the 'Additional Rallability Actions prescribed in Table 4.8-1. COOK NU~CLE.AR PLANT - UNIT I 3/4 1.1 AHERDKET NWO 46U. V4
¶183 Page 1 ofl14 Attachment 1, Volume 17, Rev. 0, Page 358 of 471
Attachment 1, Volume 17, Rev. 0, Page 359 of 471 ITS 3.8.1 ITS0 Required Action r Lm= oRat mt.b eqouired Action ac lqurm ACTO. D------e4mt 1m.1.1..t aithn1 b and at dieast oncetps S Of theabaft.:'anttd Lf th us-sel. pmerato: beams Iuopetabe due to any Gan. father than - inopetabia support "Sytem, an SneEnienly testable oowpoent, or piepsmied prmntive Required Actions eV~tetm &mmarat sw oluaaumv of the malu1ing Opu*3TZ B.3.1 and B.3.2 dl. ee pwato: b Pf 4a uMytl2me 4.6 .1.1l.2.a.4 - 2 L2 ACTION D Sucst ~ gs t ~ G 1;i t1itM ACTION F a*WttedeseL enratot resteed to 01h5A11Z status, follow AZ tatmata. iththeoffite~aircuit restored to OPDMLZ stes olo adMODE 5 vithin3 or ~ ACTION C A44 witI ano of the aboys gerqufted offalte &C. circuits Inprbe restore at LIeant one of theinpral offaits sources to 1U3Zstatus within 24 bours ACTION F -E~ be In at 'Leant MT? tZifY within tbe Shbouts ACTION E &two of --the sbove re rd diesal amatrst i"emhtab de-moustrate the Required Action B.1 l .la within I bowr and. at lest ams" I aorthereaftex et~ at ACTION E leasmon of the tooperable dieselL geeators to OIPU=A1 status within I boas ACTION F be In at least MT UTMWI within the wxt £ haws mA in COM SUWmO I~ss#4iontw&orka ueCasI d ssuuiea sysia sh 0Allb 1,mm tUad indiatedpew S*lbithe aMAdprpsdNoeioSR381 SR 3.81.9 "v emontyted La3*got at let thispr ACT ouha-trensft. n hei p0V5? sPomm auto~ecLmy fine the usomal .muLazy sourc to the preferred resetID sourc and by trnfertin P -- aly 3 to the astexuate mesev sourc. C=K HUCUM~PLAINT W.a? 1 3/4 1.2 ANUSON11T No. A"5 183 Page 2 of 18 Attachment 1, Volume 17, Rev. 0, Page 359 of 471
Attachment 1, Volume 17, Rev. 0, Page 360 of 471 ITS 3.8.1 ITS (i 314 LLMIMflG CONDMfONS FOR OPEPATION AND SURVEILLANCE REQU[REMEN'S 314.8 ELECTRICAL POWER SYMTMSL.
'SUVEILLANCgE RgEqURMgENT§ (Continzef 4.8.1.L.2 Each diesel generator shall be demonstrated. OPERABLE:L.
SR 3.8.1.4 1. Veyr*Wgthe fulllevel in thodaytawk. vr~dy
- 2. Vetig tefutlevIn deuelsorag 3.8 SR 3.8.1.6 [I Verifing that the fue transfer ca estarted, that k transfe fuhel-4rom the torg urtem tothe daytank.
SR 3.8.1.22 vey31das tedystt SR 3.8.1.8 4.vorItheerosta3740iosanacheves in ess t SR3.8..8votage874O 2d CT equaglO to, eon'h lg- 4160 V, freueMc- 60* H. SR 3.8.1.16 Lfrequency 588 _-I__L.1 th diese b synhroize ad kae a peae fr grae tha or SR 3.8.1.3 eu to 60 m~inutes at a toad ofa 0k* n L.2 every~~ldays 6. Veoyf ta te diese gee os toov ypower to L
- b. By removing accumulaed 3'.8.3[~S~gS~
SR 3.8.1.5 1) From fthea tank at least once pr31 j1. N a mi See ITS 12.) From fthstorage tanks at least oce per 31dy.i3.8.3J C. By sampling new ai accordance dia appi be gudeintes ofAM D4057-81 prior to adding new fuel to the storag Maks and SeM
- 1) By verifying, in accordance with the tests specified InASU( D975-81 and prior 6 J to aftddig new tued to doe stora tanks, tht fthsamIc has:
SR 3.8.1.8 SR3.8.1.8 ~ i~diesel
~~184~ generator tartm 1 eod)f standby cditions;hllb fmd at lesonceI days Inthes surveillanc tests. ~o rengine stasis (or the purpose of this surveillance Note 2 to tetnd coTP ~ action maet at reduced acceleration rate as rcomnended 6 the SR 3.8.1.2 A SR3.8.1.3~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~R ...
See ITS COOK NUCLEAR PLANTr-UNTf 1 Pape 314 8.3 WO E 3,273.8.3J Page 3 of 18 Attachment 1, Volume 17, Rev. 0, Page 360 of 471
Attachment 1, Volume 17, Rev. 0, Page 361 of 471 ITS 3.8.3 ITS(Ii 314 LXHTIN~bG CONDITIONS FOR OPERATION AMD SURVEILLANCE REQUIREMEN4TS 314.8 ELECTRICAL POWER SYSTEMS
'SURVE1LLANJCE REOUIRPAENTS(otnef 4.8.1.1.2 Each diesel generator shl be demonstrated OPERABLE: L SR 3.8.3.1 2. Verifying the fuel level In dhe fuel storage tank. evr41dy
- 3. Verifying that the fuel transfer pump cao be started and tat it transfers fuel from the storage system to the day tank,
- 4. Verifying that the diesel staxts from standby conditions and achieves inless tha or equal to 10 seconds, voltage - 4160+/-L420 V, an frequepicy - 60 1.2 Hz, rsee rTs
- 5. Verifing the diesel is synchronized and loaded and operates for greater than or 3.8.1J equal to 60 minutes at a load of 3500 kw**, and
- 6. Verifyin that the diesel Senerator is aligned to provide standby power to the gssociated epergncy busses.
- b. By removing accumulated WXCZEt~i C-;
I1) From fte day tank at least ncem per 31 days And after eadh occasion whnt4 See rrS I diese Isoeadfr reater tgm I howr aed 381 SR 3.8.3.3 2) From the storage tanks at least once per 31 days. Ad rpsdSR 3.8.3.2 tes.n an Bynesamoplaciong mayfuel atreuce aodaceleratio rtes apprecotnmengdedieby Athe38.
**Mometary loD40ranent dror tonaddinganew th toest. soae U"
*"The ons tob 1 should Bta y ingthe rcoertines bihtefoun so specified o In miTs958are Aror3, Atoddrooed geACTIaN C Ascodd propoemATO
) 0ffordaccumlatbed s paerfre atMonow COOKpNULEAR PAy NTbimUNvIllwT ess1 APtagie 314rdep8-3 AMbi~ENDEN 207 See, ay e t rducd aceeraionuPage tesingandcomamoryacton he14 2 ofWby 8 Attachment 1, Volume 17, Rev. 0, Page 361 of 471
Attachment 1, Volume 17, Rev. 0, Page 362 of 471 ITS 5.5 ITS 314 LNITMIG CONDMTONS FOR OMMUMTON AND SURVEIlLIANCE REQ LRFUNTs 314.8 ELECTRICAL POWER SYSTEMS
'SURVEILLANCE =1ojrREMENTS eniud shall be demonstrated 4.8.1.L.2 Each diesel OPERABLE:See generator IT 3.8.1 and
- a. Io accordance with the frequency specified in Table 4.8-1 on a STAGGERED TEST II. Verifyin the fue level In the day tank,.
rSee ITS 3.8.3) ITS 3.8.1J
- 12. Verifying the fuel level In the fuel storag SeeITS
- 3. VerifyWn that the fuel transfer pump can be simed and ftat translers -fuel383 from the storage system to the day tak,
- 4. Verifyhg that ihe diesel sturt from standby conditions and achieves inless a-- See ITS1 or equal to 10 seconds. voltage - 4160+/-420 V.and frequemsc - 60+/-1.2 H{z, -3.8.1j
- 5. Verify"n dh diesel is synchronized sad loaded and operates for greater than or equlto 60uinuies ataload of3500 kw*, and
- 6. VerIfyig tham the diesel generator Ii aligned to provide standby power to th 3.e1en IT associated eMergenc busses. /t . ITS 3.8.3).1 lb. By removing accumulated Water` L SI IT II) ro-= fte da" tank at teast ocm per 31 dSY5 kw amte eacli occasion whe 3.8.
I di esel Is operad for zEater thm I hour and 5.5.1 1.a C. B nWfe ol*Irn pedfance withithe 11 deblfnesifASlM I 5.5.11.a ) BY verifying wtte fijn D71 pror testing and compessatoty action may be at reuced acceleration raze as recoommnded by the See IS mauatrrso that mechanical stress and wear on the dieel ewnin are mInImized. 3.8.1 TIN actions to be take should any of the properties, be found outside ofaspeciie limits ame See ITS deflncdinthe~~~~~~~~~~~~~~~~~~asu. ~~~~~~3.8.3J COOK NUCLEAR PLANT-UNIT I Page 314684 ANMNDbMNT 4A5 207 Page 25 of 69 Attachment 1, Volume 17, Rev. 0, Page 362 of 471
Attachment 1, Volume 17, Rev. 0, Page 363 of 471 ITS 3.8.1 ITS(I ) 314, LIMITING CONDITONS FOR OPERATON AND)SURVEILLANCE REQUIREMENS 314.3 ELECTRICAL POWER SYSTEMS SURVEILLANCE REOdikEMENTS (Continued) A) A kinematic viscosity of greater than or equal to 1.9 centlstokes but less than or equal to 4.1 centlstokes at 40'C (alternatively. Saybolt viscosity, SUS at 100QF of greater than or equal to 32.6 but less than or equal to 40. 1), If gravity was not determined by comparison with supplier's certification. b) A flash point equal to or greater tha 125'1F.
- 2) By verlfying, in accordance wihbheep~ specifled in ASTMI D129S.S0 an prior to adding the new fuel to the storage tanks, that the sample has eithe an API gravity of greawe than or equal to 30 degrees but less than or equal to 40 degres at 601F or an absolute specific gravity as 601601F of greater than or equal to 0.82 but less tha or equal to 0.83, or an API gravity of within 0.3 See rTS degree at 601F when, compared to the suppller's certificate or a specific gravity 6. )
of within 0.0016 at 601600 when compared to the supplier', certificate.
- 3) By verifying, inaccordance with the test specified InASTM D41176-82 and prior to adding new fuel to the storage tanks, that the sample has a clear and bright -
appearanc with proper color. See ITS 3.8.3
- 4) By verifyin within 31 days of obtaining the sample that the other properties specified in Table 1of ASTM D975431 are within the appropriate limita when
- d. At least once per 31 days by obtaining a sample of fuel oil from the storage tanks in SR 3.8. 1.1 0 through SR 3.8.1.19 e. At least once per~jJmnhuisudw
*The actions to be taken should any of the properties be found coulsde of the specified [imits are defined inteSee ITS Bases. 3.8.3 COOK NUCLEAR ILANTSUNI I Page 314 384 AMENDMENT 125 Page 4 of 18 Attachment 1, Volume 17, Rev. 0, Page 363 of 471
Attachment 1, Volume 17, Rev. 0, Page 364 of 471 ITS 3.8.3 ITS (11 314 LINMITNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUMIREMNTS 314.8 ELECTRICAL POWER SYSTEMS SURVEILLANCE REOdikEMENTS (Continued) a) A kinematic viscosity of greater than or equal to 1.9 centlstokes but less than or equal to 4.1 centistokes at 401C (alternatively. Saybolt viscosity, SUS at 10OOF of greater than or equal to 32.6 but lesn than or equal to 40. 1), it gravity was not determined by comparison with supplier's certification. b) A flash point equal to or greater than 125SF.
- 2) By venfyln, inaccrdance with the tega specifiied InASTM D)1298-0 and prior to adding the new fuel to the storage tanks, that the sample has. either an API gravity of greawe than or equal to 30 degrees but less than or equal to 40 degrees at 60)F or an absolute specific gravity at 60/601F of greaer than or equal to 0.92 but less tha or equal to 0.811, or an API gravity of within 0.3SeIT degrees at 60OF when compared to the supplier's certificate or a specific gravity .
of within 0.0016 at 60/60' when compared to the supplier's certiflicate.
- 3) By verifying, Inaccordance with the test specified InASTM D4176-B2 and prior to adding new fuel to fthstorage maobs that the sample has a clear and bright appearance with proper color.
- 4) Dy verifying within 31 days of obtaining the sample that the other properties inpcified inTable I of ASTM D975-81 are within the appropriate limits when tested Inaccordance with ASTM D975-S1 except that the analysis, for sulfur may be performed in accordance with ASTM D262242.
- d. At leat once per 31 days by obtaining a sample of fuel oil from, the storage tanks in acodneWith ASM 127 ,advifyin that toal pudastci contaminatMo is less tha 10 mg/liter when, tested Inac~cordance with ASTM D2276-83. Method A .
C. At least once per 18 nmonths, during shutdfown, by:
- 1. Subjecting the diesel engine to an Inspection In accordance with procedures See MTS prepared Inconjunction with Its manufacture's recommondation for this clsss 3.8.1) ofsadyservice,
'The atos tenshould any Of di sbe found outside of the ad imts are defined In the COOK NUCLEAR PLANT-UNIT 1 Page 3/4 8-4 ANMENMEN.T 125 Page 3 of 14 Attachment 1, Volume 17, Rev. 0, Page 364 of 471
Attachment 1, Volume 17, Rev. 0, Page 365 of 471 ITS 5.5 ITS 314 IMITING CONDMTONS FOR OPERATION AND1SURVEILLANCE REQUIRE&METS 314.8 ELECTRICAL POWER SYSTEMS SURVEILLAN~CE RE06ilREMENTS (Coucined)Wtms 5.5.11.a.2 ~~~~~~~~A) A kinematic vicsagetr or equal to 1.Ycentsoe b 5.5.1 1.a.2 b) A flubhpointe o e 2 5.5.1lta.1 3) By veriy JIng3cc wit te 82 pri4er addressed i to adding fleew fulto testorage tak, d theuampl has eas and brgh SPcIfiain55iaoe 5.5.1 1Te.aains o3e tke Bhuday oftepropertie bcc foutd ie othie opfftepecifid InitS_7arD46 deddedessted SeeITn COOK NUCLEAR PLAN~toUN din newPage to4 8.4 W t~tf ml Atrg MENDMENT 125 iictin 1 boe appearance withpropPager26oofr6 Attachment 1, Volume 17, Rev. 0, Page 365 of 471
Attachment 1, Volume 17, Rev. 0, Page 366 of 471 ITS 3.8.1 ITS 3/4 LIMITING CONDITIONS FOR OPERATION AN" SURVEELLANCERQUEMNM. 314.8 ELECTRICAL POWER SYSTEMS acdent load
~1~~LLANCE REOU1RMENT (Contizued) Ad ooe oe2t R38.1.10L9 SR 3.8.1.10 Z. Verifying the generator capability t0 rjct ~
oapeertan or equal t. M~whilemanaun ot at 4160 freueny a 60+/-1. U*equenoy :S64.4 Hz andw.4tAn~eod A-Add proposed Note 2to SR 3 8.1 35lAn SR 3.8.1.11 3. riyensIthe generator capabilit to relect:loa0o3500kwwihutpii ~ L1 175% nf theA~~~f&-M= ovd and die oversoW m" tkint Es~~o-ltag O,' tnaintaln
- 4. imul~~atlogss05 of oifaite power by islad d propo2sed Note I to SR 3.8.1.12 SR 3.8.1.12 b) Verifyig tha tde diesel stails on the au~toata signa, energizes the emergncy peranenly cnnced lAdd wit usse rohi10secodNoeiosR,..11 SR3.8.1.13 . S. a~~eerp thSafetoyonnecio achuatdonoan t w Omrload s stue at tor.1 sandbyorperaterthfor Suaw hnor&Wto mminutes ddhile i~ats gener andr Add NoteroItoo SRNote3.8.1SR13.8.1 osed SR 3.8.1.13 5~~~. Vi'mu tatlonaSaofoeaty welcnntowtaabyjection anto*Ua. ls f011e o SR3.8.1.19 b) er)V~~~~po fi, gnro starts on the au1to-start signal, energies the the diesel lsdt euncrandboyertes thanfrrgreter or ddS38113prsabdan to 5 minutes equa Aht 10t3 e geeaor Ifsh with rec loadsfeter Floaded ah l~toad s)eftquencingeIs com o ofthe emeadgesnat boutaesand Ireqsheddofitg frm i eegency busses.salb 10+/- 21vlsad6 []z h tvolaean busshallh rqency permaientai cnned I within thes lisefornthsM.
load euee nde io erates p o ra d o iue COOK NUCLEAR PLANT4UNrIT 1 Page 314 8-S AMENMENT 125 Page 5 of 18 Attachment 1, Volume 17, Rev. 0, Page 366 of 471
Attachment 1, Volume 17, Rev. 0, Page 367 of 471 ITS 3.8.1 ITS 3(4 LINiTING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (IContinued) SR 3.8.1.14 C) Verifying that all automatic diesel generator trips, except engine SR 3.8.1.15 7. Verifying tha -f desel Generator -oprates at a pwer factor of less than o SR3,8.1,16 to 0.8 ~or at least 8 hours.*
~~~~~~~~qual During this test the diesel generator shall 300 kw.
be loaded thin5 minutes after completing this S-hour Ie ance equiemn 4.8.1.1 .2.a.4 (at eisting~ conditionsl).* Add proposed NoCe" armurvca 9F Verifying the diesel generator's capability to: A) Synchronize with the offette power source while the generator is loaded SR 3.8.1.17 jwith Its emergency loads upon a simulated restoration of offsite power. b) Transfer its loads to the offsite power source, and L c) Be restored to its standby status.
- 10. Vlerit g that with the diesel ge oroperating in a test m.ewhile connected toIrs oad, a simulated Sa ryIjcion signal ove r4S threst mode by:
a) Returning the diese genrator to standby o aonand
) Verifyig the e egnyloads are serviced yoffsire power.
SR3.8. 1.1 8 SR3.8.1.18 r I~~~11Verifying that the automatic sequence timing relays are OPERABLE with each L
~~~~~~~load sequence rime within plus or minus 5% of its required value and that each load is sequenced on within the design allowable time limit.
SR 3.8.1.20 f. At least once per 10 years by: tanks: r ~~~~~~~~~~~ RTS1 L3.8.3 SR 3.8.1.16 Note I Momnentary transients outside the load and power factor range do not Invalidate this test. SR 3.8.1.16 Note I
- If Surveillance Requirement 4.8.1.1.2.a.4 Is not satisfactorily completed, it is not nece~ssary to repathe -hur est Intea te dese geeraormay be operated a 50k o ecein COOK NUCLEAR PLANT-UNIT t page 314 8-6MNU M M.0..0 Page 6 of 18 Attachment 1, Volume 17, Rev. 0, Page 367 of 471
Attachment 1, Volume 17, Rev. 0, Page 368 of 471 ITS 3.8.3 ITS() 314 LiM1ITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIR.EMENTS 314.8 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) C) Verifying that all automatic diesel generator trips, except engine
,overspeed and generator differential. are automatically bypassed upon loss of voltage on the enmergency bus and/or Safety Injection actuation signal.
- 7. Verifying that the diesel generator operates at a power factor of less than or equal to 0.86 for at least 8 tours.* During this test the diesel generator shall be loaded to 3500 kw. Within 5 minutes after completing this 8-hour test.
perform Surveillance Requirement 4.8.1.1 .2.a.4 (at existing conditions)."*
- 8. Determine that the auto-connected loads to each diesel generator do not exceed 3500 kw.
- 9. Verifying the diesel generator's capability to:
See, MTS A) Synchronize with the offsite power source while the generator is loaded 3.8.1J with its emergency loads upon a simulated restoration of offsite power. b) Transfer its loads to the offsite power source, and c) Be restored to its standby status.
- 10. Verifying that with the diesel generator operating in a test mode while connected to its test load, a simulated Safety Injection sigsual overrides the test mode by:
a) Returning the diesel generator to standby operation, and b) Verifying the emergency loads are serviced by offsite power. Ii. Verifying that the automnatic sequence timing relays are OPERABLE with each load sequence dine within plus or minus 5 % of Its required value and that each load is sequenced on within the design allowable time limit.
- f. At leI once per 10 yearsby I. Employing one o~f th oigCleaning mtosolenthe fuel oil storg tanks:
a) Dratin each cioil itorage tank, remv e cuuated sediment, and clean thet or
&fo=1ntary trwsients outside the load and power factor rane do not invalidate this test.
If Surveillance Requirement 4.8.1.1.2.a.4 is not satisfactorily completed, it is notniecessary to See rrS repeat the preceding 8-hour test. Instead, the diesel generator may be operated at 3500 lcw for 3,8.1 2 hours or until operating temperature has stabilized.- COOK NUCLEAR PLANT-UNIT I Page 3/4 8-6 AMENDMENT IM.435 IJ, 07 Page 4 of 14 Attachment 1, Volume 17, Rev. 0, Page 368 of 471
Attachment 1, Volume 17, Rev. 0, Page 369 of 471 ITS 3.8.1 ITS ELECTRICAL-POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)- b) Agitate the fuel oil in the storage tank while Pumping the oil from the bottom of the tank through a 5-micron fil-ter, and back to the opposite end of the tank. Three successive samples shall be taken and analyzed SeerT according to ASTh 02276-83. If the contaminant level 3.8.3 in any of the samples isgreater than 10 mg per liter, the agitation, filtration, and sampling processes shall be repeated. If the contaminant level remains above 1e gper liter after 3 iterations, the draining and
'cleanring method described in surveillance requirementA.
4.8.1.1.2. f.l.a shall be employed.
- 2) Performing a precision leak detection test to verify that [Add proposd Note the leakage rate from the fuel oil system isless than or t S .812
.qua1 tn -05 dxlln~n per hnUr-SR 3.8.1.20 31).,.Starting both diesel generators simultaneousy sa , erIyi -- tat othdiesel generators I interei1~ aceleraftert any mjfle aton wIn cousd thanorequal teeo to1(9.
Ldd proposed vPage 7 ofm18 Attachment 1, Volume 17, Rev. 0, Page 369 of 471
Attachment 1, Volume 17, Rev. 0, Page 370 of 471 ITS 3.8.3 ITS ~I ELECTRICAL-POWER SYSTEMS SURVEILLANCE-REQUIREMENTS (Continued)- b) itate the fuel oil in the storage-tan hile pumping heoil from the bo om of the tank thug a 5-Micron iliter, and back to the opposite end of h tank. Tree successive sa pies shall be take adanalyzed according to ASTH 276-83. If the co tamnnant level in any of the samp es is greater than 0mg per liter, the agitation, fi11rtion, and sampli processes shall L. be repeated. If e contaminant leve remains above 10 mg per liter afte 3iterations, the rtaining and cleaning method scribed in surveillI nce requirement 4.8a.1.1.Z.f.1.a hal be employed.
- 2) P rforming a precisi leak detection te tto verify that e leakage rate fro the fuel oil syste is less than or~
qual to .05 gallo'ns per hour. shutdown, and verifyid1g that both diesel generators SeeITS1 accelerate to at least 514 RPM in less than or equal to 103..J
'seconds** -~Sbal I be eroiR ediv -fter a-ny modif ications which could af fect diesel- generator ISee ITS1 Iinterdependence.38.
- 0. C. COOK - UNIT 1 3/4 8-7 AMENDMENT NO. 125I Page 5 of 14 Attachment 1, Volume 17, Rev. 0, Page 370 of 471
Attachment 1, Volume 17, Rev. 0, Page 371 of 471 ITS 3.8.1 M_0 3/4 LIMITINiG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRCAL POWER SYSTEMS TA-BLE 4.U-Nu of Failures in L ohnr equasltolI At once per31ldays hmor uaL~to 2 At OncFE 7#s3 criteuia dtrnignumber of failn and valid tesb shall be inwith Regulatory Positi C.2 of Regulatory Guide 1. ,csin3, where the a o tests aNd failures Is on a per dies elneratorb s For doe purposes, Of OLis shdl, only valid tests cond afterthe OL Issuance dice halbe included In die co Onf the "las 20 vali 1 vo: frequocy $absl be Malt until Weme consecutive ur fe demands have been c~jdaaRndteumber oft In thelIan 2Ovalid has been reducedto on'eor COOK NUCLEA PLANT-UN11T I Page 314 -AM DEN1322 Page 8 of 18 Attachment 1, Volume 17, Rev. 0, Page 371 of 471
Attachment 1, Volume 17, Rev. 0, Page 372 of 471 ITS 3.8.3 ITS 314 LIMITIG CONDITONS FOR OPERATION AMD SURVEILLACE REQIJIREMENT 314.8 ELVCTRCAL POWER SYSTMS
?Nmbcr CFailures in Lens or eglolI At once per 31days haor uat2 At oner 7!!s'*
Criteria determfinia number of aieand valid test shall belIin Regulatory Posii C.2.1 of Regulatocy Gde1 Revision 3, where fthea o et failures IS on aperdiesd gsencrrbi.Forthe purposes of th ~ sceuenyVANi testsL2 coed a hdoOL Isuamdute be Inclded In the co onfte"a 20 vali tests t'-.st frqiufmay shall be man until seve coasecdve CedemAnds have been id dand ihe nubero Inuhe last 20valid hnbeeafreduced to one or COOK NUCLEAR PLAMMM4NI I Page 3(44 AMNDEN 1,222 Page 6 of 14 Attachment 1, Volume 17, Rev. 0, Page 372 of 471
Attachment 1, Volume 17, Rev. 0, Page 373 of 471 ITS 3.8.2 ITS 3/4 LIMfI1NG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRMEWIM 3/4.8 ElECTRCAL POWER SYSTEMS LMITIN CONDITION FOR OPERATION LCO 3.8.2 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be, OPERABLE: )
- a. [~~jcwe h fst rnmsinntokadthe onsite Class IE distribution
- b. ne iel enerat, ith SR 3.8.2.1 1. A day fuel tank containingoaminimum of aleso ul .
ACTIONS accordance A with S tio 3'11. fueMOD otrn Spcinficatio a.. inrmODE 6inditI thie etpor oldw 1.1. SR3.8.2.1 4.8.1.2 The above required A.C.electrical w r sour es to iradiated fuldsemonsra ed iPnAL the APPLIC perforM ODcE of Seach of the-S----ilanceRequie , and benlsiof Uni 2 . xcettfoiLn 3.8.2.1~~~~~~~~~~~~~~~ATO dd SR3...1exetin proposed
-;With urngth eleteided A.Cng.99 ptower sourcaes inERA997,1-mnhsrilac1.
fnvoh* C anE 4.8. Ac); o pi.2.elOy)ad )t n 4.8. 1, xcq2pe:a be dlaye or adtim unti jusctpror toodie At ACTIOSA rovidd tht UToW MARGIw tohe omdt h geI anandi isinrst ny oeo les peiod n MOE 5,of 2 of Pagefro1thofWS2 Attachment 1, Volume 17, Rev. 0, Page 373 of 471
Attachment 1, Volume 17, Rev. 0, Page 374 of 471 ITS 3.8.3 ITS ~I 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRMEMET 3/4.8 ELECTRICAL POWER SYS1EMS LIMIT~ING CONDITON FOR OPERATION LCO 3.8.3 3.8.1.2 AsabiuG th u ig rff&5- 1DMATRI
- a. One circuit between the offsite transmission network and the onsite Class IE distribuion system, and See rrs
- b. One diesel generator with: 3.8.2J 1 A day foal tanic comtaiiin' iiu vof 701gallons of f~iale SR 3.8.3.1 2. A fuel storage system contaning a minimum indicated volume of 46,00() gallons Of WoI, and With less than the above minimum required A.C. electricI power Sources OPERABLE, suspend all operations involvng CORE ALTERATIONS or positive ractivity changes except: 1) beatup or cooldown of abe reacto coolan volume provided that SHUTDOWN MARGIN sufficient to accommodate the change In temperature is maintained in accordance with Specification 3.1.1.2 in MODE 5 or Specification 3.9.1 in MODE 6. and dhe heatup or cooldown, See ITS rate is restricted to 50 01F or less in any one-hour period in MODES5, of 2) addition of water from the RWST, 3.8.2J provided thie boron concentration in the RWST is greater tha or equal to the minimu required by Specificaton 3.1.2.7.b.2.
SURVEILLA~NCE REQUJIREMENTS See CTS markup SR 3.8.3.1, 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE bte pages 2 of 14 SR 3.8.3.2. efrac fec fteSrvilneRqieet C D81 M.1ad 4. 1 . cPt
. fr through 5 of 14 SR 3.8.3.3reuemn requirements 4.8.1.1.2.e.4.a) and b); 4.8.l.l12.e.6.a), Ib)and c); 4.8.1.1.2.e. ; 4.8.1.1.2-e9.a), b)See ITS and c); 4.8.1.1.2.e. 10a) and b); and 4.B.1.1.2.e.l I , may be delayed one time until just prior to die 3.8.2 COOK NUCLEAR PLANT-UNIT 1 Page 3)4 8-9 AM'ENDMENT 425, 4.49, M, 230 Page 7 of 14 Attachment 1, Volume 17, Rev. 0, Page 374 of 471
Attachment 1, Volume 17, Rev. 0, Page 375 of 471 ITS 3.8.7 ITS EI ELECTRICAL POWER SYSTEMS
-3/48;.2 ONSIl& POWE*71HSTRIU71ION1SYSTEMS-A.C. DISTRIBUTION OPERATING LIMITING CONDITION FOR OPIRA'TION See ITS
.8,2.21Thit'fo11bwif'g
*%Ctrical bs~isA.C. &hill be OPERALE and 2rjargi338.9 4100-volt Emergency Bus 91T hA & T 1U 4160-volt Emergency Bus #T 21C &
60O-volt.Emergency Bus l12A & IU u~ CSee ITS 3.8.9 600-volt Emergenacy Bus UliC & 120 01i0-volt A.C. Vital Bus fthannel I
'l22Ovolt A.C. Vital Bus Uthannsl It i120-volh A.C. Vital Bus fthannel III
'i220volt A.C. Vital Bus DChernnel IV ACTION A les then the ov eOP nt o .C. busses OPERABLE, restore the ACTION C wtntent hurad S DOWN within thei following 30 hours.
SR 3..7.1 4.8.2.1 The s'pecified A.C. busies shall be determined OPERALE and energized oL A.C. sources with%tit breakers open between redundant busses at least once 'Pr7 days byverifying correct,breaker alignment and indicated power *vallabllity. LCO 3.8.7 0.C.COOK *UNIT 1 '3/4 11-IO AMWEN~DMENT NO. 3251 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 375 of 471
Attachment 1, Volume 17, Rev. 0, Page 376 of 471 ITS 3.8.9 ITS Gi ELECTRICAL POWER SYSTEMS
-3/4-.8B 2 DNSIlt- POWIft-fflSTRI BUT I0NYSTEMS-A.C. DISTRIBUTION - OPERATING LCO 3.8.9 LCO 3..9.a {
3.8.2.1 The folltewir 4260 alIt Everget A.C. electrical But (11 & T 1D sh MIbtDPAL19 02 J r O~lt. A.C. VLiBus #Ch nael I 120 volt A. C. Vtol Bus #C annel 11 TanA and Train Br2 A ia ditiution LCO3.8.9.b120 volt A.C. Ital Bus ic annal IIIA2 ACTIONS A 11th esthn the above complement of A.C bus OPERABLE, restore the and B ~LUIn arable bus to OPERABLE status within~ o beou-in It STANDB ACTION E V in EF -r1(tO 6 ours and n COD51UI t the following 30 hours. SR 3.8.9.1 4.8.2.1 The s eicitid A.C. busies hall be determined PP ASL lad entals z amf. days -by verifying correct bieaker alignmenit and Vr AV least once 7 1
~-Add SR ~3.8.9.1 forUnit 2 electr~ical vhg .
p~ower distribution subsystems SeIT1
'oEftrgitid frms `It 1111115ial111 Invartelr cobneted toaD us ..
- 0. C. COOK *UNIT , -3/4 8-10 AM1ENDMENT NO. 1225 Page 1 of 6 Attachment 1, Volume 17, Rev. 0, Page 376 of 471
Attachment 1, Volume 17, Rev. 0, Page 377 of 471 ITS 3.8.8 ITS 314 LWIMIJNG CONDMTONS FOROPWERAT1ON AND SMVLV1ANCZtEUI~MNT 3/UE4 CRZA POWER SYSIMM 382.2 As a mbinmi. &e MoE gA.Q- e~cctribusses oahalbe OPERABLE imd w~i&gfzL I -410.voitEniermecy~xu. nd See rrS 3.8 .10J APPIJCAB-= MODES 5 and 6; nd, movemenon=%ftiacf ACTION A Weasado above caopk1m tofA.CCbwsum OPERAMLE mndaegied
- b. hmndkteyinftia actlo, rstr 6rTqVing qmto dAE AniiUaEPA170OP vmmg f iamats fa Usembifand sff . zesidi .
orea-z5niu1 BF oin See ITSrcoim SR 3.8.8.1 4.8 in acrnc jxd.~bseato 311.a~b dtorhdOPA ficaiomp d iz3ed andayfi byvO LCO 3.8.8 {~~~~~~~~~~~~~~4 .81 COOK NUIZcAR PLANqT-UNIT 1 Page 3/4 8-11 AMENDMIENT 1-3, 259 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 377 of 471
Attachment 1, Volume 17, Rev. 0, Page 378 of 471 ITS 3.8.1 0 IT-S LCO 38.10 th fkw.2.2ecim ACTION A Ia~h~eaoeCfi1HDof A.C.blw50 PERAXL~MAd proposed Required ActionA.
- b. tsubdae, yzitte abx o rstr qihedRW.rC eectxiluOer I ~ llto Es., m C. Imediately dwlm ruaaoated sqnfred, =did htwonrlr ka bops) bpeahl.
SR 3.8.10.1 4.8.21 Ilbs qpecliod A.C. bwses salbe dctem~im~dOP3RADLE at~kast perpa7 days by I fromits associated mvit connected toa388 Enertud COOK NUCLFAR PLANT-UNTIT Page 3/4 5-11 AMENDMENT U2S, 259
~Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 378 of 471
Attachment 1, Volume 17, Rev. 0, Page 379 of 471 ITS 3.8.4 ITS(3 31/4.0 LWafMIG CONDMON FOR OPERATION AMD SURVEW.ANCE -REQUIRMEMET 314.8 ELECMRCAL POWER SYSTEMS D.C. DL~RB QNOr- OPERATING LI?4JMN0 CONDMnON FOP, OPE3A8.9 LCO 3.8.4.a 3.8+/-23 The foMowing DC. sllb OPERABL7E ~Ije breakrbetweenbw onscnof 250-volt D.C. bus
- 20-lt D.C. hpeybank ld lAB, M.
APPLICABILT: MODES 1, 2, 3 and 4.
- a. With one 250-volt D.C. bus inopeable,, restre the inopetzble bus to OPERABLE status See- ITS within 2 homrs or be In at'least HOT STANDBY within the next 6 hours and in COLD1 3.8.9 ACTIONS A and B b.. [ With.=n
...... 250-volc D.C. is c ttchm ba ACTION C STANDBY ~~~~within the next 6 bours and in COLD S~flrDWN Within the following 30 14.8.2.3.1EBAcD.C. bus Wain shall be daterIned OpERABLE and onerized with tie break oers at leSee ITS I ~~~~onc Rye 7 drys by verifying correc breaker afirnien and Indicted vower xavaiabfiity 3.8.9 4.8.2.3.2 Each 2504vol battery bank and charger shal be demonuzrraed. OPERABLE SR3.8.4.1 ~~~a..A laseoce per 7 days by verifying that:
k=
- 1. Thm electrolyte level of each pilot ce.U is between die minimum and maximu level Mnticauiz taks Zee MlS
- 2. The pilot cell specific gravity, con~ctd to 77F, and full electrlyte level (fluid .386 at the bottom of the maximum level Inictin eah, is greaer than or equa to 1.200,
- 3. The pilot Cell voltage is greater than or equal to 2.13 voltst, and to theL5 SR 3.8.4.1 4. The overall battey voltage is greter than or equal tUKENAI ~ minimum established (Addproposed at vltag COOK NUCLEAR PLANT-UNIT 1 Page, 3/4 8-12 AbMENMENT 435, 15, 198 Page 1 of 12 Attachment 1, Volume 17, Rev. 0, Page 379 of 471
Attachment 1, Volume 17, Rev. 0, Page 380 of 471 ITS 3.8.6 ITS 314.0 LBTh4'fNG CONDMTON FOR OPERATION AND SURVEaLLANCE REQUUIREMET 314.8 ELECTRICAL POWER SYSTEMS D.C. IMSTIUBUON - OPERATING LIMMTNG, CON~DMTON FOP, OPERATION Adpooe C .
.+/-2.3 Tho following D.C. bus trins SWal be energized and OPERABLE with tie breakers between bus trains Open:
See rTS 3.8.4 and TRAINT AD consisfti of 2.50-volt D.C. bus All, 250-volt D.C. battery bank No. 1AD,. and 3.8,9 a WI capicity charger, xnd TRAIN CD ionsisting of 250-volt D.C. bus CD, 250-volt D.C. battey bank No. ICD, and APPLICABiTY MODES I,, n . IL Wmhi one 250-olt D.C. bus mnoperable rttoe h inoperable bus to OPESeeBLE
- b. Wah. one250-volc D.C. battery and/or fts charger inperable, restore the inopera SeM
-STANDBY within the next 6 hour and inCOLD SHUTDOWN within dhe following 31 SURVEIL ANCE REOUTJREMEMT d rpsdATOSA ,C ,E n j4.8+/-23.1 FcD..bstrain shall be darmiuned OP LERA and coergzod with de breakers ope At I See ITS pr 7day byverifying correct breaker alignment and Indicated power ava~ilabiy.
oncc 4.8.2.3.2 Ec25vltbattry bank and charge shall be demonstratd OPERABL.E( ) SR 3.8.6.2 a.
- b~yer~ifyig that:
At least once; perffay boetto ofthe: fcc CUI ewe teroA..and the or equa
- 2. stcfi o 77F. and lft&=yte level (flufid SR 3.8.6.2 3. The pilot cell voltage is greater tha -or equal to vls n
- 4. The ovRa-M battery Voltaige Fs grecater than or equal to 250 volt-S. Se F COOK NUCLEAR PLANT-MUNIT Page 314 8-12 AM[ENDMENT 4U, MS,198 Page 1ofl10 Attachment 1, Volume 17, Rev. 0, Page 380 of 471
Attachment 1, Volume 17, Rev. 0, Page 381 of 471 ITS 3.8.9 ITS(I 314.0 LUhITIIG CONDMON FOR OFEAInm AND SURVEaILANCE REQUIRXEMNT 314.8 ELECFRICAL POWER SYSTEMS D.C. DISR!UTIOr - OPERATINO LIWMINO. CONDITION FOR OPEATON Train A an-dTrain ~B250 ~VDC distributi!on subsystems LCO 3.8.9 3.S.2..3 Thfbai, E. us&' shallib OPERABLE tteWu L. LCO 3.8.9.c m guf " ACTION C ----- ltDC bus inoperable, restore the inoperable bus to OPERABLE sau h----e--------O o ACTION E UTONwithin the floin 30 hurs_ =Add proposed ACTIO F Ad proposed ACTION G /\ SR 38.91 4..2..1 Eclb.CW.bsnuha2bede-zrineD.C.bamryamfbr tsc h tieb~ M.3hehpeba 4.82.32 Edi 504ohbamttey o bank charger to i e OPERABLE eitone power distributions H subsystems M.4
-.TANDBlea ithone thenext 6y versinfnCODSyTDW that:l hig b See flSeIT hou__ _ _ __ _ __ _ _ __ _ __ _ _ __ _ __ _3__ _ __ _ _ __ _ __ _ 38.4n 4.8.Z3.2 ach 25N~at bther banom ofr the axim levdemonstcateod matRM,isgetr dsrbthano equasys3.8s.6V
. 4. Thea o vc; er7 al baey s voerigeins greater thno qa o20vlee ITS
- 4. ~~~~~~~~~~~~~~~~~~
an NULEAR PLNT-UNIT17 COOK Pagtrlye 314e8of eahpltAMli ewen die T 33,58 19 level action maricsPge,2of Attachment 1, Volume 17, Rev. 0, Page 381 of 471
Attachment 1, Volume 17, Rev. 0, Page 382 of 471 ITS 3.8.4 ITS 314.0 L7MMG CNOMMOPOROPERA71TONAD SVVEI[LANCE REQU1RMENT 314.3 ELECTRICAL P'OWER SYSTEMS
- b. Atleatonceper92daybyveirffyhgtat:
- 1. Thevoltagofeachcomectcd cellis gretertb orequulto 2.13 volts izdrfloat
- 2. Mme speifia gravity, comrected to 771F, and fall cleczolyte level (fli atT See rus bottom of fte M~nzxm level ZindicSIatJ mark), of each connected cell is greate 3.8.6J than w equal to 1.200 and has not decrased nun than 0.03 fium the vabue observeddu=ingto pzoous teAt and
- 3. The lectolyte leve of oach comectcd co,11 is between the top of to irinm SR3.8.4.2 indficaioa~mrk and the bottom of tbe muxiim=leveidc atimrzr.dN le~~~~~~~'vcl SR3.8.4.2 C. At kst Mcc per mt~T
- 1. Vrifyng/tetdte cells, Cell plates odbattery nck show no LvAisl o pljlainaseor abrornl
- tat could degrd 1.
- 2. viaile conusion eifigthatt icl-tce adernl cc are dlean, tigt, wiL fdcor io SR 3.8.4.2 3. Vcring*fi d barY Chargeril WMMPplY at least 3 00 inupcres at greater than or eual to 250volts for atekmt4hbowsx SR 3.8.4.3 sown the aeftla or simlted emergency loads for te desig & C Note I to 115thistis erforiudizi l~ofaa service tanumdified rmunce SR 3.8.4.3 7Anima perfoamace tErt obattery capnct isma be given to any battery thaI shows usgs1 of dcgrada~io or lie rcadhed RS%.of lhe service life xlpecrd for 6.e applitaiioam Degradati~on is hmdi when dw battery capacit droPe n. than 10% flmn its cap~YL See RTS on The pevious pedrmance test or is below WI. of the =amzitur=oez' raudg& ifte 3.8.6J battexy barn readiied 85% of service Nel, delier a capacity of 100%A or greaw of the miznzrrsrated copacity, anidhas shown rno sign of degadatimn perfomance Ustesli t two yea hntevals is =Accpable tmtll the bater shows sOgM of deraatoon.-----
COOKNUCLEARPLANT-UNIT 1 Page 314 8-13 AMENDMENT426, &K498, "6C 269 Page 2 of 12 Attachment 1, Volume 17, Rev. 0, Page 382 of 471
Attachment 1, Volume 17, Rev. 0, Page 383 of 471 ITS 3.8.6 ITS 314.0 LwM2GCo>NVMo1NFOR OP A77ON ANDSURVEILANCR REQUnUZMEMl 3/4.8 ELEcnuCALPQWEMRSYST~MS
- b. At leasn CcepCr byrfynia SR 3.8.6.5 1. Thgepofea&hcawsmetd 30 callii greater gm or equal volts wider float charge.
- 2. The ~iflgezgrvity, corrteded 77-F, and gWfclcr evel (flrid at fte SR 3.8.6.3 3. The elecjo ~~~~minleve o each klctnnece cell, of designslimits
- c. Aticestance per 1deresed8=from teatrbha hevah
- 1. Vrifyngtai te cos, cll patesand batey acsshwqouial idiatono phyicl drugeoalomu dterortio tat oud dgrde minimeummnnc conetinsue luofigteand coatedwits Want-canio gmaeria
- d. At bast omm per I18 zueby,pefmsbtrysvcettdrighuow(MDS5r 6)bVaifyiigilto tdebutellrye plateys and battertupy rands shoMintai inOPi of the ctuaor sinulatmd oduftycyce. Tbattererycharge dx~getyladsnorathe design Vmfb fsrvierdabechda%
ttebattery life deplvr ceapacty of300% at ora greu othemo 6). 'byfactixcz's rted caacty capactyus ahrnrto signs of drand abiproiare b tistingAB stwoi tyeainteorvuls aetabedni is the. boattr fhor &esigns of~degrdto. hbatrcsr COOKIUCLERILANTwiNl 1bae 314the4test 8-1ct AMENDMENTI5, 269 Atkam~ct onceper MfoPagee 6 rimcft, 2t Of 10a Attachment 1, Volume 17, Rev. 0, Page 383 of 471
Attachment 1, Volume 17, Rev. 0, Page 384 of 471 ITS 3.8.4 ITS Y14.O LXN(MG CONDMlON FOR OPIRATON AMDSREL.~ RzQTumEMbTs sf419 ELDCT1&CAL POWER SYSTEMS This page ibt=&naIy kftbmak COOK NUC[ZAR PLANT-UUT 1 Page 314 8-14 N TIS4S26 Page 3 of 12 Attachment 1, Volume 17, Rev. 0, Page 384 of 471
Attachment 1, Volume 17, Rev. 0, Page 385 of 471 ITS 3.8.5 ITS 3/4.0 - LUI2iGCON=~TONFOROPERAON AM SURVEILLACE DQIEE SMU UE~kCAL:POwMSYS~hMS LCO 3.8.5 3.8.2Dst.btonSyte4eqird yLC 38.0 3.8.10s APPL~~~7 d iuake nd couxectnd vfaliy. haiw~mmofmdiWaId 81 SRIO 3.A. 4+/-2.4.2 equttmz bakadragrsalle c~wrtdO~AL aboveoukteqn* 25-olt. Thef Surveilance1lcquie~ncn4.8.2..2 Ad propsed Nte toSRe.85. L.2 Page 314 1-15 COOKN1JCLEA1~PL4.NT-t~l'UT1 ANDNT42SL 3.8250 a.SU 'mwditdy mpea COE LTRA70M UPage of1 pmfow tolvig ofe2 Attachment 1, Volume 17, Rev. 0, Page 385 of 471
Attachment 1, Volume 17, Rev. 0, Page 386 of 471 ITS 3.8.6 ITS 3/440 IJUMflG CONMONFlOR OFMUA1ON AM~ SRVEMLANCE EURMQ 314. ELECYRICAL POWER SYSTEMS 3,8k4 As amninim wlfollowing D.C detcaquipw=an bs a i eaen O
-a LEIZSe T t-25ov.c~bus and SerS 381 1 25G~~~~~~~Ok ~~~~~ c.~~~~~
.1~~~~~ S~ee ITS APAL LfR=: MODES5 adC.:nd zii=ven.tofiidiu~dfui.l Wit~es~aI~hcabvccoup~enofD.CcquprwntadbiuOE~A LE Add proposed ACTIONS A, B, C, D, E, and L.
- a. lnxzndiately impend Ol opcrmlimn hvolvkig CORE ALTERA move= fhmile e awusbaeml, and pywilhr meaviVl change czept: 1)heastp or cooldWn of the =lawto cool=n Vch=~
provided tat SHU'WWN MARCEN sufficelnt to acconzvodtc the cbang in fteniertu= Isn~abined See in accordan wit Specification 3.1.1 in MODE S or Specificafion 3.9.1 hi MODE 6, snd the heakup 'T cooldown rat is restrcted to 500Por les in an one-bour period in MODE S. cr2) addition of atwr frian 3.8.10, bySpecficatioa 3.1.2.71b2
- b. Iwm~at* b*xeactioi= la reamr fthreqwred D.C. clecti~lclq but to OPERABLE apsnta MMaos See IFS1 C~~ Th2UbbedIwiD AS~tiu u =oyal"1298 3.8.10J 4A2A.A1 Mica ocarx 4 250-vohD.C~bus bev ineO UB onecee' l~tSee ITS pa7da~ys byvedfyig cc ctkvb iakrulgmamdi~hdIcedpowersulaflty .3..1.
See CTS markup pages Iof 10and 2ofl J0 cioOKNuaCLAkrPINT-UN1cT1 Pape 314 S-IS AENDENT4259&P3, 259 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 386 of 471
Attachment 1, Volume 17, Rev. 0, Page 387 of 471 ITS 3.8.1 0 ITS LCO 3.8.1 0 3.8+/-4A 1)Q SeetTSoitriutio su.b+/-.
- b. :wrque .. im~1 ~ OPP~E~See 3.8.5 ITS SR 38.11 48+/-41 Te aovez~qine 250'vvl+/- D.C.1w inaD1~ dc9.1emnedd OP beaLo pbv 3.U7sbyv.Z cotbeaeuld reutien DW o orncoc voltageure
~~d~
4O~~~~~~~~~~~4~~~~~~~~ b lO EP BESee ITS 4.82A2 M30 i equan 250-vult btiaty bank and charge shili be- demostrated OPZL 3.ee and urvece~~~~~~~q1*E2~~~~~~1E~~~i.2.3+/- ~~~~~3.8.6 cooxNIaCEAk PL&NT-uN1Ti Page 314 8-15 A~WgN)MENT4W8, 259 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 387 of 471
Attachment 1, Volume 17, Rev. 0, Page 388 of 471 ITS (3 ITS 3.8.4 3140 lMfMG COZ(DflION FOR OPERA'flON AND SURVEILLANCE REQUIREMENTS 314.3 ELECIMICAL POWER SYSTEKS D.C. DISRBUrION - OPERATING - TRAIN N BATTERY SSE LCO'3.8.4.b 3.3.2.'5 Mhefollowing I. shallbe ift d OPD.RABEL238 A~LI~&Dfl 1~: MODES 1.2 and 3. ACTION1 ACTION D Nbatr ytnIoebldcaetetbierieAularFewar SURVEILAN-CE REQ1IU EET 14.8.2.5.1 D.C. bnus Kmlb verfyig Wo=c breake algnet OEAL and ecrgzcmd mi Ieamto dinia -dpo milabilft. per 7days bySeIT I 3.8.9J 4.8.2.5.2 The 250-volt battery bank and hgare shall be dmafzntzut4 OPERAELE SR 3.8.4.1 IL At leas once per?7 days by verifyin tht
- 1. The elctroLyte level of each pilo ccll Isberween the minmo and mxmm Leve hndiodaniwz
- 2. noe pilot c~li specific pravt, cpnvctW to 77P1and fi& eletroyte level (Aild See8.6 st the bottom of toe -maxii level indication mard), Is greater tha or equal to 1.200,
- 3. Mme pilot cell volage Is mm eqal'to 2.13 volts, and thean t h SR 3,8.4,1 4. The ovenal bautuy voltae is gre ate, tha or equal I. . etbihdL
- b. At 1Castonper 92 dapby VUWfhiAMtm I. zh volrag of each Veaictd cell is greaer Oha or "qato 2413 Volha =unt flot charg.
2.1 Ib The S pecfcgavity. coirected to 77qF and 1alU electroyte leie (MMuiat the See flTS bomtm of (he maxidmm level Imleatioan ark), of each conneted cell Is greate 3.8.6J tha or equal to 1.200 and has tot deceased more tha 0.0 from fth value obseve durig tie -mi tes, and.
- 3. Te electroyt level of acwh connected cell Is betweenath op of dth minimum level indiation mark and fthbotto of the muiamun lade Indcation mark COOK NUCLEAR PLANT..UWAl lae 314 8-16 AED NT426, 565,198 Page 4 of 12 Attachment 1, Volume 17, Rev. 0, Page 388 of 471
Attachment 1, Volume 17, Rev. 0, Page 389 of 471 ITS 3.8.6 ITS 3/4.0 LVA=WG COMMIION FOR O1'ERA'ON MMD 5UVEILLANCE REQUOUEMMM~ 314. ELECTICAL POWIR MYTMS D.C. DISTRIBUTI -OPERANING - MMAI N LATTER SYSTEM 3.9.2.5 The foilowing D.C. bus Usin "blbemt dadPRAL See ITS1 TRIIAN N consistig of +/-50-volt D.C. bus K. 250-volt D.C. beatey bulk K. and ILull, 3.8.4 and charger. 3.8.9)
~~~jfl: IMODES 1,2ad. u Wih fthTrain N barttey system inoperable, daclare the U bn~eAuuiuiy rh Ffedwawe Pump inoperble andj follow the ACTON sub~ment of Speci~carion 3.74.-2. IFSee ITS 3.8.4 and
&MUMVLACE, REOU BMNS1.3.8.9 I4.8+/-25.1 The D.C. bus train K shall. be deemndOPERABLE and energizd it least once per?7 days wISee ITS I verifyinm~ g corvec breaker aligumnte and Indcated power ivalailiy.I 3.8.9 4.8.2.5.2 The 290-volt bagwey bank aznd ahall be demonstrate OPEP-ABLE SR 3.8.6.2 A. A woed idd proposed SR 3.8.6.1 Q~
SR 3.8.6.2 3*. n pllgt crf1 Voltage Is gpester ton or eqal0 ots a See ITS I4. Th eoverall banery LU i~sg grete tfor
&IS eMga to 250 val:M:. I 3.8.4J
- b. Al pelero 31d= lvl .
nocvoltage Of cah wneczddmC* sgS-mmrthanor oquAl to v ue SR 3.8.6.5 ltchre
- 2. Mm gaiy correced 77"F and fnullceo (flui at the ofthe maidMunilevel aw* ' 110 CUh&A or to 1.200 and mot decreased mor 0.3 rm h value graethno SR 3.8.6.3 3. ~lbe electra level of ech connete cell Is m dew of the m COOK NUCLEAR fLAT4NIT1U Page 314 8-16 2 z"NM~
,455199 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 389 of 471
Attachment 1, Volume 17, Rev. 0, Page 390 of 471 ITS 3.8.9 ITS CI 3/4. LNUAMG CONIDMfON FOR OPER'11ON AMD SURVEILLANCE, REQ11UMWEMEI~ D.C. D-ISTRIRUTO-N -OPERATING - TRAIN N BATMEY YTMM LMIiTING CONDIMIO FO OEATO LCO 3.8.9 3.1.2.5 The followmgS D.C. bus s b bal, LCO 3.8.9.d TAwiN toaisngof53voD8C,4o A21U~&1fl: MODES 1,2 an 3. SR 3.8.9.1 4.8925.1 The D.C. bus train N shal be deemndOPERABLEui at-8 leam nce per 7 days by verIfylg comc breaer aligamat andimwmp 4.8.2.5.2 The 250-vol battey bank and chargr shall be dcuizutratecl OPERABLE: eT
- a. At leastocepEldysyvM yigwmthw 38.
- 1. The electrlye level of each pilot cell. Isbetween fte sininm- and malmum level bilication markF, See ITS
- 2. The pilot cell speclflogmv*, cormeced to 77P andl fill elctrlyte level (fluid 3.8.6) at the. bottom of the maximo level hieica~iflo MArk, Is grete gma or equal to 1.200.
- 3. The pilot cell vohage Is master d=a oir equolto 2.13 volts. and
- 4. The overall batuey voltage is grete Oma or equal to 250 volts. --------- rSee UTS
____________________________________________________________L_3.8.4
- b. At km ncper 92 dqaby verlynt* at
- 1. Th voltage of eac comnnete cel is Xretwer tha or equal to 2.13 volts umdcr Bloat charge.
2.: The qiedifc gravity, correctd to 77-F and1 full electrolyte kid (flid atth See ITS bOtoof Mhe maximum level wulewton ark), Of each eonected cean is greater 3.8.6 than or equal to 1.200 and bas no decresed more tOm 0.03 from fth value obsaerved durn~g the prevous tea and
- 3. The ele~bctlt level of each cnetdcell Ls betwee the top of dte mnlnnmm level Indication mark and fthbottom of the maximum level Idcation mark COOK NUCLEAR PLANTF4JNJr1 Page 314 8416 A[NJM 2Ts, IS, 198 Page 3 of 6 Attachment 1, Volume 17, Rev. 0, Page 390 of 471
Attachment 1, Volume 17, Rev. 0, Page 391 of 471 ITS 3.8.4 ITS(3 314.0 LMMM1~G CONDMON FOR OPERATION AND SIIRVEIILNCE REQUIREMENT 314.8 aLICrflICAL POWJR SYSTEMS SR 3.8.4.2 C. AstkaoneCP4Knh1Y p( . I. V that *a ceallcell platesmn ttxrackaaowzmnoa1e daeor abzxoul detedzir tha could degrade beatey
- 2. viabl~e corrosion And tda te cel-tocel arcean, b1ih, andcawt-uiso SR 3.8.4.2 . 3. Verfing gmatoh battery chargerwill uupply at least 25 amp~ess at greater gma or
~I to Note ~ ~ ~ ~ W o25 o fratIn4 om SR3.8.4.3 fte-Sfba-ttery capacity adqae I~~~~~AnUaljE7S %efrifnc sal toven to any baintter ina hOwssgn omsfm w or as reachd 85%~rofh emielf for epc& the apsication amspedrcate when; DerAation tea3battery Cap~cty rops artey thpan 10%frmIi0t CSPSWY14 See ITS rviu prbyznance &as of below 90%d onte aftekmnnctm' rofng Ift 3.8.6 bttegrydtono has reached 5%1 servi1e deliver a&
oifte~ capciteof10%or reapiatirofnth nuifcmzzrated capacity, sad has shovre no ~sigsof degr&Adain performance testing at two M~ intervals isAcceptabe Until the saft ShwIO f eaao COOKNUCULAR PLANT-UNIT I Page 3/4 8-17 AMNI)MT44!9U,4K,4K2269 Page 5 of 12 Attachment 1, Volume 17, Rev. 0, Page 391 of 471
Attachment 1, Volume 17, Rev. 0, Page 392 of 471 ITS 3.8.6 ITS 3/4.0 LIMCMIG COrDITON FOR OPERATION AND SMVRVELANCE RPQUIREMEN 3/4.8 1XXUflMCALPGWUk SYSTEMS C. Atkss~toepalBflafthsby-
- 1. Veffiiqg that tde cells, cell plftes and battery sacks& how Viib2a Wnicatimn of physical danuge or abuomaal deteroration that could degrad bataey perforroance.
- 2. Renxvizg viaile corrosion and Variykig tha Ir cell-toCell and temiml cwmnections am dlean, tight, and coaW wdwh ancmzroion mterial.
- 3. vaffiyi* d=C am wrgrv ya Ind 25 an tgetrdno See ITS oqU4 to 250 volts fo at Inn bou. 3.8.4J
- d. At least, once per 18 namib perfoma battry service Wte, ring ulmtdown (MAODES 5 or 6atteby lieeache 85 farc ifdlvr capct o ift100 or OreaerAofte ienu l tiie' ated bttr capacity, nb ishwnodignstofOc adaIonefracetig SR3.8.6.6 f~~~~~tw year ners isbacep~tabl OWi the baftrey capocit igsatof defaaion.
16o macu r CoiidprormUIARL ae34 -7 AN8 6 3-NTI 4~5~$,6 [ddischarge bc ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ag 5--of--10 Attachment 1, Volume 17, Rev. 0, Page 392 of 471
Attachment 1, Volume 17, Rev. 0, Page 393 of 471 ITS (~ ITS 3.8.4 3/4.0 LDHMiNG CONDITION FOR OPERATION AND SURYELLANCE REQUIREMENT 3/4.8 ELECTRICAL POWER SYSTEMS - This page fifxteniosiatly efttlank COOK NECIZAR PLANT-UNIT 1 Page 314 848 AMENDMENT a~f M9,266 Page 6 of 12 Attachment 1, Volume 17, Rev. 0, Page 393 of 471
Attachment 1, Volume 17, Rev. 0, Page 394 of 471 CTS 3/4.8.3 314.0 L~1T~ COMMiTON FOR OE TI AMD SURVEILANCE REQ 314.8 ELE AL POWER SYSITMS 3.8.3.1 steady state bus voltg o h alternate reerve source" shall greater than or equal App ~~~~Wheneer fte manual sit reserve. sourre (69 kV) Is c adto morm than two AC~~n0N- bus voltage less than 90% no iAadjust load an the ranng to maintain steady aebus voltage grater than or to 90% limit. 4.8.3.1 No addtional surveillance - other than those reqiied by S Tcations 4.8. 1.1.1 and with D.C. Cook Unit 2. COOK LARPLANT-UNIT 1 Page 3/4 8-19 AhMENMENT 35 I9" Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 394 of 471
Attachment 1, Volume 17, Rev. 0, Page 395 of 471 ITS 3.9.1 LTS 111 314 LIMff[NG CONDITONS FOR OPERA11ON AND SURVEIANCE REQUIRMENTS 349REFUELING OPERAITONS-LOR~ ON L EAW-NR fO eeuelrFIn LCO 3.9,1 3.9.1 The boron concentration of all (iII r;Tis fte Reactor Coolant SystcmjgJ the refueling cal shall be. maintained urn frm an filciest to ensure atth more restrcn of te rolowig tv conditions met.
- a. Hi a Kirf of 0.95 or *wih includes 1% ktk conservati aalwne for un nesorL.
- b. boroft conce n1greater th or equal to 24 pp.which inci a 50 ppm cnservative, allo efrncertaintie.
APPY1t'AI4H 6 MODEfl'V~~~~~~~ t-within the limit seecifled IntheCL AfMON, 4 ---- proposed Applicability Note
=~~~~~~~~~~~Add .
- a. With the requirements of the above specification not satisfied, 1) Immediately suspend all ACTION A oaerations involvini CORE ALTERATIONS or pgtive reactiviV chan" -sexcept V n o waterm theRWST, ,rrovided the boron Ancentration in VRWST is grater anthe uyrXxification 3.1.2.7).2, MA2) initiate and continue borall a rae thanor t3gm 5 p a solution or it entun ira edcdt ICU whchvr sthhratitie lb. Th~provisions of $p6'cficatioA3.0.3,p~iot appiab. Q3j 4.9.1.i TUe restrictive of teboew/ecilyconditions shl ed mnd prior to:
a Remnoving orunotnthcovessel head, and 13
- b. Withdrawal Of ayfulghcnrlrod inexcess o3 tfrmisfull inserted position.,
SR 3.9.1.1 SR 3.9.1.2 4.9.1.2 I The boron concentration of the reactor coolant system and the refoelinz canal shall be deterinined[W wCb2al anlisat least once per 72 hours.(
)
COOK NUCLEAR PLANT-UNNIT Page 3/4 941 AMENMENT W,O,i6 3O 24 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 395 of 471
Attachment 1, Volume 17, Rev. 0, Page 396 of 471 ITS 3.9.2 ITS(I 314 W4JWIG COMDMTONS FOR OPERATION AND SURVIULLANCE REQUMENT 314.9 REFUELING OPERATI7ONS LMITNGc IbmN FOR OPERAION LCO 3.9.2 3.9.2 As a uVm iw orera et flux monitors sllbe ea catm AEEIPLLlfB MODE 6. cutrt ici hl eOEAL ACTION ACM ACTION A Ead sohc rde racukmont ofudieaw A~~~..2 sallobe demnsraedOPRALEbypefooint!Am
- a. A COEFUNCtTIONALTST olie or per 7!jndays. saodwte f&th SR 3.9.2.1 ~~.92Ec AuCHaNNE CHC atu lmnonctrft eperm2 ours COPEAL byTerbrATeoN.-M COOK NUCLEAR ]PLANT-UNIT I p*3M 9-2 230 ANmZANTIUWO Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 396 of 471
Attachment 1, Volume 17, Rev. 0, Page 397 of 471 CTS 314.9.3 314 CONMSecfiatONS 3FMa Septcmb 15AMhlo 5 mn~nie+/-fr~t .V4.9 o~~~pmcfiatonm.+/- F Jz~1 bogiSpe1 4 xm~to idae
- b. 148bum
~~ ~ ~ ~ ~ ~ ~ Pge1 f Attachment 1, Volume 17, Rev. 0, Page 397 of 471
Attachment 1, Volume 17, Rev. 0, Page 398 of 471 ITS 3.9.3 ITS 3/4 L~h(dlG CONDMOZsFOR oFr~mnlOAND SURYXILA nm M 3/439 PRFUEIM'G OPERAITONS LCO 3.. 3.9A 11m couthinn tba~ft npmeteuicm ubuflbehifafoflDowhigsuc LCO 3.9.3.a L. Th cnipaqtmdocrch odandsinphacbysnkiaihxooffo.bob, LCO 3.9.3.b L -Awi=ofme door ineachaflockis cbg4GdTar lb. 4Q- caviWtvefl~nreatera23 fat~bove Ogf4 LCO 3.9.3.c C. EacbpmentatOlpovifsdhmam cootahwo~t aunxopbmto gm aulade anoqrepbecab~lbe ftrcczhm~tC
- 2. Be capable of being dozed by an OPERA3JIS autouxti Cmntizzzmture ndExbamstbaolahmo Penctzutiu saowPafl3) pnoyidg direct access hiom&e cotann tumxpbm to the outside abnzosphere vhttea ybmlfg v zmybeumso a dun atd 'kisfttvecosiol ACTION A WAh toe of the above pecificstioni not safismed iilne51 5011edImcmCR SR3.9.3.1, 4.9A Each of tou above re P=== aba! be detumned. to be in hi requived. ulwm ~
SR 3.9.3.2 100bopi tkhe ~1ewastccE atto 7da dudniqgICORALEmflN mxmxemt bf hufintd Rxteftpwpce o Siice;I o. on OP'ERABW airlock door is a door tWi =ispulmof being dlosed and iecire& hoeumerf~lt "aht be2fldeind to ahlw for I'mi~ymme~~. COOK NUCLEAR PLANT-UNIT PAge 3/4 94AMENDBMETM259 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 398 of 471
Attachment 1, Volume 17, Rev. 0, Page 399 of 471 ITS 3.9.3 ITS 3/4 L&WMrG CONDMlONS FOR OPERMfON AND SMRIMACE RZQJEIEE 3/4.9 REFEML[G OflRA7ONS SR 3.9.3.1 L. Vcdif gtc paeiutmti ut kiatzrequired sbs or SR 3.9.3,2 l~ bTo*gmf~ Cmoti~m Pmpg and EMbU= isolato valve per the applcable portion of Spwffiajim COOK NICLEAR PLAN.T-UfiT 1 Page 314 9-4a AIhNDMENT 259 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 399 of 471
Attachment 1, Volume 17, Rev. 0, Page 400 of 471 CTS 3/4.9.5 LMITING Co ITION FOR OPERATION 3.9.5 Direc commnuiucations shall be aintained between the co rol room and personne at the refueling statio APPLICABILI :During CORE ALTERATIO S ACTION: When direct cochmwnicatlons between t e controlt room and person eI at the refueling s ation cannot be maintain d.suspend all CORE AL TIONS. The provisi ns of Specification 3.0. 'are not applicable. SURVEILLA EREQUIREMENTS start of nd at least once per 12 ours during CORE ALTERTI NS. Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 400 of 471
Attachment 1, Volume 17, Rev. 0, Page 401 of 471 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSI 314.9 REFUELING OPERATIONS 3.9.6 DELETED COOK NUCLEAR PLANT-UNIT 1 Page 314 9-6 AMENDMENT 267 Attachment 1, Volume 17, Rev. 0, Page 401 of 471
Attachment 1, Volume 17, Rev. 0, Page 402 of 471 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS THIS PAGE INTENTIONALLY BLANKI COOK NUCLEAR PLANT-UNIT 1 Page 3/4 9-7 AMIEND)MENT 267 Attachment 1, Volume 17, Rev. 0, Page 402 of 471
Attachment 1, Volume 17, Rev. 0, Page 403 of 471 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUJELING OPERATIONS 3.9.7 DELETED COOK NUCLEAR PLANT-UNIT 1 Page 3/4 9-8 AMENDMYENT- 43 46,
-O, 267 Attachment 1, Volume 17, Rev. 0, Page 403 of 471
Attachment 1, Volume 17, Rev. 0, Page 404 of 471 ITS 3.9.4 ITS Qi a
/& rX.ItDt'AL 11aT 3L'!OVAL AN~C~TAT C!Ikcu.A?6'J LCO 3.9,4 3.91.1.2 At Least one residual heat removal loop shall be in operation.
ajZZ~j1L: ODE . vselfag ACTION A a. With twas than one residual beast removal loq in o ortion, exceptL. as arovided La b. belw. susp end, all orartio Iinvolying an I arms i heMc- e I t0La rla, it Oon- Ln baron concentration of;, theactor Coolant system'M0 c8 .me containson . penetrations Vrovidiq direct macces ac ocmthcontairmea Atma hors LCC) Noteb. 3.9.4 The residual boat removal lomp masy be emovod fromt operation for UPM. LCO Note3..4 tolIho~a per I howr poriod duuing the perfasmmnco of CORE ALUAWXS ia the vicinity of the reactor pressure vessel hos log. SR 3.9.4.1 4.9.1.1. A roeLdua1. hoat removal looo shall. be decezuinod to be in operation
-and circulating reactor C"o 2 t a flow rate of greator than or equal to 1000 Dpa at leaot once per hor..
0 Ibr puwpoaeaos-I this specification. addition of watsr from the RWST doom not conariture a dilution activity provided the boron concentration in theL. RVST is greata? than or equal to the minism required by specificatton
- 0. 0. Coo .UNITl 3/,49.9 AMIW 120 NODT1.
Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 404 of 471
Attachment 1, Volume 17, Rev. 0, Page 405 of 471 ITS 3.9.5 ITS-S.I TIDt'AL NUAT ItMI§VAL A!M -OIAL%- QCLTk~ LCO 3.9,5 3.9.8.1 At least Oon residual hee: remoV&l loop shall be in a eration. ACTION B 4. With less than one residual beat reoa.loop to evraLou, except-
- 1 1 ~Add proposed Required Action52 SL [T r ~~~ Th~~~b.
residual beat veovwal Imop may be garnered fzum operation for up 1 hour per S heor period duriap Che performeucs of COM SR 3.9.5.1 4.9.1.1, A residual beat removal looo shall be determined to be in operation and efteulatin reactor coo at a floW VAMe Of greater thAU or eqUal'to 1000 as at least once per hours. 0 or-purposes ofthis specification, addition of water from the PBST does not counsitute a dilution activity provided the baron concentration intheL1 PBS? Ls greater than or equal. to the miniumu required by specification
- 0. C. COMi UNITlI 3/4 9.9 AMKWD NO.- 120 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 405 of 471
Attachment 1, Volume 17, Rev. 0, Page 406 of 471 ITS 3.9.5 ITS ~I II :W 'AE LTEVE-. LCO 3.9.5 3.9.8.2 T.W. indilper.ent ReSidual Heat ReMoVAl (RHR)..l1gpLshalklb Ej&A5 0t1LCABILITY: MODE 6 when the water level above the top of the reactor
~
Ac ~ ~ pesuevsslfanaIsls ta 3 et ACTION A a. With less than the required RHR loops OPEWALE, lmamdiately finitiate correctivb action to returni the requIre4 RHR loopS to OPERABLE St~atus as soon CS Possible, (Add proposed Required Ac~tion A.2
- b. prvs ofsa S30Ficatlon 3.0.3 nrtotAPplcbe .
SUPVttL~fCEREWIURLEDI!TS
~4.9.8. recutred Residual e Reoval loops shall deteroined OPEAL L roose R3952ad NoteJM.
"T'Ve cr emergerncy~ ;owe core ay b invp..-ec e ec AH MD..
I .C(
-. ~~~~Ii'~3/~~ )-~a AmendmeEnt mo.7B Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 406 of 471
Attachment 1, Volume 17, Rev. 0, Page 407 of 471 ITS 3.3.6 ITS REFUELING OPERATIONS LCO 3.3.6 3.9.9 The Containiment Purge and Exhaust Isolation systm sIl be Table 3.3.6-1APPLICABILITYZ During Core er rmvement of irradiated fuel within Footnote (a) thlEiii nuMIent. ACTION: ACTION C 111th, the Containment Purge and Exhaust isolation systemIoeab, close each of the Purge and Exhaust penetrations providing direct 184 days for (containment radiation monitos . 24months (for manual Initiation . IJURVEILLANCE-RE UTREMENTS SR 3.3.6.6, 4.9. 9 The ontainmen Pu,' e and Exhaust isolation £y teo shallL. SR 3.3.6.7 demonstr a ERAB t t 19: aan at least SeU once te Iduria-M Avar iyin th contAi 3.9. j.read xas isaai ocus n manual initiation and on a hi gh eITj rediation signal from each of the containment radiation i nstriumentation mionitors.
- 0. C. C:'CK -~,UNIT 1 214 !-`11 Amendment No. 80 Page 15 of 29 Attachment 1, Volume 17, Rev. 0, Page 407 of 471
Attachment 1, Volume 17, Rev. 0, Page 408 of 471 ITS 3.9.3 ITS REFUELING OPEAA1IONS CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM IMiwITING CONDITION FOR OPERATION LCO 3.9.3.c.2 3.9.9 The Containment Purge end Exhaust fuolation systam shall be OPERABLE. APPLICASILITY: During Co t itraeti olr mavement at irradiated fuel within Zhe containment. ACTION: LCO 3.9.3.c.1 . With~ the Containment Purge and Exhaust Isolation system inapereble, close each of the Purge and Exhaust penetration$ providing direct SURVEILLANCE-REQUIRMENTS SR 3.9.3.2 demonstrated OPERABLgEor rt h'jato nr- es radiation s nel ram each af t a containment radiation instrumentato 3.3.6T3
- 0. C. CUSCIC- UNIT I 3/14 9-10 Am* drnent No. SO Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 408 of 471
Attachment 1, Volume 17, Rev. 0, Page 409 of 471 ITS 3.9.6 ITS(I) RIMINCEZK OPLRATUON 3/',. .10 VATE LEVL REACTOR VESSEL LutNITING CObMtTION FOR_OPERATION LCO 3.9.6 3.0.10 At least 23 feet of vater shall be aaLnvtaned over ths topo ths reactor pressure vessel flang. rrdite raEUUITY Bur% 2*bve taaoffe assemblies lor @1o n v Itn tho,-,f-vess3. whLI&le KODK 6.` ACTION A the requirements of the above a ecificacjon no l~~~Lch f ad e S.8 3Lo.ofI0!!clm~n S~~lVEILLANCE SR 3.9.6.1 4.9.10 The Vatsr wev shl de be
.oamndc asal Lts ulnimim requiired deplivth i 2 h g=d0ato he start of and at least otice z 2(s baurs Ithereafter dur of fuml. Ma'ssblies Ior caidio ro~ds.
atmve"
- 0. C. COOK UNMT 1. 3/4 9.11 AMendmient No. 78 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 409 of 471
Attachment 1, Volume 17, Rev. 0, Page 410 of 471 ITS 3.7.14 ITS ~I RMFEL!NG0 CPERAT'aCNS STORAGE POOL WATER LEVEL L!MUI-,NG CMNITION FOR OPERATIONl LCO 3.7.14 3.9.11 At least 23 foot of water shall be maintained over the top of irradiatad fuel assemblies seaed In the storage racks. ACTION A WAPPICABILThe rwitsve
- eq iof~ a=~:~ 1ftaei h trg SR3.7.14.1 4.9.11 The water level~~~~~~ssemlie Inthe storage poolsalb fe eemndt ea DA C.CTOONK- UZ ~ ~
ACTION WI A irments a "Mi 'cation not tatlfPage 1uofa2 Attachment 1, Volume 17, Rev. 0, Page 410 of 471
Attachment 1, Volume 17, Rev. 0, Page 411 of 471 ITS 3.7.13 MTS 3/4 LIMITING CONDMTONS FOR OPERATION AND)SURVEILLANCE REQUIREMENTS 314.9 REFUELING OPERATIONS LCO 3.7.13 3.9.12 e spent fuel storage pool exhaust ventilation syseshl be0 ACTION A a. With no fuel storage Iehutventilation system OPRA msuspnd all operations L ACTIONS Note b. The provisions of Specifications 3.0. anoj.O ar not applicable. SURVEILLANCE REQUIREMENTS dpooe SR 3.7.13.2 4.9.12 The above required fuel storage pool vqn*lon system salbe demonstrated OPERABLE
- a. At least once pe dy yiit lwtrog itr and c oal adsore ri L .
- b. At least once per 18 months or (I) after any structural maintenance on the HEPA filter or charcoalA3 adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:
- 1. DeletedSe SJ
- 2. Verif~ying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm +/- 10%.
Icrne 5;-updo-r-a-d aor ? fiebuulirdbuidi LCO 3.7.13 Note
- The crne - or n eso orfeax udi canba ybe opened under1.
Shareds syteg ~E .CCOOK -UNIT 2. COOK NUCLEAR PLANT-UNIT 1 Page 314 9-13 AMENDMENT424U3279 Page 1 of 8 Attachment 1, Volume 17, Rev. 0, Page 411 of 471
Attachment 1, Volume 17, Rev. 0, Page 412 of 471 ITS 5.5 ITS 314 LIMITIG CONDITIONS FOR OPERATION ANID SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS _ _ _ _ _ _ _ _ _ _ _ _ _ _ STORAGE POOL VENTILATION SYSTEM" LIMITING CONDITON FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilati n system shall be OPERABLE. See ITS 3.7.13 APPLICABILIT'Y: Whenover irradiated fuel is in i e storage pool. ACTIO:
- a. With no fuel storage pool exhaust ventilation system OPERABLE. suspend al operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storag pool exhaust ventilation system is restored to OPERABLE status.*
- b. The provisions of Specifications 3.0.3 nd3.0.4 are not applicable.
SURVEILLANCE R MEQREMNENTSIS55. eei pormsatm ~~ . 14.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE: SeITS
- a. At least once per 31 days by initiating flow through the FIEPA filter and charcoal adlsorber train 3. 7.13J and verifyong that the train leimgt 15mintates aprtsfrt
- b. At least once peLjnnh r()at~any structural maintenance on the HEPA filter or charcoal 5.5.9 adsorber -houigo 2floigpitng, fire or chemical release in an ventilation zone communicatin withsthepesyiotenat by:
adversely affect the filter bank orA8
- 1. Deleted caca dobrcpblt 5.5.9.b 2. Verifying that the charcoal adorbers remove ~t 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI NS 10-1980 while operating the exhaust ventilation sytem at a flow rate of 30,000 cfm +/- 10%.
- The crane bay roll-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel wthin the storage pool or crane operation with loads over the storage pool.Se S 3.e7I13
** Shared system with D.C. COOK - UNIT 2.
COOK NUCLEAR PLANT-UNIT I Page /49-913 AMENDMENTW 4M,13.27.9 Page 27 of 69 Attachment 1, Volume 17, Rev. 0, Page 412 of 471
Attachment 1, Volume 17, Rev. 0, Page 413 of 471 ITS 3.7.13 ITS 3/4 [JMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.9 REFUELING OPERATIONS SURVEILLANCE REgMIRMENTS (Continued)
- 3. Verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating- the exhaust ventilation system at a flow rate of 30,000)cfm plus or minus 10%.
- 4. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less than or equal to S%6 for radioactive methyl iodide when the sample is tested in accordance with ASTM fl3903-1989, 30Q1C, 95% RML, andŽ> 46.9 fpm face velocity. The carbon samples not obtained from test canisters shall be prepared by either.
(a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or (b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length 5 1 equal to the thickness of the bed. Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI 1N510-1980 while operating the ventilation system at a flow rate of 30,000 cfm plus or minus 10%.
- 5. Verifying a system flow rate of 30,000 olin plus or minus 10% during system operation when tested in accordance with ANSI N510-1980.
- c. After every 720 hours of charcoal adsorber operation by either:
- 1. Verifying within 31 days after removal that a laboratory analysis of a carbon'samnple obtained from a test canister shows a penetration of less than or equal to 5% for radioactive methyl iodide when the sample Is tested in accordance with ASTM D3803-1989, 3001C, 95% RU.H.
and 2 46.8 fprn face velocity; or COOK NUCLEAR PLANT-UNIT 1 Page 314-9-14 AMENDMENT*24,4ff, 25 Page 2 of 8 Attachment 1, Volume 17, Rev. 0, Page 413 of 471
Attachment 1, Volume 17, Rev. 0, Page 414 of 471 ITS 5.5 ITS 314 LIMITNG CONDYITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT 3/4.9 REFUELING OPERATIONS SURVEILLANCE REQUJIREMENTS (Contined') 5.5.9.a 3. Veriffying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1980 while operating- the exhaust L. ventilation system at a flow rate of 30,000 cfrn plus or minus 10%. 5.5.9.c 4. Verilying1ihn3 afemr e4* a aarat anayi ofa carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers shows a penetration of less than or equal to 5%for radioactive methyl iodide when the sample Is tested in accordance with ASTI 1)3803-1989, 30'C, 95% R.H., and > 46.8 1Ipm face velocity. The carbon samples not obtained from test canisters shall be prepared by either. 5.5.9.c.1 ~~~~(a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent 5.5.9.0 ~~~~~~~~thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or 5.5.9.c.2 (h) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. Subseqent rinstalling the. adsore t$uefoobainingthe onsaPle, the system shall be de ostrated OPERALE S aso verifying that the ch coal adsorbers remove greater th or equal to 99% of a halcate hydrocarbon refrigyt test gas when they arem4 teste inlce in accordance with 4SI NSlO-1980 while or/ng the ventilation system at a i aeof 30.00 cfm plus ojius 10%. 5.5.9.a, S. Verify'ing a system flow rate of 30,000 efmn plus or minus 10% during system opiration when 5.5.9-b tested in accordance with ANSI N510-1980. 5.5.9 C. After every 720 hours of charcoal adsorber operation by either. 5.5.9.c I. VerifYing a n3 sMatr mrov a arao analysis of a carbon'sample obtained from a test canister shows a penetraton of less than or equal to 5% for radioactive maethyl iodide when the sample is tested in accordance with ASTM D3803-1989, 300C, 95% R.H., and k 46.8 fpm face velocity-, or COOK NUCLEAR PLANT-UNIT I Page 3/4 9-14 AMENDMENT*24,4"6, 25 Page 28 of 69 Attachment 1, Volume 17, Rev. 0, Page 414 of 471
Attachment 1, Volume 17, Rev. 0, Page 415 of 471 ITS 3.7.13 ITS (3 LIMITG CONMMTONS FOR OPERATON AND SURVEIL[ACE REQUIREMEMT R~EFUELING OPERATIONS fEILLANCEROUREBNS(Continued'
- 2. Verifying within 31 days after removal that laboratory analysis of at least two carbon samples shows a penetration of less than or equal to 5% for radioactive methyl iodide when the samples, ame tested in accordnanc with ASThM D3803-1989, 300C, 95% JUL andA 46.8 Jpm, face velocity and the samples ame prepared by eithec:
*(a) Emptying one entire bed from a removed ~Adsorber tray, mixing die adsorbent thoroughly, and obtaining samples at least two inches in diameer and width a length equal to the thickness of the bed, or (b) Emptying a longitudinal sample from an adorer try, mixing the adsorbetmaSe
- thoroughly, and obtaining samples at least tWm inches in diwamee and with a lengthi equal to the thickness of the bed; Subsequent to reinstallng the adsmrber tray 6sed for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove greate han or equal to 99% of a halogenated hydrocarbon reffigerant test gas When they are tested Inplace in accordance with ANSI NS1O-1980 while operatin the ventilation system at a flow ratea of 30,000 cfm Phus or minus 10%.
SR 3.7.13,4, d. At least once Meslllnonds by: ~I SR 3.7.13.5 SR3.7.13.5 4~~~. Verifying that die exhust ventilationsysthe cmbinansdi sMPen fuelstors age phrool asrbesatear bngaiv pIssuelforwte at than equal 618inch to WateresG augehrelativeato the ustsvnideio oxh aytemoshra uit yte pran.wt flow rate 27,0000cnfpusrrnmnus.2%
- 2. Deeted acuat) [theFHAE Systm SR 3.7ON.13RPAN.4rII ag 34 45 AMENDMor simulate 3.a Vedf~isd~n Pt .ft~j~t31-WzPage b3tof 8 Attachment 1, Volume 17, Rev. 0, Page 415 of 471
Attachment 1, Volume 17, Rev. 0, Page 416 of 471 ITS 5.5 ITS 314, LIMiTG COMM~rONS FOR OPERATON AND SIRVEILLACE REQUORMMMII 314. flFULnM G OPERATIONS 5.5.9-c 2. Verifyfn awtd 31 £6 afterAm aoyaayi of at leat two cm'oon samples shows a penetration of less thnor eulto 5% for radioactive methyl Iodide when fthpatnla= raeteted in accorance with ASTM D3803-1989,3SOV 95% RJL, and ?Ž46.8 fpm face velocity and the samples are prepared by either~ 5.5.9.0. (a) Emptying one entire bed from a removed adsorber tray. mixing the adsorbent thoroughly, and obtaining samples at last two Inches in diameter and with a length equal to the t~hiness ofthe bed, or 5.5.9.c.2 (b) Emptying a longitudinal sample from an adsorbec tray. mixing the adsorbent thoroughly. and obtaining samples at tbast two inches In diametter and wit a length equal to the thickness of the bed; Subsequn to the adsdrber Ge for obtalnin the cuib sample, the system shal be dicsrae OpERtABl by 0verifying that he adsozbers remove getr orequalto99 ofa bn hya 1.4)cabntstp tselcein accordance SI 1ih0L-1980 while the ventilation system rtof 30,O000cfm phusor lnsl%. atfo 5.5.9 d. Atleadtonce pg oathsby: 5.5.9.d ~~~~~1. Verifing that the pressure drop scross the combined IiEPA filters and charcoal adlsorber 5.5.9.d ~~~~~~~banks Is less than or equal to 6 Inches Water Gauge while operating the exhaust ventilation system Ataflow iate of 30,000 cfin plus or minus 10%.
- 2. Deleted.
- 3. Ver~iyng that n a blgh--radlation signal,the system automatically directsItsexhaust flow thrgoug hecharcoal adsorber banki and automatically ahuts down the storage pool ventilation system supply fans.
- 4. Verifying thm theexhaust ventilation system maintains thespent fuelstorage pool are at a See ITS negative pressur of greater than or equal to118 inches Water Oauge relative tothe outside37 )
atmosphere during system opmeation. 257 COOKNtUCLEARPLANT-UN1TI Page 3/4 9-15 AMENDMUW*r*s4KM Page 29 of 69 Attachment 1, Volume 17, Rev. 0, Page 416 of 471
Attachment 1, Volume 17, Rev. 0, Page 417 of 471 ITS 3.7.13 ITS ~iI ILRKUMSC I S=1J~gF (OIS~Imtiadl
.. After each complete of partial ropiacemme: of a RUNA filter bank by verifying that the HRA fiter banks remove & HC of the 00?P wben theQY ave tested Lntoplace in ateetdance, vich ANS? lfl0-1UIO while op.:ating tha ventiLation systes at a flow varte of 30.000 efa & lo0,.
C. After each complete or paztial replacemeut of a cliagesl adsorber Se.s bank by 'verifying; chat the charcoal &dsorbere teami ?. 19% of a halogated hydrocarbon rogri~erant test gan wheM they are. tested Ln-place, in accoocdezs with 4hSZ 5510-1980 while oparating theI ventilation system a: a flow rare of 30,000 aft 100 D. C. COO% UNZ?1 S/A94, o 2 Page 4 of 8 Attachment 1, Volume 17, Rev. 0, Page 417 of 471
Attachment 1, Volume 17, Rev. 0, Page 418 of 471 ITS 5.5 ITS 5.5.9 .. e.ftei each Complatf of partial replacement Of a.RUA filtei baftk~by
~~ I waxlfy ~tug:hat tbe HUA ILAUTe bUUa MMse a: 94 DC the DOP War, 5.5.9.a I the axe eet.in-place in accordance with MISt 3310.1910 whi~le L~.rating the 'etiztlacteu systes as a flow rat. of 30.000 Cia I la.0 C.Ater each MOMplt Or Partial replacammut of a cheagol. adoiorber 5.5.9 &Mby vurifying that the -charcoal1 adiorbera reamo ?, Oh of a halojenaued bydrocabou refrlgerant teat gas vha~te reeie 5.5.9.b L~~~n-VISCO La 4CCordance itch AISI 551041990 while oporatiug the Ventiatton, systea at a flow rate of 30,000 eft 10l0.
D.C. CCUK MTN!L 3/& 9416 NO. 124 Page 30 of 69 Attachment 1, Volume 17, Rev. 0, Page 418 of 471
Attachment 1, Volume 17, Rev. 0, Page 419 of 471 CTS 3/4.9.13 be.2 on ith the spent fuel cas`k anling crane operating ith Contro dPath Node of operation APPLC ILITY: Wi1th fuel assembl es in the storage pool. With t erequirements of the abo a specification not satis aed, place he crane load in a safe c ndltlon. The provisionisf Specifica-tion 3 0.3 are not applicable. 4.9 3 Crane interlockcs whic prevent raising thebt of the spent ful cask more than 6 inches vethe top of the C'aoskp Protection Syst cyclinder and restrict tecrane's novement to thContr~olled Pat shall be demonstrated OP RALE within 7 days prior ocrane ope ation in the Controlled.P th Node and at least once pr 7 days the eafter during crane opera ion inthe Controlled Pat Node. D.-C.UNIT COOK13/4 9-17 kedetN.2 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 419 of 471
Attachment 1, Volume 17, Rev. 0, Page 420 of 471 CTS 3/4.9.14 3.9.14 aTaxeu weight of a spen shalsed fuel cask vWfe toheCas 1D0rons theoc n l)road to its ufe oth io.The pakropisiotes o Speisctem.
*C. CODK -UNIT 1 3/4 9-18 Amendment No. 23 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 420 of 471
Attachment 1, Volume 17, Rev. 0, Page 421 of 471 ITS 3.7.15 ITS ~I STORAGt POOL _1O3tOl COICV.;AT'Olq' LCO 3.7.15 3.9.15 A boron concentration of greater than~ of .qus1 to 2.'O0 ppua shall be
.aincained La the fuel. storage pool..
At ~and APLt~~~A3U.Z~~: me a fuel storage pool verification hs not ben perfrmed ... ACTION A WVith the rsquairemmncs of the speoificatLon not sat.sf Led. suspend. all. A ACTION movement of fual assesbLies in chs fuel. storage pool. and iesteoc the boron concntraionto KaLcin its haWt prio t o resuming fuel moveesnt. The provisions of Spalfloaction 3.0.3 are not appittable. poedReure AtonA.. A.9.l.5 The boron conteucration'Lu the fua; snorags pool. shall be datarained SR 3.7.15.1 to be at lesta at Uts Minimam require4 at least auc* per 7 days. 7SharelA scr K~MZk1_ -Uit2 (_~fuloiPl COOK IUCLUAL MWI! UN1J? 2/ 49 Mo IDICWT s~o. 71;6. 169 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 421 of 471
, Volume 17, Rev. 0, Page 422 of 471 CTS 3/4.1 0.1 3.10.1 ~SHUTDOWN MAO1k= of Sps1fdkimo.3.1.1.1 be mwpmodud (O otmae A woo* abtmmh pWfui lb sqivalem to at des blshmi o ob vlbb ulp inm bo OFEMUBLE hio~ ~ amd*1hys dL ~ 4pro RuSgpn" for ordwp134 Wolwuof gmld by So&13.L1.I vmniW.
- b. WIhmWSI g.<1.by mhad=b secdivily quvalent, mmiffi-laybumlaas
- Sgse ppabodlsukldnhiulom oIat Itsva~udI IUOWMARO =Dmzspi SpaIlmdomS .1.1.1 IsM.
4.IOA.1 m*pceb"mtU~fuUS1q*r aIduwpwyub1rt *aIbodstmuioiguma 4.10.1.2 zukMw~ghzeoufbf *ulbodmu" ifif I fdi dmsrubsif2.4sam*= 7dVaplw1Dozodw1u~ MARGIN so Iew a dosildsfpacfmi1.1 COOK ~CLEAR MLANT-UNIT 1 Page 314 10-1 AbMNDMENT 74, W.~216 Page 1 of 2 , Volume 17, Rev. 0, Page 422 of 471
, Volume 17, Rev. 0, Page 423 of 471 OTS 3/4.10.2 gpoup height, 1ns= 0 and ;o.mft diettihitto UlAits of BpecifLoau one1.lS4l 34.3..4, 1.3.5,)2. and 3.1.4 bih sumps 44d dhe Plort aoea Wmi3CS IUSS ptovLded:.
- i. aTHEUMAL PMVR La amd less than or.o to 65 of
- b. elimits of SpesiaL ios3.2.2 axA 3.2.3 ar oitained and tofi~ned at the fro sls pedifled in Spec icatlon
.1.2.12 belov.
Vith a:y Unhelits of SpooL .t 3.2.2 or 3.1.3 b LOS exceeded rbl equirements of Speai cain 3.1.3.1. 3.1.3. ,1135 ..
.532 are ausonded. either M.
a.~ Raduce ?liftAQL MO=fl iciet to satisfy efiTO
*requirements of SPOOL aos 3.2.2 mad 3.2.3 or
- b. ieiuLa H3a EOsmy vt Ehbours.
4.10.2. the 2If% EC~ bde tomindedto eis, sn'azaorequA1 to 63t f RA TEDlificL NOe bt.oce per hour lug MIH3CS WTS?. a 4.10.2 MmThSuzvailaucs us of Speciftcati 4.2.2.2ad 4.2.3 be Performd at olwn frequecies. IMYSIC US?!: Specification 4.2.1 At least one, Pat b owrs. Speaifiation 4.I.1 *at least oe.e per 1 ours. D.
- OOOK -'UlIT I . '3/1.10 2 . kwbDoE UP2C Page 1 of 2 , Volume 17, Rev. 0, Page 423 of 471
Attachment 1, Volume 17, Rev. 0, Page 424 of 471 CTS 3/4.10.3 ITSZSM USSprvndG LIN~~~~~~~~~~~~~~~~~ 3.13 RecoTolatSke rature and pre=0cndossfore rlea ionsip its ae~l mfS uteno wihi reib 3th I acetble ouperat duiong ton iriat A. e KA lOd.e"a ha 5'poeent of SkATI POUD,
- a. Tb iateor Trpe $tenaoo trip breakrs.utro C. Vt h oseCoolant B." tmertr and pressur r elainshipL Vhnteritus of reane Acetable operation ona f igures3..2an
.43,ia itely open th reactoe rti breakers. adetr h euearure-pressure nlart hi to vithinatLudhat thin 30 ro: perform the na reurdby Specifierti 3.4.9.1 prior th neum reactor 41d £dy
&.L0.3. Te Reactor Coolant Syst oball be vetified to be thathe, accep 1. esion for operation o siures 3.4-2 and 3.4.3 a Leat once, per 'i.l0.3. The rAMWA~L PO=D shall be determined to be less or equal to' 5% j C. -U~~~iITL 3/A04 LO - KEMT 30. 120 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 424 of 471
Attachment 1, Volume 17, Rev. 0, Page 425 of 471 CTS 3/4.10.3 D. C. COOK-UNIT 1 3/4 104 Page 2 of 2 Attachment 1, Volume 17, Rev. 0, Page 425 of 471
Attachment 1, Volume 17, Rev. 0, Page 426 of 471 ITS 3.1.8 ITS s9~~~~~C!At T!~~~~~~~~~~r erofreuiedchnel frOCO3.. LCO 3,118 3.10.4 The ILMILM1a: ou Spettf catL 'ns 3.1.1.4, 3.1.3.1, 3.1.3.41and 3.13.3. may be suspMene twihpedfosaenc.of WTUICS TETS provLded: d rpsdLO...
- a. The TWIMML PWUa does not anteed St of PA=TE MIAL PIM.u &11d
- b. mm2"tr Tzp I r. the OPEUABMI n -e aC~e Rang9..
3leuon flux =an.th ag, 1111mteu 11 , 1wSetpoint. are an at lossthen uZof a RAW vDam ACTION B 111th the ?RIMMW 1O0 peacter then SC1 oil PAM TmIMAL MM,3K Linedlstely I open the reaitor trip breakers.AdprpedCTOAM1 SR 3.1.8.2 4.10.4.1 The 'ZHUAL MM13 shafl be dateniftnd to be laes thAn or equal to St of RATED ?)IJWAL P013 a: 1est once pelr r ug MTIXCI TLST.
-4 ~~~~~~~~~~~~~~~~d roposed SR 3.1..
4 ~~ ~ ~ ~ ~ ~ ~ ~ ~ d roposed SR3.83(?
~.C. COOK -MIT.I 3/4 10.5 AK1XJDKUT UO.. 120 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 426 of 471
Attachment 1, Volume 17, Rev. 0, Page 427 of 471 CTS 3/4.10.5
- 3. 10. 5 The catioafns of specSifioat on3.4.1.1. say b.sep d during the
- b. beeto: ItLp Setpoints oEthe OIDBLZ Intebm ate Range.
i Lmz 4~the pfloer ntf *, utton nlue Low otpoint are se
£less than at equal. to I% of U THEUMAL POD..
Duuing-operation bel the 1.7 Interlock to e With the POU peat.r than the P-7 Interlock Setpoi *Lmsdiatsly 4.10.5. I The TIOMAL ?MU sball detuumined to be Le. the P.7 4.10.5.2 Lath Intermediate. Powerae Chsamnl eCa 1-7y lnock shall be subjects to a CUHNIEL FLCTIOU&L T vthin 12 hours prio to initiating D.C. *UJIT 1 3/4120-6 AJMW ID IDIN.12 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 427 of 471
Attachment 1, Volume 17, Rev. 0, Page 428 of 471 ITS 5.5 ITS 5.5.10, 3.11~.l The quantity of radioactive material contained in each of the 5.5.10.c follodwL tanks abU e 1xtad to less than or equ.t u s
- a. Outside temporazy tanks.
MIZMMJX: At all times.
- a. Wihthe quantity of aiactive material In ayof the above L.
listed tanks exce the above unmit, vit delay suspend all additio'ns of radioac L material to the an ithin 48 hours reduce the tank on teto vithin, the t b The provisions of pecifications 3.0.3 3.0.4- art not applicable. 5.5.10.c 4.11.1 The quantity of radioactive material contained In each of the above 5.5.1O~~cl*stdtanks inclludedeinthrisnSedifieathonar thoe aoute lmtbyankstalyzire notsurroundtied sa lnrmpie, tetn' rvll otnsa of aalees holding 7htn an that do nT contents hae taviins ovefloRvs0 and SRu.. rronigae drains connected to the liquid radwaste treatment system. COOK NUCIMh PLANT - UNIT 1 3/4 11-1 AJWNDEM NO. 189 MA,~S~ Page 31 Of 69 Attachment 1, Volume 17, Rev. 0, Page 428 of 471
Attachment 1, Volume 17, Rev. 0, Page 429 of 471 ITS 5.5 ITS 3/4.11.2 CASEGUS jEW!L8T LUMMTN CONDITIOII FOR OPIRTO =oga d rooe T .. 1 eei ttmn 5.5.10, 3.11.2.1 The coneentratlon of oxygen in the vast. holdup system shall 5.5.10.a bCCIW t061to toss than or equal to/31 by vwhine If ho GoC uteQ AZ ~~~At all times. a.. t the concentration a ozygen In the waste ga hodup, system
&aterthan 31 by Io but less than or eqalt 41 by vrolume Icontainins greater anor equial to 41= ,ydoen.
restore the ---------- A concentratiou of ozg oless than or equal 31 or reduce the hyroen concentration loss than. 41 within t9 hours.
- b. Vith the concentratlo of oxygen in the wasteas holdup system or tank greater than Iby volwae and greater 41 hydrogen by volume. wLthm~t delay usedall additions of ato gases to the sym tex or tank and r duethe concentration a oxygen to less than or eqVa to 31 r the concentration of sogn to loss than or equal to 41tvi L 96 hours In the systes or tank.
The provisions of £ efications 31.0.3 aiDA .0.4 are not applicable. 5.5.10.a 4.11.2.1. The concentration of oxygen in the wastgegs holdup system shall becoox iedt UNth n 1 wiuithip os 11.2 ts/ b tinKEDyMUntor0. th4e18 vaste,gasholft ases L the gm wate thPagexy32 of 69r Attachment 1, Volume 17, Rev. 0, Page 429 of 471
Attachment 1, Volume 17, Rev. 0, Page 430 of 471 ITS 5.5 ITS 314 LIMITIG CONDITIONS FOR OERATION AND SURVEILLANCE REQUIREMENT 314.11 RADIOAC-TMV EFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 5.5.10, 3.11.2.2 The q~uarntty of radioactivity contained ineach gas stora e tank shallt& 16ieo curtes 5.5.10.1b Inbegs( arda CM AP 1CAWl At ailtines. ACTION:
- 1. With the quantity of adociematerial in an'y gas so getank exceeding the above limit, without delay usedall additions of radioactive atra to the tank and within 48 hours reduce th an contents to within the limit.
- b. 'Tke provisions oSeifications 3.0.3 and 3.0.4 are applicable.
SURVEILLANCE REQUIREMENTS 5.5.10.b .4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be COOK NUCL iEA PLAN abv UNiT 1ay- ocPger 31 11-3 AMenDMrrrENMEMO54 are,489,231 COOK-UNITIUCLER PLNT Pae 3/ 11,3 AMENMENTPage5A33, of, 69 Attachment 1, Volume 17, Rev. 0, Page 430 of 471
Attachment 1, Volume 17, Rev. 0, Page 431 of 471 ITS 4.0 ITS 4.0 SCDES ON TKATwKs 4.1 5.2. SZEn newCT.SON amE 4,11 5.1.2. The ezm2.ua5* item&shall be ia Sb~uu ?g= fa 5.14L. WO POUTATZON ZONE alteln ihnacrl 4.1.2 5.2 The 1isv populatLou zone shall be lagshe" t-. L2 containment structures and 5L~rt -loodaty low Casesue and U~utd EfjLwnes 4.1.1 5.1.3 'Ae 9=T BOUNDAR fort asems s:A MAMqud eMwmtsa sball be as shovu it Tisuze 5.20.. 5 .2I COMA?4 COMO TX1 5.14 he etow counua ~ dqLa a sual, I d, reafotfoad onrete b: dins of C7=11dtLC Shpe Vith a daMe and hariag r.b f aL2.wlml sLg teetnrest
- a. o La2Laas.de disama - LIS feet..
b.,!au laxiSa.hel, 1.60 fest.* d: UL..+/-= thbescneaa concexte vwll - 3'S1 S. ULULin= thicknss concrate floor pad 'LO teer..
- f. Nominal thicInea, steel, Liners side 4dome - 2/3 inches.
- g. Nominal thiLeaicas f steel Wanr, bat -1/4 Inch.
. 'Not free volume .14 x 2.0cubic fast
~From ad. (EKiev. 60a9 to LWide ot dose.
COOK lN1UCzj-k
!AP.%P - 1V-I. E~D~ '(o 5J 1 Page 1 of 25 Attachment 1, Volume 17, Rev. 0, Page 431 of 471
Attachment 1, Volume 17, Rev. 0, Page 432 of 471 ITS 4.0 ITS Figure 4.1 -1 STATE 0F MCHIGAN SCAE 2.24 000 IK&RAMdO S8a00 I5 o ~ ~ ~~~~~~ Lo"kas 7 A~~~~~~~A ___ ~~~~Figure 8.1-1 Don I C. oo NU~~~leaf PPagl2afn2 Attachment 1, Volume 17, Rev. 0, Page 432 of 471
Attachment 1, Volume 17, Rev. 0, Page 433 of 471 ITS 4.0 ITS
-01 L~!e -1 -
JI.~ ~ ~ ~ ~~. 4*A' ~ ~ ' cv-~~~~~~~~~-
'A.~~~~ 4. .OAL C. C O res NUCLAR LAN LO OUAINjN u~~~ary~~~~e4~~~FI C. COOK-UHITI 5-3 Ameudment X0~~~~~~~~~~~~~~~~~~~~.
7
~~~~~~'~~~~f9
;~ag 3of2 Attachment 1, Volume 17, Rev. 0, Page 433 of 471
Attachment 1, Volume 17, Rev. 0, Page 434 of 471 ITS 4.0 ITS 5.0 DESIGN FEATURES 5.21 Th or conuainment buildingis ds eandshallbe malntahnednto rdcWith the odgmra deIgn roIsons contained In SectIon .2 ofthe FSAR. S523 atosthroughbthe reco bidn r eindad albe uiantalned'inaccordance heiginal ja desigproilncnandn clnAfh A withuallowane for normal d aainpursuant to ihe appiaeSvilacReuemns 4.2 I's -BE&=O muR FUELASSMMM ~ ~~~~~~~~~~~~~~~~~~consisting of amatrix of] 4.2A1 5.341 The reactor core shall contain'193 fuell assemblies with each fuel assem bly O~4iWiW did~ LI% ZIIcaIOM or ZILO except that limited substitutions of zirconium, alloy or swasnensseemi fer rfuel rods with In) ---As' wA rM with NRC-approved applicattions of fuel rod configpration. may be used. Fuel ' initial assemoblie. shall be limited to those fue designs tht have bea analyzed with applicable NRC L. composition of staff-approved codes wanmetods, and shown by tests or anablyis to complywith all fue safey design, enatural or 2slighly. A limited number of lead test assemblies that have not cmleted te tative tesing Mu be enrichedUO010 I Mn-1inis ms-los.FFiifuel rdshinlve a nominalwactve fadl d~inhf4-bbj fula trilo 1b tWcr 4!&" bvaM hnm; o . eit rc -35 Feodfl 4.3.1. 1.a shall be siaMiar in physical design to the Initial cor loading; and shal have a maiubm nominal enrichment of 4.95 'weight percent U-235. 4.2.2 5.3.2 'The reactor core shal contain 53 full lens and no azi th controlrod assemblies. e ul lnth COK1(CmLEAro su e s ot a wm ge1-42 nlso A Msrer narD.MiEN M of9 3 absorer 80 prcen al silvr. 15M* bil= pr4eof Page 25d Attachment 1, Volume 17, Rev. 0, Page 434 of 471
Attachment 1, Volume 17, Rev. 0, Page 435 of 471 ITS 3.7.16 ITS - L.O DESJG? rEATUMF
- a. In ccodanc wiht dhe cods equrement specified is Sctlon 4.1.6 of the FSAR. wOh alloance for nomiul deshdain pursuantto the apphcable Surveiflanc Requirements.
CSee ITS Chapter 4.0 b. C. For a pmssumof2485 psg, and Eorna temposa of 650'F excpt for the pressurizer which is680P. SS.t. 7a enmerency Core coolin sysms ams designed and sha be maintained InAedordance, with the original design provision contaned in Section 6.2 of the PSAR widt allowance for sormal degradakion pursuant to tde mi:lidable Surveillanc Requirements, with one excption This cxceptioa is fthCYCS boron makeup
$Yste and the DMT CSee ITS Chapter 4.0 a.
~b.
A kjrquvalnt to lsstadi 095when floodedwith uboraed wate. A nominal 8.97 Inchmtse4qoeater dis m betwee fue assemblies placed in the o racks
~
LCO3.7.16 ~ ~ ~ ~ sal W ws urnls we bcepehusiled a n Retol 1.Reg&n , and R egin 2, mor e h LCO ~~~ 3.7.16 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Ad rpoe R .. 6. . COOKNUJCIZAR LA"r-Umr I PapS- AMZDIIUf'46S4G464,3&3 4 241 CNP Unit I Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 435 of 471
Attachment 1, Volume 17, Rev. 0, Page 436 of 471 ITS 4.0 ITS LO DEIMGN FEATURES SA.1 Th ocoolan system is designed salbe maintaind: L
. nacordance, with the code isspecified in Sectiol 4. MofteFSA. 'With allowance for normAl degtadstion'pt to di pplicable Surveillance uireznenl.
IL ftrapuesure of 2485pe C. Pars1 tmupieam oef65 zc for th prurlaimwbch s S.5.1 0 me Cooft ~~~and shal be accadacewith the aodgnal L. deul~priisonscontained In Seto 2of the PSRwt loac onldegradation pursuant to th sbiurveallance, pi mswith one exeho.Ti xpo tshe CVCS boron makeup 4.3 1i.6IQE hQ 4.3.1 CRMnCALTY - J= NFUEiL 4.3.1.1 5.6.1.1 Thusofuelstorug raks aedesinedandshab e mantaned with: 4.3.1.1 .b L. A karf equlvalt to les dws 0.95 whon (looded with unhoraWe wate. 4.3.1.1 .c ~~~b. A nominal 1.97 inch cesuserto-center digance between fu u~ pae In1 swap rwSe IT 3.7.1 6 4.3,1.1 .d, C. 110 foe! asseblies wigl be classifled aacceptable for Regiom IJReon2Io 4.3.1.1 .e based upon thei uusmbly aveapg bumntp Waus Initia aomind emichaasL- Cell *=cptabl for Region L Region 2. and Relion 3 usasebly storag are indicaed in Fl 5.-1 andi 5.6-2. Asaenibfle dist w acptable fur stoap In Reg=o 3.KjN2 nd R most nuet the ddsm. aku odefla the resiosua follo*& See ITS 3.7.16) COOK'NUCLY" PLA-NT-UM I faw 54 AMM%9r 441S& 40,I3,314 241 Page 5 of 25 Attachment 1, Volume 17, Rev. 0, Page 436 of 471
Attachment 1, Volume 17, Rev. 0, Page 437 of 471 ITS 3.7.16 ITS 5.0 DESIGN FEATURES [ 5.6 FUEfL STORAGE (Continumed) See ITS I. Region I Isdesigned to accommodate new fuel with a maximum nominal enrichment of 4.95 Chapter 4.0wfoU25orsetfelrgrlsoftedshreflbrnp
- 2. Region 2 is designed to accommnodate fuel of 4.95% initial nominal enrichment burned t at least 50,000 MWD/MtU, or fuel ofother enrichments with equivalent reactivity.
Table 3.7,16-1 3. Region 3 is designed to accommodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.0 The equivalent reactivity criteria for Region 2 and Region 3 is defined via the following equations: For Reeion 2 Stornee Mininuim Assembly Average Burmup in MWD/MTU -
-22,670 +22,220 E - 2,260 E3 + 149 E' For Reaon 3Storage MinimumnAssembly Average Burnup in MWD/MTU 2645+ 18,746 F, 1,631 gI +98.4' WeeE -lnitial Peak Emricbment COOK NUCLEAR PLANT-UNrT I FIag. 5.6 ANNbW6~ K 4 0 U 29, 243 CNP UnitI1 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 437 of 471
Attachment 1, Volume 17, Rev. 0, Page 438 of 471 ITS 4.0 ITS 5.0 DESIGN FEATURES 5.6 FUEL STORAGE (Continued) 4.3.1.1 .a, I1. Region I isdesigned to accornmodate new fuel with a maximum nomninal enrichment of 4.95 4.3.1.1 .d wt%/ U-235, or spet fuel regardless of the discharge fuel bumup.
- 2. Region 2 Is designed to aconmmodatc fuel of 4.95% Initial nominal enrichment burned to at 4.3.1.1 .e least 50,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
- 3. Region 3 is designed to accomumodate fuel of 4.95% initial nominal enrichment burned to at least 38,000 MWD/MtU, or fuel of other enrichments with equivalent reactivity.
The equivalent reactivity criteria for Region 2 and Region 3 isdefined via the following equations; - See ITS For Reizion 2 Storage 3.7.16 Minimum Assembly Average Bumnup in MWM/BMT -
-22,670 +22,220 E - 2,260 E2 + 149 t 3 For Region 3 Storae Minimuam Assembly Average Bumnup in MWD/MT
-26,745 + 18,746 E - 1,631 E2 + 98.4 E' Where E - Initial Peak Enrichmentt COOK NUCLEAR PLANT-UNIT I -Page 56 AMNMN 239, 243 Page 6 of 25 Attachment 1, Volume 17, Rev. 0, Page 438 of 471
Attachment 1, Volume 17, Rev. 0, Page 439 of 471 ITS 4.0 ITS Figure 4.3-1
~
COCK P.A~ ~~::: I PZ.7:5tl :flix.dL'fr NO.Zone: Wl1: -1 rl I~age7 o 2 Attachment 1, Volume 17, Rev. 0, Page 439 of 471
Attachment 1, Volume 17, Rev. 0, Page 440 of 471
~~~:ID ~~~~~ITS 4.0 ITS Figure 4.3-2
'U WV~?
I&me 3 ai Ouae ~zUna ri.
- ecia *-6&ihcbaI (I COCK ML-C=r.A PLf oi3 YO CZL5-cMt 6
.iA~
~~~~~~~ag f2 Attachment 1, Volume 17, Rev. 0, Page 440 of 471
Attachment 1, Volume 17, Rev. 0, Page 441 of 471 ITS 4.0 ITS 5.0 DESIGN KAUF Fjpur 5.6-3 ii~ntcayddctcw& COOKNUCLEARPLANT-UNrT1 Pape Mb AMENDMENT *69 243 Page 9 of 25 Attachment 1, Volume 17, Rev. 0, Page 441 of 471
Attachment 1, Volume 17, Rev. 0, Page 442 of 471 ITS 4.0 ITS 5.0 IDESGN FEATUR 5.6 FUEL STORAUF (C~ontinued) 0RLUCALEM-NWEL 4.3.1.2 5.6.2 'The new fuel storage radcs are designe and shal be cuntanianed with: 4.3.1 .2.a a. Westinghouse fuel assemblies having either a maximum enrichment of 4.55 weight S U-235. or an enrichmet between 4.55 and 4.95 weight S U-23S with greater Than or equal to the minimum amnber of inegal fuel bummable absorber pins as shown on Figure 5.64(interpalatiou of the Boron-10 loading between LOX and I.SX and betweeni I.SXand I-OX ts accptable); 4.3.1 .2.b bi. kf S 0.9S if filly flooded wit unbornted wase. which Includes an allowane for Uncertainties as described In SectIon 9.7 of she UPSAR; 4.3.1 .2.c C. Jf :S 0.98 If moderated by aqueous foam, which includes an alloweane for unce:rtaiate as described In Section 9.7 of the UFSAR; and 4.3.1 .2.d 4. A nombna 21 inc center to center distanc between fuel assemblies placed Inthe ssorage racks. IDRATNAG 4.3.2 5.563 YUe spent fuel storage pool Is designed and shal be maintained to prevent inadvertent drsainn of the pool belw elevation 629'4'. COOK NUCLEA PLA#NT43N1 1 hsgol AMMDMfN~fIW S, 233, 239 Page 10 of 25 Attachment 1, Volume 17, Rev. 0, Page 442 of 471
Attachment 1, Volume 17, Rev. 0, Page 443 of 471 ITS 4.0 ITS Figure 4.3-3 SAO DESIGN FEATURES FiUrc 5.6-4; New Fuel Storag Rack Integral ftdl~wrble Abwrber OR~fA) Rcqizirment 32 _ 22M
- .OX IFBA Loading
-- .GXIFOA Load~Ing - -
24 ~ **~2.OX iFBA Loading E
&16 ~ACCEP-
'~j~ACCEPA 8CPALE -
0~~~~9* 4.60 4.60 4.70 ~ 4.804.0 4.95 6.00 5 U Enrichment M (wia) COOK NUCLEAR PLANT.1U~UT I RaeSbAMENMEN 2391 Page 11 of 25 Attachment 1, Volume 17, Rev. 0, Page 443 of 471
Attachment 1, Volume 17, Rev. 0, Page 444 of 471 ITS 4.0 ITS 5.0. DESIGN flATUESM 5.6 EDIL UDOA&M (C*oiitluedfl 4.3.3 5.6.4 The fuel storage pool is desipied and shAll be maintained with a sterago capacit limited to no more tha 3613 fuel assemblies. 5£7.1 Ohstanus ytms aE opn dniid as Cseowry I tF SAR shall be designe A6 andnahzaiedto the Oriia dsgiprovisions coutaedW in dhe F Rwith allowance for normal d~aanpMUnan to fth e Suxvemlance 4ppoppezeat. COOK NUCLAR PLANT-UNIT 1 Page 5-9 AMENDMENT 63, 424%, 4#, 486201-Page 12 of 25 Attachment 1, Volume 17, Rev. 0, Page 444 of 471
Attachment 1, Volume 17, Rev. 0, Page 445 of 471 ITS 4.0 ITS Figure 4.1-1 5.9 DESIGN FEATURES FLIGURESJ-3 SITE BOUNDARY FOR LIQUID AND GASEOUS EFFLUENTS cooiK NUbIwAR ILAkrrvmf 1 Page.5-10 AMNDMbhfr 440, 201 Page 13 of 25 Attachment 1, Volume 17, Rev. 0, Page 445 of 471
Attachment 1, Volume 17, Rev. 0, Page 446 of 471 ITS 5.1 ITS 6.0 ADMINISTRATIVECONTROLS 5,1 6.1 RESPONSIBILITY 5A1.1 6.1.1 Th~a9aae hl eresponsible for overall facility operation and shall delegate in writing the 5.1.2 6.1.2 The/hifteanage(o during his absence from the'control. room corn lexs shasignM. ra.nines fof coutroriy resonsbltymn commun i nicatin sall diestablt ben tisheanefine d fo h ieVePoesidetios.al Thee relaudtionhp sall bttoedoumelnted basiaporitinsefomo anndupated 6 2 1Ons organdfsiatinlcat.Tse organi zation al be cartswl documented inrthe and operatio a updoae ageeted repcineyacorane with 10dCFRt oraiatosshl.ncueth1(etosfo)civte.afcin h ofthe~ safety nuclear ~plant. ~ power ~ ~ ~ ~ ~ ~ ~ ~ Se fl
- a. ThnesPlanthMaagrishaly responsib b letyforoverallunictisfo oeaionn shall fovr heetbihdavdefcontro 5.2e tihoeosite maaceetivte neessahryorg safnoermdateon lst and m intnnceuin of therpatnt.
l raizto c osithSeiors Vise PreltoshidetpNcea prtos shall coporatedresapronsibtiityeformoveal hedcmtdave plganiztionulclartsaf. andeshltae oranyztoa measres wieededtocuensuedi acetabe peformance ofdathed sTheffPintopeatnagr mhaintaning aepndilporoviding tecnica supotf ote ant plrtin toal nucear52 haecnstrel safety.
- d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
COOK NUCLEAR PLANT-UNIT 1 Page 6-1 AMENDMENT!", U2, I", 48,312, 279 Page 1 of 4 Attachment 1, Volume 17, Rev. 0, Page 446 of 471
Attachment 1, Volume 17, Rev. 0, Page 447 of 471 ITS 5.1 ITS IjI INSERT I 5.1 .1 The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affects nuclear safety. Insert Page 6-1 Page 2 of 4 Attachment 1, Volume 17, Rev. 0, Page 447 of 471
Attachment 1, Volume 17, Rev. 0, Page 448 of 471 ITS 5.2
~~~~~~~~~~~~~~~~~~
6.0 ADMINI1STRATIVECONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence. See JS 6.1.2 The Shift Manager (or during his absence from the control room complex, a designated individual) shall be responsible for the control room command function. A management directive to this effect signed by the Site Vice President shall be reissued to all station personnel on an annual basis.I 5,2 6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATIONS 5.2.1 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities afetngth safety of the nuclear power plant. 5.2.1 a ~~~a. Lines of authority, responsibility, and communication shall be established and defined for theM1 5.2,1.b b. The/4 ant~k1anager shall be responsible for overall unit safe operation and shall have control ovelr L those onsite activities necessary for safe operation and maintenance of the plant. 5.2.1 .c C. ITe Rdnior Yce BEsident - Nue rainshall have corporate responsibility for overall staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety. 5.2.1 .d d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. COOK NUCLEAR PLANT-UNIT 1 Page 6-1 AKME MENT!",4M,44,4S6, 2U, 279 Page 1 of 12 Attachment 1, Volume 17, Rev. 0, Page 448 of 471
Attachment 1, Volume 17, Rev. 0, Page 449 of 471 ITS 5.2 ITS EhIINSERT I 5.2.1 .a requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications Insert Page 6-1
'Page 2 of 12 Attachment 1, Volume 17, Rev. 0, Page 449 of 471
Attachment 1, Volume 17, Rev. 0, Page 450 of 471 ITS 5.2 ITS 6.0 ADNMINISRAIV CONTROLS 6.2 ORGANZAITION (Continued) FACILTYSTAFF 5,2.2 6.2.2 The Facility organization shall be subject to the following:
- b. At lensj ne licensed Operator shall be te control room when fue Ite reactor. In addition, whil ~e unit is in Mode 1, 2, 3, ra es one licensed Senio ertr Ihl be in the controlA.
5.2.2.c C. An individuald qualified in radiation protection procedures shall be on site when fuel is in the reactor.
- d. All COd 'ALTERATIONS shall be dectly supervised by a license enor Operator trained or qualj~ed in refueling and CORE ATR IOS(SO-CA wahsno other concurrentA3 res6onsibilities durina tis opera n 5.2,2.d a. The amount of overtime worked by plant staff members performing safety-related functions must 5.2,2.e g. Thel eraonis trmust hold or have held a Senior Operator Licens tCo ula ln or a similar reactor, or have been certified for equivalent senior operator knowledge. If the onse ecto does not hold a Senior Operator License, then a line v.rtons middle mne halhold a Senior Operator License for the purposes of directing operational 5.2.2.c The unexpected absence, for a period of time not to exceed 2 hours, of the on-site individual qualified in radiation protection procedures is permitted provided ixnmediate action is taken to fill the required position.
COOK NUCLEAR PLANT-UNIT 1 Page 6-2 AMENDMENT 87, 432, 45, 208,M, 279 Page 3 of 12 Attachment 1, Volume 17, Rev. 0, Page 450 of 471
Attachment 1, Volume 17, Rev. 0, Page 451 of 471 ITS 5.2 ITS 6.0 ADMINISTRATIVE CONTROLS TABLE 6.2-1 NMINIUM SHIFT CREW COMPOSMTON* SQL 1None OL 2I 5.2.2.a Non-Licensed 2 1 5.2,2.fIShfe-hja v I* Nn 5,2.2.b
- Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on duty shift crew
-members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
5.2,2.f ** Shared with Cook Nuclear Plant Unit 2. COOK NUCLEAR PLANT-UNIT 1 Page 6-3 AMENDMENT 63, 80,4I2,454, 279 Page 4 of 12 Attachment 1, Volume 17, Rev. 0, Page 451 of 471
Attachment 1, Volume 17, Rev. 0, Page 452 of 471 ITS 5.2 ITS ~~~~~~~INSERT 2 5.2.2.f An individual shall provide advisory technical support to unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. Insert Page 6-3 Page 5 of 12 Attachment 1, Volume 17, Rev. 0, Page 452 of 471
Attachment 1, Volume 17, Rev. 0, Page 453 of 471 ITS 5.2 ITS ~I 6.0 ADMINISTRATVE CONTROLS 5.2.2.f bachelor's degree or equivalent in a scirntific or engineering isciplinefitrnngn 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction See CTS of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of 6.0 J ANSI N18.1-1971 and 10 CFR Part 55. 6.5 DELETED COOK NUCLEAR PLANT-UNIT 1 Page 6-4 AMENDMENT 49, 63, 18, 14R, 1, M9,M2,243, 279 Page 6 of 12 Attachment 1, Volume 17, Rev. 0, Page 453 of 471
Attachment 1, Volume 17, Rev. 0, Page 454 of 471 ITS 5.3 ITS 6.0 ADI)NISTRATIVE CONTROLS 53 6.3 FACILITY STAFF QUALIFICATIONS L. 5~~3.1 ~~6.3.1 Each member of the facility staff shall meet or exceed the im qualifications of ANSI NI 8.1-1971 f bachelor's degree or equivi ent in a scet c regnen iscipline with secific ann~ . 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the directionSeCT of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of 6.0 ANSI N18.1-1971 and 10 CFR Part 55. 6.5 DELETED COOK NUCLEAR PLANT-UNIT!1 Page 6-4 AMENDMENT 49, 63, 43,454,486, 192,326,343, 279 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 454 of 471
Attachment 1, Volume 17, Rev. 0, Page 455 of 471 CTS 6.0 6.0 ADMINISUTRAIVE CONTROLS 6.3 FACIHiT STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-197i for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed See ITS 5.2 qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a and rTS 5.3) bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents and, (3) the Operations Director, who I must be qualified as specified in Section 6.2.2.g. 6.4 TRAI4NIN 6.4.1 A rtfing and replacement training p for the facility staff shall be aitied under the direction .1 of Training Manager and shall me rexceed the requirements and rnedations ofSection 5.5 of 1N18.1-1971 and 10 CFR Part 6.5 DELETED COOK NUCLEAR PLANT-UNIT 1 Page 64 AMENDMENT49, 63, N, 454, 486, 493,U6,w4,- 279 Page 1 ofl10 Attachment 1, Volume 17, Rev. 0, Page 455 of 471
Attachment 1, Volume 17, Rev. 0, Page 456 of 471 __ ~~~~~~~~~~~~~~~~~ITS Chapter 2.0 ITS 6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ATO 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted pursuant to the requirements oa T 10 CFR 50.73. Chapter 6.OJ
- b. Each REPORTABLE EVENT shall be reviewed by the PORC, and the results of this review shal be submitted to the NSRB and the Site Vice President.
6.7 SAFETY LIMIT VIOLATION 2.2 6.7.1 The following actions shall be taken in the event a safety limit is violated:
- a. The NRC pratios Cetershall bentfred Lejee es sonas nosibe adinall a
- b. ASaft L tViolation Report shalwbe prepte LSRB and !ySenior Vice President - Nuglear Oerations within 14 days of the viola n
- d. I pratiow the unit shall not bwesurmed until authori the COmmsin COOK NUCLEAR PLANT-UNIT 1 Page 6-5 AMENDMENT 87, 454,489,492,236, 279 Page 10 of 20 Attachment 1, Volume 17, Rev. 0, Page 456 of 471
Attachment 1, Volume 17, Rev. 0, Page 457 of 471 CTS 6.0 6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTAB F& NT A TIN 6.6.1 The fowng actions shall be taken fr PRALE EVENTS:A.
- a. The Commission shall b tiedada report submitted usntto the requirements of 10 CFR 50.73.
6.7 SAFETY LIMIfT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
- a. The NRC Operations Center shall be notified by telephone as soon as possible and in- all cases within 1 hour. The Chairman of the NSRB shall be notified within 24 hours.I See ITS
- b. A Safety Limit Violation Report shall be prepared. This report shall be reviewed by the PORC. Chapter 2.0 This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the -
violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence. C. The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSRB and the Senior Vice President - Nuclear Operations within 14 days of the violation.I
- d. Operation of the unit shall not be resumed until authorized by the Commission.
COOK NUCLEAR PLANT-UNIT 1 Page 6.5 AMENDMENT 87,154,418, 492,226, 279 Page 2 of 10 Attachment 1, Volume 17, Rev. 0, Page 457 of 471
Attachment 1, Volume 17, Rev. 0, Page 458 of 471 ITS 5.4 ITS 6.0 ADNMINISMTRA CONTROLS 5.4 6 See ITS L5.5 5.4.1 6.8.1 Written procedure W1l be esamblised implemened and maban~aed coverin Oie Actvidies icferenced below:~ 5.4.1 .a L The applicable procedue& eomne nAzedxAofRgltr ud .3 e.2 5.4.1.d 12~. Fieetd posedctSpeciogrmatponmenr4tiob 6 .3 Deleted & IOOKNUCLER PLANT-UNITOL 3 14 1,13 LaA66AAENMN 5.4.1.e OVF17EC. DOSE CMZR~~~~~~~~~~~~01,308,36,2U6 5.4.1c L QalityAgurance Fogmm-or efloemand evhvmmnPagew 1dofe 2 Attachment 1, Volume 17, Rev. 0, Page 458 of 471
Attachment 1, Volume 17, Rev. 0, Page 459 of 471 ITS 5.5 ITS 6.0 ADMMISTA7hT CONTROLS 6.8.1 Written, procedures Whlbe establised impleramded. and maitained covering fte actvities reftrebd below: A. The applicable procedures recozanended fn Appendix 'Al of Regulatory Guide 1.33, Rev. 2, Februamy 1978. See ITS 5.4
- b. Deletd.
C. Deleted.
- d. PROCESS CONTROLPROGRAM implezunatbion C. OFFS1T DOSE CALCULATION MANUAL L Quality Assiucie Program, for efflen and eavkmaumml oniowring wing ffe guidanc in R~egultatoyGtide 1L21,FRev. 1,June 1974, and RepultoiyGuide 4.1, Rev. 1,April 1975.
5.5.4 Section 4. 1, cyclic and trmanset occxrees to ensure fiat compoaent are maintdaied within the A1 Ii. Pie Profctimuprogrms mnatw 6.8.2 Each procedure and .udm~istrtve policy of Specificatio 6.8.1 above and changes therto, ddn temporary hanges, aball be reviewed prior to imlzmto asle forth in Qudlity Assurmnce Progm Des~pi~ApenixC, Sect-o= 6.5. SeITS] 6.8.3 Deleted. COOK IC IY.LAR PLANT-UNIT I Page ~ ANMI)NMM ;2U,W489A9 , 401,308A,332,61 Page 34 of 69 Attachment 1, Volume 17, Rev. 0, Page 459 of 471
Attachment 1, Volume 17, Rev. 0, Page 460 of 471 ITS c~~~~~~~~~~~~I~~~
~ITS 5.5 MOADIMISTRAM¶MGJNRAM(otinu 5.5 6.8A The foilwb programs shall be ts li&ed.ml nt a nd maintabuxe&
5.5.3 8~~~~~.R~a eIfln Ot~lPor 5.5.3 A.program salln be provided aonforming writh 10 CWRt 50.86a. for the control of radioative effuienta and for maintaining the doses to ~MBERS OF THE PMIJhO from radioactive emfuents as low as reasonably achievable. The program. (1) shall be contained in the.ODOM14 (2) shlul be implemented by operating procedures, and (8) salln ignclude remedial actions to be taken whenever the program limita are exceeded. Tihe program sball.include the following elements: 5.5.3.a 1) Limitations on the opeambility of radioactive liudand gaseous Mmoitoring lns~ummntatn indluding survellance teats and setpolnt dtriaion accordance with the mefthdology in tb OD)CMK 5,5.3.b ~~~~~2) Limiations an the enaetbatiozis of radioactive material. released in liquid 5.5.3.b ~~~~~~emfuento to UN3TITDAREA conforming to 10OCFR20.1001-20.2402, Appendix B, Table 2, Column 2, 5.5.3.c 3) Monitoing, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CPR 20.1802 and with the methioddlogy and
'Paameter intho ODCM I
5.5.3.d 4) Limitationg'on the &-nnal and quarterly doses or dose commitment to a IIRMBBYI OF THE PUBIJC from radioactive material In liquid effluents released from each unit to UNRESTRICTED ABEA conforming to Appendix I to 10 OFE Part 60, 5.5.3.e 6) etriaonof cumulative and projected dose confrihutions from radioactive effluents for the current calenda quarter and current calendar yerin accordance with the methodology and parameters In the ODOM at leost overy 81 days, 5.5.3.f ~~~~6)rLimtations en the operability and use of the H4qudd and paseous efun 5.5-3-f ~~~~~~treatment suytems to enamre that the appropriate portin of these eyutems are used to reduce releases of radioactivity when the projected doses in a S1-day parid would emceed 2 percent of the guidelines for the a--al done or dose conmftment co ~nfo n to Appendix Ito 10CFR Psart80 COOIC NUCLEAR PLANT-UNIT 1 page 6-7 . AMMNMENT M. &U. 245 Page 1 of 69 Attachment 1, Volume 17, Rev. 0, Page 460 of 471
Attachment 1, Volume 17, Rev. 0, Page 461 of 471 ITS (I) 5.5
~~~~~~~~~~~~~~~~~ITS
&0 ADMINITATIV CONTROLS PROCEDUR'ES AND PROGRAM (Contipnued) 5.5.3.g 7). Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY shall be lmnited to the followhing a) For noble gases: Les thanor equal to a dose rate of 500 mrem/year to the total body and less than or equol to a dose rate of 8000 mnrem/year to the skin, and b) For lodine-131, Iddine-183, tritiuzn, and for .fl radionuclides In particulate form with half-lives greater than 8 days: Less than or equal to a. dose rate of 1500 mrernlyear to any organ.
5.5.3.h 8) Limitations on the annuail and quarterly air doles resulting from noble gases released in gaseous effluents from, each unit to areas beyond the SITE BOUTNDARY conformiing toAp~pendixlItol10CFR Part 50, 5.5.3.1 9) Limitations on the anall and quarterly, doses to a MEMBER OF THE PUBLIC from Iodine-131, Jodine-183, tritium, and all radlonuclides in particulate formn with thalf-lives greater than 8 days in gaseous effluents released from each unit to are'as beyond the SITE BOUNDARY conforming to 5.5.3.j ~~~~THE PUBLIC due to releases of radioactivity and r r rmuw iue theenoureonfent ming danc wit Pthe art 0.hepo viios gyR3. and SRrae3es0i the~OD~~ ~ ~ ~ ~~~~aplcbe othlaiocivllun
- 2) adloandEiaee ensstot thtcaneite fara t.nbyn t heSIT bepoUNdARY tdetied anditatm catlosntth m initorin inndte pendnt. chcsheepr prciin n accr yftemauements, of riadfioactive migtert in enioBetl YapE. r e formeda ote pa of t teeffuelitya rcepoamfre monitoring.eig nl xosr theODM
~~ ~ ~ ~~~~~Pae2 f6 Attachment 1, Volume 17, Rev. 0, Page 461 of 471
Attachment 1, Volume 17, Rev. 0, Page 462 of 471 ITS 5.6 ITS 6.0 'ADMINLMU.TIV CONTROtS 5.6 6.9REORTINE REPORTSMNT 5.6 6.9.1 In mddhiou toteaplcb oTil10Co o Federa Regu~tonp, the fopllf 69.1.1 stmOMWr report of pha= adpwrecltinIsi eab~~ foflaow4ng (Z) ipofan Operaliri liene, (2dote lkcense lnotpaz tmnces inpower (3)Iunstmaion of tildn dfenrsgnhat bee by a dffee fuel supplie. and (4) mo~iain htmay harw sgnficant al ti Mxdear, fthmal, or 6.9.1.2. TM tarto report salu each of gme tast Idenife ha FiSAR and ncie ahl desu W fcD5men ueor dieOpemtincodhtoor Obtaneddurlng ft tea progra and a Of tges values adhqm sefication Amy tomucle acinsta fmWet t to obtain saifcoy sal agm be desPibd. Amy additonal specific derais hi license conditon ba otcher.commnmlnen shl be COOK NUCLEAR ANT*UNIT I Page 6-9 AM2DMUM( 3, M6,I8W 22 Page 1 ofl16 Attachment 1, Volume 17, Rev. 0, Page 462 of 471
Attachment 1, Volume 17, Rev. 0, Page 463 of 471 ITS 5.6 ITS 6.0 ADMINXSTRATIVE CONTROL.S 0.9 SART POR(continued) 6.9.1.3 totpreports shall be Su itdwithin (1) 90 days fo wn completion of the satptest program, (2) 0days following rea p nor commencement ofL. comercial power operatio or(3) 9 months followg . l criticality, whichever is earliest. - If the Staru atdoes not cover all the xt ieinitial criticality, completion of s'tartup t prraand resumption or omeieetof commercial power operation), sp mentary reports shall be a itdaeast every three months unitil all three eeishave been cornpleted. 5,6.1, 6.9.1.4 Annual reports covering the activities of heui srbdbelow for the pevious 5.6.7 Calendar XMshall be submitted oeahyear. The inifis report 6.9.1.6 Reports required on an annual basis shall include: 5.6.1 a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) recefvmng annual. exposure greater than 100 mrem, according to work and job fimctions', e~g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. Also included is a tabulation of the total person rein expoisures for station, utility, and other persionnel associated with each work and job function. The dose assignment to various 'duty functions may be estimates based on pocket dosimeter, electronic dosimeter, TLD, or Eilm badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for, In the aggregate, at least 80% of the total deep dose received shall be assigned. to specific major work functions. 5.6.7 b. 'Me complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.6.b). 5.6.1 Note A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. 5.6.1 ~~This tabulation supplements the requirements of 20.2206 of 1.0 CFR Part; 20. COOK NUCLEAR PLANT-UNIT 1 Page 6-10 AMENDMENT 87, 4M,U44, 48, 2=, 245 Page 2 of 16 Attachment 1, Volume 17, Rev. 0, Page 463 of 471
Attachment 1, Volume 17, Rev. 0, Page 464 of 471 ITS C) 5.6
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6.0 ADAMINSTRATIV CONTROIS ANNAL R.ADIOLOGICAL ENVIRONMENTAL OPERATINGREOTbyay1 5.6.2 6.9.1.6 1he Annual Bndlolgical Envirmenta OprOmig h operation of doe unit durin fthprevou calendar year sh" bsubmte e Io each yea. The rpodt sha include summnaries, interpretstions. and anablyss of rends of Mhe resuls of the Radiological Enviromenta monitorin Program for the repor*n periodL The mawwia provided sham be consitent with fth objectve oudined. In (I) the ODCM and (2) Sections IV.D.2. IV.B.3, am! 1V.C of Appendix I to 10 CPR Part 50. 5.6.3 6.9.1.7 'Te RdocieEfletRlaeReotcvrn h operation of the unit during the previou 12 months of operaton shall be sumitted within 90 dasp after Januazy 1 of each year. ie report s whal a summary of the quanitie @1raioactive liquid and gaeuem effluents adx nld solid wast releaed. from the unit. Mm. mateia provided shl be (1) consisten with the objective outlined In the ODCMA and PCP and (2) Inconforance whith 10 CFR S0.36a and Section V.B.lI of Appendix I to 10 CFR Pant 5D. 5.6.2 Note, ' A singe submittal may be made for a multiple uni station. Mhe submIttal shoul combine thos sections 5.6.3 Note that ame comnmon to all Units at the f uits separat adwat ftens h COOK NUCLEAR PLANT-UNIT Page 6-11 AMFJNDbMV 7, 484,4K474,48M, 226 Page 3 of 16 Attachment 1, Volume 17, Rev. 0, Page 464 of 471
Attachment 1, Volume 17, Rev. 0, Page 465 of 471 ITS 5.6 ITS ~~~~~~~INSERT I 5.6.2 The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. Insert Page 6-11 Page 4 of 16 Attachment 1, Volume 17, Rev. 0, Page 465 of 471
Attachment 1, Volume 17, Rev. 0, Page 466 of 471 ITS 5.6 ITS 6.0 ADMINSTRATIVE CONTROLS MONMMY RE CO PRATIWOEPORMT 5.6.4 6.9.1.8 Routine forta of Operauing satistics and shutdown experience lnclud cmn o l 5.6.5 CORE OPERATING LIMITS-RP~ 5.6.5.a 6.9.1.9.1 Core operating limnits shall be established and documented in the CORE OPERATING LIMITS Reactor Core Safety Limbt; SHUTDOWVN MARGIN; b. RdD i imt o' eiato 1... RTSInstrumenationd. Conrolpo InsrtionLimits for SpecIfication 3/4.13.3.5, OverowerAT Alowale Vlue C. AxiutdFlu Rd Iffereince for Specificat iit ioon3344.2.4 FlowDnBtLimints;andBoon f etFu o hne atrfrSeiiain3422 OverpessueATand g. uClerontrolpRo RInsertoLiotsCanlFco for Specification 3/4. 2.3, an Overowe ATAlloabl Vaue h. Alxoable Flxoiwer ee for Specification 3/4.2.6., Flow Liits; NB nd B ron ev ewed and appovetbChanel FatrCfo pcnia:n 2 A. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,' (Westinghouse Proprietary),
- b. WCAP. 5 srbution Control and Load Following Procedures - Topical Re-port,"I S tmer c197 (Westinghouse Proprietary),
C. WCAP-10216-P-A.1 Rvson J7"Relaxation of Constant Axial Offset ControliF0 Siwvcilance Technical Specification,9 (Westinghouse Proprietary),
- d. WCAP-10266-P-A ' The 1981 Version of Westinghouse Evaluation Mode Using BAH.Code," 1 7 Wcstinghouse Propritary).
- e. WCAP-12610-P.A, `VANTAGE+i Fuel Assembly Reference Core Re-port," JulA9 (Westinghouse Proprietary).
COOK NUCLEAR PLANT-UNIT 1 Page 6.12 AMENDMENT 69,494, 1!4, 48, 3" 22, 79 Page 5 of 16 Attachment 1, Volume 17, Rev. 0, Page 466 of 471
Attachment 1, Volume 17, Rev. 0, Page 467 of 471 ITS 5.6 ITS 6*0 ADMINIS ATIV CONTROES C-OBE OPERATING EiMIS RlEMO' (Cconthmed) 5.6.5.c 6.9.1.9.3 The cmorecmfrtig mits shal be determined so thdatll1 applicable lmimit (e.g., Foel zbenai-mechanical hilts, cmr fthrma-hydmaulc hmiut, EMCS lbimit, nucleu arkimsuch as &ukzzdm mas and uumlet and accident analysis Hfts) of fthsafet analysis arm met. - 5.6.5.d 6.9.1.9.4 The CORE OPERATING LIMIT REPORT, whiftudg x mid-cycle ftyision or Itmerts 6.9.2 hal ~report sha be submintd the atention of toe -docme desk. U.S. Nuclar' glmyCommission( D.C. 20555), wiih ccples to MeinH Adminisumo the Reident Inspecto at ucea PI= ulantfthidh WMpeio apecf for each mm esrp= SWu theb .ldc -belwpm toh of the appliable apvecfiaiornf
- a. Joeab scismic Juaslnancnazin 3.3.33.
- b. Seismic Monlmrind- Amaesud, Speiiain..32 C. hoperablaedetcorowo Monitoing lntzE ntlo.S lial 3.33.4. A
- d. froh SpecificAciv RCS Coolan, Specflcat6a 3.4..
- e. Rcs PresureTrmn Mitgted By RHR Safey V or RCS Vent(s), Specfificaio
- f. Moderator CofiinSpecfcT=io 3.1.1..
Wed45 Inxcnffhait 4.7.7.1.3. Lt ECC c iuao 3.5.2 aid 3..5 I. .Violatio of Limit Speciication 6.7.1. hJ6.1HTELE COOK NUJCL&'MRPLAN-U~rIr I Post 6-13 AMENMMPT 87, VA, 49, 236 Page 6 of 16 Attachment 1, Volume 17, Rev. 0, Page 467 of 471
Attachment 1, Volume 17, Rev. 0, Page 468 of 471 ITS 5.7 ITS 6.0 ADIMNISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM SeCT Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 . ) and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HI1GH RADIATION AREA 5.7 6.2. ,-Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mruer but less than or equal to 5.7.1 1000 mrem in 1 hour at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit . Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
C. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the nt axadiationy(rotection/~1aager inth -I-LAi Radiation Work Permit. 5.7,2 6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 rnrem in 1 hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the ke s shall be maintained undr the administrative control of thei'hift V(anager on dutyfig'or the t it in aigr Doors shl]+-LA1 remain locked' except during periods of access by personnel uonder oatnapproved RWP whichshl specify the dose rate levels in the immediate work areas. In the event that it is not 'possibleor practicable to provide locked doors due to area size or configuration. the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. 5.7.1 Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas. COOK NUCLEAR PLANT-UNIT 1 Page 6-14 AMENDMENT 04, 45, 154,4ISO, 2Z, 245, 279 Page 1 of 2 Attachment 1, Volume 17, Rev. 0, Page 468 of 471
Attachment 1, Volume 17, Rev. 0, Page 469 of 471 CTS 6.0 6.0 ADMINISTRATIVE CONTROLS. 61RAIATIO PROETE IONPORA Procedures rpsonlradiation protcio al eprepared consistent with thrqurmet of 10 CFR Part 20 L. and shall approved, maintained and ah tofor all operations Inovg peonlradiation exposure. 6.12 HIIH RADIATION AREA 6.12.1 Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CPR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 inrem but less than or equal to 1000 marem in 1 hour at 30 cm from the radiation source or 30 cm from any surface that die radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit . An~fy See UTS individual or group of individuals permitted to enter such areas shall be provided with or57 accompanied by one or more of die following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in die area.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
C. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Plant Radiation Protection Manager in the Radiation Work Permit. 6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in 1 hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of die Shift Manager on duty and/or the Plant Radiation Protection Manager. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in die immediate work areas. In die event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during die performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas. COOK NUCLEAR PLANT-UNIT 1 Page 6-14 AMENDMENT 94,450,454, 4S, =2,U54$ 279 Page 3 of 10 Attachment 1, Volume 17, Rev. 0, Page 469 of 471
Attachment 1, Volume 17, Rev. 0, Page 470 of 471 ITS 5.5 ITS 6.0 ADMINISTRATVE CONTROLS 6.13 PROCESS CONTROL PROGRAM aPCP) 6.13.1 Changes to the PCP:
- a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n. This documentation shall contain:
I. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2. A determination that the change will maintain the overall conformance of the solidified See CTS waste product to existing requirements of Federal, State, or other applicable regulations. 6.0
- b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
6.14 OFFS17M DOSE CALCULATION MANUAL (ODCM) 5.5.1 .c 6.14.1 Changes to the ODCM: 5.5.1 .c.1 a. ~~Shall be documented and records of reviews performed shall bee bahsul 5.5.1 .c.1I.a) 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 5.5.1 ,c.0b) 2. A determination that the change will maintain the level of radioactive effluent control pursuant to 10 CFR 20.1302. 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. 5.5.1 .c.2 b. Shall become effective after h approval of the ~ln and thearntnc
'4anager. L.
5.5.1 .c.3 C. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by mrigs in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented. COOK NUCLEAR PLANT-UNrr 1 Page 6-15 AMENDMENT 8,4S4,4S9,2MU,4, 279 Page 35 Of 69 Attachment 1, Volume 17, Rev. 0, Page 470 of 471
Attachment 1, Volume 17, Rev. 0, Page 471 of 471 CTS 6.0 6.0 ADMINSTRATIVE CONTROLS 6.13 PROCESSC PROGRA PCP) 6.13.1 Changes t ePCP:
- a. hall be documented and records freviews performed shall be rti as required by the Quality AsrneProgram Description, pedxC, Section 6.102n Ths ocmnainshall contain:
- 1. Sufficient information osupport the change together wi. the appropriate analyses or evaluations justifying echange(s) and
- 2. A determination that echange will maintain the over conformance of the solidified waste product to ex igrequirements of Federal, State, other applicable regulations.
- b. Shall become effective atreiwand acceptance by the P Cand the approval of the Plant Manager.
6.14 OFFS17E DOSE CALCULATION MANUAL (ODCM) 6.14.1 Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.l0.2.n. This documentation shall contain:
See UTS5.5
- 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2. A determination that the change will maintain the level of radioactive effluent control pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix]I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
C. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented. COOK NUCLEAR PLANT-UNIT 1 Page 6-15 AMENDMENT 87, 4", 48, 326, US~, 279 Page 4 of 10 Attachment 1, Volume 17, Rev. 0, Page 471 of 471}}