ML20012B988

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Proposed Tech Specs Re cycle-specific Core Operating Parameters,Relocating Parameters from Tech Specs to Core Operating Limits Rept
ML20012B988
Person / Time
Site: Callaway 
Issue date: 03/06/1990
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20012B984 List:
References
ULNRC-2168, NUDOCS 9003190270
Download: ML20012B988 (52)
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c m t' 't 1 o. INDEX i DEFINITIONS i SECTION 4 PAGE 1.0 DEFINITIONS 1.1 ACT I 0 N......................................................... 1 - 1 1.2 ACTUATI ON L OGI C TEST........................................... 1 - 1 1.3 ' ANALOS CRANNEL OPERATIONAL TEST................................ 1-1 I 1.4 AXIAL FLUX DIFFERENCE.......................................... 1-1 i 1.5 CHANNEL CAL I B RATI ON............................................ 1 4 1.6 CHANNEL CHECK................................................... 1-1 1.7 CONTAINMENT INTEGRITY.......................................... 1-2 1.8 CONTROLLED LEAKAGE............................................. 1 -2 1.9 CORE ALTERATION.......g.g..,.gpg..g.g..pp...... 1-2 f.h,T-AVERAGEDISINTEGRATIONENERGY... f DOSE EQU IVALENT I-131.......................................... 1 - 2 l 1.% l

1. % ENGINEERED SAFETY FEATURES RESPONSE TIME.......................

1 3 l

1. $ FREQUENCYN0TATION..............................................

1-3 l i. w! DENTI F I E D L EAKAGE............................................. 1 - 3 l l ,( 1.Hft, MASTER RELAY TEST.............................................. 1-3 l

1. % MEMBER (S) 0F THE PUBLIC........................................

1-3 l 1.MJp 0FFS ITE DOSE CALCULATION ' MANUAL................................ 1-4 l 1.36t0PERABLE - 0PERASILITY......................................... 1-4 l j.

1. W p 0PERATIONAL MODE *- M0DE........................................

1-4 l -l 1 JRfy PHYS I CS TE STS................................................... 1 -4 l 1 1 Xp PRESSURE BOUNDARY L EAXAGE...................................... 1-4 l 1.22$ PROCESS CONTROL PR0 GRAM........................................ 1-4 l jlf 1.2SjfPURGE - PURGING................................................ 1-4 I U 1 Ji{fQUADRANT POWER TILT RAT!0...................................... 1-5 I ll 1.2 @, RATED THERMAL P0WER............................................ 1-5 l 1.36p' REACTOR TRIP SYSTEM RESPONSE TIME.............................. 1-5 I 1.26pREPORTABLE EVENT............................................... 1-5 l 1, 1.)>8', RESTR I CTE D AFD 0 P ERATI ON........................................ 1 - 5 { !i 4 4 I CALLAWAY - UNIT 1 I Amendment No. 15.28. 35 3, a .f. a. 1. 9 ( - i fj( b ir

~ 4 I p =. j p' -) ~ j INDEX g d DEFINITIONS g. q-y' SECTION PAGE 7 p DEFINITIONS (Continued) 1.MjoSHUTDOWN MARG I N................................................ 1 - 5 I l[-

1. 3, S I TE B 0U N D A RY.................................................. 1 - 5 l

1 #jz SLAV E RELAY TEST............................................... 1 - 5 l j 1..Hb SOL I D I F I CATION..................................'............... 1,6 l ~ [L 1 J +S OURC E CH E C K................................................... 1 - 6 1. 1.,W55TAGGERED TEST BAS I S........................................... 1 -6 l J'. 1.Mjt. THERMAL P0WER.................................................. 1-6 l l 1..WsfTRIP ACTilATING DEVICE OPERATIONAL. TEST......................... 1-6 l l r-1 J$r DN I DENTI FI ED L EAKAGE...............................-............ 1 - 6 l j y 1 JI6f UNRESTRICTED AREA.............................................. 1 -6 l j 1 1.WA/ENTILATION EXHAUST TREATMENT SYSTEM........................... 1 -7 l 4 1.40W VENT I NG........................................................ 1 - 7 l -)f ( 1.MJWASTE GAS HOLDUP SYSTEM........................................ 1 -7 l .) TABLE 1.1 FREQUENCY NOTATIONS.......... 1,-B l ij TABLE 1.2 O P ERATI ONAL M0 0ES......................................... 1 - 9 l 3 d .1 : t t:

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t j .h r' yj. CALLAWAY - UNIT 1 II Amendment No. J3.23,35 3 i,j g g iti. laiI

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w ? il q t L t f RE VIE,cy 3 l } s INDEX . LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS t SECTION PAGE 344.0 APPLICABillTY................................................ 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL. 1 o-i f Shutdown Margin - T,yg :> 200*F............................ 3/4 1-1 i Shutdown Margin - T,yg i 200*F........................... 3/4 1-3 l Moderator Temperature Coefficient........................ 3/4 1-4 l Minimum Temperature for Criticality...................... 3/4 1-6 P 3/4.1.2 BORATION SYSTEMS ( Flow Path - Shutdown..................................... 3/4 1-7_ Flow Paths - Operating................................... 3/4 1-8 F }. Charging Pump - Shutdown.................................. 3/4 1-9 y. ;, Charging Pumps - Operating............................... . 3/4 1-10

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v.., Borated Water Source - Shutdown.......................... . 3/4 1-11 3 Borated Water Sources - Operating........................ 3/4 1-12 3 /4.1. J' MOVABLE CONTROL ASSEMBLIES i Group Height............................................. 3/4 1-14 -t l ABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R00............................................... 3/4 1-16 Positiun Indication Systems - Operating.................. 3/4 1-17 Position Indication System - Shutdown.................... 3/4 1-18 Rod Drop. Time............................................ 3/4 1-19 Shutdown Rod Insertion Limit........... 3/4 1-20 / Control Rod Insertion Limits................. 3/4 1-21 IIOUE[ 3.1 1 EOC CANE INSEEI'.ON LIMIIC V[ ECUS INCEMAL ICWC2 r00E LOO" 0*EEAT 0N. 3/4 1-22 j; CAllAWAY - UNIT 1 IV 4 o

x I I t L ? INDEX ] f LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS { SECTION PAGE l 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................... 3/4 2-1 T!OUn: 3.2-1 AXIAL TLUX OITTERENCE L4Mf-TS AS A TUNC+1M-CT PAT C O T : n"AL P0'.':R................................. 3/ 4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fg(Z)...................... 3/4 2-4 l 1 -i GUR: 3.2-2 X(Z) NCn"A!.!ZCO T (Z) AS A TUNCTION OT LORE ll[IGlii.... 3/4 2-5 Q 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F g............ 3/4 2-8 l [ N 3/4.2.4 QUADRANT POWE R TILT RAT I0,................................. 3/4 2-10 3/4.2.5 DNB PARAMETERS............................................ 3/4 2-13 TABLE 3.2-1 DNB PARAMETERS.......................................... 3/4 2-14 t; 3/4.3 INSTRUMENTATION ~ g 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................... 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.................... 3/4 3-2 ' TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES..... 3/4 3-7 .I -TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................................... 3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION......................................... 3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM L INSTRUMENTATION...................................... 3/4 3-14 l l TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0!NTS....................... 3/4 3-22 L TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE. TIMES.............. 3/4 3-29 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............ 3/4 3-33 l t CALLAWAY - UNIT 1 V Amendment No. 28 h Y

a INDEX )- ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2_NUCLEARSAFETYREYlEWBOARD(NSRB) Fu n c t i o n....................................................... 6 - 9 C o mp o s i t i o n..................................................... 6 - 10 Al t e r n a t e s...................................................... 6 - 10 C o n s ul t a n t s..................................................... 6-10 Me e ti n g F re q ue ncy............................................... 6-10 Qu a l i f i c a t i o n s..................................... /............ 6-10 Quorum.......................................................... 6-10 Review..........................................................6-11 Audits..........................................................6-11 Records.......................................................... 6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Ac ti v i ti e s..................................................... 6-13 Records......................................................... 6-14 m, 4 a -6.6 RE PO RTABL E EV ENT ACT !0N........................................... 6-14 6.7 SAFETY LIMIT VIOLAT10N............................................ 6-14 6.8 P ROC E DUR E S AN D P R0G RAMS........................................... 6-15 .6.9 REPORTING REQUIREMENTS 6.9.1 RO UT I N E R E P 0 RT S................................................. 6 - 1 7 S ta r tu p Re p o r t.................................................. 6-17 An n u a l Re po r ts.................................................. 6-17 Annual Radiological Envi ronmental Operating Report.............. 6-18 Semiannual Radioactive Effl uent Release Report.................. 6-19 Mon thly Ope ra ti ng Re po rt........................................ 6-20 . edir.; T;;ter L bi t."cpert.4//.. $Wed(y 49.dt. 8tprf........ 6-21 669.2 S P E C I AL R E P0RTS................................................. 6-21 6.10 RECORD RETENTION................................................. 6-21 6.11 RAD I AT I ON P ROTE CT I ON PR0G RAM..................................... 6-2 3 1 CALLAWAY - UNIT 1 XX Amendment No. 28 u

m. DEFINITIONS _b. f-CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

a. -

All penetrations required to be closed during accident conditions are either: 1) Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2) Closed by. manual valves, blind flanges,.or deactivated automatic valves secured in their closed positions, except as provided in-Ta'ble 3.6-1 of Specification 3.6:3. b. All equipment hatches are closed and sealed, c. Each air lock ~is in compliance with the-requiramentt of-Specification--ac p 3.6.1.3. d. The containment leakage rates are within the limits of Specification 3.6.1.2, and e. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE. CONTROLLED LEAKAGE yf), yl 1.8 CONTROLLED LEAKAGE shall be that seal water flow from the reactor coolant pump seals. ( CORE ALTERATION CORE ALTERATION shak1 be the movement or manipulation of any component 1.9 within the reactor vessel with the vesset head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a u^ component to a safe conservative position. jbD r^fster A MtM" DOSE EQUIVALENT !.131 /.// l' h49-DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram)l which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, I-133, I-134,~ and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test c Reactor Sites." 1 l CALLAWAY - UNIT 1 1-2 Amendment No.15,35 ,.k

p, 3 i [. 11 o t .o ' l a: INSERT A (ADD TO PAGE l-2) .i t: [ CORE OPERATING LIMITS REPORT { i' l! 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit i specific-document that provides core operating limits.for ? h.. the current operating reload cycle. The cycle specific core operating limits shall be determined for each reload cycle j in accordance with Specification 6.9.1.9. Plant operation i within these operating limits is addressed in individual - l C specifications. f e: - i I-e I f I r t i k s (

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L I j 3 1, i DEFINITIONS \\ (~ ) T. AVERA3E DISINTEGRATION ENERGY 1.k I shall be the average (weignted in proportion to the concentration of each radionuclide in the reactor coolant at tne time of sampling) of t,he sum of the average beta and gamma energies per disintegration (in MeV) for isotcpes, other than iodines, with half-11vss greater than 15 minutes, making up at least 95t of the total noniodine activity in the coolant. l ENGINEERED SAFETY FEATURES RESPONSE TIME 1.N The ENGINEERED SAFITY FEAT 1)RES (ESF) RESPONSE TIM l interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor unt11 'the ESF equipment is capable of performin safety function (i.e... the valves travel to their required positions,g its pump discharge pressures reach 'their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. FRE0VENCY NOTATION 'I 1.h The FREQUENCY NOTATION specified for the performance of Surveillance l Requirements shall correspond to the intervals defined in Table 1.1. ~, L IDENTIFIED LEAXAGE 1.kIDENTIFIEDLEAKAGEshallbe: ( a. Leakage (except CONTROLLED LEAKAGE) into closed systems. such as l pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or i b. Leakage into the containment atmosphere from sources that are both I specifically. located and known either not to interfere with the operation of Leakage Detection Systems or not to be-9RESSURE BOUNDARY LEAKAGE, or l l c. Reactor Coolant System leakage through a steam generator to the l Secondary Coolant System. l MASTER RELAY TEST 1.M' A MASTER RELAY TEST shall be the energi:ation of each master relay andI verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associsted slave relay. MEMBER (S) 0F THE PUBLIC h 1.N MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-I L tionally associated with the plant. This category does not include emoloyees i of the licensee, its contractors or vendors. Also excluded from this category e are persons who enter the site to service eeufpment or to make deliveries. This category does include persons wno use cortions of the site for recrea-tional, occupational, or other purposes not associated with the plant. (- CALLAWAY - UNIT 1 1-3 Amendment No. 75, 35 4 4

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t DEFINITIONS

( OFFSITE 005E CALCULATION MANUAL e 1.h The CFFSITE COSE CALCULATION MANUAL (00CM) shall contain the 1 and parameters used in the calculation of offsite doses cue to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip 54tpoints, and in the conduct of the Environmental Radiological Monitoring Program. i CPERABLE - OPERA 8!LITY 1.N A system. subsystem, train, component or device shall be OPERA 8LE or l have OPERASILITY when it is capable of performing its specified function (s), 1 and when all necessary attendant instrumentation, controls, electrical power, . cooling or seal water, lubrication or other auxiliary equipment that. ace. required for the system, subsystem, train ~ function (s) are also capable of performing, component, or device to perform'its their related support function (s). OPERATIONAL MODE - MODE ik An 0PERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive l combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2. 1 PHYSICS TESTS 1.h PHYSICS TESTS shall be those tests performed to measure the f;ndamental l nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, or (2) authorized under the provisions of .10 CFR 50.59, or (3) otherwise approved by the Commission. J PRESSURE B0UNDARY LEAKAGE 20-1.pr PRESSURE BOUNCARY LEAKAGE shall be leakage (except steam generator tube l J 1eakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. PROCESS CONTROL PROGRAM

1. N The PROCESS CONTROL PROGRAM shall contain the current formula, samp l

l analyses, tests, and determinations to be made to ensure that the processing ~1 and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to l assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal anc State i regulations, burial ground requirements, and other requirements governing the disposial of the radioactive wasta. PURGE - PURGING 1.k+ PURGE or PURGING shall be any controlled process of discharging air or l gas from a confinement, to maintain temperature, pressure, humidity, concentra-tion or other operating concition, in such a manner that replacement air or gas. is required to purify the confinement. . ( CALLAWAY - UNIT 1 14 Amendment No./,15 L5 m o I

9 L f. i- ? 1 ) DEFINITIONS OUADRANT POLER TILT RATIO i 1d[ QUADRANT POWER TRT RAU0 shall be the ratio of the maximum upper excore l detector calibrated output to the average of the upper excere detecter cali-brated outputs, or the ratio of the maximum lower excore detector calibrated i output to the average of the lower excore detector calibrated outputs, which-1 ever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average. RATED THERMAL POWER 2G 1.26' RATED THERMAL POWER-shall be a total core-heat-transfer rate to the-'* ~ reactor coolant of 3565 MWt. REACTOR TRIP SYSTEM RESPONSE TIME IN The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time int l when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. REPORTABLE EVENT 2r IX A REPORTABLE EVENT shall be any of those conditions specified in l Section 50.73 to 10 CFR Part 50. b RESTRICTED AFD OPERATION av 1J8' RESTRICTED AFD OPERATION (RAFDO) limits the AXIAL FLUX DIFFERENCE (AFD)l to a +3% target band about the target flux difference and rettricts power levels to between APLND and either APLRAFD0 or 100% RATED THERMAL POWER. whichever is less. APLND and APLRAF00 are defined in Specifications 3 ? 1 and 4.2.2.3. respectively. RAF00 may be entered at the discretion of tni. licensee. SHUTDOWN MARGIN 1 9 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which j the reactor is suberitical or would be suberitical from its present condition assuming all full-length red cluster assemolies (shutdown and control) are fully inserted except for the single red cluster assembly of highest reactivity worth which is assumed to be fully withdrawn. SITE BOUNDARY 1 ' The SITE SOUNDARY shall be that ifne beyond which the land is neither owned, nor leased, nor othenvise controlled by the licensee. l SLAVE RELAY TEST

1. k A SLAVE RELAY TEST shall be tne energi:stion of each slave relay and verification of OPERABILITY of eacn relay. The SLAVE RELAY TEST snall incluce a continuity checx, as a minimum, of associated testable actuation devices.

CALLAWAY - UNIT 1 1-5 AmendmentNo.13./S, 35 4=

Q l y y j il r ~ .p. DEFINITIONS ,y-3; ~~ SOLIDIFICATION 'ld SOLIDIFICATION shall be the conversion of wet wastes into a form that = meets shipping and burial ground requirements. l SOURCE CHECK 3 4' l.33" A SOURCE CHECK shall be the qualitative assessment of channel response l when the channel sensor is exposed to a source of increased radioactivity. STAGGERED TEST BASIS l.k A STAGGERED. TEST 8 ASIS-shall-consist of:~ ~ """J' -l a. A test schedule for n systems, subsystems, trains, or other y designated components obtained by dividing the specified test j,. interval into n equal subintervals -and.... --- r 1 b. The testing of one system, subsystem, trek or other designated

J component at the beginning of each subinterval.

]. THERMAL POWER 36 1.PT THERMAL POWER shall be the total core heat transfer rate to the reactor 1 coolant. l 1 .[ TRIP ACTUATING DEVICE OPERATIONAL TEST

1. N A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the l

Trip /.ctut.cing Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy. UNIDENTIFIED LEAKAGE ~1.k UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. UNRESTRICTEDARFJA, 29 1.34' An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDN?i access to which is not controlled by the licensee for purposes of protection [ of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, comercial, inscitutional, and/or recreational purposes. o CALLAWAY - UNIT 1 1-6 Amencment No.,IE, 23, 25 l

Nt 't. t 7.E l DEFINITIONS {"' 8 VENTILATION EXHAUST TREATMENT SYSTEM k,

1. k A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system l-installed to reduce gaseous radiciodine or radioactive material in particulate fi fann in effluents by passing ventilation or vent exhaust gases through charcoal j-adsorbers and/or HEPA filters for the purpose of removing iodines or partic-

.; x ulates from the gaseous exhaust stream prior to the release to the environment. L' i Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features (ESF) Atmospheric Cleanup Systems are not considered 4 to be VENTILATION EXHAUST TREATMENT SYSTEM components. a 3 VENTING . o. 1..W VENTING shall be any controlled process of. discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or l other operating condition, in such a manner that replacement air or gas is not L,. provided or required during VENTING; -Ventrused -in system names;-does not'~--~~ " imply a VENTING process. L WASTE GAS HOLDUP SYSTEM 4.:L 1.M A WASTE GAS HOLOUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off- [ gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing tb1 total radioactivity prior to release to the s environment. =, .(. a \\ EL ( -. '1 Ii\\_ L. p j> li'[ u CALLAWAY - UNIT 1 1-7 Amendment No. JS, 2PJ, 3S 1 H a-s . + -

t t 3: REACTIVITY CONTROL SYSTEMS-MODERATOR TEMPERATURE COEFFICIENT { w i LIMITING CONDITION FOR OPERATION l 3.1.1. 3 The moderator temperature coefficient (MTC) shall bey w, Win #Ae /t.iine s,yeified is1 aa Cara o & ~n, Ltu;/g. _ p,.y (ca.A.. ga ...su... ~- .e

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.' "'". 22t. O'O. 2 ". o",m"n."u.m ' ' L'1", L,' ". ".?. 1 F"._,'. ',.'" ? f. '." h. w." Y W"' nn . <v-sn so. o.. n. 5:;i ming of cy;1: life (SOL) ::ndition; :nd b. Le;; negetive then 4.1 x 10-' ek/k/"T for the all red; reithdr;wn, and of cycic life (COL), RATCO T";;;;AL r"O'.':" ... m.. u... pay;o,ein o f Gyele lik hol) Limi/ APPLICABILITY:-(Sp::ifi,c: tier.3.1.1.30. - MODES I and 2*#. Sp::i'ic:ti:n 3.1.1.35. - MODES 1, 2 and 3#. t&J of dyela L*fe (EDU 4.im.'f ACTION: BoL spes; Fled in he 60 % ( .a. With the MTC more positive than theAlimit -0. S;;;if!::tien 3.1.1.3e. i Ob:';;, operation in MODES I and 2 may proceed provided: i 1. Control rod withdrawal limits are established and maintained. sufficient to restore the MTC to within the d::: -it' SOL //bifJ within 24 hours or be in HOT STAND 6Y within the next 6 hours. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6; G g,ce.fr.a- ,n g, cot 4 2. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and 3. A Special Report is prepared and submitted to the Commission-pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition. EOL. Sf*0IS!ed /*, +he COLA b. With the MTC more negative than theAlimit of Specific:ti:n 3.1.1.35, 2:';;, be in HOT SHUTDOWN within 12 hours.

  • With K,ff greater than or equal to 1.
  1. See Special Test Exception Specification 3.10.3.

k l CALLAWAY - UNIT 1 3/4 1-4 Amendment No. 44 1-

6 6 c... p J REvisl0N 1~ REACi[VITY CONTR0l SYS1FMS ' SURVEILLANCE REQUIREMENTS 4.1.1. 3 The MTC shall be determined to be.within its-limits during each fuel cycle as follows: Sfeelhed in

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a. The MTC shall be measured and compared to the BOL limit of-A-Ces.;if;;etie, 0.1.1. 0... etes;, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading; and sur ye;llane f.- tt sp* ci Aed in d e c0LA The MTC shall be Masured at any THEbL30WER and compared to A 4 300 m b. -3.2 - 10

  • it'h/*"-(all rods withdrawn, RATED THERMAL POWER condi-tion) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.

In the event this comparison indicates the MTC is more e negative thang 2.2 : 10 ' th/h/"", the'MTC shall be remeasured, and compared to tie EOL MTC limi -f 5;;;fff;;th. 3.1.1.35., at least once per 14 FPD during the r mainder of the fuel cycle. Spectfred in /h e do!.A lb' 3 00 frm S w vgiflance /,m;/ sp' fed a in +ke dotA .). 9 h a v M ) 1-1 CALLAWAY - UNIT 1 3/4 1-5

L. SD O 2. i REACTIVITY CONTROL SYSTEMS REVISION 3 l 3/4.1.3 J MOVABLE CONTROL ASSEMBLIES GROUP' HEIGHT-LIMITING CONDITION FOR OPERATION 1 3'.1.3.1 All full-length shutdown and control rods shall be OPERABLE and f positioned within

  • 12 steps (indicated position) of their group step counter demand position.

~ APPLICABILITY: MODES 1.* and 2*. ACTION: a. With one or more full-length rods inoperable due to being immovable-as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour and be in HOT STANDBY within 6 hours.

b. -

With more than one full-length rod inoperable or misaligned frort the group step counter demand position by more than 2 12 steps (indicated position),. be'in HOT STANDBY within 6 hours. c. With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its - group step counter demand height by mnre than t 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour: 1. The rod is restored to OPERABLE status within the above alignment requirements, or 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within t 12 steps of the inoperable rod while~ maintaining the rod sequence and insertion limits of ri;rse 3.114 The THERMAL POWER level shall be restricted' pursuant to Specif ation 3.1.3.6 during subsequent operation, or S ec; hedien 3, j,1,6 p 3. The rod is declared inoperable and the SHUTDOWN MARGIN I requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that: a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm j that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; q b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours; "See Special Test Exceptions Specifications 3.10.2 and 3.10.3. - CALLAWAY,- UNIT 1 3/4 1-14 AUG 2 0 385 L 1

D. ...r REACT!v!TY CONTROL SYSTEMS SHUTD0'.'N R00 ~ 1NSERT10N t.!MIT LIMITING CONDITION FOR OPEPATION f withd.e a '02; etepe er hi h;r). l All shutdown rods shall beg elly/cd-in p ylikAL i 3.1.3.5 fi h infe&len AS l' ore opero64 'Ls' spec A*</ in Jhe mi +r pap,,.y gg, APPt.!CABILITY: MODES 1* and 2*#, ACTION: Mserded b. yond- +he inserdion hmil sp*c/Ned in +h' d*M) With a maximum of one shutdown ro47.ct felly withdr;wn, except fcr surveil- ~j lance testing pursuant to Specification 4.1.3.1.2, within 1 hour either: a. -ft Hy withdr:a th: nd, es/oce +4. tvd 4 M/Mi" M' -l inser4 ton /tmi+ sprei ie.' In +he 60%

  • b.

Declare the rod to be inoperable and apply Specification 3.1.3.1. f \\ SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be detennined to.be f.ily withdsun; j utidin +he inte4w hm,4 specifled in #e - doLA: a. Within 15 minutes prior to withdrawal of any rdds in Control Bank A, B, C. or D during an approach to reactor criticality, and b. At least once per 12 ' hours thereafter. L l

  • See Special' Test Exceptions Specifications 3.10.2 and 3.10.3.

j. fWith'K,ff greater than or equal to 1. 1. l } L l, CALLAWAY - UNIT 1 3/4 1-20 knendment No. 29 l. 1 1 'w.

L [', l ' ..j t ') y

y. n REACTIVIIY CONTROL SYSTEMS

.REYlsl0N 2 ',t ' CONTROL R00 INSERTION LIMITS ' LIMITING CONDITION FOR OPERATION 7 t 3; 1. 3. 6 The control banks.shall be limited in physical insertion as :h:2 ir k i'i= 2. ?1. C eeilieel in /Ae Core Opera 9 Liark fepo,f (cola), f ' APPLICABILITY: MODES la and 2*#. p ACTION: With the control banks inserted beyond the-ebeve insertion limits, except for surveillance' testing pursuant to Specification 4.1.3.1.2: ( a. Restore the control banks to within the limits within 2 hours, or b. Reduce THERMAL POWER within 2 hours to less than or equal to that. fraction of RATED THERMAL POWER which is allowed by the bank position using the 2=; 'i;=;, = inser km /to ;/s speciNed to, +he COLQ oV. .r Be in at least HOT STANDBY within 6 hpurs. c. SURVEILLANCE REQUIREMENTS 4 3 4.-l.3.6. The position of each control bank shall be determined to be within the insertion limits at least once per 12-hours except during time intervals when -the Rod Insertion Limit Monitor is inoperable, then verify the individual -rod positions'at least once per 4 hours, i .j .+ "See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

  1. With K,gg greater than or equal to 1.

d -j. f CALLAWAY - UNIT 1 3/4 1-21 .4:

j p 1 .r- ' bELE TE b - ./ m l)l j j; FULLY WITHDRAWN (2"25 steps or hisher) ' TOW = ./ O T' _ 200; l .j .. = nc- = 1 .r 3goi '100= 1^*+- L, !--/ .i l-l '160 & p 3 l 9 f i, -140- , ' u ;; - 2 'y .I. '120 f_ ~ _f-E 100 _f' l t:: f a o a L 80 f' .- 5 A N E E i g z R -j 60 f.' f =~ C ,3 k-W N', 40 20 m vy_a =::ss 0-20 40 60 80 10h 0 FULLYINSERTED \\ RATED THERMAL POWER (Percent) N FIGURE 3.1-1 RCD SANK INSERTION LIMITS VERSUS RATED THERMAL POWER - FOUR LOOP OPERATION L: Amendment No.15.29 [. l, cal.LAWAY - UtlIT 1 3/4 1-22

([. n

y>

@n ~ 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION n 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the f ll: wing target band (flux difference units) about the target flux-differencef as spenfted in +he Cww ope ra +.4 Limth de p t (dou). y +3%, 12% f;r ".0;. 1 Op;r;tica 3 -L. 13% f;r "iST"!CTE0 AfD 0^t"J,T!0'l The indicated AFD may' deviate outside the applicabge'gequired target band at - greater than or_ equal to 50% but less than 0.9 APL u or 90% of RATED THERMAL i L POWER, whichever is less, provided the indicated AFD is within the Acceptable ~ Operation Limiteg' "?;= 2.2 ' and the cumulative penalty deviation times does -not exceed I hou during the previous 24 hours. Sfacihad in +As. COLA The indicated AFD may deviate outside the applicable required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumula-tive. penalty deviation'. time does not exceed I hour during the previous 24_ hours. APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER *,f- ) ACTION: a. With the indicated AFD outside of the applicable required tarcet band and with THERMAL POWER greater than or equal to 0.9-APLN0** or 90% of RATED THERMAL POWER, whichever is less, within 15 minutes, either: i 1. Restore the indicated AFD to within the applicable required target band limits, or et, fed /n. 4 Ae dot 4

  • See Special Test Exception Specification 3.10.2. JxYhannel-may be per-
  1. Surveillance testing of the Power Range-Neutron F formed pursuant to Specification 4.3.1.1 provided the indicated AFD is.

maintained within g* Acceptable Operation Limits %f figure 3.21 and THERMAL POWER <APL A total of 16 hours operation may be accumulated with the AFD outside of the applicable required target band during testing without penalty deviation. E

    • APLND is the minimum allowable power level for RESTRICTED AFD OPERATION

,;3 _ sp, c t /t, d, ando... .,r....... in theg"Coreeeking Tacter LimikReport per Specification 6.9.1.9. Ogrwhy s

      • APLN0 is equal to the U*

K(Z) minimum fh

  • 100 over Z

,F (Z)

  • W(Z)NO and Fh(2) and W(Z)NO are defined in 4.2.2.2.c.

l ] 'CALLAWAY - UNIT 1 3/4 2-1 Amendment No. M, 44 c w-w

c.. ..m q- : POWER DISTRIBUTION LIMITS ) ! LIMITING CONDITION FOR OPERATION-j I ACTION (Continued)' 2.- Reduce THEFFAL POWER to less than 0.9 APLiiD** or 90% of RATED THERMAL POWER, whichever is less, and discontinue RESTRICTED AFD OPERATION (if applicable). 1 j -b. 'With the indicated' AFD outside of the applicable required target band for more than i hour of cumulative penalty deviation time during the previous 24 hours or outside the Acceptable OperationND** Limits of Figm 3.0 hand with THERMAL POWER less than 0.9 APL . or 90%, whichever is liess, but equal to or greater than 50% of RATED THERMAL POWER, reduce:k spec /We/ in 44, vou 1. THEPMAL POWER to less than 50% of RATED THERHAL POWER within 30 minutes, and 2. The Power Range lieutron Flux-High Setooints to less than er y equal to 55% of RATED THERMAL-POWER within the'next 4 hours. 3 With the indicated AFD outside of the applicable' required target l c.- band for more than 1 hour of cumulative penalty deviation time during the previous 24 hours and with THERMAL POWER less than 50t but greater than 15% of RATED THERMAL POWER, the THERFAL POWER shall not .be increased equal to or greater than 50% of RATED THEPyAL POWER until the indicated AFD is within the applicableerequired-target band. 1 SURVEILLANCE REOUIREMEhT5 x 4.2.1.1 The indicated AFD shall be determined to be within its. limits during POWER OPEPATION above 15% of RATED THERPAL POWER by: Mo'nitoring the indicated AFD for each OPERABLE excore channel: a. 1. At least once per 7 days when the AFD Monitor Alam is OPERABLE, and L l' 2. At least once per hour for the first 24 hours after restoring ~ the AFD Monitor Alam to OPERABLE status. l-L b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours and at least i once per 30 minutes thereafter, when the AFD Monitor Alarm is L inoperable. The logged values M the indicated AFD shall be assumed to exist during the interval preceding each iugging. -l-p l l: l-CALLAWAY - UNIT 1 3/4 2-2 Amendment No. 28 i -i

b a.:, a. c, .DELATE D RE', tis;cy y a FIGURE 3.2-1 ~ AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER ~./ ETrE 5.5 ~ "P t __._n =:1 '. -

_, o-.g_

-::ip.( ...w ~~- o --- - -. _ : ', T _ 1 =: r==i':- ::._;(:m. }f--E E- -*--Q,a. ; = 1 _;ayg-m .p $3,:3 .~ I - i$ ~ ~ _,5 -- - - 1 gi .x a,' i* 100 liEiS t11. 9013ii 1/N ACCEPTABLE i==: Eiii UNACCEPTA884. it 11.904::::::

=

. OPERATION - \\~ ,_-"'~ ~_~ / ' OPERATION C ~ aw _y E /C --A . g : aa x; 4 ~

l r

.t g. w _ g-. _-[-' ACCEPTABI,1kf% RATION 7'i. -o y j. r en A g ~ an. som g

i.n. noi t

.t) i W J .E -40 r 'W ' a. n m 7 ^ f l .m .m o ,o = = a og F1.UX DIFFERENCE ( AD% i CALLAWAY - UNIT 1 3/4 2-3 )

4, wn ;. i .7 ' POWER' DISTRIBUTION' LIMITS 3/4.2.2 - HEAT FLUX HOT CHANNEL FACTOR - F {Z)- O r . LIMITING CONDITION FOR OPERATION' 3 5 3.2.2-F(Z)shallbQimitedbythefollowing' relationships: n F (Z) < {-. 50) K(Z)5 for P > 0.5, arid l Q T- {g# F (Z) ((5.00]IK(Z)l for p < 0.5. l ^ 9 Where: f de F /;,,, f of kyro rHEtMAL fpyg 4 (ATP) ~ 9 Specihed in #e Core O en hm p p. THERMAL POWER , and g,.g g g,gg (c 4 RATED THERMAL POWER + K(Z) = the '- core height IA$$5iSr[ E 7 E A'c 3 e 7 2n N M + ' j APPLICABILITY:. MODE 1. ACTION: -T With F (Z) exceeding its limit: g a. Reduce THERMAL POWER at least 1% for each _1% F (Z)-exceeds -the limit n within 15 minutes and similarly reduce:the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours; POWER OPERATION may proceed' for up to a total of -72 hours; subsequent POWER OPERATION i .may proceed provided the Overpower AT_ Trip Setpoints have been- .i l reduced at least 1% for each 1% F (Z) exceeds the limit; and-9 b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by-1 ACTION a., above; THERMAL POWER may then be increased provided F (Z) is demonstrated through incore : napping to be within its limit. g L i L I CALLAWAY - UNIT 1 3/4 2-4 Amendment No. 44 h

i > *; 7g i -o_ z ,e. ? ix Y DELETED \\ i 3 3 1. .( .....s... .........3.....- t / ; -, h

c p'-

.s..n . +/ j ( i \\ n, = i-fi-l:, -.A. y.5 i t r a g. t ..j (. - J / i ;.: . g-j -.a ..j. /* .j :? + a. t t ee w i T,. ) 1 ~ l \\ )- i ./- \\- i, i [': j\\ l' 6 l 6 u i - .i. u. N- _ ;/ G i 4 o .. \\ f. . : 5.. e 1: 1 \\: /* t .t i i. g X / ,f 4\\ /* 8 l i j\\i ' #9

  • w4 r

t f . \\.: i+ n!-

i.a
hi-6 g

.= /. ,.\\ 2 .6 t in. 5 ---3,,, !/ \\i 5 e c. b 8 8- /

\\

I !.; O 3* i [". t \\ t . y.. W a... 4 2

h:.

W ~ .i.. \\ l- / + -( / i

\\

i,i : W \\:;.' l l' .1. t- "n dii g .~ \\ -l /} h y i t i/ s r n .= N u / i- / '

i ip?q"

' l y. 1.. 1 .. i \\ j ~ i ~ l e e et e e e n d d 6 6 e = \\ o 0 -(21 4 car:7vnwon - tm - t b - 1 CALLAWAY - UNIT 1 3/4 2-5 Amendment No. 44 o.

) i

t 3

u, L POWER DISTRIBUTION LlHITS Il g h' ' SURVEILLANCE REQUIREMENTS e I 4.2.2.1 The provisions of Specification 4.0.4 are not applicable. 4.2.2.2.'For Normal Operation, F (z) shall be evaluated to detennine if F (z) Q Q j is within its limit by: 1 a.- Using the movable incore detectors to obtain a power distribution. h. map at any THERMAL POWER greater than 5% of RATED THERMAL POWER. l. Increasing the measured F (z) component of the power distribution. b.- Q map by 31 to account for manufacturing tolerances and further ' increasing the value by 5% to account for measurement uncertainties. c. Satisfying following relationship:- 1 l Q(z).1 dW x K(z) for P > 0.5 I M l F L; P x W(z)NO Fg(z)1 x K(z) for P 1 '0. 5 4nowheadFhlibf M .W(z)NO x 0.5 4.r a,Cecvbm o# i= core hey % ~ whereF$(z)isthemeasuredF(z)increa d by the allowances for-Q neertainty, 2.00as tne k 'r.e[ manufacturing)tolerancesandmeasuremen Folimit,K(z is giv:7. i; Fi;;r: 2.2 2, P is the relative THERMAL POWER,andW(z)NO is the cycle dependent. Nonnal Operation function = ar# N(c) an/ that ar. counts for power. distribution. transients encountered during ) Norma' Operation. ATP,i; f ::ti:r. f: given in,the " :ki.; F::t:r*do-1 3 Ser* Qa e r* M4o Are Limi Report as per Specification 6.9.1.9. M d. Mer.suring FQ (z) according to the following schedule: i. Upon achieving equilibrium conditions after exceeding, by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which-F (z) was last det, ermined,* or Q 2. At least once per 31 Effective Full Power Days (EFPD). whichever occurs first. i

  • During power escalation at the beginning of each cycle, power level imay be increased until a power level for extended operation has been achieved and a power distribution map obtained.

. ) CALLAWAY - UNIT 1 3/4 2-6 Amendment No. ?#. 44 r

n. iA) '_ ' ,.[ u.c r <l '. POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS'(Continued) l 4.2.2.2 (Continued) e. ' With measurements indicating maximum [ overz(Fh(z)_ g(z) .has increased since thei previous determination.of Fg (z), either i M of the following actions shall be taken: M Q (z) shall be increased by 2% over that specified in. 1. F Specification 4.2.2.2c., or MQ(z)shallbemeasuredatleastonceper7EffectiveFull 2. F Power Days until two successive maps indicate that ""*f*r is not increasing. ,y f. With the relationships specified in Specification 4.2.2.2c. above not being satisfied: -)' 1.. Calculate the, percent-Fg(z) exceeds its limit by the following o 2 expression: (max, over z of F((z) x~ W(z) N )-1 x 100 for P y_ 0.5 3 are

  • K(z) l-y Q

.c (ma. 2 of Ff (z) x W(z)NO )-1 x 100- for P < 0.5 1

2. Z x K(z) 6 BT o

2. Either one of the following actions shall be taken: (a) Comply with the requirements 'of Specification 3.2.2 for-Fg(z) exceeding its limit by the percent calculated above, or (b) Verify that the requirements of Specification 4.2.2.3 for. RESTRICTED AFD OPERATION are satisfied and enter RESTRICTED AFD OPERATION. 9 The limits specified in Specifications 4.2.2.2.c., 4.2.2.2.e., and 4.2.2.2.f. above are not applicable.in the following core plane f regions: 1. Lower core region.from 0 to 15%, inclusive. i 2. Upper core region from 85 to 100%, inclusive. CALLAWAY - UNIT l 3/4 2-7 Amendment No. @, 44 L l

q m x y." 7 ~*j-POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.3 RESTRICTED AFD OPERATION (RAFDO) is permitted at powers above APLND if the following conditions are satisfied: L a. Prior to entering RAFDO, maintain THERMAL POWER above APLND and'less than or equal to that allowed by Specification 4.2.2.2 for at least the previous 24 hours. Maintain RAFD0 surveillance (AFD within-HH6 Ms- /w/s sp,c/hr./ Of t:r;;t flen diff;r::::) during this time period. RAFD0 is then APLgd providing THERMAL POWER is maintained between APLND and-per -in A co t.4 or between APL D and 100% (whichever is more limiting) and N F0 XYrYtillance is maintained pursuant to Specification 4.2.2.4. APLWW is defined as: w APLRAFD0 = minimum x K(z) x 100% l. ~ ,7 M(g)xg(g) over z FD0 F5(z)'is the measured F (z) increased by the allowances for where: Q manufactuFing) tolerances and measurement uncertainty. The Fg limit pe I s & j a si,e,.1,. Figui. 0.2-2. W(z)RAFD0 is the cycle l '. p dependent function that accounts for limited power distribution transients encountered during_RAFDO.$ Thi: functi:n +:r given in the P : kin; bF::t:r Limit 4 Report as per gl fi cation ' 6.9.1.9. ,,Q Cort opom Af eb and tJOUngpo a re b.- During RA , if the THERMAL POWER i decreased below APL N then the conditions of 4.2.2.3.a shall be satisfied before re-entering RAF00. 4.2.2.4 During RAF00, F (z)'shall be evaluated to determine if F (z) is Q Q within its limits by: a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER above APLND, b. Increasing the measured Fg(z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. c. Satisfyin e following relationship: (z) 5, b x K(z) for P > APLND P x W(z)RAFD0 giv:rf.:(z)isthemeasuredFg(z). F The F limit is -l g# where: 9 f(a), i: Figur: 2.2 2. P is the-relativ THERMAL POWER. RAF00 g g. bce),M - a is the cycle dependent function that accounts for limited power distribution transients encountered during RAFDO. -This functi:n i: given in the "::hing F::t:r Limig Report as per Specification 6.9.1.9. L og O' CALLAWAY - UNIT 1 3/4 2-7(a) Amendment No. JA, 44 i <+

_ ~. .~ e ..- 3 . / 'POWERDISTRIBUTIONLIMiTS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.4 (Continued)' Measuring F$(z) in conjunction with target flux difference determi-d. nation according to the following schedule: 1. Prior to entering RAFD0'after satisfying Section 4.2.2.3 unless a full core flux map has been taken in the previous 31 EFPD'with the relative thermal power having been maintained N above APL u for the 24 hours prior to mapping, and

2. -

At least once per 31 Effective Full Power Days. e. With measurements indicating 3 maximum Fh(z) 1 ver z. _ (g) _ g - has' increased since the previous determination of Fl(z) either of. the following actions shall be taken: Fh(z)shallbeincreasedby2percentoverthatspecifiedin 1. A 4.2.2.4.c, or-M s0c(cessivemapsindicatethatFn z) shall be measured at least onc 2. Fh(z)' is not increasing. maximum over z g 1 f. With the relationship specified in 4.2.2.4.c above not being j. satisfied, comply with the requirements of Specification 3.2.2 for'F (2) exceeding its limit by the percent calculated with the Q i.' following expression: (max. over z of Fh(z)xW(z)RAFD0 )-1 x 100 for P y. APLND F p P H g. The limits specified in 4.2.2.4.c. 4.2.2.4.e and 4.2.2.4.f above 1 are not applicable in the following core plane regions: 1. Lower core region from 0 to 15 percent, inclusive. l. 2. Upper core region from 85 to 100 percent, inclusive. 4.2.2.5 When Fo(z) is measured for reasons other than meeting the re n) ments of Speciffcation 4.2.2.2 or 4.2.2.4, an overall measured Fg(z) quire-shall be .(d obtained from a power distribution map and increased by 3% to account for manufacturing: tolerances and further increased by 5% to account for measure-ment uncertainty. j .CALLAWAY - UNIT 1 3/42-7(b) Amendment No, M *44 i

n. 7 m fp g ' POWER DISTRIBUTION dMITS b ). '3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - Fh 1 -LIMITING CONDITION FOR OPERATION l l< 3.2.3_ Fh shal,1,be limited by the followig relations)ip: j G: The L /,wH d bro 7m " V; fin . ffy Fh 1 t-5+ (l' + 4+ (1-P)) f,g g. G re) sf < e/ 4 < d <w y o,.+ w.s n.~ es ~ b THERMAL POWER /6u h rA, / b A + / W N/r 'e r "M 4e Q" spreid*d A +O caA. Fh = Measured values of Fh obtained by using the movable incore ~ detectors to obtain a power distribution map. The measured-values. of Fh shall be used since'an uncertainty of 4%-for incore measurement of Fh has been included in the above limitl ~ A_PDLICABILIT_Y: MODE 1 1 ACTION: WithFh.exceedingitslimit: a.~ Within 2 hours either: Restore the Fh to within the above limits : or 1.- ~ Reduce THERMAL POWER TO LESS~ THAN 50%'of RATED' THERMAL 2. 4 U . POWER and reduce the Power Range Neutron Flux-High Trip Setpoint to 155% of' RATED THERMAL POWER within the next 4 hours. j . Demonstrate through -in-core flux mapping that Fh is within [ b.- !~ its limit within 24 hours-after exceeding the limit or reduce ' THERMAL POWER to less than 5% of ' RATED THERMAL POWER within the next 2 hours, and c. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER:above the reduced limit required by a or b, above; subsequent POWER OPERATION may pro. seed provided that Fh is demonstrated through in-core flux mapping to be 'within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and 4 within 24 hours after attaining 95% or greater RATED THERMAL I - POWER. CALLAWAY - UNIT 1 3/4 2-8 Amendment No. /ljt,44 r l 1:

' 'S ik 7g, ,V i-I ' REACTIVITY-CONTROL SYSTEMS. o BASES 1 l . MODERATOR TEMPERATURE COEFFICIENT (Continued .(f / The most negative MTC value equiv nt to the most positive moder tor 1 density coefficient (MDC), was obtai d by incrementally correcting t e MDC used in the FSAR' analyses to nomi operCing conditions.. These co ections involved subtracting the increm t 1. change in the MDC associated h a. core condition of all= rods inserted most positive MDC)-to an all rods ithdrawn condition and, a conversion fo the rate of change of moderator d sity with temperature at RATED THERMAL. WER conditions. This value of the DC was then transformed into the limiting TC value,4.1 : 10-' ch/k/*F. The MTC value

' 2.2 - 10 ' :.h/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and-is obtained by making these corrections to the limitingA MTC value. f 0.1 a 10 ' ek/k/"F.

E04-The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel-cycle are adequate to confinn that the MTC remains within its limits since this coefficient changes slowly due principally to the-reduction in RCS boron concentration associated with fuel burnup. 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average taperature less than 551*F. This ~ limitation is required to ensure: (1) the moderator temperatu're coefficient within its normal operating range (3)ge. (2) the trip instrumentation is is within its analyzed temperature ran the pressurizer is capable of.being in an OPERABLE status with a steam bubble. and (4) the reactor ves sel is aboy.e its minimum RT temperature. NDT n[ 3/4.1.2 BORATION SYSTEMS The Boration Systems ensure that negative reactivity control is available .during each MODE of facility operation..The components required to. perform this L function include: (1) borated water sources, (2) centrifugal charging pumps, E (3) separate flow paths. (4) boric acid transfer pumps, and (5) an eimergency power supply from OPERABLE' diesel generators. With the RCS average temperature equal to or greater than 350*F, a minimum of two boron injection flow paths are required to ensure single functional ~ capability in the event an assumed failure renders one of the flow paths . inoperable.. The Boration capability of either. flow path is sufficient to provide-a SHUTDOWN MARGIN from expected operating conditions of 1.3% ak/k after xenon l-decay and cooldown to 200'F. The maximum expected boration capability require-L - ment occurs at EOL from full power equilibrium-xenon conditions and requires 17,658 gallons of 7000 ppm borated water from the boric acid storage tanks or 83.745 gallons of 2350 ppm borated water from the RWST. With the RCS average l temperature less than 350'F, oly one boron injection flow path is required. E CALLAWAY - UNIT 1 B 3/4 1-2 Amendment No. 44 i

(

3: I A: [ 3/4.2 POWER' DISTRIBUTION tfMITS I y [ BASES

q' The specifications of this section provide assurance of fuel integrity p

-during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the minimum DNBR in the core-at or above the safety 3 1 analysis DNBR limits during normal operation and in short-term transients, and L (2) limiting the fission gas release, fuel pellet temperature, and cladding t [ mechanical properties'to within assumed design criteria. In addition, limiting 4 the peak linear power density during Condition I events provides assurance that' O the initial condi.tions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded. i 1 .i i The definition of certain hot channel and peaking factors as used in { these specifications are as follows: p, F(Z) Heat Flux Hot Channel Factor, is defined as the maximum local heat flux q on the surface of a fuel rod at core elevation Z divided by the average fuel' rod heat flux, allowing for manufacturing tolerances on fuel { pellets and rods; and '~ N FaH Nuclear Enthalpy Rise Hot Channel Factor, is defined.as the ratio of f 'the integral of linear power along the rod with the highest integrated 1 J power to the average rod power. '3/4.2.1 AXIAL-FLUX DIFFERENCE N N Opmfrm Law.4r9"depe-f - (00& .l ThelimftsonAXIALFLUXDIFFERENCE(AFD) assure.that.theFn(Z)upperbound. J envelopes of".02 end' 2.50 f;r OTA end "ANTA0

5. respectively, limes the normalized axial-peaking factor are not exceeded during either normal. operation
)

or in the-event of xenon redistribution following power changes. ~ Target flux difference is determined at equilibrium xenon conditions. The full-length rods may be positioned within the core in accordance with their e respective insertion limits and should be inserted near their normal position j' for steady-state operation at high power levels.- The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux: difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL -POWER levels are obtained by multiplying the RATED THERMAL' POWER value by-the appropriate fractional THERMAL POWER level. The periodic updating of'the. target ~ flux difference value is necessary to reflect core burnup-considerations. The limits on AXIAL FLUX DIFFERENCE (AFD) are given 0-Two modes of operation are permissible. One mode is Normal Operation, h;r: th:

ppli;;tle A'O limit i
d; fin;d by i;;;i'f::ti - 3.2.1.:. J'he AFD limit f:r thi:

t d: Of Op:r:ti r 1: : +3, 12% t:rg;t 5:nd :b :t th: t:rg;t fi n differ;;;;. After extended load following maneuvers, the AFD limits may result in restric-tions in the maximum allowed power to quarantee operation with F (Z) less than 1 Q its limiting value. To prevent this occurrence, another operating mode which u $ff$4W$ &f v ); .CALLAWAY - UNIT 1 B 3/4 2-1 Amendment No JJ, y,44 ] + ~.:T h. ~

u n I Y l POWER DISTRIBUTION LIMITS. [ BASES 3/4.2.1 ' AXI AL FLUX D!FFERENCE (Continued) ' " de k h.poci h n te Jh e dotA restricts the AFD to a relatively small target band and does not allow signif-icant changes-in poner level has been defined. This mode is called RESTRICTED, . AFD OPERATION, whicn restricts the AFD to e t3% t:rgd band : bout the ter;"lFD0 - flux diffenn:c and restricts poner levels to between APLNDandeitherAPj or 10M of FATED ThEF."AL FCWER, whienever is less. Frior to entering P.ESTRICTED AFD GPEFATION, a 24-hour waiting period at a power level (+21) above APL D and N belcw that allo.ted by Non al Operation is necessary. During tnis time period d Iced enanges ano c:r. trol roc m: tion are restricted to that allowed by the RESTRICTED AFD OFEFailDh prc:edars. After tns waitir.g peried, RESTRICTED AFD j I 0PERATION is permittee. Although it is intended that the plant will be operated with the AFD within the target band required by Soecification 3.2.1 about the target flux q difference, during rapid plant THEP?AL POWER reductions, control rod motion 4 will cause the AFD to deviate outside of the target band at reduced THERHAL l POWER levels. This deviation will not affect the xenon redistribution suffi-t factors which may be-reached on a l ciently to change the envelope of peaking (with the AFD within the. target band) i subsequent return to RATED THERMAL POWER provided the time-duration of the deviation is limited. Accordingly, a 1-hour l penalty deviation limit cumulative during the previous 24 hours is provided for operation outside of the target band but within the limit cf Figure 3.2-i-1 while at THERFAL POWER levels between 50% and 90% of RATED THE SAL POWER. For THERPAL POWER levels between 15% and 50% of RATED THERMAL POW R, deviations of i the AFD outside of the target band are len significant. Th penalty of 2 hours actual time reflects this reduced significance. syca.had in./ke coy Provisions for monitoring the AFD on an automatic basis are derived from i the plant process computer through-the AFD Monitor Alam. The computer deter-mines the 1 minute average of each of the OPERABLE excore detector outputs and a provides an alam message imediately if the AFD for.two or more OPERABLE excore 1 channels are outside the target band and the THERMAL POWER is greater than 90% i of RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% 1 and 90% and between 15% and 50% RATED THERMAL POWER, the. computer outputs an alarm message when the penalty deviation accumulates beyond the limits' of I hour and 2 hours, respectively. Figure B 3/4.2-1 shows a typical monthly target band. j 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHAlpY RISE HOT CHANNEL FACTOR j The limits on heat flux hot channel factor and nuclear enthalpy rise hot minimum DNBR are not exceeded, and 2) gn limits on peak local power density channel factor ensure that 1) the desi in the event of a LOCA the peak fuel clad temperature will not. exceed the 2200*F ECCS acceptance criteria limit. I CALLAWAY - UNIT I B 3/4 2-2 Amendment No. 15, 28 4 e i

i ( i j si -j POWER'0!STRIBUTION LIMITS ~ . ') ; _ BASES 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND-NUCLEAR ENTHAL'PY RISE HOT CHANNEL FACTOR (Continued) (12b%'for VANTAGE 5 fuel) and the appropriate fuel rod bow DNBR penalty (less I than 1.5% per WCAP-8691, Rev.1). The margin between design and safety analysis DNBR limits of 6.3% for Optimized fuel and 17.4% for VANTAGE 5 fuel includes l greater than 3%' margin for both Optimized fuel and VANTAGE 5 fuel for plant 1 design flexibility., 1 The hot channel factor F (z) is. measured periodically and. increased by a I cycle and heignt dependent power factor'ap repriate to eithe'r Normal Operation or RESTRICTED AFD OPERATION, W(z)NO or W z RAFDO. to provide assurance-that the limit on the hot channel factor, F (z), is met. W(z)NO accounts for the' q effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)RAFDO. accounts.for the more restrictive operating limits required by ' RESTRICTED AFD OPERATION which result in less severe transient values. The W(z)' functions are provided in the "::hhg F;ct;r Limit Report per Specifica-tion'6.9.1.9. hor. Operafy Y Provisions to account for the possibility of decreases in margin to the FQ(z) i limit during intervals between surveillances are provided. Any decrease in -the minimum margin-to the FQ(z) limit compared to the minimum margin determined from the previous flux map -1s determined by comparing the ratio of: .i maximum Fl(z)- over z g(g) . taken from the current map to the same ratio from the previous map. The ratios r i to be compared from the two flux maps do not need to be calculated at identical D z locations. Increases in this ratio indicate that the minimum margin to the l F (2) limit has decreased and that additional penalties must be applied to the Q measured F (z) to account for further decreases in margin.that could occur L Q before the next-surveillance.. More frequent surveillances may also be-substi-tuted for the additional penalty. 3/4.2.4 QUADRANT POWER TILT RATIO i The QUADRANT POWER TILT RATIO limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis. l Radial power distribution measurements are made during STARTUP testing and periodically during power operation. The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A l CALLAWAY - UNIT 1 B 3/4 2-5 Amendment No. 15,28,44 ... w __ ,n-

v. 1' 6 ' ADMlHISTRATIVE CONTROLS L r:=:= =d L:":T n:= The Wiz) functions for Normal and RESTRICTED AFD OPERATION 9.1.9 ad ND (as required) shall be established for at least each r ! c' ' - va or APL The ts shall 11 be maintained available in the Control Room. be establishe nd' implemented on a time scale consistent wi ormal proce-core an ggf dural changes. 7 g f _ The analytical: cethods use generate the W( unctions and APLI D shall be those previcusly _ reviewed and ap ved by NRC*. If changes to these e evaluated in accordance with r'ethods are des: ed necessary, they w ied and approval prior to their 10 CFR 50.59 and submitted to the "... for use if _the change is determi to involve' an viewed safety question or if such a.cnznge would r tre amendment of previou submitted documentation. i A report contai ' g the W(z) functions, as a function of cor eight (and icable) and APLHD shall be provided to the NRC Do nt Control burnup, ifcopies to the Regional Administrator and the Resident Inspe r Desk '~ n 30 days of their implementation. w SPECIAL REPORTS Special Reports shall be submitted to the Regional Administrator ~ of the 6.9.2 -NRC Regional Office within the-time period specified for each report. 6.10 RECORD RETENTION _ In addition to the applicable record retention requirements of Title _10, Code of Federal Regulations, the following records shell be retained-for at least the minimum period indicated. 6.10.1.The following records shall be retained for at least 5 years: Records and logs of unit operation covering time interval at each a. power level;- Records.and logs of principal maintenance activities, inspections,- b. repair and replacement of principal items of equipment related to nuclear safety; c. All REPORTABLE EVENTS; Records of surveillance activities; inspections and calibrations d. required by these Technical Specifications;

  • WCAP-8385, " Power Distribution Control. and Load Following Procedures,"

WCAP-9272-A, " Westinghouse Reload Safety Evaluation Methodology." and WCAP-10216-P-A, " Relaxation of Constant Axial Offset Control / Fg Surveillance Technical Specification." CALLAWAY - UNIT 1 6-21 Amendment No. 26 =~

.~I
r q

b h JN_ SERT B_(ADD TO PAGE 6-21}_ CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating-limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for-the following: a. Moderator-Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 1 3/4.1.1.3,_ i i b. Shutdown Bank Insertion Limit for-Specification 3/4.1.3.5, i c. Control Bank Insertion Limits for Specification 3/4.1.3.6, d. Axial. Flux Difference. Limits, target band, and APL" for Specification 3/4.2.1, HeabDFlux Hot Channei Factor, F K(Z), W(Z)NO' c. AFL and W(Z)RAFDO f r Specifibation 3/4.2.2, f. Nuclear Enthalpy Rise Hot Channel Factor, F and Power Factor Multiplier, PF limitsforShSc,ification AH, 3/4.2.3. The analytical methods used to determine the core operating l limits shall be those previously reviewed and approved by the .1 NRC,-specifically those described in the following documents. 1 a. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (W Proprietary). j 'i (Methodology for. Specification 3.1.1.3 Moderator i Temperature Coefficient 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limit, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor). 3 i b. WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983-(W Proprietary). (Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodolgy for W(Z) surveillance requirements).

1 s-3 i c.- WCAP-10266-P-A, REV. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH-CODE", March 1987 (W Proprietary). (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor). The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core ' thermalhydraulic. limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. i

1 .,y s-s3

-prJ.

ULNRC ':- s q;lii(;' 1.'

Attachment 4 MJgj;f, n-M-. i..

4 t 4 gA.. 4 .,jp-:- praft Core = Operating Limits' Report' i.I r -. '1s1 ^. + 8 i' ,f.'". 1 4 i r 3 / \\. 'N. 4 2 .b, e I 4 5? i N 4- 'b [l- 'l_" 3,.. ' 4

q:, y. ,1 . _s':', 1: OJ ^. 6, Callaway Cycle'5 Rev. 0.

j b'
  • s i

1 'CALLAWAY CYCLE 5 CORE OPERATING LIMITS REPORT September 1, 1990 i i-) 1 e 1 3 fl i ? -? i 7 1 Page 1 of 15 5 f I' k i m

T@. '; ;' ~' t P ~ .Callaway Cycle 5' Rev. 0 1.0' CORE OPERATING LIMITS REPORT- -This' Core Operating Limits Report (COLR) for Callaway Plant' Cycle 5 has been prepared in accordance with the requirements of Technical Specification ~6.9.1.9. The Core Operating Limits affecting the following ~ Technical Specifications are included in this report. t 3.1.1.3 Moderator Temperature Coefficient 3.1.3.5 Shutdown Rod Insertion Limit l 3.1.3.6 Control Rod Insertion Limits 3.2.1-Axial Flux Difference 1 3.2.2 Heat Flux Hot Channel Factor 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor .1 Page 2 of 15

o e" r Callaway Cycle 5 Rev. 0 2.0 OPERATING LIMITS The cycle-specific parameter limitt for the -specifications listed in Section 1.0 are presented in the subsections which follow. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.9. 2.1 Moderator Tamnerature coeffiqignt (Specification 3.1.1.3) 2.1.1 The Moderator Temperature coefficient shall be less positive than the limits shown in Figure 1. These limits shall be referred to as the Beginning of Cycle Life (BOL) Limit. The Moderator Temperature Coefficient shall be less negative than -41 pcm/'F. This limit shall be referred to as the End of Cycle Life (EOL) Limit. 2.1.2 The MTC 300 ppm surveillance limit'is -32 pcm/'F (all rods withdrawn, Rated Thermal Power condition). Page 3 of 15 i

x I FIGURE 1 l MODERATOR TEMPERATURE COEFFICIENT VS POWER LEVEL l T_...__.._.... 7,......................................................................a,

4..

7.. 4. mm en.................... <......., g a........... L. 1 5,70% 5.. 1. 4 t.. ..............i 5 2 3 t33...................................................................... r-- - -1 AOCEPTABUE OM5WION ........ !. \\ w.. ................ = 8 l l .i .l j. j. j,.............g......g......,......f....................,......g.. ...g,, j

3..

.l i 1 .I

g.....................................................................

..f -' '- 7 '~~' ' ~"'P -'~ l - ' - l -'~' ~' T - r-- T" ' ' ' ' I T-' I Il 20 ll il 50 il 70 Il il 100 % OF RATED THERMAL POWER PAGE 4 0F 15

t Callaway cycle 5 Rev. 0 2.2 Shutdown Rod Insertion Limits (Specification 3.1.3.5) The shutdown rods shall be withdrawn to at least 225 steps. 2.3 control Rod Insertion Limits (Specification 3.1.3.6) The Control Bank Insertion Limits are specified by Figure 2. t I e 9 I l i Page 5 of 15 1

t3' J 'y b ^ s FULLY WITHORAWN (T25 ste;s or hisher) 225 ,'i2 E Q E 22 43 TAW 2d 220I j =j 200 1 / / L. /my-j_ + 180 / f i-/ / ~

O W Stk I SO ' D5A B%--

s ~ g f 4

___l, j-f' "

i 140-f =;.xx c y

~.

g ~~ ~ F 120-g f.-- e g 9 100_ j ,.f J 1 O 80; .f /= ~~ e, A M i w E 60 L_. / ,f a l E 40 / 20-l ~ i3Gd %9 00 20 40 60 80 100 FULLY INSERTED RATED THERMAL POWER (Percent) FIGURE 2 ROD BANK INSERTION LIMITS VERSUS RATED THERMA'L POWER - FOUR LOOP OPERATION CALLAWAY - UNIT 1 1 Page 6 of 15 .___--___-____--______-_-_______________--_____--_____--__-_-__2

-6 ( Callaway Cycle 5 Rev. 0 2.4 Arial Flux DifferenER (Specification 3.2.1) 2.4.1 The Axial Flux Dif ference (AFD) target bands

are, a,

+3%, -12% for Normal Operation b. 13% for Restricted AFD Operation t ?. 4.2 The Acceptable Operation Limits are shown in Figure 3. 2.4.3 The minimum allowable power lggel for Restricted AFD Operation, APL is 90% of RATED THERMAL POWER. Page 7 of 15

f I' 6 4 l ~ i ARIAL PLIE DIFFEMME LIIIITl A8 A I PIECitti W R475 TIESI4L MlER t I l i s. i t [ g g 3'I 1 11 1 M I 4j l ~ g 4 rj ', "0"i f l si: .r, 2 m;

2

i is i ;i, "'l '1 ...i i 2 f M i i-Ir i: 1 + I See . ~, 21 -{ = - t N l m 1 i,

n =E h h_ x,= 1 + EE _=_; _dEE2 g

=c. _.. z. - p E :- = = = =.

f. {. ' :.^ : -~% ~^ : ^.C= 0 5-

'7 I u.R.E.__-RE!75ws==c@=a,is_ 55EE!_=MW=9 r. ._-L __ =... - J g ; = ~'---- T ~X '=:=: = a- ---= r.:1 ~.-.L--~7-=;;.35= -=.-_c-.= g ___--.----d a - - f-- _ - 24- =- rwEE 2 . g+

== i c a l E5.h b 5. =- - h -5 _ E i

  • +1K 6hM]/5E~~~- =EEEE 5 ~5I$~~~ ~=*]=====0 55 1

1.N Ed =.. ~-~ s_ _. !_5_1_-~~~ 5 b-~555 =r= E23- --d== . z : r m-r = =--- r = = - :- _ GEE =2,b==r=E==a i. 5 iE:: I =m:u.__.__ E ggClimii.. fi[;:Ei:?!! cfiRE5F._iEEEN. ; f.i:._ I E3 e :. : . i.: '-----.7 ~ :'.. .[. ... -. _._ _, _ ; ; ;, 7, - - ;.- !'~-

,_ ; n;- ;

2[ - - ~; 2 7 L - 7-- . :. :.= j. ~ t L 7~...~.:.:- . n: . f-e ,.1-1 ~~E j y . y 2 l, .n ~ f ~ 1 ---- II 3 t _3 n -4 ~;_[.:~ ..-U.:; -l

. :: q:.;

.--:=,. '.m .a 3 3 .ie e 10 3 m.ux owanance tanW CALUN4Y - UNIT 1 PIGURE 3 Page 8 of 15

[i i 4 4 c; e Callaway Cycle 5 Rev. O t 2.5. Heat Flux Mot channel Factor - F (Z) 9 (Specification 3.2.2) RTP [ y F (Z) $ S---

  • K(Z) for P > 0.5

~ g P RTP F -F (Z) 5 9---

  • K(Z) for P 5 0.5 i

g 0.5 I THERMAL POWER ~ where P = ------------------- RATED THERMAL POWER i 2.5.1 F RTP = 2.50 g 2.5.2 K(Z) is provided in Figure 4. 2.5.3 The W(z) functions that are to be used in Technical Specifications 4.2.2.2, 4.2.2.3, { and 4.2.2.4 for F surveillance are shown in q Figures 5 through 8. Because significant margin exists between the analytically determined maximum F z)*P l valuesandtheirlimit,Restrictah(Axial,hlux Difference (RAFDO) operation is not expected i to be required for Cycle 5. For this reason, no W(z)RAFDO values are supplied for Cycle 5. t The Normal Operation W(z) values, W(z) have been determined for three specifiUO' burnups in Cycle 5. This permits determination of W(z) at any cycle burnup through the use of three point interpolation. Thew (z)UherateswiththeCAOCstrategyand values were determined assuming cycle 5 uses a +3%, -12% delta-I band about the i target flux difference. Also included is a W(z)$21 Cycle 5 burnups. function that bounds the W(z) curve for Use of the W(z)$O curve will be conservative for any cycl 5 burnup, however additional margin may Page 9 of 15

h 1 I i i FIGURE 4 i K(Z)- NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT n g,g.r......'*..........-..'...-..........-.'-...,......................=..'........... ~~ - g,g.............s................. j 4 1.0,6 a .0. 0.9-s. s '.o.93,12 I 3 1 4 0.8 4 l O.7-1 8. t 0.6............. q q t 0.5-.s.i>$<.- l o,4 g,3 ......,.....s.... .....e..... .....s........... .....s........... 4 0.2 ' 1. 0.1 ' s - c - s'*.' rr 0.0 riI T' i ' i 'i'T' i ' i i ' i i i i 0 1 2 3 4 5 6 7 8 9 10 11 12 l ? I CORE HBGHT (FT) PAGE 10 0F 15 W 4 r

I r 8 MSIGHT SQL (F557) W(Z1 e 0,00 1,0000 4 I

  • .C.25 1.0000 e 0.50 1.0000 1.30
  • 0.75 1.0000 1.00 1.0000 4

1.25 1.0000 j 1.50 1.0000 1.75 1.0000 i 2.00 1.1968 2.25 1.1927 j 2.50 1.1890 1 1.25 2.75 1.1845 l 3.00 1.1792 3.25 1.1738 1 3.50 1.1982 3 75 1.1957 l 4.00 1.1818 4.25 1.1567 1.20 4.50 1.1510 J 4.75 1.1445 y 5.00 1.1375 1 5.25 1.1297 i r 5.50 1.12t3 g 5,75 1.1102 8,00 1.1059 Q N t.25 1.1125 [ 1.i5 g 8.50 1.1174 w 3 3, .8.75 1.1211 7.00 1.1232 7.25 1.1238 7.50 1.1223 g-m w H 7.75 1.1101 7L M 8.00 1.1139 1.10 8.25 1.1067 x 8.50 1.0974 "]L,. 8.75 1.0897 s 00 1.0853-3.25 1.0818 9.50 1.0811 0.75 1.0812 l '10.00 1.0801 08

  • 10.25 1.0000

.+

  • 10.50 1.0000
  • 10.75 1.0000
  • 11.00 1.0000
  • 11.25 1.0000
  • 11.50 1 0000
  • 11.75 1,0000-1._______.

e 12.00 1.0000 0 2 4 6 8 10 12 CORE HEIGHT (FEET) FIGURE 5 Callaway Unit 1 Cycle W(z), at 150 MWD /MTU i e Top and Settes 15% Smeluded as per Tech Spec 4.2.2.20 i Page 11 of 15 i- -, - - - - ~, - ~ - - ~ - - - ~ ~ ~ ~ ~ -

i e i l I f HEIGHT MOL (FEET) Wi21 1 a 0.00 1.0000

  • 0.25 1.0000

-)

  • 0.50 1.0000
  • 0.75 1.0000 1.30 1.00 1.0000 i

a 1.25 1.0000 f a 1.50 1.0000 = 1.75 1.0000 l 2.00 1.2053 2.25 1.20C2 2.50 1.1941 1.25 2.75 1.1871 3.00 1.1789 3.25 1.17C9 3.50 1.1535 3.75 1.1878 ~! .1535 4.00 4.25 1.1485 3L 4.50 1.1431 i 1 20 y 4.75 1 1358 A 5.00 1.1285 5.25 .%1217 l 5.50 1.1128 5.75 1.1075 I M 5.00 1,1113' Q N 5.25 1.1188 1.15 5.50 1.1238 e 3 M 5.75 1.1277 l A 7.00 1.1295 i g ,g 7.25 1.1297 w 7.50 1.1278 ^ 7.75 1.1238 w,, 8.00 1.1177 g a 1.10 0.25 1.1095 i w 8.50 1.1002 t ^ 8.75 1.0022 1 3t7, Z 9.00 1.0857 S.25 1.0807 [ 5.50-1.0803 B.75 1.0811 e ( 10.00 1.0808 l 1_ 1.05

  • 10.25 1.0000
  • 10.50 1.0000
  • 10.75 1.0000
  • 11.00 1.0000 a 11.25 1.0000

(,

  • 11.50 1.0000
  • 11.75 1.0000 l

1 _________

  • 12.00 1.00C0 r,

(. 0 2 4 5 8 10 12 BoTTW CORE HEIGHT (FEET) FIGURE 6 Callaway Unit 1 Cycle W(z)g, at 8000 MWD /MTU i

  • 7ep and letten 151L Excluesel as per Tech Spec 4.2.2.20 l

Page 12 of 15 1'

. q o. j I HEIGHT ECL (FEET) Wi 2 ) 0.00 1.0000

  • 0.50 1.0000
  • 0.25 1.0000-
  • 0.75 1.0000 J

1.30 1.00 1.0000 1.25 1.0000 1.50 1.0000 -l 1.75 1.0000 t 2.00 1.2419 2.25 1.2277 2.50 1.2117 1.25 2.75 1.1938 u 3.00 1.1757 2.25 1.1838 t 3.50 1.1501 i ^ 3.75 1.1584 l 4.00 1.1957 4.25 1.1525 1 4.50 1.1485 i*20 x 4.75 1.1437 3 5.00 1.1381 1 5.25 '1*.1314 at 5.50 1,1344 5.75 1.1494 .I L JNY 5.00 1.1944 I Q "aly if x e.25 1.1s07 1.15 I m ^X x g 5.50 1.1947 s.75 1.iss2 " J lt 7.00 1.1853 + 7.25 1.1918 7.50 1.1557 ? 7.75 1.1470 5.00 1.1357 a 1.10 8.25 1.1219 j a dl 8.50 1.1050 i ya 4.75 1.0888 a 0.00 1.08B3 9.25 1.0858 9.50 1.0480 9.75 1.0926 10.00 1.0963 8 1.C5 . 10.25 1.0000

  • 10.50 1.0000
  • 10.75 1.0000
  • 11.00 1.0000
  • 11.25 1.C000
  • 11.50 1.0000 1 _________
  • .11.75 1.0000
  • 12.00 1 :::

I O 2 4 6 8 10 12 i CORE HEIGHT (FEET) t FIGURE 7 1 Callaway Unit 1 Cycle t W(z), at 19140 MWD /MTU i e Top and letten 15% Suctueed as per Tech Spee 4.2.2.20 Page 13 of 15

q r

~

O ; b ) e l-4 l l HEIGHT max (FEET) W121

  • 0.00 1.0000 l
  • 0.25 1.0000
  • 0.50 1.0000
  • 0.75 1.0000 1.30 1.00 1.0000 1.25 1.0000 e

1.50 1.0000 I 1.75 1.0000 2.00 1.2418 2.25 1.2277 2.50 1.2119 1.25 2.75 1.1938 3.00 1.1796 3.25 1.1749 3.50 1.1703 A 3.75 1.1980 4.00 1.1618-l 4.25 1.1567 l 4.50 1.1510 l 1.20 4.75 1.1445- ) 5.00 1.1381 ) i-5.25 .h1315 5.50 1.1344 " X 5.75 1.1484 I JXN S.00 1.1544 l r N jg-X 5.25 .1.1007 U. 1.15 8.50 1.1847 x g g .75 i.i. 2 Q ll 7.00 1.1853 7.25 1.1918 i w 7.50 1.1957 z 7.75 1.1470 a 8.00 1.1357 8.25 1.1219 O ^ dl 8.50 1.1000 t gm 8.75 1.0988 e 9.00 1.0883 9.25 1.0858 9.50 1.0880 9.75 1.0328 10.00 1,0883 a 1.05 e 10.25 1.0000 l

  • 10.50-1.0000 1

= 10.75 1.0000 e 11.00 1.0000 e 11.25 1.0000 l e 11.50 1.0000 a 11,75 1,0000 1 :22:2Z :: 2222222 ' 12.0C 1,0000 O 2 4 6 4 10 12 1 BOTTOM CORE HEIGHT (FEET) FIGURE 8 l Callaway Unit 1 Cycle Bounding W(z)g, for Cycle .g e Top and Bettes 15% Exclusse as por Tech Spec 4.2.2.26 i Page 14 of 15 l _ -. _.. _. ~.. - -,.... _ _... _ _... _.... _ _ _.. -...

s s. .., = ~f '" I f t : callaway cycle 5 Rev. O i I be gained by using the burnup dependent W(z)NO values. The W(z) values are provided for 73 axial points assuming the core height boundaries of 0 and 12 feet and intervals of.167 feet i between the core boundaries. 2.6 Nuclear EnthalDV Rice Hot Channel Factor - F N l! (Specification 3.2.3) ON F g5F.6H (1 + PFjg(1-P)) } i.; where: THERMAL POWER p. -----.........___._ RATED THERMAL POWER ![ RTP 2.6.1 F = 1.59 gg 33 - 0.3 2.6.2 PF

t r

I l;;[ ?:, 7 U k, E T v. c 0 t':at Page 15 of 15 i ii n i.s g. t 9}}

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