ML20094E512

Proposed TS Table 2.2-1 & Sections 3/4.2.1,4.2.2.2 Through 4.2.2.4 & 6.9.1.9 Re Relaxed Axial Offset Control

ML20094E512
Person / Time
Site:	Callaway
Issue date:	01/14/1992
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20094E511	List: ML20094E500 ML20094E512
References
NUDOCS 9201240187
Download: ML20094E512 (23)

Text

. .

ULNRC-2546 ATTACHMENT FOUR PROPOSED TECIINICAL SPECIFICATION REVISIONS FOR RELAXED AXIAL OFFSET CONTROL (RAOC)

PAGE S2CTION DESCRIPTIQN 2-8 2.2.1 Change in negative value for Table 2.2-1 the OTDT setpoint f1(delta-I) l penalty term.

3/4 2-1 3/4.2.1 Change from CAOC to RAOC, 3/4 2-2 AFD Insert A.

3/4 2-2(a) 3/4 2-6 4.2.2.2-4.2.2,.4 Changes to implement RAOC, 3/4 2-7 F Surveillances 0

Inserts B-F.

3/4 2-7(a) 3/4 2-7 (b)-

6-21 6.9.1.9 Change from CAOC to 6-21a. RAOC, Insert G.

B 3/4 2-1 B 3/4.2.1 Change to AFD Bases, Insert H.

B 3/4 2 ( B 3/4 2-3 I

l I

L L

l 9201240187 920114 PDR I

P ADOCK 05000483 PDR l

~

!v 'v' ,

1 TABLE 2.2-1 (Continued) h TABLE NOTATIONS (Continued)

G s

NOTE 1: (Continued) ,

I' 588.4*F (Referenced T,yg at RATED TilERML POWER); l

z M K3

= 0.00116; P = Pressurizer pressure. psig; .,

i P' = 2235 psig (flominal RCS operating pressure);

S = Laplace transform operator, s 1; and (3(al) is a function of the indicated difference between tog and bottom detectors of the power-range neutron ion chanbers; with gains to be selected based on measured instrument

'P response dering plant STARTUP tests such that:

• o' 4.of, (1) for qt -9 b betweenV-MG and + 61, fg(AI) = 0, where qt and q are percent RATED TilERMAL l POWERinthetopandb6ttomhalvesofthecorerespective1f.b and gg + qb is total tiler!!AL POWER in percent of RATED Ti!ERilAL POWER; l

(+ -[4 dr nure neyNye & -24*/s, -l (11) for each percent that" myitM: ef q - gg-mccc& ?E L the ATiTrip Setpoint shall j J

g be automatically reduced by 1.0! Q f its value at RATED TilERHAL POWER; and l e 3.2S% .

y (111) for each percent that the magnitude of qt -9b exceeds +6%g the AT Trip Setpoint shall .

" be automatically reduced by 1.89% of its value at ilATED THERMAL POWER. l

.N t*

U fl0TE 2: The channel's maxinasm Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3%'

• y of AT span. ,

m ,

k' i  %

I' 9

. t

fEA. A CE ff/Z7?t' 3/4.2 POWER DISTRIBUTION LIMITS ZMfdE4 f A .

3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.

1 The indicated AXIAL FLUX DIFFERENCE (AFD) nhall be maintained with th target band (flux difference units) about the target flux difference as spec fied in the Core Operating Limits Report (COLR).

The ind 4ated AFD may deviate outside the applicable required targe band at l greater t an or equal to 50% but less than 0.9 APL N D** or 90% of R ED l

THERMAL Pa rR, whichever is less, provided the indicated AFD is thin the Acceptable l eration Limits specified in the COLR and the cumul ive penalty deviation tim does not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 urs. l

\ l The indiented A may deviate outside the applicable requir d target band at greater than 15% t less than 50% o' MTED THERMAL POWEP rovided the cumulative penalty eviation time does not exceed I hour during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, l

APplICABIL ITY: MODE 1, bove 15% of RATED THERMAL WER*,#

ACTION:

a. With the indicated D outside of t e applicable required taroet band and with THERMAL POWER great than or equal to 0.9 APLND**

}

or 90% of RATED THE minutes, either:

POWER, w ichever is less, within 15

1. Restore the indicated D to within the applicable required target band limits, o

• See Srecial Test Exception pecification 10.2.

1. Surveillance testing of pne Power .tnge Neut on Flux channel may be perfortned pursuant to pecification 4.3.1.1 p vided the indicated AFD is maintained within e Acceptable Operation L mits specified in the COLR and THERMAL PO R <APLN0*** . A total of 16 ours operation may be accumulated with t AFD outside of the applicable required target band

.during testing w hout penalty deviation.

• • APL"O is the m' imum allowable power level for RESTRI ED AFD OPERATION and is specif ed in the Core Operating Limits Report pe Specification 6.9.1.9. l NO "

• • • APL is qual to the minimum F g

K(Z)

• 100 over Z , F"(Z)

• W{Z)N0 <

aa 3

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

_)

ALLAWAY - UNIT 1 3/4 2-1 Amendment No. 29, AA, 5 y

$E/kACE k)17W POWER OISTRIBUTION L'MITS N LIMITING CONDITION FOR OPERATION N (Continued)

2. Reduce THERMAL POWER to less than 0.9 APLND** or 90% RATED THERMAL POWER whichever is less, and discontinue STRICTED FD OPERATION (if applicable).

b. With the 4dicated AFD outside of the applicab) required target band for mor thar. I hour of cumulative pen (ty deviation time during the pre us 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outside e Acceptable Operation Limits specified the COLR and withf ERMAL POWER less than 0.9 APLIg,,l or 90%, whichever is ss, but equer, to or greater than 50% of RATED THERMAL POWER reduce:

1. THERMAL POWER to less M 50% of RATED THERMAL POWER within 30 minutes, and

2. The Pos,er Rap Neutron Flux-Hig Setpoints to less than or equal to , of RATED THERMAL POWER' ithin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c. With the dicated AFD outside of the applica required target band f more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative penalty a iation time during the revious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER less (thap 50% but eater thar.15% of RATED THERMAL POWER, the THERMAL POWTR shall not be increased equal to or greater than 50% of RATED THERMAt POWER x

)- until the indicated AFD is within the applicable required ta t band. ,

f SURVEILLANCE REQUIREMENTS _

4.2.1.1 The indicated AFD shall be detemined to be within its limits during POWER OPERATIONSo* above 45ta/oof RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore channel:

1. At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and

2. At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter restoring the AFD Monitor Alam to OPERABLE status,

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once pe. hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AFD Monitor Alam is inoperable. 'he logged values of the indicated AFD shall be assumed

, to exist duri .9 the interval precedir.g each logging.

CALLAWAY - UNIT 1 3/4 2-2 Amendment No.18, 58

INSERT A 3 ,2 . 1- The indicated AXIAL FLUX DIFFERENCE-(7.FD) shall be maintained within:

a. the allowed operating space as specified in the CORE OPERATING LIMITS REPORT (COLK) for Relaxed Axial Offset Control (RAOC)-operation, or

b. the target band specified in the COLR about the target flux difference during RESTRICTED AFD OPERATION (RAFDO).

APPLICABILITY: Mode 1 above 50% of RATED THERMAL POWER.*

ACTION:

a. For RAOC operation with the indicated AFD outside of the limits specified in the COLR,

1. Either restore the indicated AFD to within the COLR limits within 15 minutes, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. For RAFDO above APL ND** with the indicated AFD outside of the applicable target band about the target flux difference:

1. Either'rectore the indicated AFD to within the COLR specified target band limits within 15 minutes, or-

2. Reduce THERMAL POWER to less than APL and discontinue RAFDO witi,'ia 30 minutes, s-

c. THERMAL POWER-shall not be increased above 50% of RATED

~

THERMAL POWER unless the-indicated AFD is within the L limits:specified in the COLR.

i *

-See-Special Test Exception 3.10.2.

t APL is the minimum allowable (nuclear designs power level for RESTRICTED AFD OPERATION and is specified in the COR2 OPERATING LIMITS REPORT per Specification d.9.1.9.

i

._-m. ._ _ . . . _ . . ._ . - . _ _ _ _ _ _ _ ~

POWER DISTRIBUTION LIMITS

)' SURVEILLANCE REQUIREMENTS

//mr/r

-4.2.1.2 The indicated AFD shall be considered outside of itsYt:rget b:nd wnen 4/. /esuf two **-meme. 0PERABLE excore channels are indicating the AFD to be outside the //,,t/r, H target 5:nd._ Pen:lty d:viction cutt 4d Of th; :beve required t+rget band

h;l' be accu eleted er a time b::i: Of'

e. On minut; p;n:lty devietien fer e&ch I sinute- ef P0"ER OPERATION vettid: Of the target b:nd at *.EER"f1 POWER '^v:!: : qual to er :beve

--- _, - ,rn

e. .u _2 sv. v. nn.m. m r .,oms .-.

, nn,i ,e n, , . . . ,

b. On h lf minut: p:n:lty devieti:n f r ::ch 1 r.inut: Of POW"R OP"R* l TIO"e Out:id: Of th:,ot:rge: 5:nd :t THEP.".fi POWEP 1:v:1: betu::n 15%

__2

..~.,m. -

m.,,r

. .< . m,m r no . , mm

....,m u ,. un.

4.2.1.3 The target . flux difference of each OPERABLE excore char.. al shel' oc determined by measurement at.least once per 92 Effective Full Power Days. The previsions of Specification 4.0.4 are not applicable, j 4.2.1.4 The targe; flux difference shall be updated at least once per 31 Effec-tive Full Power Days by either determining the target flux difference per;;:nt-t: Sp::i'i::t i er '.2.'.2 :b v 'or by linear interpolation between the most ,

recently measured value and th> calculated value at the end of the. cycle life. I The provisions of .Specificati n 4.0.4 are not applicable. l l in conjw :fien suff/ +/a survef//once tefairemahl1 of haci$caffen 3l4.2.2 4 .,

-)

2 ,;

CALLAWAY - UNIT 1 3/4 2-2(a) Amencment rio. /f,44

m POWER DISTRIBUTION LIMITS

-SURVEILLANCE REQUIREMENTS 3 __

4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 is withinFor its Normal limit by:Operation QF (z) shall be evaluated to determine if FQ (z)

a. Using the movable incore detectors to obtala a power distribution map at any THERMAL POWER greater than 5% of PATED THERMAL POWER,

b. Increasing the measured F Q (z) component of the power distrroution map by 3% to account for manufacturing tolerances and further inc E Var sing +th9 value by 5% to ascount for measurement uncertainties.

h be rey lrekenfe rf freciAcefisn .P. 3. 3 arn saNdied, c .- Sati fying the following relationfhip:

p M(7),FhTP x K(2) for P > 0.5 l ~ P x W(Z)NO P

y M(7) , F x K(Z) for P < 0.5

~ W(Z)NO x 0.5 where Th (Z) is the measured F g (2) increased by the allowances for manufacturingtolerancesandmeasurementuncertainty.FhTPis the Fg limit, X(Z) is the nomalized F (Z) g as a function of core height.

P is the relative THERML POWER, and W(Z)NO is the cycle dependent.

Normal Operation function that accounts for power distribution transients encountered during Nomal Operation. F TP , X(Z) and

• W(Z)39 are specified in the Core Operating Limits Report as per L Specification 6.9.1.9.

d. M Measuring FQ (z) acc.ording to the following schedule:

1. Upon achieving equilibrium conditions after exceeding, by 10%

or more of RATED THERMAL POWER the THERMAL POWER at which FQ (z) was last determined,* or

2. At least onc.e per 31 Effective Full Power Days (EFPD), whichever l occurs first.

4 em}s'en abf ewer lenI brf redte N^

• During power escalation at Qxhu}ejof)f each cycle, power lev 7 hourr beginning o.

. increased until a power level or extended operation 1Yhas been achieved e.+aherwMc4

} a power distribution mapAobtained.

willbe CALLAWAY _ UNIT 1 3/4 2-6 Amendment No. 28.44, 58

1 P0dERfDISTRIBUT20N L1MITS y ..

- SURVEILLANCE MOUIRD'rNTS (Continued) .-

. . .c 4.2.2.2 (Continued)

e. With' measurements indicating maximum _ .Fo(z)

.over z- - g(g) has increased since the previous detemiaation of cQ M (z), either of the f,911owing actions shall be taken: -

cc .1. FgM (z) shall be increased Sr 2% over that specified in y

specificatior; 4.2.2 2c., or s

^

2.' F QM {zi shall be m2asured at least once-per 7 Effective Full Power ~0ays until two succe*.sive maps indicate that maximum- Th(z)- is not increasing.

ov e z- g(z) ,

- T. With the relationships.sp ut'iad in Specification 4.2.2.2c. above not being satisfied:

, l' .

Calculate the percent FQ (z) exceeds its. limit by the following expression:

't kinsv. 'over z of[F (z) x W(z)N9\)-1 x 100 for P > 0.5

'x

~ L 'pRTP K(z) 0  ;

-P / _

(max.over2of[F(z) x W(z)-NG )-1 x 100 for P . < 0. 5 7

P x .K(if ~

/. . . .

2. , Either'one of the folinwing actions shal1~be taken:

fgstgr 8'----+4et .

Conra y with' the, requirements of Specific.a' ion 3.2.2. for

(&).En(z: exceeding *tslimitby,t"epercentcalculated' L; aSove, or '

y

-4rt- Verify that-the requirements of Specification 4.2.2.3 (c) 1or RESTRICTED thD OPERATION are satisfied and enter g

- RESTRICTED AFD OPERATION.-

p

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 regions:

1. Lcuer core region from 0 to 15%, ir.r.lusive.

j< [ 2.  ; Upper core region from 85 to 100%, inclusive.

CALLAWAY - UN R 1 3/4 2 7 Amendment tio. 2B,ff,58 corrected

_ .. ._ . y _ _ . . _ _ . .

I e POWER DISTR 130T!'sN LIMITS S U RV E l t. L ANC_E R E QU I R EM ENT S ( C ogi,n,u ed,1,__,_,,_, __

4.2.2.3 RESTRIr.*ED 8.FD OPERATION (kAFDO) is permitted at powers above d APL"U*

if the following condi.tions are satisfied:

a. Prior tn entering PAFDO, msintain THERMAL POWER above APL" and less than or equal to that alloed by Specification 4.L2.2 for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintair. RAFD0 surveillance (AFD within the limits specified in the COLR) during this time period. RAFD0 is then permitted providing'lHE POWE) is trainta;nec: between APLND and APLRAF00 or between APLp'and 10N (whichever is more limiting) and f05 APl.ggillance is mt as:

intained pursuant to Specification 4.2.2.4 is defined APLMFN = minimum # NI) ,

x 100%

over : p 1(g) x w(z) pg l

whereFh(Z)isthenaaseredF(Z) n increase,ibytheallowancesfor l_ manufaa.ur ing tolerances snd measurement uncertainty. The Fg limit is RTP F , gg7) FD0 is the cycle dependent function that accounts for

' T N X A' T (.n limitec' power distribution transients encountered during RAF00. F gRTP K(Z), and W(1) ppg are specified in the Core Operating Limits Report as per Specification 6.9.1.9.

"p

!' b. During RAFDO, if the THERMAL POWER is decreased below APL"U then the i

conditions of 4.2.2.3.a. shall be satisfied before re-entering RAFD0.

4.2.2.4 During RAFDO,g F (Z) shall be evaluated to determine if F (Z) is within its limits by: 9

a. Using the movable intore detectors to obtain a power distribution map at any THERMAL POWER above API NO.

b. Increasing the measured Fn(7) -omponent of the power distribution map by 3% to account for manuYac uring tolerances and further 4 :rm sing the value by 5% to account for measurement uncertainties. Ver/f y &f 4he refMittmerr[.r of fyecl+fca-fien 3,2..*3 are falltfid ,

c. Satisfying the following relationship:

RTP F (Z) < Fg x MZ) for P > APL ND

~

P x W(Z)MF00 r~ ION #T h M RU where F (Z) is the measured F (Z)F The9 F limit is F . P is the relativhTHERMALPOWER. W(Z)9 is the cycle depen 0ent function mited thataccountsfor{F,K(Z)powkb9stributiontransientsencountered during RAFDO. FgR ,

and W(Z) MFD 0 are specified in the Core Operating Limits Report as per Specification 6.9.1.9.

1. .TNMRT E CALLAWAY - UNIT 1 3/4 2-7(a) 'enendment No. Z8.44,58 l

l

} . ,

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.4 (Continued)

d. Measuring 0F (z) in conjunction with target flux difference determi-nation according to the following schedule:

1. Prior to entering RAFD0 after satisfying Sectiut 4.2.2.3 unless a full core flux map has been taken in the provivus 31EFPDwightherelativethermalpowerhavingbeenmaintained above APLN for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and

2. At least once per 31 Effective Full Power Days.

e. With measurements indicating ,

maximum Fh(z) over z

_g(7) _

hasincreasedsincethepreviousdeterminationofFh(2)ei.herof the following actions shall be taken:

1. F (z) shall be increased by 2 percent over that specified in 4 2.2.4.c. or

2. Fh(z)shallbemeasuredatlesstonceper7EFPDuntiltwo successive maps indicate that maximum F"g(z) is not increasing, over z

-g(7) -

f.gZNtcxtF

~

Y l'ith t4+e-celctionship specified in E.2.2.4.c above not bch9-

4. Comg/7_ s:tisfied, comply witn the requirements of Specification 3.2.2 for F0(z) exceeding its limit by the percent calculated with the following expression: _

(max over z of Fh(2)xW(z)RAFD0 ) -1 x 100 for P > APL ND p RTP x g(7) 0 -

P

g. The limits specified in 4.2.2.4.c, 4.2.2.4.e, and 4.2.2.4.f ebove are not applicable in the following core plane regions:

1. Lower core region from 0 to 15 percent, inclusive.

2. Upper core region from 85 to 100 percent, inclusive.

4.2.2.5 When rg(z) is measured for reasons other than meeting the require-ments of Specification 4.2.2.2 or 4.2.2.4, an overall measured Fg(2) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and furtner increased by 5% to account for measure-ment uncertainty.

CALLAWAY - UNIT 1 3/4 2-7(b) Amendment No. /B ,W , 58

ADMINISTRATIVE CONTROLS

,) MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics r.nd shutdown experience, including documentation of all challenges to the pressurizer PORVs or RCS safety valves, shall be submitted on-a monthly basis to the Director. Office of Resource Management U. 5. Nuclear Regulatory Comission, Washington, D. C.

20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.  ;

CORE OPERATING LlHITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE l 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 3/4.1.1.3,

b. Shutdown Bank Insertion Lin.it for Specification 3/4.1.3.5,

c. Control Bank Insertion Limits for Specification 3/4.1.3.6,

d. ND Axial Flux Difference Limiu.gtarget band, and APL for Specification 3/4.2.1, gg74 RTP ND

e. Heat Flux Hot Channel Factor, Fg , K(Z), 's(2)N0 APL and W(Z)MFDM or Specification 3/4.2.2 Nuclear At teraird '

f. (EnthaPsy Ris.)

e Hot Channel Factor F aH' and Power Factor Multiplier, PF H, limits .for Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically-those described in the following doct.ments,

a. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (W Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator Temperaturc I Coefficient 3.1.3.5 - Shutdown Bank Insertion Limit: 3.1.3.6 -

Control Bank Insertion Limit; 3.2.1 - Axiel Ilux Ciff;rencci----

3.2.2 " cat flux llst Chennel I;ctor,- and 3.2.3 - Nuclear-Enthalpy Rise Hot Channel Factor.)

bl. "CA?-0305, "POWn DISTRIBUTION CONTROL AND LOAD TOLLOWI!G PROCCDU3::

TOPICAL REPORT", September 1974 (' Picprietary).

-(Me;nesviv;y ix Specif ke den 3.2.1 - Axi&F4ttx Difference -  ;

(& m tant Axici Offset Centrol).)

)

CALLAWAY - UNIT 1 6-21 Amendment No. 2E,ED, 58 corrected

- . _ -. - .-- . .- ~ . - - - - . ~ . - - --

ADMINISTRATIVE ONTROLS , .

CORE OPERATING LIMITS REPORT (Continued)

L2, ' "

^-d:rter to ". K- %1:(Chief ;f Oct; Par';n.;n;; Breach, imC)- l

~J ensa ry_ 31. 1000 ^tt: dr.:nt: 0;;r:ti:n :nd h fety "n:1y;i:

t;:::: Of r Mpreved L::d F:11:n P::h;:.

(ethcdeles7 for Specificati;n 3.2.1 Axial flux Di'ference

-fCenet;nt Axi:1 Off::t Centr:1).) t t

t]. N'J '; 0 0800, St:nd:rd tview P1:n, 'J. S. 5:1::r h;;ht ry C:-i::icn, 5::ti r *.2 'e:1:er D::ign, July 1981. Er:n h iacnnic:1 P;;iti n t C"; t. Li, "estin;hou. Ocastent-Axiel Offset-Centrel (CA00), hv. 2

- J o i ., 1001.

(L thede h;yLf r 5;;;ific:ti:n 2.2.1 Sh1 "h Pferen:+-

-(Constent Axici Offset C;ntrol).) '

ANb -

f. t WCAP-10216-P-A, SURVEILLANCE TECHNICAL'" SPECIFICATION,"RELAXATION JuneOF 1983CONSTANT

(~W Proprietary . AXIAL OF

> IN.nrer* G L '":th: ;hsy f;r specification 3.2.2 "est rid t:st Ch;na;1-Tecter_ (TQ "ethedeh;y f;r "(2) ;;rveilkn:: r:;uirr:nte).

c.4. WCAP-10266-P-A, REY. 2. "THE 1981 VERSION OF WESTINGHOUSE EVALUATION i MODEL USING BASH CODE." March 1987 (W Prop 'ietary),-

i (Methodology for Specification 3.2.2 - Heat Flux Hot- Channel Factor).-

The core operating limits shall be detennined so that all applicable limits (e.g., fuel :hermal-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 OFERATING LIMITS-REPORT, including any mid-cycle revisions _or supple-ments shall be provided _upon issuance for each reload-cycle, to the NRC Document. Control Desk with copies' to the Regional Administrator and Resident Inspector. '

SPECIAL REPORTS 6.9.2 Soecial Reports shall be submitted to the Regional Administrator of the 1 HRC Regional-Office within the time period specified for each report.

.6.10 RECORD RETENTION In a-dition to-the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least L the minimum period _ indicated. "

6.10.1 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level; CALLAWAY - UNIT 1 6-21a Amendment No. 28,50, 58

>_ _ ._ _ - ~ . . _ - - - . ._ - . - . _ _.. . _ . _ _ - . _ . - _ . . . -

/ .. .:

., INSERT B (a) Within 15 minutes, centrol the AFD'to within new AFD limits wh.'h aro~ determined by tightoning both tho negative and positive AFD limits of Specification 3.2.1 L by 1% AFD for each percent F oxceeds its limits as l determined in Specification k.(z) 2.2.2.f.l. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD Llarm setpoints to these modified limits, or INSERT C K(Z) is the normalized Fg(Z) as a function of core height.

INSERT D increased by-the allowances for manufacturing tolerances and measurement function of core height.

uncertainty, K(Z) is the normalized F9(Z) as a l INSERT E 1

ND

• APL is the minimum allowable (nuclear design) power level-for RESTRICTED AFD OPERATION in Specification 3.2.1 and specified in the Core Operating Limits Report as por Specification 6.9.1.9.

INSERT F With the relationship specified in 4.2.2.4.c-above.not boing c satisfied, either of the following actions shall be taken:

1. Place the core in an equilibrium condition where ghe <

limit in 4.2.2.2.c is satisfied, .and roncasure Fg (n), or INSERT G (Methodology for Specification 3.2.1 - Axial Flux Differenco c (Relaxod Axial Offset Control) and-3.2.2 - Heat Flux Hot -

I _ Channel Factor (W(Z) surveillanco requirements of Fg Metho-dology) p

. __ _ _ .. _ _._._ _ - - . _ _ ~ _ _ . _ . _ _ . - _ _ . _ _ _ _ _ _ _ _ _

s 7

-3/4.2 - POWER DISTRIBUTION LIMITS

) BASES The specifications of this section provide assurance of fuel integrity 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 analysis DNBR ifmits during normal operation and in short-tenn transients, and (2) limiting tu fission gas release, fuel pellet temperature, and cladding-mechanical properties to within assumed design criteria. In addition. limiting

-the peak lineer power density during Condition _I events provides assurance that the initial conditions assumed for the LOCA analyses are. met and the ECCS acceptance criteria limit of 2200*F is not exceeded.

The definition =of certain hot channel and peaking factors as used in these specifications are as follows:

F(2) q Heat Flux Hot Channel Factor, is defined as-the maximum lo:al heat flux on the_ surface of a fuel rod at core elevation Z divided by the average l fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods; and ,

F"H 4 -Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of . I the integral of linear power along the rod with the highest integrated )

power to the average rod power. I 3/4.2.1 AXIAL FLUX DIFFERENCE l

The . limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (2) upper bound g envelopes of the Fn limit specified in the Core Operating Limits Report (COLR) [

times the normalized axial peaking factor are not exceeded during either normal operation or in the event of xenon redistribution following power changes.  !

l Target flux difference is determined at equilibrium xenon conditions. The i full-length rods may be positioned within the core in accordance with their i respective insertion limits and should be -inserted near their normal position '

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 i 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 4 flux difference value:is necessary to reflect core burnup considerations. '

SNJ"ERT" -+

N Th li * ;" ^ * * * = * (^IO) 'r* iivi" i" **

• R- 7""

modcs ;f operction are pecrii35ible. One mode-is-Notesi-Operetion ernf the AFD

-limit is sp;cified in the COLR. Af ter extended 4eed-folicwing menetwers, the

-AFD iimis cey. result in restrictions in the meximum ellowed pc ar to guarantec cp:r; tion ..ith F9(Z) less than its limiting valuz. Tc-prcvent this occurrence, enothcr operatin3 madc hich restricts thc ?F0 to a rcletivcly small t rget  !

)

CALLAWAY - UNIT 1 B 3/4 2-1 knendment No.15, y, A4/ , 'A corrected

--. - . . - - . -- - - _ ~_

I INSERT H At pJwer levels below APL"U , the limits on AFD are specified in the COLR-for RAOC operation. These limits were calculated in a manner such that expected operational transients, e.g., load

-follow operations, would not result in the AFD deviating outside of those limits. However, in the event such a deviation occurs, the 15 minete period of time allowed outside of the limits at reduced power levels will not result in significant xenon redistribution suci that the envelope of peaking factors would chagge sufficiently to prevent operation in the vicinity of the APL power level.

At power levels greater than APL ND two modes of operation are permissible: 1) RAOC with fixed AFD limits as a function of reactor power level and 2) Restricted AFD Operation (RAFDO) which is defined as the maintenance of th( AFD within a band about a target value. Both the fixed AFD limits for RAOC operation and the target band f NDRAFDO are specified in the COLR,

, RAgg operations above APL are the same as for operation below APL . However, it is possible when following extended lead following maneuvers that the AFD limits may result in restrictions in.the maximum allowed power or AFD in order to-To guarantee. operation allow operation at with Fthe max 9m(Z) less than um permissible its limiting value, the RAFDO value.

operating procedure restricts the indicated AFD to a relatively smalltargetbandanddoesnotallowsigngficantchangesiggggger level (i.e., power maintained between APL and either APL or-100% RTP, whichever is less). For RAFDO, it is expected t.at the plant will operate within the target band. Operation outside

- of the target band for the short time period allowed (15 minutes) will not result'in significant xenon redistribution such that the envelope of peaking factors would change sufficiently to prohibit continued operation in.the power region defined above. To assure there is no residual xenon redistribution impact for past operation on the RAFDO operation, prior to enterigg RAFDO a 24-hour waiting period at a power level above APL and less than

-or-equal to'that allowed by Specification 4.2.2.2 is necessary.

During this time period, load changes and control rod motion are restricted to that allowed by the RAFDO procedure. After the waiting period, extended RAFDO is permissible.

Provisions.for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm.. The computer determines the one-minute average of each of the OPERABLE excore Seteci or outputs and provides an alarm message immediately is the one-minute average AFD for at least two OPERABLE excore channels are: 1) outside the-allowed delta-I vs -power operating space (for RAOC operation), or 2) outside the acceptable AFD target band (for RAFDO). These alarms fare active when power is greater than5D ) 0% of RATED THERMAL POWER (for RAOC operation), or 2) APL (for RAFDO). Penalty

, deviation minutes for RAFDO are not accumulated based on the short period of time during which operation outside of the target band is allowed.

l

4 POWER DISTRIBUTION LIMITS ,

BASES 3/4.2.1 AXIAL FLUX DIFFERENCE (Continued) bend :nd dets not elk" significant-ehanges-in-power leveMes-been-defined, s mode is called RESTRICTED AFD OPERATION, which restricts the AFD g the li s specified in the COLR and restricts power levels to between APL and eith PLRAFD0 or 100% of RATED THERMAL POWER, whichever is less. Prior enteri RESTRICTED AFD OPERATION, a 24-hour waiting period at a power i el

(+2%) abo APLND and below that allowed by Normal Operation is neces ry.

During this (me period load changes and control rod motion are res cted to that allowed bf the-RESTRICTED AFD OPERATION procedure. After th aiting period, RESTRICT AFD OPERAT!0N is permitted.

Although it is in ded that the plant will be ope _ed with the AFD within the target band req red by Specification 3.2.1 out the target flux difference, during rapid pla THERMAL POWER reducti , control rod motion will cause the AFD to deviate tside of the targe and at reduced THERMAL POWER levels. This deviation wi not affect t xenon redistribution suffi-cieatly to change the envelope of p fac rs which may be reached on a subsequent return to RATED THERMAL P0 king (w the AFD within the target band) provided the time duration of the deviat is limited. Accordingly, a 1-hour penalty deviation limit cumulative dur g e previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target nd but thin the limits specified in

--) the COLR while at THERMAL POWER 1 els between  % and 90% of RATED THERMAL POWER. For THERMAL POWER level etween 15% and  % of RATED THERMAL POWER, deviations of the AFD outsid f the target band are ss significant. The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual .e reflects this reduced s gnificance.

Provisions for . itoring the AFD on an automatic are derived from the plant process computer through the AFD Monitor Alann. Th computer deter-mines the 1 minut overage of each of the OPERABLE excore detec r outputs and provides an ala message immediately if the AFD for two or more RABLE excore channels are tside the target band and the THERMAL POWER is greate than 90%

of RATED T POWER. During operation at THERMAL POWER levels betw n 50%

and 90% d between 15% and 50% PATED THERMAL POWER, the computer output n alarm ssage when the penalty deviation accumulates beyond the limits of 1h r and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

rigere B 3/d .2-1 : hows-a-t-ypical montMy-terget-band.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor and nuclear enthalpy rise hot channel factor ensure that 1) the desi minimum DNBR are not exceeded, andin2) gnevent limitsofona peak LOCAlocal powerfuel density clad and the the peak temperature will not exceed the 2200*F ECCS acceptance criteria limit.

}

CALLAWAY - UNIT 1 B 3/4 2-2 Amendment No. M///2V, 58

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-30% -20% -10 % 0 +10 % +20 INDICATED AXIAL FLUX DIFFERENCE FIGURE B 3/4.2-1 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERM POWER CALLAW AY - UNIT 1 B 3/4 2-3 Amendment No. 15

-4 .~, ...

ULNRC-2546 ATTACHMENT FIVE PRELIMINARY CYCLE 6 COLR CHANGES FOR RELAXED AXIAu OFFSET CONTROL (RAOC)

'EAGE SECTION DESCRIPTION 7 of 155 24 Change from CAOC to RAOC, AFD Insert 1.

-8 of 15 2.4 Change of the CAOC Figure to the AFD RAOC Figure, Insert 2.

9 of 15 2.5 Change from CAOC to RAOC (Fg) description.

i