ML20065P781

Corrected Amend 58 to License NPF-30,replacing Pages 3/4 2-4,3/4 2-7,3/4 2-7(b),3/4 2-8,B 3/4 2-1 & 6-21

ML20065P781
Person / Time
Site:	Callaway
Issue date:	12/07/1990
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065P783	List: ML20065P781
References
NUDOCS 9012140057
Download: ML20065P781 (10)

Text

"

FIGURE 3.2-1 DELETED CALLAWAY - UNIT 1 3/4 2-3 gm 9012140057 901207 PDR AT;OCK 05000483 PDC m

/.

}

h l

POWER DISTRIBUTION LIMITS

- 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z) 0 LIMITING CONDITION FOR OPERATION '

3.2.2 F (Z) shall be limited by the following relationships:

9 F(Z)1 FhTP*K(Z)forP>0.5,and n

P F(Z)1 FhTP*X(Z)forp1 0. 5.

g

0. 5 WhereFf=theF limit at RATED THERMAL POWER (RTP) g specified in the Core Operating Limits Report (COLR) p, THERMAL POWER

,-and RATED THERMAL. POWER K(Z) = the normalized F (Z) as a function of core height as 9

specified in the COLR.

A_PPLICABILITY: MODE 1.

ACTION:

With'F(2)exceedingitslimit:

9 a.

Reduce THERMAL POWER st 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% F (Z)- exceeds the-limit; and g

.b.

Identify'and correct the cause of the out-of-limit condition prior to increasiny THERMAL POWER above the reduced limit required by ACTION a., above; THERMAL POWER may then be increased provided F (Z)-is demonstrated through incore mapping to be within its limit.

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

'T r

e

,--_4

-,,,,.,_,..,-------..,,--v

yl,,

POWER D15TRIBLITION LIMITS s

y

[

StJRVEILLANCE ' REQUIREMENTS (Continued)

L.

h 4.2'2.2 (Continued)'

f e.

With measurements indicating r

maximum Fh(z)-

l over z-K(z) has increased since the previous determination of F MQ(z),either of the following actions shall be taken:

M Fg (z) shall be increased by 2% over that specified in

-1.

Specification 4.2.2.2c., or M

Q (z) shall be measured at least once per 7 Effective ?ull 2,.

F Power Days until two successive. maps indicate that maximum Fhz) is not increasing.

over z.

K(z) f.

With the relationships specified in Specification 4.2.2.2c. above not being satisfied:

1.

Calculate the percent F (z) exceeds its limit by the following Q

expression:

t imax,overz'of F (z) x W(z)N0 )-1 x 100 fnr P > 0.5 M

RTP x.K(z) p Q

P

_kmax, over z of[pTP F(z) x W(z)

)-1 x 100_for P < 0.5 x K(z) l

)

0. 5 p

2.

Either one of the following actions shall be taken:

(a) Comply with the requirements of Specification 3.2.2 for Fo(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.

The limits specified in Specifications 4.2.2.2.c., 4.2.2.2.e., and 9

4.2.2.2.f. above are not applicable ir. the following core plane regions:

1.

Lover core region from 0 to 15%, inclusive.

2.

Upper core region from 85 to 100%, inclusive.

CALLAWAY - bHIT 1 3/4 2-7 Amendment No. 2B,ff,58 i

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

_ _ _, ~,

POWER DISTRIBUTf0N LIMfTS SURVEIL.ANCE REQUIREMENTS (Continued)

NU 4.2.2.3 RESTRICTED AFD OPERATION (RAFDO) is permitted at powers above APL if the following conditions are satisfied:

ND a.

Prior to entering RAFDO maintain THERMAL POWER above APL and less than or equal to that allowed by Specification 4.2.2.2 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 />.

MaintainRAFD0 surveillance (AFDwithinthe limits specified in the COLR) during this time period.

RAFD0 is then permitted providing THEPMAL POWER is maintained between APLND and APLRAFD0 or between APLW and 100% (whichever is more limiting) and APL@illance is maintained pursuant to Specification 4.2.2.4.

F05 is defined as:

APLRAFD0 = minimumFhTP x K(2) x 100%

N over z F9 (Z) x W(Z)RAFD0,

N where F (Z) is the measured F (Z) increased by the allowances fnr 0

manufact'ur Ing tolerances and measurement uncartainty.

The F limit is g

.FhTPy[7)RAFD0 is the cycle dependent function that accounts for limited power distribution transients encountered during RAFD0.

FhTP K(Z). and W(Z)RAFD0 are specified in the Core Operating Limits Report as per Specification 6.9.1.9.

NU b.

During RAFDO. if the THERMAL POWER is decreased below APL then the conditions of 4.2.2.'3.a. shall be satisfied before re-entering RAFDO.

4.2.2.4 During RAFDO. F (Z) shall be evaluated to determine if F (Z) is g

9 within its limits by:

a.

Using the movable incore detectors to obtain a power distribution N

map at any THERMAL POWER above APL D, by 3% to account for manu9a(Z) component of the power distribution map b.

Increasing the measured F cturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c.

Satisfying the following relationship:

RTP F (Z) < F x g(7)

ND f r P > APL P x W(Z)RAFD0 M

RTP where F (Z) is the measured F (Z).

The Fg limit is F

. P is the relativ0THEn"** POWER. W(Z)q is the cycle depen 9ent function RymitedpowNp09stributiontransientsencountered that accoun-during RAFDO.

.g

,KfZ).andW(Z)RAF00 are specified in the Core Operating Limits Report as per Specification 6.9.1.9.

CALLAWAY - UNIT 1 3/4 2-7(a)

Amendment No. 28./A.58

r w

n p

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

Measuring Fh(2) in conjunction with target flux difference determi-d.

nation according to the following schedule:

1.

Prior to entering RAF00 af ter satisfying Section 4.2.2.3 unless e full core flux map has been taken in the previous 31 EFPD with the relative thermal power having been maintainea ND above APL 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 Fh(z) maximum over z A z).

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

Fh(z)shallbeincreasedby2percentoverthatspecifiedin 1.

4.2.2.4.c, or

~

2. -

F(z)shallbemeasuredatleastonceper7EFPDuntiltwo

/

s ccessive maps indicate that

~

maximum Fg(z) is not increasing, over z K z')--

f.

With the relationship specified in 4.2.2.4.c above not being satisfied, comply with the requirements of-Specification 3.2.2 for F (z) exceeding its limit by the percent calculated with the Q

following expression:

(max.overzof[F(z)xW(z)RAFD0 )

-1 x 100 for P > APLND Q

l p

TP 'x K(z) 3 g.-

The limits specified in 4.2.2.4.c, 4,2.2.4.e. and 4.2.2.4.f above 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 Fo(z) is measured 'for reasons other than meeting the iequire-ments _of Specif fcation 4.2.2.2 or 4.2.2.4. m overall measured Fg(z) shall be obtained from a power distribution map che.icreased by 3% to account for manufacturing tolercnces and further i,a used by 5% to account for measure-ment uncertainty.

CALLAWAY - UNIT 1_

3/4 2-7(t '

Amendment No. /Nott, 58 i

?

POWER DISTRIBUTION LIMGS 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FN 3

LIMITING CONDITION FOR OPERATION N

3.2.3 F shall be. limited by the following relationship:

3H N

F 1 F D + PF3g (1-P)]

oH 3

where: F RTP = The FN 3

3H limit at RATED THERMAL POWER (RTP) specified in the Core Operating Limits Reprt (COLR).

PF3g = the Power Factor Multiplier for F specified in the COLR.

g P = THERMAL POWER RATED THERMAL POWER N

F

= Measured values of F g obtained by using the movabic incore 3g detectors to obtain a power distribution map.

The measured values N

of F shall be used since an uncertainty of 4% for incore measure-g N

ment of F has been included in the above limit.

3g APPLICABIL ITY: MODE 1 f.CTION:

N With F exceeding its limit:-

3H a.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

N 1.

Restore the F to within the above limits, or 3H 2.

Reduce THERMAL POWER TO LESS THAN 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux-High Trip Setpoint to 1 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 />, N

b.-

_ Demonstrate through in-core flux mapping that F is within its 3

limit within 2' hours after exceeding the limit or reduce THERMAL POWER to less snan 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and Identify-and correct the cause of the out of limit condition prior c.

to increasing THERMAL POWER above the reduced limit required by a or b,. above; subsequent POWER OPERATION may proceed provided that F

is demonstrated-through in-core flux mapping to be within its H

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 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.

CALLA' LAY - UNIT 1 3/4 2-8 Amendment No. JE,ff,58

~~

a

, 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 limits during normal operation and in short-term transients, and (2). limiting the fission gas release, fuel pellet temperature, and cladding mechanical properties to within assumed design criteria.

In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS l

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(Z)

Heat Flux Hot Channel Factor, is defined as the maximum local heat flux g

on the surface of a fuel rod et core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel l

pellets and rods; and N

It.H Nuclear Enthalpy Rise Hot Channel Fcetor, is defined as the ratio of the integral of lineer power along the rod with the highest integrated l

power to the average rod power.

l 3/4.2.1 AXIAL FLUX _

7ENCE The limits on Anm. rLUX DIFFERENCE (AFD) assure that the F (Z) upper bound g

envelopes of the F limit specified in the Core Operating Limits Report (COLR) l g

times 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 respective insertion limits and should be inserted near their normal position for steady-s ate 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 consideraticns.

The limits on AXIAL FLUX DIFFERENCE (AFD) are given in the COLR.

Two modes of operation are permissible. One mode is Normal Operation and the AFD limit i' specified in the COLR. After extended load following maneuvers, the AFD 1 m may result in restrictions in the maximum allowed power to guarantee 3

operatie lith F (Z) less than its limiting value.

To prevent this occurrence, n

another operating mode which restricts the AFD to a relatively small target CALLAWAY - UNIT 1 B 3/4 2-1 Amendment No. JE, /p,A4/, 53

. ~ - -

POWER DISTRfBUTION LIMITS BASES 3/4.2.1 AXIAL FLUX DIFFERENCE (Continued) band and does not allow significant changes in power level has been defined.

ThismodeiscalledRESTRICTEDAFDOPERATION,whichrestrictstheAFDgthe limits specified in the COLR and restricts power levels to between APL and either APLRAFD0 or 100% of RATED THERMAL POWER, whichever is less.

Prior to entering RESTRICTED AFD OPERATION, a 24-hour waiting period at a power level (t2%) above APLND and below that allowed by Normal Operation is necessary.

During this time period load changes and control roj motion are restricted to that allowed by the RESTRICTED AFD OPERATION procedure.

After the waiting period, RESTRICTED AFD OPERATION is permitted.

Although it is intended that the plant will be operated with the AFD within tne target bard required by Specification 3.2.1 about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels. This deviation will not affect the xenon redistribution suffi-ciently to change the onvelope of-peaking (with the AFD within the target band) factors which may be reached on a subsequent return to RATED THERMAL POWER provided the time 6 ration of the deviation is limited. Accordingly, a 1-hour penalty deviation limit cumulative during the 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 3 gt band but within the limits specified in the COLR while at THERMAL POWER levels between 50% and 90% of RATED THERMAL POWER.

For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the~ target band are 1ss 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 time reflects this reducad significance.

Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer deter-mines the 1 minute average of each of the OPERABLE excore detector outputs and provides an alann message immediately-if the AFD for two or mcre OPERABLE ~ excore channels are outside the target band and the THERMAL POWER is greater than 90%

c4f RATED THERMAL POWER. During operation at THERMAL POWER levels between 50%

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

'l hour and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

Figure B 3/4.2-1 shows a typical monthly target band.

134.2.2end3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CAXI4NEL FACTDR T1e limits on heat flux hot channel factor and nuclear enthalpy rise ho' t channel factor ensure that 1) the desi minimum DNBR are not exceeded, and 2) gn limits on peak local power density and l

in the event of a LOCA the peak fuel ci d temperature will not exceed the 2200*F ECCS acceptance criteria limit.

CAU.AWAY - UNIT 1 B 3/4 2-2 Amendment No. JE///W, 58 3

-.w.

~

-c-r D

' ADMINISTRATIVE CONTROLS 3

~

MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer PORVs or RCS safety valve.s. shall be submitted on a monthly basis to the Director, Office l:

of Resource Management U. S. Nuclear Regulatory Commission. Washington, D. C.

20555, with a copy to the NRC Regional Office, no later than the 15th of egh month following the calendar' month coverad by the report.

CORE OPERATING LlHITS 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 serveillance limit for Specification 3/4.1.1.3, b.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, c.

Control Bank Insertion Limits for Specification 3/4.1.3.6, ND d.

Axial Flux Difference Limits, target band, and APL for 1-Specification 3/4.2.1, RTP i

e.

Heat Flux Hot Channel Factor F

, K(Z), W(Z)N0' APL"U and W(Z)RAFD0 f r Specification 3/4 2.2 f.

Nuclear Enthalpy Rise Hot Channel Factor FAH. and Power

-Factor Multiplier, PFoH, 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 documents, a.

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

July 1985 (W Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator 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.)

bl.

WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOPICAL REPORT", September 1974 (W Proprietary).

l l

-(Methodology for Specification 3.2.1 - Axial Flux Difference (ConstantAxialOffset' Control).)

I CALLAWAY - UNIT 1 6-21 Amendment No. 7E.ED, 58

~

- -. ~,

I l

_ ADMINISTRATIVE (DNTROLS CORE OPERATING LIMITS REPORT (Continued) b2.

T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC)

January 31, 1980 --

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Folicw Package.

(Methodology for Specific 6 tion 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

b3.

NUREG-0800, Standard Peview Plan, U. S. Nuclear Regulatory Commission.

Section 4.3 Nuclear Design, July 1981.

Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

c.

WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION " June 1983 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodology for W(Z) surveillance requirements).

d.

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 applicEcle limits (e.g., fuel thermal-mechanical limits, core thermalhydraulic lim',ts, nuclear limits such as shutdown margin, and transient and ace. dent analysis limits) of the safety analysis are met.

The CORE OPERATING 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 Irspector.

SPECIAL REPORTS 6.9.2 Special Reports shall be submitted to the Regional Administrator of tha 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 shall be retained for at least 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 6-2ia Amendment No. 7E,ED, 58 i