ML20092A543

Proposed Tech Specs Expanding Unit 1 Power Distribution Section to Include Base Load Operation in Addition to Currently Approved RAOC Operation

ML20092A543
Person / Time
Site:	Mcguire, McGuire
Issue date:	06/14/1984
From:	DUKE POWER CO.
To:
Shared Package
ML20092A539	List: ML20092A532 ML20092A543
References
TAC-55177, TAC-55178, NUDOCS 8406190255
Download: ML20092A543 (33)

Text

. - . _

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Attachment 1 Proposed Modifications to the Power Distribution Limits Sections of the McGuire 1 Technical Specifications for Base Load Operation h

F

. 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 .

AXIAL FLUX DIFFERENCE (UNIT 1)

LIMITING CONDITION FOR OPERATION 3.2.1 4

a. S y* the allowed operational space defined byThe womw n t1mcwr ranssr amo amour rwt rneur rs. Figure 3.2-1x FoA RAOC #F'M"*",*8 indicated AXIAL I F APPLICABILITY: >2

(

MODE 1 above 50% of RATED THERMAL POWER *.>c osmornes a ACTION: -

- g'oa MAbc opsxAnua

{

a. N With

1. the indicated AFD outside of the Figure 3.2-1 limits, /;>

Either restore the indicated AFD to within the Figure 3.2-1 ,

limits within 15 minutes, or  ;

)

2. <

Reduce THERMAL POWER to less than 50% of RATED/ T within 30 minutes and reduce the Power Range Neutron Flux -

High Trip setpoints to less than or equal to 55% of RATED ) 1

)

s. Gi% 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 />. c>

c.g. '

[>

THERMAL POWER shall not be increased above 50% of RA

(.

)

POWER unless the indicated AFD is within the Figure 3.2-1 limits .

SURVEILLANCE REQUIREMENTS g) 4.2.1.1 ,

i POWER OPERATION above 50% of RATED THERMAL f>i POW a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1. /)

At least and once per 7 days when the AFD Monitor Alarm is OPERABLE (

'?

2.

i At loast 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 /> after restoring the AFD Monitoring Alarm to OPERABLE status. -

2 *

b. '

Monitoring and logging the indicated AFD for each OPERABLE excore 7 channel 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 /> and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. (

i to exist during the interval preceding each logging.The < log 4.2.1.2 t, least limits. two OPERABLE excore channels are indicating7 the

• y t.s v l

• See Special Test Exception 3.10.2. '

( $$ M AFL * $5 rht hovonwu AnowAssG yowCA L$vis f ok GAK LoAO CPiMATlow AMD Wiu-fnovieto ou rus McAxisve FAcron Linor REron,r />tn ErscirocArion 6.9.s.q, <

i McGUIRE - UNITS 1 and 2 3/4 2-1

! Amendment No. (Unit 1)

Amendment No. (Unit 2)

g

^

• Insuzr A

b. For Base Load operation above APLND** ~

with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target flux difference:

l'.i Either restore.the indicated AFD to within the target band limits within 15 minutes,or

2. Reduce THERMAL POWER to less than APLNDof RATED THERMAL POWER and di,scontinue Base Load operation within 30 minutes.

'l M sen.T B _

4.2.1.3 When in Base Load operation, the target axial flux difference of each OPERABLE excore channel shall be determined by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 When in Base Load operation, the target flux difference shall be ~

updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4.2.1.3 above or by linear interpolation between the most recently measured value and 0 percent at the -

end of cycle life. The provisions of Specification 4.0.4 are not applicable.

.40%,481

• 4%= 4 "

w

a o fJ O CV)/)NG S 35 h t

ar a c-^

u:

C @

a 5 i

=

100

,00)

UNACCEPTABLE "

OPERATION UNACCEPTABLE OPERATION 80  : ACCEPTABLE -

-__0PERATION

.___. ) _ .

60 j

(31,50) (17,50) 40 __.

20

.= . .. -.______ __ .-

2 0 '

-50 -40 ,-30 -20 -10 0 10 20 30 40 50 Flux Difference (aI)".

FIGURE 3.2-la AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL h

McGUIRE - UNITS 1 and 2 3/4 2-4 Amendment No.32 (Unit 1)

Amendment No.j3 (Unit 2)

.o .

(~

p D CV/J)W&tU POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F g

. - . ~

LIMITING CONDITION FOR OPERATION ,

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

q F (Z) 1 [2.32] [K(Z)] for P > 0.5 (Unit 2)

~

Fq (Z) 5 [2 5] [K(Z)] for P > 0.5 (Unit 1)

Fq (Z) 1 [2 _] [K(Z)] for P 1 0.5 (Unit 2)

Fq (Z) 1 [2 [K(Z)] for P 5 0.5 (Unit 1)

Where: P = THERMAL POWER RATED THERMAL POWER '

~core and height K(Z) isllocation.

he' function obtained from Figure 3.2-2 for a given APPLICABILITY: MODE 1.

. ACTION:

With Fq (Z). exceeding its Ifmit:

a.

Reduce THERMAL POWER at least 1% n for each 1% F (Z) excee 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 Delta T Trip Setpoints -

(value of K 4) have been reduced at least 1% (in AT span) for each 1% qF (Z) exceeds the limit; and -

b.

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

. McGUIRE - UNITS 1 and 2 3/4 2-6 Amendment No.32 (Unit 1)

Amendment No.13 (Unit 2)

A,..,,_.. ,, ,

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (UNIT 1) .

i' 4.2.2.1 <

The provisions of Specification 4.0.4 are not applicable. <

f OS PACC ortnArtM,

(,

4.2.2.2 Fq (z) shall.be evaluated to determine qif F (z) is within its limit by: 7 a.

?

Using'the movable ~incorb detectors lo obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. <

Incriasing the measured Fq (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. Satisfying the following relationship:

M <l 2

Fq (z) $ p.15 EI I f r P > 0.5 W(z) (

M 2 $

Fq (7) < x0 ) f r P $ 0.5

(, where F (z) 1.s the measufed Fq'(z) incre~ai'ed byTh'e allowa'nces for manufacturing tolerances and measurement uncertainty, 2.15 is the F q

l' '

limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL POWER, '

and W(z) is the cycle dependent function that accounts for power >

distribution transients encountered during normal operation. This function is given Specification in the Peaking Factor Limit Report as per 6.9.1.9.

li? '

?

d. M c Measuring Fq(z)accordingtothefollowingscheduli:

1.

Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at $l which Fq (z) was last determined,* or <

2. c At least once per 31 Effective Full Power Days, whichever P,

, occurs first.

c,

(

b

')

Y]'

• 0uring power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.

j'

. o J

McGUIRE - UNITS 1 and 2 3/4 2-7 Amendment No. (Unit 1)

Amendment No. (Unit 2)

.Mh'd M $ 4*.I  % '

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (UNIT 1) (Continued)

e. With measurements indicating maximum fF"(z) 9 -

over z K ,

N (z) ) (<

has increased since the previous determination of F N the following actions shall be taken: q (z) either of < [

M

1) 'F <

q (z) shall be increased by 2% over that specified in Specifi- i cation 4.2.2.2c. or

- M  ?,

2) F z PSwe(r)Daysuntiltwosuccessivemapsindicatethatshall b <

2 maximum G IFM (z) is not increasing. '

over Z f (K(z))

f.

With not being i.he relationships satisfied: specified in Specification 4.2.2.2c. above '

c ,'

s 1)

Calculate the percent F q (z) exceeds its limit by the following expression:

Imaximum M Fq (z) x W(z) l x 100 b<'

2.15 for P > 0.5 (,

xK(z}/-1',

~

{)(overI p j i

C

( ,

'I *

)f[ maximumrM(*)*NCZ)[-1'x100'

' p 0

for P < 0.5 c#

2.15 / I Ll(overZ s 0. 6 x K(zl J 1 S

out > -

2) -E!therof the following. actions shall be taken: i s

i a) Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the~ AFD limits of (c -

3.2-1 by 1% AFD for each percentqF (z) exceeds its limits ,

as determined in Specification 4.2.2.2f.1). Within 4 8limits, hours,orreset the AFD alarm setpoints to these modified [

,7 c'

b) Comply with the requirements of Specification 3.2.2 for <

(

Fq (z) exceeding its limit by the percent calculated above,ox ,( ,

. c) venofy runr nrs Ptournantun oc specific 4rrou 't.1.z.3 foA BAsc - ,

t s.oAD GPGA/17 ou AAE SArijfile AND GurEA BAK LCAD QPlMT/oNo ,

McGUIRE - UNITS 1 and 2 3/4 2-8 Amendment No. (Unit 1)

Amendment No. (Unit 2) h .. . . . .

g, ,- ,

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (UNIT 1) (Continued) '

g. I A

The limits specified in Specifications 4.2.2.2c, 4.2.2.2e., and < L 4.2.2.2f.

regions: above are not applicable in the following core plane 2 3

l>

1. Lower core region from 0 to 15%, inclusive. '

7

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

~ \

4.2.2.,23rWhenF'(Z)ismeasuredforreasonsotherthanmeetingtherequirements i I?

of Specification 4.2.2.2 an overall measured FQ (z) shall be obtained from a power <

c' distributio~n map and increased by 3% to account for manufacturing tolerances c, and further increased by 5% to account for measurement uncertainty.

Q, tit.3 9.2. t. v (usertr&

4

\

r L

s i

' McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No. (Unit 1)

Amendment No. (Unit 2)

, . , y;q.x -: i .' , t

F lN5tter C- (wE 10F })

4.1.2.3 Base Load operation is permitted at powers above APLE if the following conditions are satisfied: ..

a. Prior to entering Base Load operation, maintain THERMAL POWER above-APL O ..

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 />. Maintain Base Load operation survet11ance time period. (AFD within 13% of target flux difference) during this Base Load operation is then permitted providing THERMAL POWER is maintained between APLO and APLBL or between APLO and 1005 (whichever is most limiting) and Fg surveillance is maintained-pursuant to Specification 4.2.2.4 APLBL is defined as:

gp BL , minimum g (2.15) x K(Z) over Z ] x 100%

/q(g) x y(g)BL where:

i F (z) is the measuredgF (z) increased by the allowances for j manufacturing tolerances and measurement uncertainty. The gF limic is 2.15.

i K(z) is given-in Figure 3.2-2)l. W(2)gti s the cycle 0

dependent function that accounts.for limited power distribution transients encountered during base load operation.

The function  :.

I

b. is given in the. Peaking Factor Limit Report as per Specification 6.9.

During APL O Base Load operation, if the THERMAL POWER is decreas thenBase re entering the.Loadconditions operation. of 4.2.2.3.a shall be satisfied befor F

" **' * "' I#

Swt n s1 ib a.

e Using the movable intore detectors to obtain a power distribution ma at any THERMAL POWER above APLO . ,

b.

Increasing the measured n F (Z) cor.ponent of the power distribution map.by 3% to account for manufacturing tolerances and further increasing the value by 5%.to account for measurement uncertainties. A A f_. . . y

I, ,

d lNjb(2T lC ( WA&41- 0F b )

,. 7 i

r#  !

c. Satisfying the following relationrhip:

2 (Z)$ W(Z for'P > APLND where: ((Z)isthemeasuredF(Z), The Fg q limit is 2.15.

K(Z) is given in Figure 3.2-2/. P is the relative THERMAL POWER.

W(Z)BL is the cycle dependent function that accounts for limited power distribution transients encountered dufing normal operation. This function'is given in the Peaking Factor Limit Report as per

• Specification 6.9.1.9. '

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

determination according to the following schedule.

1.

Prtor to entering BASE LOAD operation after satisfying, ,

' Section 4.2.2.3 unless a full core flux map has been taken in the previous 31EFPDwiththerelativethermalpowerhavingbeen maintained above APLNO 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- [ N) 3, over Z K has increased since the previous determination Fh(Z) either of

.the following actions shall be taken: -

/<

, t

1. F (Z) shall be increased by 2 percent over that specified in 4.2.2,4.c,or 9

r .

1 #

I t

,a, 3

r . .

INHA7 c (mor- 3 or 3)

2. (Z) shall be measured at least once per 7.EFPD until , -

2 sue:essive maps indicate that .

l Qximum['d(Z) is not increasing.

f. With the relationship specified in 4.2.2.4.c above not being .

satisfied,either of the following actions shall be taken: -

1. Place the core in an equilbrium condition where the limit in -

4.2.2.2.c is satisfied,and. remeasure (2),or ,

2. Comply with the requirements of Specification 3.2.2 for -

Fg (Z) exceeding its limit by the percent calculated with .

one of the following expressions: -

F$(2)xW(2)gt])-1]

x 100 for P > Apt ND

[(max. over z of [ 2.1r, y- x K(2) .

(Z)xW(2) ND

] ) -1 3 x 100 for 0.5 < P< APL

[(max. over 2 pof [ 315 _ K(Z)

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 plan regions: -

1. Lower core region 0 to 15 percent,inclusivo. -

2. Upper core region 85 to 100 percent inclusive. - -

m u.. . .

' * * ^

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0 2. 4 6 8 10 12 BOTTOM

, CORE HEIGHT ( FEET ) TOP FIGURE 3.2-2a K(Z)-

NORMALIZED Q F (Z) AS A FUNCTION OF CORE HEIGHT (UNIT 1)

McGUIRE -~ UNITS 1 and 2 3/4 2-12 Amendment No. 32 (Unit 1)

Amendment No.13 (Unit 2)

F . .

3/4.2 POWER DISTRIBUTION LIMITS

, BASES

• The specifications of this section provide assurance of fuel integrit during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the calculated DNBR in the core at or above the 4 design limit during normal operation and in shirt-term transients, and (2) limiting P(.

the fission gas release, fuel pellet temperatu~e, and cladding mechanical prop- P erties 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 acceptance criteria limit of 2200*Feis not exceeded.

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

F9 (Z) Heat Flux Hot Channel Factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing toler- '

ances on fuel pellets and rods; F

g Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of

" the integral of linear power along the rod with the highest integrated power to the average rod power; and (y*i*FxY(Z) -

Radial Peaking Factor, is defined as the ratio of peak power density to average power density in the horizontal plane at core elevation Z.

a -

3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the FQ(Z) upper bound envelope of 2.32 (Unit 2), 2.15 (Unit 1) times the normalized axial Q{

peaking factor is not exceeded during either normal operation or in the event ['

c of xenon redistribution following power changes. 2' Target flux difference is determined at equilibrium xenon conditions. '

l-Y(Thefull-lengthrodsmaybepositionedwithinthecoreinaccordancewith atheir respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels. The value of the t '

l hUtarget flux difference obtained under these conditions divided by the fraction )

j (P.of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER 3 < for the associated core burnup conditions. Target flux differences for other i, THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value g ;by the appropriate fractional THERMAL. POWER level. The periodic updating of

F J 'the target flux difference value is necessary to reflect core burnup

{ considerations. , ,

b McGUIRE - UNITS 1 and 2 8 3/4 2-1 Amendment No. (Unit 1)

Amendment No. (Unit 2)

, .w .~ c >

( . .

POWER DISTRIBUTION LIMITS

.. BASES .

AXIAL FLUX DIFFERENCE (Continued)

Although it is intended that the plant will be operated with the AFD within the target band 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 envelope of peaking factors which may be reached'on a subsequent ret 0rn to RATED THERMAL POWER (with the AFD within the target band)

" provided the time duration of the deviation is limited.' Accordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> d

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 target band but within the limits of Figure 3.2-1 d 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, devia-5 tions of the AFD outside of the target band are less 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 reduced 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 alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

ChMar oV for nit 1, e co ute dete ines e mi te a lrag of e ho the '

OJERA or detec ro puts nd pr ides na mm sage mme at ,

< l 'the FD or lea 2o 4 or of OPER Ee ore anne if U dA ower ace d,th ar ou ide de { /

' ing HER POV R is eat t n5 f /,

f A D Ty MAL WE 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, RCS flow rate, and nuclear enthalpy rise hot channel factor ensure that: (1) the design limits on peak local power density and minimum DNBR are not exceeded, and (2) in the event of i

a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS accep- -

l tance criteria limit.

L Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is sufficient to insure that the limits are maintained provided: .

McGUIRE - UNITS 1 and 2 8 3/4 2-2 Amendment No. (Unit 1)

Amendment No.

,,..n...+

(Unit 2) '

b. . .

I N % 12 T D For Unit 1. at power levels below APLhD . the limits on AFD are defined

by Figure 3.2-1/. i.e. that-defined by the RA0C operating procedure and limits.

These limits were calculated in a manner such that expected operational transients, e.g. load follow operations, would not result in the AFD deviating outsiderof those limits. However, in the event such a deviation occurs, the short period of time allowed outside of the lienits at reduced power levels will not result in l significant xenco redistribution such that the envelope.of peaking factors would change sufficiently to prevent operation in the vicinity of the APLND power level.

E At power levels greater than APLND, two modes of operation are permissible; '

1) RAOC, the AFD limit of which are defined by Figure 3.2-1g, and 2) Base Load

1. operation, which is defined as the maintainence of the AFD witpin a 13% band i 8 about a target value. The RAOC operatin OAPL is the same as

f. hat defined for operation below AFLND.However, g procedure it is above possible when following extended.1oad following maneuvers that the AFD limits may result in restrictions ,

in the maximum allowed power or AFD in order to guarantee operation with Fg(r) less than it's limiting value. To allow operation at the neximum per.nissible

~ value, the Base Load operating procedure restricts the indicated AFD to relatively _

small target band and. power swings (AFD' target band of 3%, APLND < power <_  !

APLBL or 100% Rated Thermal Power, whichever is lower). For Base Toad opeTation, it is expected.'that the plant will o>erate within the target band. Operation outside of the target band.for the s1 ort-time period allowed 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 from past operation on the Base Lead operation, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> waiting period at a power level above APLND and allowed by RAOC is necessary. During this time-period load

changes and rod motion are restricted to that allowed by the Base Load procedure.

After the waiting: period extended Base Load operation is permissible.

. O At t i r For Unit 1, the computer determines .the minute average of each of the OPERABLE excore detector outputs and provides an alann message irrediately if the AFD for -

l at least 2 of 4 or 2 of 3 OPERABLE excore channels are: 1)outsidetheallowed r

l AI power operating space (for RA00 operation), or 2) outside the allowed al target band (for Base Load operation). These alarms,are active when power is greater than: 1) 50% of RATED THERPAL POWER'(for RAOC operation), or 2) APL N D (for Base-Loadoperation). Penalty deviation minutes for Base Load operation are not accumulated based on the short period of time during which operation outside of

,,,the target band is allowed. .. ,

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-30% -20% -10% 0 +10% +20% +30%

INDICATED AXIAL FLUX DIFFERENCE

' FIGURE B 3/4 21.

s. TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWER v

McGUIRE - UNITS 1 and 2 B 3/4 2-3 n.. . . .

CHANGU POWER DISTRIBUTION LIMITS

• BASES '

HEAT' FLUX HOT CHANNEL FACTOR, and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

- a. Control rods in a single group move together with no individual rod insertion differing by.more than + 13 steps from the group demand

-position;-

b. Control rod groups are sequenced with overlapping groups ~as described in Specification 3.1.3.6; .

c. -The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and

d. The axial power distribution, expressed in terms of AXIAL FLUX

- DIFFERENCE, is maintained within the limits.

F will be maintained within its limits provided Conditions a. through

-d. above are maintained. As noted on Figures 3.2-3 and 3.2-4, RCS flow rate andFhmaybe"tradedoff"againstoneanother(i.e.,alowmeasuredRCSflow I rate is acceptable if the measured F is'also low) to ensure that the calcu-

~

H ,

' lated DNBR will not be below the design DNBR value. The relaxation of F as H

-a function of THERMAL POWER allows changes in the radial power shape for all

, permissible rod insertion limits.

Rt as calculated in Specification 3.2.3 and used in Figure 3.2-3, accounts for F H

less than or equal to 1.49. This value is used in the various accident analyses where F influences parameters other than DNBR, e.g., peak clad tem-H perature, and thus is the maximum "as measured" value allowed. R2 , as defined, allows for the inclusion of a penalty for Rod Bow on DNBR only. Thus, knowing -

the "as' measured" values of F N and RCS flow allows for " tradeoffs" in excess of R equal to' 1.0 for the purpose of offsetting the Rod Bow DNBR penalty, j Fuel rod bowing reduces the~ value of DNB ratio.

!' . partially offset this reduction.

Credit is available to This credit comes from a generic or plant-l specific design margin. For McGuire Unit 2, the margin used to partially l: offset rod bow penalties is 9.1%. This margin breaks down as follows:

I 1)' Design limit DNBR ,

1.6%

2) Grid spacing K 2.9%

s

3) -Thermal Diffusion Coefficient 1.2%

4) DNBR Multiplier 1.7%

5) Pitch Reduction ,

1.7%

McGUIRE - UNITS 1 and 2 8 3/4 2-4 Amendment !!o.32 (Unit 1)

Amendment No.13 (Unit 2)

. , .. m n. + n -

, e

[

J u o C 11A y (c GS POWER DISTRIBUTION LIMITS i BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY HOT CHANNEL FACTOR (Continued)

However, the margiri used to partially offset rod bow penalties is 5.9%

with the remaining.3.2% used to trade off against measured flow being as much

• as 2%N lower than thernial design" flow plus unceFtsinties.' The ' penalties applied  ;

to FaH to account for rod bow (Figure 3.2-4) as a function of burnup are consistent with"those described in Mr. John F. Stolz's (NRC) letter to T. M.

Anderson (Westinghouse) dated April 5, 1979 with the difference being due to the-amount of margin each unit uses to partially offset rod bow penalties.

For McGuire Unit 1, margin betw?en the safety analysis limit DNBRs (1.47 and 1.49 for thimble and typical cells, respectively) and the design limit

-DNBRs (1.32 and 1.34 for thimble and typical cells, respectively) is maintained.

A fraction of this margin is utilized to accommodate the transition core DNBR penalty (2%) and the appropriate fuel rod bow DNBR penalty (WCAP - 8691, Rev.1)

When an qF measurement is taken, an allowance for both experimental error '

and manufacturing tolerance must be"made. 'An allowance of 5% is appropriate for a full core map taken with the Incore Detector Flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance.

When RCS flow rate and Fh are measured, no additional allowances are

-necessary prior to comparison with the limits of Figures 3.2-3 and 3.2-4.  !

Measurement errors of 1.7% for RCS total flow rate and 4% for F g have been allowed for in determination of the design DNBR value.

The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators. Potential fouling of the feedwater venturi which might not be ~

detected could bias the result from the precision heat balance in a non-conservative manner.- Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi is included in Figure 3.2-3. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by  :

monitoring and trending various plant performance parameters. If detected, 1

action shall be taken before performing subsequent precision heat balance 1

measurements, i.e., either the effect of the fouling shall be quantified and l,

compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

• i The '12-hour periodic surveillance of indicated RCS flow is sufficient to '

detect only flow degradation which could lead to operation outside the accept-able region of operation shown on Figure 3.2-3.

McGUIRE - UNITS 1 and 2 B 3/4 2-5 Amendment No.32 (Unit 1)

Amendment No.13 (Unit 2)

. .n,n. - . -c -

W POWER DISTRIBUTION LIMITS

(.s

. BASES

. HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEA

. HOT CHANNEL FACTOR (Continued) -

ho cha nel ctor q'N(z) s me ured eriod all~ and i creas d by a cy ea he ht pende pow fact ,W , to rov' e ass ance }

li to the ot annel acto , F ( , is t the 4

q et. z) count for e ffe s y no al per . ion. nsie s an was termi ed f om exp ted I cond' ion in the core. T we con o) an ver av ~the 11 r ge o burn ,

.fu cti fo norm ope tion s pr ided i the Peaking Factor L mit W(z / f pr ecif catio 6.9 .9. port ~ 7 J

3/4.2.4 QUADRANT POWER TILT RATIO The QUADRANT P0WER TILT RATIO limit assures that the radial power distri-bution satisfies the design values used in the power capability analysis.

. Radial power distribution measurements are made during STARTUP testing and

periodically during power operation.

i -The 2-hour time allowance for operation with a tilt condition greater than '1.02 but less than 1.09 is provided to allow identification and correc-

~

tion of a dropped or misaligned rod. g 4

In the event such action does not cor-rect the tilt,'the margin for uncertainty on F qis reinstated by reducing {k-

i. the1,.0.

of power by 3% from RATED THERMAL' POWER for each percent of tilt in excess

-For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the. moveable incore detectors are used to confirm that

-the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.

flux map or two sets of four syametric thimbles..The incore detector monitoring is thimbles is a unique set of eight detector locations.The two sets of four symmetric C-8, E-5, E-11, H-3, H-13, L-5, L-ll, N-8. These locations are ~

l i

3/4.2.5 DN8 PARAMETERS The limits on the DNB related parameters assure that each of the para-meters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses.

. The limits are consistent

with the initial'FSAR assumptions and have been analytically demonstrated f adequate to maintain a design limit,DNBR throughout each analyzed transient.

. The 12-hour periodic surveillance of these parameters through instrument i readout is sufficient to ensure that the parameters are restored within their

) limits following load changes and other expected transient operation.

E l

1:

}

McGUIRE - UNITS 1 and 2 B 3/4 2-6 l Amendment No. (Unit 1) ,

l .

Amendment No.

. . . + . - .

(Unit 2)  ;

6 .-

I. .

INSEM7 E -

The a cycle hot and heichannel factor d(z) is measured periodically and increased by Load operation,ght dependent power factor appropriate to either RAOC or Base channel factor, Fo(z), is met.

W(2)orW(z)gt,W(z)accountsfortheeffectsofnormalto i tion transients arid was determined from expected opera- i the full range of burnup conditions in the core. power control maneuvers overW restrictive severe operating transient limits allowed by Base Load operatien which result in less i.

values.

the Peaking Factor Limit Report per Specification 6.9.1.9.The W(t) func I

I l

r. , ~ ~

ADMINISTRATIVE CONTROLS

, RADIAL

• PEAKING FACTOR LIMIT REPORT -

. ,e

6. 9.1. 9 The Fxy RTP limit for RATED THERMAL POWER (Fxy ) shall be provided to m the Regional Administrator of the NRC Regional Office, with a copy to the 2 Director, Nuclear Reactor Regulation, Attention: Chief, Core Performance

$ Branch,.U. S. Nuclear Regulatory Commission, Washington, D.C. 20555 for all core planes containing Bank "D" control rods and all unrodded core planes at a

E least 60 days prior to cycle initial criticality. In the event that the limit

• would be submitted at some other time during core life, it shall be submitted 60 days prior to the date the limit would become effective unless otherwise exempted by trie Commission.

Any information needed to support FRTP will be by request from the NRC and x

, need not be included in this report.

RAoc A~o ban tono

'The W(z) function 5for mer:Svoperation"Ago ws VAL 4 Fen APL (MRE%mEo)

Nuclear Reactor Regulations, Attention: shall be provided to the Director, Chief, Core Performance Branch, g U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 at least 60 days  ;>

s prior to cycle initial criticality. In the event that these values would be J E submitted at some other time during core life, it will be submitted 60 days u prior by thetoCommission.

the date the values would become effective unless otherwise exempted f,

}

l'$ ' W(2)gAMD APL"*

Any information needed to support W(2),"will be by request from the NRC and need not be included in this report.

l i

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

McGUIRE - UNITS 1 and 2 6-21 Am endmentNo.33(Unit 2)

. ,4,, . s . -

a

[ .; .s.

n Attachment 2 Justification and Safety Analysis 4

lThe McGuire Unit 1 Cycle 2.Zero Power Physics Testirg was performed April 27 through May 4,-1984. During the low power flux mapping a 7.5% quadrant power i

tilt was identified. ? Additional rod swap measurements were performed to evaluate the possibility of dropped control rods or broken rodlets. A review of the

_ core loading. videotape was also made. No cause for the tilt has been identified.

lA11(zero; power physics parameters met acceptance criteria except the all rods

-out hot zero power critical boron concentration and the radial power distribution.

, ..A' review of:the hot zero power.results was performed by Westinghouse before commencing power escalation.

Power' escalation was performed consistent with the Westinghouse position statement g con core tilt. Safety evaluations were perfcrmed'for the next power level plateau

-based on measured results of the current' plateau. . At 100% full power the measured incore quadrant power tilt decreased to 1.9% c.d the. measured power distribution met acceptance criteria; however, the power in the peripheral fuel assemblies remained. higher than predicted.

iDue to the quadrant power tilt and the in-out shift'in power distribution the

measured FAH and Fq were higher _than predicted but still less than the Technical

.  ; Specification limits. After.taking a flux map on June 6, 1984 it was determined that Fq"(z)

• W(z) exceeded the limit (2.15) by approximately 11% forcing a reduction

in the RAOC limits (AFD limits crossed at a maximum rated thermal power of 96%)

,such that unit operation is effectively restricted to 95% full power. Design predictions indicate that no improvement in F m(z) q

• W(z) or FAH is expected within

at least the~next-thirty to' sixty effective full power days (EFPD). In fact, further increases in Ffm(z) e W(z) or FAH may lead to further reductions in reactor 7 power level.

-The RAOC W(z). functions account for power peaking increases resulting from power

- maneuvering within the-allowed RAOC Power-AFD limits and do not allow credit

. .to'be'taken.for near steady state xenon distributions occurring during Base Load

0peration.- Because of the wide RAOC limits the corresponding W(z)'s are large.

- The proposed base load Technical-Specification-amendment imposes a tight 3% AFD _

band about'the target axial flux difference, a twenty-four hour equilibrium xenon

. hold, and limits on upper and lower power levels to ensure that no significant xenon' transients can take' place. The1 corresponding W(z)BL are therefore signifi-tcantly reduced when-compared to the RAOC W(z) values (as shown in the attached McGuire. Unit 1 Cycle 2 Peaking Factor Limit Report for RAOC and Base Load. Operation).-

10peration under the revised Technical Specification will essentially be RAOC U between 0% full power and the maximum power level allowed by the RAOC Technical-

Specification. - Should the maximum power level allowed by the RAOC Technical Specification be less than 100%' full power or if the RAOC AFD band width lLs

. less than 6% and;the other conditions for Base Load Operation are met, then the

' plant would be allowed to switch to Base Load Operation.

A e

r-- v,-w ->y.ry y- r-w+--e,-yp.,p, w-ey gw,--gi --A---

-o*9--1sm-m-ca- 9 % 9 -4

-py * - ---g-gyw' = g -

f..n.

m

' The ; expected benefits 'in Fq (z)

• W(z)BL will be higher allowed power levels (the unit will be able to return to full power), and a 3% AFD band about a -

measured target'to operate in instead of the single operating point caused by

. decreased RAOC limits (i.e., easier operation at power levels near peak power allowed by RAOC)..'In addition, the proposed amendment would prevent further derating of'~the unit which is possible without the new specifications.

The Reload Safety Evaluation for McGuire 1 Cycle 2 ensures safe operation for all' power levels including hot full power with RAOC operation. ~ Westinghouse has-performed the necessary nuclear design analysis to evaluate Base Load Operation:for McCuire 1, Cycle 2. A safety evaluation was performed by Westinghouse to address the impact of Base Load Operation on plant safety. Since the limits for Base Load Operation are a subset of the RAOC limits and maintain the same

' initial conditions: assumed for the transient safety analysis, operation in this

-mode was concluded to have no effect on the pla.it safety analysis. F n during Base Load Operation will be determined and an nilowed power level deffned

.as required.

Attachment 1 provides copies of the power distribution limits Technical Specifica-tions.as they presently appear in the McGuire Units 1 and 2 Technical' Specifications with the appropriate changes necessary to expand them to include both RAOC and Base Load Operation noted. Additionally, changes to the corresponding Bases and

~

administrative sections of.the specifications are also included.

Attachment 2A is the Peaking Factor Limit Report which is provided in accordance with the proposed spe'cification 6.9.1.9 as given in Attachment 1. The report's content has been amended to provide information which permits the exact deter-mination of W(z) versus core height as a functfon of cycle burnup through the use of three. point interpolation of three sets of bernup specific data. The report

.provides the elevation dependent W(z) values.that are to be used as inputs to define the appropriate fitting coefficients for W(z) interpolations to be performed

-as.a function of cycle burnup and axial elevation for RAOC and Base Load Operation, and the'value for APLND. The appropriate W(z) function is used to confirm that the Heat Flux Hot Channel Factor, Fq (z), will be limited to the values specified in the. Technical Specifications.

E

c. ,

Attachment 2A McGuire Unit 1 Cycle 2 Peaking Factor Limit Report for RAOC and Base Load Operation I &

u..a.. m.

{- -

AMENDMENT 1 JUNE, 1984 PEAKING FACTOR LIMIT REPORT FOR MCGUIRE UNIT 1 CYCLE 2 RAOC OPERATION This Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the McGuire Unit 1 Technical Specifications.

The McGuire Unit 1 Cycle 2 elevation dependent W(z) values for RAOC operation at beginning -middle, and near end-of-life are shown in Figures 1 through 3 respectively. This information is sufficient to determine W(z) versus core

~

height for Cycle 2 burnups in the range of 0 MWD /MTU to 10200 MWD /MTU through the use of three point interpolation. W(z) was calculated using the method described in Part B of Reference 1.

The appropriate W(z) function is used to confirm that the heat flux hot channel factor, Fq(z), will be limited to the Technical Specification values of:

Fq (z) f., 2.15 [K(z)] for P > 0.50 and Fq (z) < 4.30 [K(z)] for P < 0.50 The appropriate elevation dependent W(z) values, when applied to a power distri-

bution measured under equilibrium conditions, demonstrates that the initial conditions assumed in the LOCA are met, along with the ECCS acceptance criteria of 10CFR50.46.

t (1) WCAP-10216-P-A, Relaxation of Constant Axial Control - F Surveillance Technical Specification 9 f

A l

l W Ac .m

v .

.. f HE!Off MX (FEET) U(Z) ,

g,g 0 00 1 000 8 L l

" .29 1 000 a  !

l

' 40 1.000 * [

g,3 .se 1.sw a -

' .89 . 1.000 8

! IE 1.00 1.000 t i 1.29 1.000 8  !

, k# 1.4 1.m a i

1.G0 1.904 8 1.80 i k48 1.263 [

( ' 2.00 1.244 r 3.40 2.20 1.226  :

2.40 1.298 -

l..

2.60 1.189 [

2.80 1.170 l.S 3.00 1.155 l

• 3.20 1.148 i 8.2 3.40 1.151  ;

3.60 1.155 I 13 3.89 1.157 i 4.00 1.157 i g -3.3 4.20 1.156 {

4.40 1.155  ;

3 1,3

. 4.64 1.154  !

M 4.80 1.151 ,

5.00 1.148 E 3.3 8 <

5.20 1.144 i

i D 3,3 t

, 5.40 1.144 l 5.60 1.138 -

I I , 5.88 1.143  !

g,3 6.00 1.153 d '

E ' 6.20 1.162 '

I'E 6.40 1.166 l 5 ' 6.60 1.169  !

l'8 mer, e 6.80 1.174 i E E s' E 8 7.00 1.179 i I'38 st

, a.3 7.29 1.182  !

,E Es.

,us ,

7.49 1.184  ;

E 1l8 IE' '

7.60 1.184 kl4 0." 7.80 1.181 i bl3 8.00 1.176 r

, 8.20 1.179 '

1.10 8.40 1.159 1 8.60 1.150 '

L.

8.80 1.149  !

i 9.99 1.153 9.20 1.158 13 _,

9.48 1.1G2 g,ge

< 9.60 1.165 g l 9.80 1.171  ;

10 1.175 t i.g i 00

.2  !

. i. 1. i.S5 i...

i

= i

w . . . .

i::=  ;;=:  :

. ii.. . ii..e i .0 .  :

11.20 1.000 * '

tipE EIGHT FfET) 11.4e 1.Dee :

11.se 1.000 m ,

11.30

! 1.000 3 - l 12.e0 1.000  ;

r X Top and bottom 15 % excluded as per Technical Specification 4.2.2.2.g {

FIGURE 1 >

t l

McGUIRE UNIT 1, CYCLE 2 t

, t l  ?

RAOC W(z) at 150 MWD /MTU l r

• ^*N l a

T, .

WICHT fWof (FET1 WrZ1 e.to 1.e00 8 kW m.. -

.2e 1.006 *

. .40 1.000 3 8.te <

.60 1.eet 8

.Se 1.000 3 1.48 .. <

1.00 1 e00 3 [

1.20 1.000 8 i 8.44 < 1.44 1.000 t ,

1.64 1.00s 1 [

1.48 1.Se 1.189 '

2.00 1.188 i 3.ee 2.2e 1.185 2.44 1.181 83 2.64 1.174 2.88 1.167 I.5 '

3.00 1.165 -

3.2e 1.172 )

1.M 3.44 1.188 3.64 1.295 1.9 .II. r ' 3.88 1.223 -

1

\ E 4.00 1.238

'x 4.2e 1.251 Q

l.2 '

4.44 1.261 ,

E

(

• 4.64 1.269 .

La f i 4.80 1.274 g zaa" g 5.00 1.276 E 8 3 ,

3,3 _ _ ,,

)

5.2e 1.276 i

l- D g '

5.40 1.276 3,3 ,y 5.64 1.276  ;

i O 5.88 1.279 '

g,g , 6.00 1.291

• l l t s.2e 1.3e5 i

1.2e a < G.44 1.315 ,

( 6.G4 1.322 l

• a le 8 fr" a < S.Se 1.326

• 7.00 1.327 ,

i 3, 8 7.2e 1.324 ble l

( 7.44 1.316 ,

l bl4 7.50 1.306  !

7.80 1.296 (

1.12 8.00 1.284 i 8.2e 1.270 8.40 1.25. I

.ie 8.se 1.2ss ,

1.ge B.Be 1.260 i 9.0e 1.259 1.g 9.20 1.251  !

9.4e 1.241  !

9.54 1.247 g,m 9.88 1.261 10.0e 1.279

,,, i 10.20 1. m  !

10.4e 1.000 3 I g, g , . . . . ___. 10.64 e.. - -- .----- to.Be 1.000.

1.. 8 a.

L. 8.ee s. 8.. e.. . e.Se e.ee te,00 n.. A. ,  ;;;;;

11.4

t i

1.0o0 8 j tryE ff!Gif FIET) 11.se 1.cos a

! 11.Be 1.ees 8 --

12.8e 1.ees 8 i

s .

s -

l X Top and bottom 15 % excluded as per Technical Specification 4.2.2.2 9 .

t FIGURE 2 '

McGUIRE UNIT 1, CYCLE 2 RAOC N(2) at 4000 MND/MTU i

i

~m :' .

l -_. ..

~ __

s e . f

't l 14EIGHT f.X ,

(FEET) W(Z) $

gg " '

0.00 1.000 *

.20 1.000 8 40 k* ' 1.000 * }

.60 1.000 3 -

' .Se ~1.m a  !

I'# 1.00 1.000

• 1.E1 1.000 t k# '

1.46 1.000 E I 1.50 1.000

• k# <

1.r 0 1.194 2, se 1.182 kW <

2 20 1.171 I 2.40 1.160 kW <

2.60 1.149  !

2.80 1.138  !

LS 3.00 1.130 '

3.20 1.131 h3e ,

'3.40 1.144 '

- 3.60 1.159 C kg ,

3.80 1.175 4.00 1.188 '

g 1.3 ,

4.20 1.200 i

- 4.4e 1.210 2 g,g 4.60 1.218 l i

ar a 4.80 1.223 l E g,g 8x E, m '

5.00 1.225 '

5 20 1.226 b l* 3' E g

E 5.40 1.230 i 5.60

, . 1.238  !

o ,;:3 8 j u 5.80 1.247 i ga h3 3 5, ' 6.00 1.259 '

I .E, 6.20 1 269 l.2 r 6.40 1.272 a 6.60 1.274 I 1.10 hit a

8 6.80 7.00 7.20 1.276 1.277 1.275

+

g 7.40 1.271 ,

hl4 I ,

7.60 1.264 *

'g

, 7.80 1.252 (

ggg 8.00 1.236 '

8.20 1.217 l g,gg 8.40 1.211 t 8.60 1.216 '

8'E 8.80 1.226

• 9.00 1.233 '

9.20 1.235 l kW 9.40 1.235 l 9.60 1.223 '

8.06 9.80 1.224 i 10.00 1.230 89 10.20 1.249 v 10.40 1.000 *

• gg , ,- - - - . ---. . ... .

10.60 1.00 g,gg,0 a  !

7------

= = = = .. - 8.. . m.

Ig,gg y gyg pggg g 7.. 1= ii..

!!:=

u.4 i: :

i.000 ,

=

l.

11.60 11.80 1.000 g 1.000

• _(

12.00 1.000 ,

I e M Top and bottom 15 % excluded as per Technical  !

Specification 4.2.2.2 9 FIGURE 3 McGUIRE UNIT 1, CYCLE 2 i RAOC W(z) at 9000 MWD /MTU f s

e f

. - . . . . y

6 e PEAKING FACTOR LIMIT REPORT FOR MCGUIRE UNIT 1, CYCLE 2 BASE LOAD OPERATION /

This Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the McGuire Unit 1 Technical Specifications.

The McGuire Unit 1, . Cycle 2 elevation dependent W(z) values for base load operation between 80% at target value and 100% of rated thermal power with a 13 percent AFD about a measured 1200. 3000, and 6000 MWD /MTU Cycle 2 burnups are shown in Figures 1 through 3 respectively.

This information is sufficient to determine W(z) versus core height the use for Cycle of three 2 burnups point in the range of 1200 MWD /MTU to 6000 MWD /MTU thro interpolation.

in Part B of Reference 1. W(z) was calculated using the method described The minimum allowable power level for base load operation, APL'ND,,for McGuire 1 Cycle 2 is 80 percent of rated thermal power. The appropriate W(z) function is used to confirm that the heat flux hot channel factor, qF (z) will be limited to the Technical Specification values of:

Fq (z) ;$ *

[K(z)) for P > 0.50 and Fq (z) ;1 4.30 [K(z)] for P ;$ 0.50 The appropriate elevation dependent W(z) values, when applied to a power distribution measured under equilibrium conditions, demonstrates that the initial conditions assumed in the LOCA are met, along with the ECCS acceptance criteria of 10CFR50.46. _

(1) WCAP-10216-P-A, Surveillance Technical Relaxation of Constant Axial Control - Fq Specification

'd % 's *  %'

m...

y e ,

s '

s L

HEIGHT max (FEET) W(Z) i 1 0. 00 "* 1.000 2  !

2 .20 1.0e0 I LW . .

3 44 1.000 a i

< 4 .6e 1.000

• Lee 5 .89 1.006 *  !

, 6 1 00 1.000 *  !

1.es 7 1.24 1.00s *

' 8 1.44 1.000 8 g,ee 9 1.64 1.000 3 10 1.84 1.070 2.00 g,q 11 1.068 12 2.24 1.066 1.as 13 2.40 1.063 14 2.68 1.061 1.2 15 2.88 1.058 ,

16 3.04 1.055  !

R.E 17 3.20 1.051 r gg 3.40 1.048 19 3.60 1.e46 1.3' 29 3.80 1.e44 -

21 4.00 1.e43 1.2 22 4.20 1.041 ,

23 4.40 1.040 t LW 24 4.64 1.039 b < 25 4.80 1.037 2 8.3 26 5.00 1.038 i w , 27 5.20 1.042 l E L3 28 5.40 1.e46 29 5.64 1.054 8 3.34 30 5.88 1.054

, 31 6.00 1.062 O g,3 32 6.2e 1.069  !

s' 33 6.40 1.e72  ;

I.30 34 6.68 1.074 t E 6.86 1.e77  !

1*18 36 7.00 1.979 37 7.20 1.030 7.44 38 1.081 ,

bl8 39 7.60 1.081

, 48 7.84 1.081 ,r bl* 41 8.00 1.031 i f

42 3.20 1.00e bl2 43 B.48 1.079 .

' 44

, E.60 1.076 '

l.10 45 3.se 1.e74

. . 46 9.00 1.072 i IA gE8' m""' M ;;33 ; :IIIX: 3 47 9.20 1.e?! i-g gI'"

. 48 9.44 1.072 LW-

• I 49 9.6e 1.073 N g 50 g.33 1,073 Let E'I "- .I Si te.se g.e73 52 10.20 1.075

1. n 1 .4 ... .

54 1. 6. i.ee. .  :

i. === - .

= it:  ;;;= = -

1 M l.00 &W 15 43 Em W '%W 8.5 &W R&B lla Ib5 57 11.20 1.000

• 53 11.4e 1.000 s .

59 11.e3 1,ges g ,.

CGE E!Qs M et 11.30 1.000 3 61 12.ge 1. gee a X Top and bottom 15 % excluded as per Technical Specification 4.2.2.4 9 FIGURE 1 ,

McGUIRE UNIT 1, CYCLE 2 .;

BASELOAD N(z) FOR POWERS BETWEEN 80% AND 100% OF RATED THERMAL POWER WITHIN t.,3 PERCENT AFD OF THE MEASURED TARGET 1200 MWD /MTU  !

.,n # y,

, - . . -- -.-,_.,-,.,,---,__...,.,_,,-,,.----..,-.-..,.._..,----._.,,n,,,---n----ne-,, , ,- - - - , - - - -

j ,

/  :

e.

• I i I l 6 l

t 1

t i

l i

HEIGHT MAK '

(FEET) W(Z) '

g,g ,

1 0.5. l.gm e E .M t.See o gg '

3 .ee t.gse .

" * .se s.ame e bN ' S .g. 1.ges e

' $ 1.59 1.ges a

@ < 7 f .M 1.ges e  !

i S f.ee 9.ges e I I.e , e 1.83 1.33e e to s.go

, i. ors 18 l

u, -

, f.se l in e.= .f.e73 13 2.4e g.ggy g '

14 f.59 g.gs3 15 f.M t.gge t

b5 i t$ 3.h I

• 17 3.m ,t.gs

.355, i 18 3.4e 9.pos  !

fo 3.Es 1. pes km < M 3.m 1.ogg  !

, es . s.

, af  !

3,3 4.2e 3. qq ,

E r3 e. e s. es  ;

N 4.se i.e39

'3 g '

N 4.M l, 1.e3s I '

N rF as 5.ge 5.29 5.43 1.e3s

t. Des j

g@ ' fe 5.a.

t.seg t.egy j

r

• M 5.m 1.mt

• lee < 31 M

6.m 1.me l 6.29 f. ass lag , 33 6.4e 3.gsy 34 6.Ge t.gse Igg gg

. M 3E 37 6.5 7.2 7.Je 1.WFt 1.WFe 1.or3 M 7.9s 1.oM

" M 7.Ge 1.pps I'!9 49 7.as 3.37s t l 99 8.m 1.gM  !

blt *e s.as s.ryg  !

a e s.go 1. ore his

< ** 3.go t.syg a

as e.  !

3,3 ,

• o.as i .e,ye, e o.as t. ors i

EI gE._ EEgtgIEE[gggg; ggEE '" # o.4 1. ppg

_g _ .E

• o.se f.yys

,E 9e o.m Egg, , EEE '

83 f.e75 8e*em 1.975 r

A ug.' ,

l , I8 I.eF7

[ lag , 53 te.'IE go g,ggg . p 7

i 94 to.es 1.33,.e j

! gg m . _ _ _ . .. __ , 88 8e.M

[

se it.g. ,t.ses

,g,e e ,

M isSB &W 15 45- ES &W %e 65 &G 16 5 Itse M s7 l 1 me . t se 1,s.as

.e. ,e.a,,

,g , ,

to vs.se s.ame .

se si.83 .. e , i, CS E IftCNr R ETI et se.as i.ege .  ;

i i

b i

X Top and bottom 15 % excluded as per Technical Speci fi cation 4.2.2.4 9  ;

r FIGURE 2 '

t McGUIRE UNIT 1, CYCLE 2  !

DASELOAD W(z) FOR POWERS BETWEEN 80% AND -100% OF RATED THERMAL POWERI WITHIN + 3 PERCENT AFD OF THE MEASURED TARGET f

i 3000 MWD /MTU i

.4 .  :

l. .

en v .

a * .

b i  %

l l

1 HEIGHT Max (FEET) w(Z) .

i I

l 9 8.0e 1. sus e 2 .25 9. sus e j 3 4 9.33e e 4 . $.8 f.Ses e 1.4 5 .se f.cos e g 5 1.m t.ses e =

l. gg 7 1.2e 9.ses e I 8 9.45 1.ges e '-

i g,g e 1.8e 9.ege e {

19 0.05 f.855 I g,g - 19 2.33 1.ges 17 2.25 9.s?$

g,g 13 f.48 1.s71 14 f.Ge 1.tes ,

gm 15 f.m 1.ame  !

15 3.55 9.54 17 3.2e - t.ses a 18 3.4s 1. egg 33 to 3.de 1.e44 y j 25 3.gs 1.e43 i l

33 21 4.as f. pet t 22 4.23 9.egt p 3.3 E3 4.e 3.33s .

- 29 4.M 1.37F 2 g,, 25 4.as [

3.33 g gg 27 g,ge g,g33 ,

l l E 3.3 5.2m 1. 3 33 i

as 5.4s f.e33 3.3g 5 5.Ge f.e3s i P- 3e 5.as 1.sas i 3.ar 31 6.ge f.ses "d 32 s.2e f.es3 i 8.3 23 s.e f.as7  !

) 34 6.Ee 1.5e l

' .. M 6.as 1.ast -

l 3s 7.e. 1.as4 '

L

3. 5 3F 7.23 1.gus M 7.45 1.

I.3% 3e 7.se 9..ese I

1. 7.98 9.ert j 8.82 49 s.se f.ert 42 S.2e f.e72  !

Bel $ 43 3.gg 1.s71 ,

44 S.Se f.eTE 5 *

, I*#

'I E 8*88 1* F3 i i Iaaa ;. 48 p.Es 1.'75s '

I IIII iIII g ' gy

( IE I 2 t D.Es f.sps Ia 48 8.# 1.s77 +

M Egy,,I=sg 4e e.85 1.e77 III * '

$=# 59 te.se t.'Syy Ef 10.23 1.377 8.W ' ::: l  :"- 53 is.4s 1,gge s -

^ :: :::::: $4 i

&W 8.5 3.M &Os 49 S.5 kW 3.0. hte te.as g,ggg e l S.Se 94 5 31. 3 S&ge S5 te.Se 1.333 e t SS 15.e. t.gge e  ;

CW. EIM FE $7 ft.as 9.ame e 5e 98.4e t aus e Se it.as 9. mas e M St.h 1.sge e el te.= 0.ame e i

X Top and bottom 15 % excluded as per Technical Specificati>'n 4.2.2.4 9 FIGURE 3 1 e t McGUIRE UNIT 1, CYCLE 2 .

BASELOAD N(z) FOR POWERS BETWEEN 80% AND 100% OF RATED THERMAL P WITHIN + 3 PERCENT AFD OF THE MEASURED TARGET 6000 MND/MTU U _%.- .

e o D Attachment 3 Analysis of Significant Hazards Consideration As required by 10 CFR 50.91, this analysis is provided concerning whether the10 by propased amendments involve significant hazards considerations, as defined CFR 50.92.

Standards for determination that a proposed amendment involves no significant hazards considerations are if operation of the facility in accordance with the proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or 2) create the, possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety.

The proposed amendments would expand the Power Distribution Limits section of the McGuire 1 Technical Specifications to include base Load Operation in addition to the currently approved RAOC operation. Base Load Operation is defined as

-operation within a 3 percent AFD band about a measured target in a power range to be specified in the peaking factor limit report.

Since Base Load Operation is a subset of RAOC, the amendments would not increase the probability of an accident previously evaluated, and could not create the possibility'of evaluated. a new or different kind of accident from any accident previously The Reload Safety Evaluation for McGuire Unit 1 Cycle 2 ensures safe operation for all power levels including Fot full power with RAOC operation.

A safety evaluation was performed by Westinghouse to address the impact of Base Load Operation on plant safety. Since the limits for Base Load Operation are a subset of the RAOC limits and maintain the same initial conditions assumed for the transient safety analysis, it was determined that the conclusions of the Reloid Safety Evaluation will remain valid for Base Load Operation. Therc-fore, since no changes to accident analyses are necessary the proposed amendments do not involve a reduction in a margin of safety or an increase in the consequences of an accident previously evaluated.

Based upon the preceding analyses, Duke Power Company concludes that the proposed amendments do not involve a significant hazards consideration.

.