ML20236Q969

Proposed Tech Specs Making Changes to Ensure Plant Operation Consistent W/Design & Safety Evaluation Conclusions in Reload Safety Evaluation for Unit 2,Cycle 2

ML20236Q969
Person / Time
Site:	Catawba
Issue date:	11/13/1987
From:	DUKE POWER CO.
To:
Shared Package
ML20236Q968	List: ML20236Q965 ML20236Q969 ML20236Q996
References
NUDOCS 8711200391
Download: ML20236Q969 (46)

Text

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• F# U l

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

When in MODE 3 or 4, at least once per 24-hours by consideration of the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control' rod _ position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross thermal energy generation',

5)

Xenon co'ncentration, and 6)

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1% ak/k at least'once per 31 Effective l

Full Power Days (EFPD).

This comparison shall consider at least those factors l

stated in Specification 4.1.1.1.le., above.

The' predicted' reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each' fuel loading.

i l

l 4171?ini-(ttntr 2:enly) At leest :nce-per lo menths, the R ::ter ":Rep Watar' nn=nc cnai

• d:::nstected OPE"^."LC b, verifying' a tota! codined flu ra+e

^#

-1*"-thr equd--to=440 sp.- zi:d : T h cote of ic s than=evrequat W 120 gpr.

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,for u d e p-c l

4,14 M (Unit 4 Orly) at l ees t er:ce g :r 21 46 5.,- winhJr "00E A, one 7

4enete...Jeve o'etcr pump ;h i' be 4 -m:L :L;d ;,,,, 41

.m.- : i,, i r.; t %t i

the.T.:te. d.. it ir::ker i: :: cur:d '- t M rper peiti+n.-

l CATAWBA - UNITS 1&2 3/4 1-2 AmendmentNo.g(Unit 1)-

Amendment No. A(Unit 2)-

___ m

-]

1 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T

< 200 F ava -

LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1% Ak/k.

APPLICABILITY:

MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 1% Ak/k, immediately initiate'and continue boration at greater than'or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the. required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1 2 The SHUTDOWN MARGIN shall be determined to be greater than or equal.

k/k to 1% V:

a.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod (s) and at least once per 12. hours thereafter wnile the rod (s) is inoperable.

i 1

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untripp.ible control rod (s); and b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1)

Reactor Coolant System boron concentration, l

2)

Control rod position, l

3)

Reactor Coolant System average temperature, 1

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4)

Fuel burnup based on gross thermal energy generation,

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5)

Xenon concentration, and 6)

Samarium concentration.

per 15 irientim, cos eadw cmkeup 'itr $

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i CATAWBA - UNITS 1&2 3/4 1-3 Amendment No. M unit 1)

Amendment No. X(Unit 2).

')

- - - _ - - a

w l

'l

' REACTIVITY CONTROL SYSTEMS-

' CONTROL BANK' INSERTION LIMITS t

LIMITING CONDITION FOR OPERATION' 7-

~

i 3.1.33'

'c'entrol banks shall be-limited in.phy ical. insertion as shown.-

1 in Fi-e/ 3.1-1/ (Uri t 1) ' =d 3.1-1L (Ur" ' 2).

APPL CABILITYi ' MODES 1* and'2*#

ACTION:

With the control banks inserted beyond the above insertion limits, except.for surveillance testing pursuant-to specification 4.1.3.1.2:

a.

Restore the control banks to within-the limits.within:2 hours, or b.

Reduce. THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or' equal to that fraction of RATED THERMAL POWER which is allowed by the. bank position.

using the'above. figure, or.

l c.

Be in at'least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l SURVEILLANCE REQUIREMENTS

-(

4.1.3.6-The position of each control bank shall be determined to be'within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time: intervals-

'I when the Rod Insertion Limit Monitor is inoperable, 'then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

1 s

• See Special Test Exceptions Specifications 3.10.2 and 3.'10.3.

1. With-K,ff greater than or equal to 1..

CATAWBA - UNITS 1&2 3/4 1-21 Amendment No.1 Unit'1)

Amendment No..

Unit 2)'.

v

(/

(Fully Withdrawn) i 228 29 % 228 (79 %, 228) 1 220

)

200 BANK B 180 c

(100 % 161) l 160 (0 % 162) j j

S BANK C 140 -

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Relative Power (Percent)

FIGURE 3 1/

ROD BANK INSERTION LIMITS VE SbER5fA POWER FOUR LOOP OPER N "JN T 1l AmendmentNo.(((Unit 1 CATAWBA - UNITS 1 and 2 3/4 1-22 Amendment No.

(Unit 2)

((b (FULL WITH D WN) 228

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10 20 30 40 50 60 70 80 100 (FULLY RELATIVE POWER (PERCENT OF R ATED THERMAL POWE )

INSERTE FIGURE 3.1-1b l

ROD BANK INSERTION LIMITS VERSUS THERMAL POWER g

FOUR LOOP OPERATION (Unit 2)

CATAWBA - UNITS 1 AND 2 3/4 1-23 Axuendment No, 14 (Unit 1) l Amendment No.

6 (Unit 2)

j 3/4.2-POWER DISTRIBUTION LIMITS

)

3/4.2.1 AXIAL FLUX DIFFERENCE ( FD) ;0 HIT 1)

)

k LIMITING CONDITION FOR OPERATION i).

3.2.,Y The indicated AXIAL FLUX DIFFERENCE (AFD) shall be. maintained within:

\\

l the allowed operational space defined by Figure 3. -1)( for RAOC 1

a.

operation, or 1

i 1

b.

within a 13% target band about the target flux difference during i

i baseload operation.

~

i APPLICABILITY:

MODE 1, above 50% of RATED THERMAL POW 6: 1.

1;.*

I ACTION:

a.

For RA0C operation with the indicated AFD outside of the Figure 3 2-1 l i n. i ts,

1 1.

Either restore the indicated AFD to within the Figure 3.2 l

limits within 15 minutes, or

(

j 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 Base Load operation above APLND" with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target flux difference:

4 4

1.

Either restore the indicated AFD to within the-target band limits I

within 15 minutes, or 2.

Reduce THERMAL POWER to less than APL"U of RATED THERMAL POWER and discontinue Base Load operation within 30 minutes.

'l c.

THERMAL POWER shall not be increased above 50% o RATE THERMAL POWER l

unless the indicated AFD is within the Figure 3.2-M l' its.

J l

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• See Special Test Exceptions Specification 3.10.2.

ND

• • APL is the minimum allowable power level for base load operation and 'will be provided in the Peaking Factor Limit Report per Specification 6.9.1.9.

CATAWBA - UNITS 1&2 3/4 2-1 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

-{

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS J

^

4.2 1X The' indicated' AFD shall be determined to be within its limits during 7

POWE OP ATION above 50% of RATED THERMAL POWER by:

i a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1 1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, i

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 />'after restoring the AFD Monitor Alarm to OPERABLE status.

b.

Monitoring and logging the indicated AFD for each OPERABLE excore p

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 inoper-able.

The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

c.

The provisions of Specification 4.0.4 are not' applicable.

4.2.

.2 The indicated AFD shall be considered outside of its limits when at least4wo OPERABLE excore channels are indicating the AFD to be outside the

'f limits.

4.2.

When in Base Load operation, the target axial flux difference of eac OP RABLE excore channel shall be determined by measurement at least once

)

per Effective Full Power Days.

The provisions of Specification 4.0.4 are

(

not applicable.

[

i

4. 2 1X. 4 When in Base Load operation, the targ'et flux difference shall be upd at least once per 31 Effective Full Power Days by either determining i

the target flux difference in conjunction with the surveillance requirements of i

Specification 3/4.2.2 or by linear interpolation between the most recently mea-i sured values and the calculated value at the end of cycle life.

The provisions of Specification 4.0.4 are not applicable.

l CATAWBA - UNITS 1&2 3/4 2-2 Amendment No.

(Unit 1)

Amendment No.

-(Uni t-2)

~

I 1

5 0

3 Y

O a:

J4 u.

O E

5 2:

( 20, 100)

(10, 100) 100 UNACCEPTABLE UNACCEPTABLE OPERATION j

OPERATION ACCEPTABLE

~

OPERATION 60 I

(-36, 50)

(21, 50) 40 I

l l

1 I

20 l

l I

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0 50

-40

-30 20

-10 0

10 20 30 40 50 Flux Difference (All%

l

=-

FIGURE 3, -1g AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTI' N OF RATED THERMAL P E P - r :e -

l l

3/42-3 Amendment,No.

(Unit 1) l CATAWB A - UNITS 1 and 2 Amendment'No.

(Unit 2)

L

- - -- a

I i

\\0WERDISTRIBUTIONLIMITS h

p/

AX FLUX DIFFERENCE (UNIT 2)

N LIMITINb\\ ONDITION FOR OPERATION

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I l

3.2.1.2 The dicated AXIAL FLUX DIFFERENCE (AFD) shall be maint ned within the following rget band (flux difference units) about the targ flux difference:

a.

5% for cle 1 core average accumulated burnup of' ess than or equal to 00 MWD /MTU; b.

+3%, -9% for ycle 1 core average accumulated rnup of greater l

than 5000 MWD TU; and j

/

]

c.

+3%, -12% for su equent cycles.

The indicated AFD may deviate outside the above r uired target level at greater than or equal to 50% but less han 90% of RATED ERMAL POWER provided the indi-cated AFD is within the Accepta

.e Operation Li its of Figure 3.2-1b and the l

cumulative penalty deviation time-does not ex ed 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The indicated AFD may deviate outsid the bove required target band at greater j

than 15% but less than 50% of RATED T 8 L POWER provided the cumulative penalty deviation time does not exceed shour during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

N MODE 1, above 15% of ' ATE '\\ THERMAL POWER (Unit 2).*

l APPLICABILITY:

f

/

ACTION:

a.

With the indicated AF outside of the above required target band and with THERMAL POWER

' eater than or equ 1 to 90% of RATED THERMAL POWER, within 15 minutes, >ither:

y 1.

Restore th indicated AFD to within t e target band limits, or 2.

Reduce T RMAL POWER to less than 90% o RATED THERMAL POWER.

b.

With the i icated AFD outside of the above req ired target band for more than hour of cumulative penalty deviation imes during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outside the Acceptable Operat'on Limits of Figure

.2-lb and with THERMAL POWER less than 90% ut equal to or l

great than 50% of RATED THERMAL POWER, reduce:

1.

THERMAL POWER to less than 50% of RATED THERMAL PO ER within 30 minutes, and

• See, ecial Test Exceptions Specification 3.10.2.

C4 W A - UNITS 1&2 3/4 2-4 Amendment No.14 (Unit Amendment No. 6 (Unit 2 4

f

)

1

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v/

JN POWER DISTRIBUTION LIMITS

/

LI TING CONDITION FOR OPERATION

./

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tz ACTIO (Continued),

2.

The Power Range Neutron Flux * - High Setpoints t less than or equal to 55% of RATED THERMAL POWER within the ' xt 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

]

f c.

Wi the indicated AFD outside of the above requi' d target band for mor 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 deviation

ime during the pre-vious'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 tha 50% but greater than 15% of' ATED THERMAL POWER, the THERMAL POWER hall not be. increased

]

equal t or greater than 50% of RATED THERMA / POWER until the'indi-a cated AF is within the above required tar t band.

SURVEILLANCE REQUIREME TS 1

If

//

s 4.2.1.1.2 The indicated shall be determi d to be within its limits during POWER OPERATION above 15% o RATED THERMAL P, ER by:

a.

Monitoring the indic ted AFD fo each OPERABLE excore channel:

1)

At least once per ' day when the AFD Monitor Alarm is OPERABLE, and j

2)

At least once per hp 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 Monitor A mt OPERABLE status, b.

Monitoring and loggi the ind ated AFD for each; OPERABLE excore channel at least o per hour r 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 i

once per 30 minut thereafter, en the AFD Monitor Alarm is inoper-able.

The logge values of the in 'cated AFD shall be assumed to exist during t interval preceding ach logging.

4.2.1.2.2 The indicat ' AFD shall be considere utside of its target band when two or more OPER LE excore channels are ind ating the AFD to be outside the target band.

Pe'alty deviation outside of the ove required target band shall be accumulat on a time basis of:

a.

One mi ute penalty deviation for each 1 minut of POWER OPERATION outsi e of the target band at THERMAL POWER 1e is equal to or above 50% f RATED THERMAL POWER,'and

/

• Surveill 'nce testing of the Power Range Neutron Flux Channel y be performed i

pursua to Specification 4.3.1.1 provided the indicated AFD i maintained withi the Acceptable Operation Limits of Figure 3.2-lb.

A tota of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> ope tion may be accumulated with the AFD outside of the above re ired target b

during testing without penalty deviation.

CATAWBA - UNITS 1&2 3/4 2-4a Amendment No.14 (Un 1)

Amendment No. 6 (Unit 2)

P DISTRIBUTION LIMITS k

SURVElthANCE REQUIREMENTS (Continued) b, e-half minute penalty deviation for each 1 minute of P ER OPERATION o'- side of the target band at THERMAL POWER levels betw en 15% and 50 of RATED THERMAL POWER.

\\

4.2.1.2.3 The rget flux difference of each OPERABLE excore channel sha31 be determined by me urement at least once per 92 Effective Ful Power Dayt.

The provisions of Spec fication 4.0.4 are not applicable.

4.2.1.2.4 The targe flux difference shall be updated a least once per i

31 Effective Full Powe Days by either determining the arget flux difference pursuant to Specificati 4.2.1.2.3 above or by linear interpolation between the most recently measur value and 0% at the end o cycle life.

The provi-sions of Specification 4.

'4 are not applicable.

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CAJAWBA-UNITS 1&2 3/4 2-4b Amendment No.14 (Unit 1)

Amendment No. 6 (Unit L

b' Yg N 4 0

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..===.._.y.=.. :..n !=- t. _..t=.. -=--

'I L _j_

.! _.-._.ti.z.:P:t....E-E. i.1:i.n.2..i.l:E4=... i =.. - +4 r

1 y.

+

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

_ _ z r n,..._

=..h

3.2 =: =.==~

._ +. ::,. _.; _.. : =.. ri.=.= =- q g 1 = :

. = _. _.

-r

.._, j.

g :.,_-.-

W

-.s

-. =. _..= _ -. --t -

- _.,.. - - - -~f _- :

t\\.

r---

+ + -

O:

=

. -

120

._. w

__7

o.;=

- - - + - - -

a w.s+

=....

.4 4

.f

..x xE.

.- -r u. E 5=__

.l

= - -

. O w -__. _, -

___.___1

=

2

. UNACCEPTABLE 2.

-. g

• g_..

-i]rt OPERATION 100

~~~i U N CEPTABLE EEiH 6

--OPE

. TlON

~~5 E =1 ~~

= _.

_.-- ( 1 1,9 0 ) _..-... (11.90):- = =,_.-_.

g

=..

4 g

i

.y. i *=: ~.: -*~y.1: : **~ *..

- -' Y.=..^;~=./l.

g.

,; ;;. ;n;.

-., ;n;,

- :_y

,J 4

E

_ 4 : * : :.:'.. -...

. T..:" #-~ ~~'*. - ^

+m=4*---C

_.- 4.. - :-;== %; "-nf=

n; -

4.'

g 80

.g; 7,y --.

m

==.g.__

f g

n z:== =

rs

+

e

.A.

e' W

"--~=:/ }g.=:rQ-

/

\\_

w

-- =-

=.

g

~-'

60' o

/~~ ACC(PTABLE OfgRATION".

+

/

/i t

x

=

y 0

(. 31. 50) -

mi./

(31,50)

E W

=-

.i A

','L 40 t

m

+

/

'l+-

. f*

l' w._.

[

~' **

M 20 II...l;.= ; := h=

"=

~

s 1

7..

!:)iEi :-:=

\\

1 j;..

j

.: a./:. :[. :, =....-}-__

0 50 40 0

20 10 0

10-20 30 40 50 FLUX DIFFERENCE (61) %

FIGURE 3.2-lb

/

s

' AXIAL FLUX OlFFERENCE LIMITS AS A' FUNCTION OF

\\-

RATED THERMAL POWER (Unit 2) n.;

/

/

Amendment No.14 it 1)

CATA.

, UNITS 1 AND 2 3/4 2-4e Amendment No.

6 ( n t 2)

4 POWER DISTRIBUTION LIMITS e

HEATFLUXHOTCHANNELFACTOR-FbZ)

3/4.2.2

_1)-

LIMITING CONDITION FOR OPERATION y

j 3.

2)(

q(Z)-shall be limited'by the following relationships:

[

F (Z) $ [2.32] [K(Z)]'for P > 0.5 0

P F (Z) 5 [4.64]'[K(Z)] for'P 5 0.5-9 Where:

P _ THERMAL POWER

, and RATED THERMAL POWER K(Z) =,th'e7unctionobtainedfromFigure3.2-2for.agivencore-heigh locatiorr APPLICABILITY:

M00 1 0 :; 1).

f ACTION:

With F (Z) excee its limit:

q a.

Reduce THERMAL POWER at least 1% for each 1% F (Z.) exceeds the limit' q

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 (value of K ) have 5 4

been reduced at least 1% (in AT span) for.each 1% F (Z) exceeds the limit, and 9

b.

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

q l

)

lj H

i CATAWBA - UNITS 1 & 2 3/4 2-5 Amendment No., (Unit'1)-

Amendment No.

-(Unit'2)

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2 X1 The provisions of S edification 4.0.4 are not applicable.

).

4.2.

.2 For RA0C operatior F (z) shall be. evaluated to determine if F (z).

q is w thin its limit by:

I a.

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

b.

Increasing the measured F (z) component of the power distribution 9

map by 3% to account for manufacturing toleranceq and further in-creasing the value by 5% to account for mepsuremqnt uncertainties.

VerifytherequirementsofSpecification3(.2.2)(/aresatisfied.

/

s c.

Satisfying the following relationship:

M 2.32 x Mz)

Fq (z) 1 for P > 0.5 P x W(z)

M 2.32 m K(z)

Fq (z) $

for P $ 0.5 W(z) x 0.5 where F"(z) is the measured F (z) increased by the allowances for-9 manufacturing tolerances and measurement uncertainty, 2.32 is the F limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL g

POWER, and W(z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.

This function is given in the Peaking Factor Limit Report as per Specification 6.9.1.9.

M d.

Measuring Fq (z) according to the following schedule:

1.

Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which F (z) 9 was last determined,* or 2.

At least once per 31 Effective Full Power Days, whichever occurs first.

1

)'

• During 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 j

power distribution map obtained.

]

CATAWBA - UNITS 1&2 3/4 2-6 Amen'dmentNo.k(Unit 1).'

Amendment No. M (Unit 2) i

i

]

POWER DISTRIBUTION LIMITS 1

i SURVEILLANCE REQUIREMENTS (Continued) 1 e.

With measurements indicating

,7 j

. maximum hF (z) k

( K(z) /

over z M

has increased since the previous determination of Fq (z) either of

.(

.l the following actions shall'be taken:

M q (z) shall be i.ncreased.by 2% over that 'specified in 1)

F Specification 4.[

!2c.,or q (z) shall be measured at least once per 7 Effective Full l

2)

F Power Days until two successive maps indicate that

\\

maximum F (z) is not increasing.

Over Z K(z) j f.

With the relationships specified in Specification 4.

2)(. g. above' i

not being satisfied:

1)

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

expression:

D ' )I 9

N (z)xW(z)h r

[ maximum F

(

-1 x 100 for P'> 0.5

,over z 2.32 x K(z)

P y

e FM (z) x W(z)

[ maximuni

-1 x 100 for P < 0.5 over z 2.32 x K(z) 0.5 2)

One of the following actions shall be taken:

)

a)

Within 15 minutes, control the AFD to within'new AFD li which are determined by reducing the AFD limits of 3.2 IX b 1% AFD for each percent F (z) xceeds its limits as'det q

mined in Specification'4.2.2 X. f.1).

Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset:

f' the AFD alarm setpoints to e modified limits,"or I

b)

Comply with the requirements of Specification 3.2 2X for'

\\

F {z) exceeding its limit by the percent calculate.above, or.

q c)

Verify that the requirements of Specification' 4.2 2M 3 for -

Base Load operation are satisfied and enter Base L operation CATAWBA - UNITS 1 & 2

.3/4 2-7:

. Amendment'No.

'(UnitT1)

~

Amendment No.

(Unit 2).

__--_-_-___2,

/

POWER DISTRIBUTION LIMITS

)'

{

SURVEILLANCE REQUIREMENTS (Continued) 1

)

The Jinit s specified in Specifications 4.2.h. c., 4.2 fA. e., and l

g.

4.2f f., above are not applicable in thh ollowing plane

\\

regions:

j 1.

Lower core region from 0 to 15%, inclusive 2.

Upper core region from 85 to 100%, inclusive.

ND i

4. 2.(2)it 13 Base Load operation is permited at powers above APL if the following

/

conditi$nsaresatisfied:

/

i t

a.

Prior to entering Base Load operation, maintain THERMAL POWER above and less than or equal to that allowed by Specification 4.2.h2

)

ND APL

)

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 surveillance (AFD within 3% of target flux difference) during this time period.

Base Load operation is then permitted providing THERMAL

(

POWER is maintained between APL"O and APL or between APL"O and BL 100% (whichever is most limiting nd FQ surveillance is maintained BL

)

pursuant to Specification 4. '.2A..

APL is defined as:

APLBL = minimum g

] x 100%

(

32 x K(Z) ver Z Z) x W(Z)BL

)

M where:

F (z) is the measured F (z) increased by the allowances for

/

9 manufacturing tolerances and measurement uncertainty.

The F limit j

q is 2.32.

K(z) is given in Figure 3.2-2.

W(z)BL is the cycle dependent l

function that accounts for limited power distribution transients l

encountered during base loa:: operation.

The function is given in the 1

Peak Factor Limit Report as per Specification 6.9.1.9.

b.

During Base Load operation, if thefTHERMAL POWER is decreased below ND

\\

APL then the conditions of 4.2 Jir 3 a hall be satisfied before x

re-entering Base Load operation.(

)

l

./

4.. 2X.

During Base Load Operation F (2) shall be evaluated to determine if q

F (Z14 within its limit by:

q a.

Using the movable incore detectors ~ to obtain a power distribution ND map at any THERMAL POWER above APL b.

Increasing the measured F (Z) component of the power distribution map q

by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for me surement uncertainties.

Verify the requirements of Specification 3.

2,t'afe satisfied.

CATAWBA - UNITS 1 & 2 3/4 2-7a Amendment No. 44(Unit 1)

Amendment No. 04(Unit 2)

+

l

-l V

POWER DISTRIBUTION LIMITS

(

l SURVEILLANCE REQUIhLMENTS (Continued) j

(

l c.

Satisfy

• g the following relationship:

.32xK(Z} for P > APLND F (Z) ~

x W(Z)BL d

where:

'F (2) is the measured F (Z).

The F limit is'2.32.

9 g

P'is the rel' tive THERMAL POWER.

i K(Z) is given in Figure 3.2-2.

a W(Z)BL is the cycle dependent function that accounts for limited power distribution transients encountered during normal operation.

This

I function is given in the Peaking' Factor Limit-Report as per-

.l Specification 6.9.1.9.

j d.

MeasuringF(Z)inconjunctionwithtargetfluxldi.fferencedeter-mination-ac ording.to the following schedule:

1.

Prior to..ntert g BASE LOAD operation after. satisfying surveil-(

lance 4.

2)(.

unless a full core' flux map has been taken in the i

4 previous PD with'the relative thermal power having been ND maintained 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

,c 2.

At least once per 31 effective full' power days.

I e.

With measurements indicating

.j

'(

1 M

q maximum Fg (7)

E K(z) 3 over z M

has increased since the previous determination F (Z) either of the

)

l following actions shall be taken:

M 1.

F ( VDi'a 1 be increased by 2 percent over that specified in 4.

2)( 4 c, or 2.

F (Z) shall be measured at least once per 7 EFPOTuntil 2 successive maps indicate that maximum F (z)

K(z) ) is not increasing.

over z s;

f.

With the relationship specified in 4.

2)(. c above not being-(

satisfied, either of the,following act' n shall be taken:

1.

Plac th core in an equilibrium condition where the limit in.

a M

4.

2.)(.

is satisfied, and remeasure F (Z)', or q

CATAWBA - UNITS 1 & 2 3/4 2-7b Amendment.No. $((Unit 1)

~ Amendment No. 0((Unit: 2)"

__2_.

POWER DISTRIBUTION LIMITS l'

SURVEILLANCE REQUIREMENTS (Continued) 2.

Comply with the requirements of Specification 3.. )( for -

F (Z) exceeding'its limit by the percent calcula i.th q

the following expression:

'(

M F (Z) x W(Z)B' ND

[(max..over z of [ 2.32 L ] ) -1 ];x 100'for P >.APL g

x K(Z) p h

l 2)f l

.following c4r'.4e., and 4.2)[

g.

The limits-specified in 4.2.2)f.) c., 4.

e plan regiqns.:

above are not applicable i Wt 1.

Lower core region 0 to 15 percent, inclusiv'e.

2.

Upper core region.85 to'100 percent, inclusive.

4.

2,(,

When F (Z) is measured for reasons other than meeting'the: requirements q

of Specification 4.2.2)(.2 an overall measured F (z) shall be obtained from a power

.j 9

distribution map and ncreased by 3% to account for manufacturing' tolerances

'1 and further increased by 5% to account for measur'ement uncertainty.

I

'/

1 i

l l

l l

a l

i 1

Amendment No M

.AmendmentNo.86.((U' nit 1 CATAWBA UNITS 1 & 2 3/4 2-7c Unit 2) c______-___

h N

/

P0 DISTRIBUTION LIMITS HEAT X HOT CHANNEL FACTOR - Fn(Z) (Unit 2)

/

LIMITING C0 ITION FOR OPERATION 3.2.2.2 F (Z) s 11 be limited by the following relationships:

q F (Z

[2.32] [K(Z)] for P > 0.5

,/

q

/

F (Z) 5 4] [K(Z)] for P 1 0.5 q

tiERMAL POWER

, and

/

i Where:

P_

T D THERMAL POWER

/

K(Z) = the funct' obtained from Figure

.2-2 for a given core height location.

APPLICABILITY:

MODE 1 (Unit 2).

ACTION:

With F (Z) exceeding its limit:

q a.

Reduce THERMAL POWER at least 1% f each 1% F (Z) exceeds the limit q

within 15 minutes and similarly du the Power Range Neutron Flux-High Trip Setpoints within the ne 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 f 72 hout subsequent POWER OPERATION may proceed provided the Over ower AT Tri Setpoints (value of K ) have 4

been reduced at least 1% (i AT span) for gh 1% F (Z) exceeds the limit, and q

b.

Identify and correct th cause of the out-of-li'it condition prior to increasing THERMAL P WER above the reduced li t required by ACTION a., above; THE AL POWER may then be increa d provided F (Z) is demons rate through incore mapping to be

' thin its limit.

q

/

I

/

CATAWBA - UNITS 1 & 2 3/4 2-7d Amendment No.14 (Unit 1)

/

Amendment No. 6(Unit 2)

gLN g

POWER-DISTRIBUTION LIMITS

\\

SURVEI AN REQUIREMENTS f

\\

N 4.2.'2.2.1 Th provisions of Specification 4.0.4 are not applicable.

N 11 be evaluated to determine if F (Z) is within i limit by:

4.2.2.2.2 Fxy $

9 a.

Using the ovable incore detectors to obtain a power di, ribution map at any HERMAL POWER greater than 5% of RATED THER L POWER, b.

Increasing th seasured F component of the' power d'Atribution map by 3% to accoun \\ r manu cturing tolerances and.htherincreasing the value by 5% t account for measurement uncert inties, btainedinSp,c/

\\

C ification 4.2.2.2.2b.,

c.

Comparing the F c puted (Fxy) xy

/.

above to:

1)

The F limits for A D THERMAL POWER N P) for the appropriate xy

. x measured core planes i

ninSpeciffdtion4.2.2.2.2e.andf.,

below, and 2)

The relationship:

F

=F P [1+0.2(1-x b

Where F*# is the limit for fr tional THERMAL POWER operation P \\

expressed as a function of F nd P is the fraction of RATED THERMAL POWER at which F wasmea\\ed, x

d.

Remeasuring F according to he followin schedule:

xy RTP 1)

When F is greater, an the F limit r the appropriate xy tr.easured core plan but less than the F lationship, additional RTP powergistributio maps shall be taken and [comparedtoF Y

and F either:

xy a)

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding by 20% of ED THERMAL C

POWER o greater, the THERMAL POWER at whic was y

last termined, or

/

b)

At

'ast once per 31 EFPD, whidever occurs firs.

/

y

.j

/

\\

CATAWBA - U iTS 1 & 2-3/4 2-7e Amendment No.14(Unit 1)

Amendment No. 6 (Unit 2)

1 i

gl b

. PO\\ER DISTRIBUTION LIMITS 1

SURVNEI'l CE REQUIREMENTS (Continued)

]

2)

When the F is less than or equal to the FRTP'limi 'for the x

x

' ppropriate measured core plane, additional power / distribution m s shall be taken and F compared to FRTP an F

.at least x

onc per 31 EFPD.

q e.

The F limi s-for RATED THERMAL POWER (FRTP) s11 b'e provided.for xy x

all core plan containing Bank "D" control r, s and all unrodded core planes in adial Peakina Factor Limi ' Report per Specifica-

]

\\

tion 6.9.1.9; f.

The F limits of S ification 4.2.2.2.

e., above, are not applicable xy in the following core anes regions a measured in percent of core

's height from the bottom the fuel:

1)

Lower core region fr 0 to 1

, inclusive, 2)

Upper ore region from 100%, inclusive.

3)

Grid plane regions at 17 2%,'32.1 2%, 46.4 1 2%, 60.6 1 2%

and 74.9 2%, inclusi, ', a 4)

Core plane regions thin i 2 f core height ( 2.88 inches)

'j about the bank dem d position ' the Bank "0" control rods,

]

g.

With F exceeding F

, the effects of' on F (Z) shall be evaluated y

9 to determine if F (

is within its limi 9

4.2.2.2.3 When F (Z) is m sured for other than F terminations, an overall l

q xy measured F (Z) shall be,tained from a power distribut n map and increased q

by 3% to account for m 'ufacturing tolerances and furthe

'ncreased by 5% to account for measureme uncertainty.

/

/

l

/

/

CATAWBA'- UNITS 1 & 2 3/4 2-7f Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

0K N

6 6

6 O

10 22 2

2 3

I 1

1 T

C A

E L

5 5,K BS 2

2 AE CD

• M2 4

I O 4

2 LM 2

2#

2 2

P P

3 1

1 1

A 13 11 1

1 1

SE MLL UEB MNA 22 33 3

3 2

22 3

3 3

I NR NAE N

I HP O

MCO I

TATN E

S M

LP U

EI R

NR 2

2 2

T NT 11 22 2

2 1

1 1

S A

N HO 3

I CT 3

M E

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NN R

N 4

4 4

T LA 22 44 4

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2 AH R

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TF C

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xu l

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u w

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,gEgN EM n & N *>, c5 d g e m R+ Y m

,g E g 5' E l

l

1 TABLE 3.3-1 (Continued) j ACTION STATEMENTS (Continued)

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

)

ACTION 5 With themumbTr oMMo^9LE c%meh-Jess than-the4bbwe 1

r Channels-OPE ^3LE requke=t. ce e vre -i.he inoper:ble channel

• e05"Aamr tstoc%h" 48 heers-er-open -the P,eactordr-ip-b=kee,

-l s

gWe escend all-opnationhimo-1vivp;sitive~ re=Mvity-changescant veeHy41xsp;'! GipMVr23h *-211, 2ndJ'! '".1 chse r~f

]

ur:d ir pe., Liu wii.hi.. the et Mur ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed J

provided the following conditions are satisfied:

q i

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

(

j j

b.

The Minimum Channels OPERABLE requirement is met; however, j

the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 for surveillance testing of other channels per Specification 4.3.1.1.

s i

f ACTION 7 - Delete ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within l

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive l

status light (s) that the. interlock is in its required state f

for the existing plant condition, or apply Specification 3.0.3.

i ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

j ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 nours.

(

CATAWBA - UNITS 1 & 2 3/4 3-6 Amendment No.

(Unit 1)

Amendment No'.

(Unit 2)

L__-___-_-__-

L

TABLE 4.3-1 (Continued)

TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.

Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.

Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrates if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, evaluated an'd compared to manufacturer's data.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

j (6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) With power greater than or equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive status light.

(9) Monthly surveillance in MODES 3*, 4*, and 3* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive status light.

N " ^ L= 13, n." M -

=z= ' ' i r : : : hi ' i,;1 ud;. ; r ' " ' -- ' " -

f

-0; m Oil. tie Alo.m

t p '.t

' i m t b n. w l t; =; Mi' dd~'"~ \\

m~m

.vve v.

m -.-

-#==

(10) Setpoint verification is not applicable.

(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.

(12) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

(13) For Unit 1, CHANNEL CALIBRATION shall ensure that the filter time constant associated with Steam Generator Water Level Low-Low is adjusted to a value less than or equal to 1.5 seconds.

Amendment No. g( ((Unit 1)

CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No. d Unit 2)

i INSTRUMENTATION MOVABLE INCORE DETECTORS 1

1 LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

u i

a.

At least 75% of the detector thimbles, j

b.

A minimum of two detector thimbles per core quadrant, and c.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for:

a.

Recalibration of the Excore Neutron Flux Detection System, or b.

Monitoring ROWER-T-ILT RATIO, or s

c.

Measureme FW AH'A q ACTION:

With the Movable Incofe Detection ystem inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detec' tion System shall be demonstrated OPERABLE at.

least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by irradiating each detector used and determining I

the acceptability of its voltage curve for:

a.

Recalibration of the Excore Neutron Flux Detection system, or b.

Monitoring the QUA0

.0WFR TILT RATIO, or N

c.

Measuremen of F F (Z), and aH'g q ancL i

CATAWBA - UNITS 1 & 2 3/4 3-55

(

INSTRUMENTATION 3/4.3.3.12 BORON DILUTION MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION i

3.3.3.12 As a minimum,:two trains of the Boron Dilution Mitigation System l

shall be OPERABLE and operating with Shutdown Margin Alarm ratios set at less than or equal to 4 times the ste

-state count rate.

1 APPLICABILITY:

MODES 3, 4, AN JNIT 1 ^"LY) i ACTION:

l (a)' With one train of the Boron Dilution Mitigation System inoperable or j

not operating, restore the. inoperable train to OPERABLE status within

/

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or i

(1) suspend all operations involving positive reactivity changes and

\\

verify that valve NV-230 is closed and secured within the next j

hour, or i'

(2) verify two Source Range Neutron Flux Monitors'are OPERABLE with j

Alarm Setpoints less than or equal to one-half decade above the f

steady-state count rate and verify that the combined flowrate from both Reactor Makeup Water Pumps is less than or equal to 200 gpm-(Mode 3) or 80 gpm (Mode 4 or 5) within the next hour.

]

(b) With both trains of the Baron Dilution Mitigation System inoperable j

or not (perating, restore the inoperable trains to OPERABLE status withir 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (1) suspend all operations involving positive reactivity changes 1

and verify that valve NV-230 is closed and secured within the

)

next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade above the

'i steady-state count rate and verify that the combined flow rate from both Reactor Makeup Water Pumps is less than or equal to

(

200 gpm (Moce 3) or 80 gpm (Mode 4 or 5) within the next hour.

(c) The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

)

4.3.3.12.1 Each train of the Boron Diiution Mitigation System shall be demon-strated OPERABLE by performance of:

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Q,9 agnw L and 2. unel J+ec m+ermy M d c 2 U "' 4 N

{

-nrs+ cekhny ou%e y

CATAWBA - UNITS 1 & 2 3/4 3-92a AmendmentNo.y[ Unit 1);

Amendment No Unit 2)

l' l

(

[

.i INSTRUMENTATION 7

j SURVEILLANCE REQUIREMENTS (Continued)

?

.=-i A.. i,'21100 Cl

?"'. ^7" RATI ^ ^2i'_

su d waiad uu. $ f "ui

,m. ivy med-

_a hg) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 aysjad

\\

0 -( ) At least once per 18 months the 80MS shall be' demonstrated /

OPEPABLE by:

)

(1) Verifying that each automatic valve actuated by the BOMS moves to its correct position upon receipt of a trip signal, and' (2) Verifying eacn reactor makeup water pump stops, as designed,

/

)

upon receipt of a trip signal.

[

4.3.3.12.2 If using the Source Range Neutron Flux Monitors to meet the require-

)

ments of Technical Specification.3.3.3.12,

(

4 (a) The monthly surveillance requirements of Table 4.3-1 for the Source

)

Range Neutron Flux Monitors shall include verification that the

(

i Alarm Setpoint is less than or equal to one-half decade (square root j

l of 10) above the steady state count rate.

/

(

(b) The combined flow rate from both Reactor Makeup Water Pumps shall be g'

verified as less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 1

or 5) at least once per 31 days.

(

)I i

i l

\\

I i

)

/

/

(

i AmendmentNo'.k((U CATAWBA - UNITS 1 & 2 3/4 3-92b Amendment No.M Unit 2)

..____._.__m._________w

i l

3/4.9 REFUELING' OPERATIONS 3/4.9.1 BORON CONCENTRATE 0h LIMITING CONDITION FOR OPERATION 1

l

\\

3.9.1 The boron concentration of all filled portions of the Reactor Coolant I

I System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met either:

a.

AK f 0.95 or less, or eff i

b.

A boron concentration of greater than or equal to 2000 ppm.

J J

APPLICABILITY:

MODE 6.*

ACTION:

l l

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm baron or its equivalent until K is reduced to less than or equal to 0.95 or the boron j

concentration is r$Nored to greater than or equal to 2000 ppm, whichever is i

the niore restrictive.

SURVEILLANCE REQUIREMENTS l

4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full-length control rod in excess of 3 foet from l

its fully inserted position within the reactor vessel.

4. 9.1. 2 The boron concentration of the Reactor Cooiant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

I 41 ' '

-==T' r:

.f,' _..;~1; c;oses an m ures in po m is, r c - M n' :t;p: :t ' r:t r.;c v. ^1 1.7 A

• The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

CATAWBA - UNITS 1 & 2 3/4 9-1 AmendmentNog(Unit 1)

Amendment No.A (Unit 2)

l REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION

(

3.9.2.1 As a minimum, wo trains of the Boron Dilution Mitigation System shall j

be OPERABLE and operating with Shutdown Margin Alarm Ratios set at less than or equal to 4 times,t.

steady-state count rate, each with continuous indication

)

in the control roon.

/

k

[s APPLICABILITY:

MO 6 (" GT 1 CNLY)

ACTION:

(

(a) With one or both trains of the Boron Dilution Mitigation System inoperable or not operating, (1) immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, or (2) verify that two Source Range Neutron Flux Monitors are OPERABLE l

and operating with Alarm Setpoints less than or equal to one-

/

half decade (square root of 10) above the steady-state count

[ s rate, each with continuous visual indication in the control l

g j

room and one with audible indication in the control room and one with audible indication in the containment end control room t

within the next hour.

(b) With both trains of the Boron Dilution Mitigation System inoperable

)

or not operating and one of the Source Range Neutron Flux Monitors j

inoperable or not operating immediately suspend all operations involving core ALTERATIONS or positive reactivity changes.

)

(c) With both trains of the Boron Dilution Mitigation System inoperable or not operating and both of the Source Range Neutron Flux Monitors i

fi6perable or_not-operat4ng, determine th K-concentration of the Reactor Coolant System at least once per 12 hoGrs (d) % provisions ok $ c.c;heodion.$.0.'/ are ogf etppllc4W<..

9 SURVEILLANCE REQUIREMENT 4.9.2.1.1 Each train of the Boron Dilution Mitigation System shall be demon-

)

strated OPERABLE by performance of:

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

)

(b) An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS and (c) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days.

/

ff ypbedl< Or (Inil 2 uniflhe ederiny M@G z fllowhy &

j hrsf re&eOny oul age..

f AmendmentNo.M(U

)

CATAWBA - UNITS 1 & 2 3/4 9-la Amendment No. / Unit 2) (

7 h

REFUELING OPERATIONS

(

SURVEILLANCE REQUIREMENTS (CONTINUED) f j

i (d) At least once per 18 months the BDMS shall be demonstrated OPERABLE by:

1 i

(1) Verifying that each automatic valve actuated by the BDMS moves to its correct position upon receipt of a trip signal, and (2) Verifying each reactor makeup water pump stops, as designed, upon receipt of a. trip signal.

4.9.2.1.2 If using the Source Range Neutron Flux Monitors to meet the require-ments of Technical Specification 3.9.2, each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

j (a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, (b) An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial

[

l l

start of CORE ALTERATIONS or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaring the BORON

\\

DILUTION MITIGATION SYSTEM inoperable, and

)

j (c) An ANALOG CHANNEL OPERATIONAL TEST at lest once per 7 days.

(

l I

l

(

)

)

(

l

)

(

i

)

l

(

l

)

)'(s CATAWBA - UNITS 1 & 2 3/4 9-lb Amendment No.

Unit 1)

Amendment No.

Unit 2)

b[~fS 7

\\ REFUELING OPERATIONS C

3 9.2 INSTRUMENTATION

/

/

LIMITIN CONDITION FOR OPERATION

/

3.9.2.2 A inimum, two Source Range Neutron Flux Monitors sha be OPERABLE

.l and operating w*th Alarm Setpoints at 0.5 decade above steady-s ' ate count rate, each with continu us visual indication in the control room and one with audible indication in the ntainment and control room.

APPLICABILITY:

MODE (UNIT 2 only)

ACTION:

e required monitors inoper/able or not operating, a.

With one of the ab immediately suspend 11 operations involving' CORE ALTERATIONS or positive reactivity nges.

/

4 I

b.

Withboth.oftheaboverequiredmonitors/inoperableornot' operating, j

determine the boron conceh ration of ttyd Reactor Coolant System at j

least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

/

g

/

SURVEILLANCE REQUIREMENTS

/

\\

\\.

4.9.2.2 Each Source Range Neutron lux Monitor shal be' demonstrated OPERABLE l

by performance of:

l l

a.

A CHANNEL CHECK at le t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

An ANALOG CHANNEL 0 ERATIONAL TEST within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALT ATIONS, and c.-

An ANALOG CHAN L OPERATIONAL TEST at least once per 7 days.

l l

I l

CAT

- UNITS 1 & 2 3/4 9-2 Amendment No.17(Unit 1)

./ '

Amendment No. 7(Unit 2).

3/4.2 POWER DISTRIBUTION LIMITS i

BASES 1

l i

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 calculated DNBR in the core greater than or equal (

to design limit DNBR 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 acceptance criteria limit of 2200 F is not exceeded.

The definitions 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 9

flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on-3 fuel pellets and rods; F

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

the integral of linear power along the rod with the highest integrated l

power to the average rod power; and

)

i

)

l g764Migactw,%Am te-=tn ;#bk% _ c.my_

y g } g & & Qgant:Lp W y t_ n L 6 L ~ 1 W cd 3/4.2.1 AXIAL FLUX DIFFERENCE

.)

The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper-0 bound envelope of 2.32 times the normalized axial peaking factor is not exceeded i

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 L

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 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 l

considerations.

l l

l CATAWBA - UNITS 1 & 2' B 3/4 2-1 Amendment No.

(Unit 1) l Amendment No.

(Unit 2)

l POWER DISTRIBUTION LIMITS

{

BASES AXIAL FLUX DIFFERENCE (Continued)

'llthough ft is intended that Unit 2 will be operated with the AFD within he t et band required by Specification 3.2.1.2 about the target flux di 1 -

ence, du g rapid plant THERMAL POWER reductions, control rod motion wi '

cause the AFD to

~ iate outside of the target band at reduced THERMAL POWE evels.

This deviation

'L1 not affect the xenon redistribution sufficien to change the envelope of pe ing factors which may be reached on a subs ent return to RATED THERMAL POWER

'th the AFD within the target band) vided the time duration of the deviatio

's limited.

Accordingly, a 1-ur penalty deviation limit cumulative during the ' evious 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is pro ed for operation outside

{

ofthetargetbandbutwithint'qmitsofFigu

.2-lb while at THERMAL POWER levels between 50% and 90% of RAT BERMAL P tR.

For THERMAL POWER levels between 15% and 50% of RATED THERMAL E

deviations of the AFD outside of the target band are less significant.

1 enalty 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 N

For Unit 2, provisions f monitoring the A on an automatic basis are Y>

s derived from the plant prg s computer through theN Monitor Alarm.

The

' minute average of each of the,ERABLE excore detector computer determines th outputs and provide ' n alarm message immediately if the 4 for at least two

['

s of four or two

' hree OPERABLE excore channels are outsideM target band and the THER POWER is greater than 90% of RATED THERMAL POWtR uring opera / g tion at T MALPOWERlevelsbetween50%and90%andbetween15%hd

% RATED THERM OWER, the computer outputs an alarm message when the penaltysde 'ation a c, - ulates be ond 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.

Figu're B 3/4

-1 shows a typical monthly target band for Unit 2.

ND

-E

' " 1 St ower levels below APL

, the limits on AFD are defined by I

igure 3.2-1g, i.e., that defined by the RA0C operating procedure and limits.

ese limits wer calculated in a manner such that expected operational tran-si nts, e.

oad follow operations, would not result in the AFD deviating outsi o those limits.

However, in the event such a deviation occurs, the short period of time allowed outside of the limits at reduced power levels will not result in significant xenon redistribution such that the envelope of peaking

(

l l

factors would change sufficiently to prevent operation in the vicinity of the ND APL oveT4ev ND 6"^

' -St ower levels greater than APL two modes of oper t on re per issible; 1)

OC, the AFD limit of which are defined by Figure 3 2-l#,

nd

2) B se Loa eration, which is defined as the maintenance of the A D w' in NO a 3% band about a target value.

The RAOC operating procedure above APL is the same as that defined for operation below APL"O However, it is possible when following extended load following maneuvers that the AFD limits may result in restrictions in the maximum allowed power or AFD in order to guarantee opera-(

tion with F (z) less than its limiting value.

To allow operation at the maximum q

permissible value, the Base Load operating procedure restricts the indicated h

CATAWBA - UNITS 1 & 2 8 3/4 2-2 Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

POWER DISTRIBUTION LIMITS BASES j

AXIAL FLUX DIFFERENCE (Continued)

(

m AFD to relatively small target band a i power s (AFD target band of 3%,

APLND < ower < APL or 100% Rated hermal Power, w ichever is lower).

For i

BL p

Base Load operation, it is expected that Unit 5X wil operate within the target 3

band.

Operation outside of the tartet band for t short time period allowed 1

will not result in significant xeno redistrib on such that the envelope of peaking factors would change sufficie prohibit continued operation in the power region defined above.

To assure there is no residual xenon redistri-i

)

bution impact from past operation on the Base Load operation, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> waiting f

ND period at a power level above APL and allowed by RA0C is necessary.

During this time period load changes and rod motion are restricted to that allowed by J

the ese To'M cedure.

After the waiting period extended Base Load operation

)

3 is ermissible.

1 0

P- ""' ?-the omputer determines the one minute average of each of the PERABLE excore det tor outputs and provides an alarm message immediately 1

the AFD for at east 2 of 4 or 2 of 3 OPERABLE excore channels are:

1) outside U th llowed M ower cperating space (for RAOC operation), or 2) outside the allowed AI target band (for Base Load operation).

These alarms are active when power is greater than:

1) 50% of RATED THERMAL POWER (for RAOC operation),

or 2) APLNO (for Base Load operation).

Penalty deviation minutes for Base Load i

operation are not accumulated based on the short period of time during which

(

operation outside of the target band is. allowed.

)

3/4.2.2 and 3/4.2.3 HE_AT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, coolant 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

)

a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS acceptance criteria limit.

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:

a.

Control rods in a single group move together with no individual rod insertion differing by more than 12 steps, indicated, from the

(

group demand position; b.

Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; CATAWBA - UNITS 1 & 2 B 3/4 2-2a AmendmentNo.$(Unit 1)

Amendment No. A(Unit 2)

1 i

1.00 l

. l l

I l

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l i

.d. ! _

....q.

- -.... A-.

w-0.80 i

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..i....

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I 7:i -..

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A.

i sN ;

i i

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i i

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rget Flux Difference i

g g.... i - j..

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l // I i

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_..._.f_....._....

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-30%

-20%

10%

0

+10%

+20%

+30%

INDICATED AXIAL FLUX DIFFERENCE FIGURE C 3/4 2-1 TYPICAL INDILATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWEP (Uni CATAWBA - UNITS 1 AND 2 B 3/4 2-3 Amendment No.14 (Unit 1) -

Amendment No.

6 (Unit 2)

1 i

1 4

POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW' RATE AND NUCLEAR l

ENTHALPY RISE HOT CHANNEL FACTOR (Continued) l 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.

.l F

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

H above are maintained.

As noted on Figure 3.2-3, Reactor Coolant ~ System flow rate j

F may be " traded off" against one another (i.e.', a, low measured' Reactor g

N 0

nt System flow rate is acceptable if the measured F is also low) to ensure 9 00 the calculated DNBR will not be below the design DNh value.

The relaxation j

/

that l

of.F as a function of THERMAL POWER allows changes in the radial power shape 3g f

all permissible rod insertion limits.

R as calculated in Specification 3.2.3 and used in Figure 3.2-3, accounts for F less than or equal to 1.49.

This value is used in the various accident

)

g analyses where F influences parameters other than DNBR, e.g., peak clad temp-H erature, and thus is the maximum "as measuged" value allowed.

The rod bow pen-l alty as a function of burnup applied for F is calculated with the methods de-l aH scribed in WCAP-8691, Revision 1, " Fuel Rod Bow Evaluation," July 1979, and the maximum rod bow penalty is 2.7% DNBR.

Since the safety analysis is performed with plant-specific safety DNBR limits of 1.49 and 1.47 compared to the design DNBR limits of 1.34 and 1.32, respectively, for the typical and thimble cells, l

there is a 10% thermal margin available to offset the rod bow penalty of 2.7% DNBR.

)

When an F measurement is taken, an allowance for both experimental error q

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%

allowa c(Ts7ppropriate for manufacturing tolerance.

M r =:; 1 The ho channel factor F (z) is measured periodically and in-j s

}

c ased by a cycle a height dependent power factor appropriate to either RAOC or e Load o lon, W(z) or W(z)BL, to provide assurance that the-limit on

(

the hot channel factor, F (z), is met.

W(z) accounts for the effects of-normal q

operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the. core. W(z)BL accounts for the more restrictive operating limits allowed by Base Load operation which result in less severe transient values.

The W(z) function for normal operation is provided in the Peaking Factor Limit Report per Specification 6.9.1.9.

[

I Amendment No g ((Unit 1)

CATAWBA UNITS 1 & 2 B 3/4 2-4 Amendment No. A Unit'2) c______

ytts

)

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gERDISTRIBUTIONLIMITS

~ ~

~ ~

~

~ ~~

~~

(

BASES x

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HEAT FLUX HOT CH OR, and REACTOR COOLANT RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL ~ M R (Continued 1

For Unit 2 the Radial Pea

• ac F y(Z), is measured periodically to provide assurance tha - e Hot Channel Factor

, remains within its limit.' \\

x i

The F lim' ' 'r RATED THERMAL POWER (F RTP) as p?cvia n the Radial Peaking.

xyLimit Report per Specification 6.9.1.9 was determib

_ xpected

'/

i F

power control maneuvers over the full range of burnup conditions in ore.

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CATAWBA, LS1&2 B

2-4a Amendmedt'

.14 (Unit 1)

/

N Amendme No N junit 2)

l 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.

These limitations are consistent with the initial conditionc, assumed for the boron dilution incident in the safety analyses.

The value of 0.95 or less for K includes a

]

eff 1% Ak/k conservative allowance for uncertainties.

Similarly, the boren j

concentration value of 2000 ppm or greater _ includes a conservative uncertainty allowance of 50 ppm baron.

The locking clesed of the required scivc; during refueling sparctica precludes the possibility of unccatrolledlborca dilution

]

cf the filled pcrtica cf the Rccctor Occicnt System Thi; cctica prevent; ficw i

tc th Rcccter Ccciant Sy;t:: cf unber;ted watcr by cic;ing flew pcth; #rcr

urcc; cf unbcr;ted watcr i

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Scurce Ranga N;utron riux "cnitor; and/cr th Boron /

7 Dilution Mitigation System ensures that radundant monitoring capability is 4'

available to detect changes in the reactivity condition of the core.

1 3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.

This decay time is consistent with the assumptions used in the safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal ac'sorbers prior to release to the atmosphere.

The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

Operation of the Reactor Building Containment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis.

Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

CATAWBA - UNITS 1 & 2 B 3/4 9-1 Amendment No,W (Unit 1)

Amendment No./(Unit 2).

ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Reports shall include a list and l

description of unplanned releases.from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made L

during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics, and shutdown experience, in-cluding documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the "ir::ter, Of'i:: Of 9:0 ur "r ;:r^nt, U.S. Nuclear Regulatory Commission, 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.

ATYN: DocuMlah kn$rof btik

"? 8 PEAKING FACTOR LIMIT REPOR 6.9.1.9 The W(z) functions for RA0C and Base Load operation and the l

ND

(

value for APL as required) shall be provided to the Circ; tor, Nuclear R ::t e R gulation,,,ttention-Chief, Cer: "crf;rr.:nce Sr;nch, U.S. Nuclear Regulatory j

Commission,kWashington,D.C.

20555; t 1:0:t 50 day; pricr to cycle initial j

criticality.

In the event that th: :: v 1ue; would be submitted at :::: Other ti;; during ;re life, it will be sg'mitted C0 days pricr to the dat;. the values WOuld b :::: Of f00the unle:; Othen ;; :=;pted by the C;=i;; ion ND Any information needed to support W(z), W(z)BL and APL will be by request from the NRC and need not be included in this report.

M qi.e h Oc Tejfoned bMnk ard.4hc Res.' deny hspdor-oiht 30 hs h

of Scirtmdemed di'n-1:

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b CATAWBA - UNITS 1 & 2 6-19 Amendment No. Mi(Unit 1)

Amendment No. g (Unit 2)

I

@ L. N E ADMINISTRATIVE CONTROLS w

{

)

iM LFACTOR LIMIT REPORT (Continued)'

approved by the Commissio etter.

In addition, in the eve e limit should change requiring a new sub or an amend tal to the Radial Peaking Factor Limit Report, it will be 60 days prior to the date the limit would become effecti ss otherwise ved by the Commission P

by letter.

A mation needed to support F will be est from the x

need not be' included in this report.

n H

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l CATAWBA - UNITS 1-& 2 6-19a Amendment No Unit 1)-

Amendment No (Unit 2)

c~m---

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ATTACHMENT 2 JUSTIFICATION AND ANALYSIS OF~NO SIGNIFICANT HAZARDS CONSIDERATIONS I

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1

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4

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JUSTIFICATION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION I

1 1

The majority of the proposed changes to the Catawba Units 1 and 2 Technical l

Specifications are needed to ensure that plant operation is consistent with the design and safety evaluation conclusions made in the Reload Safety Evaluation j

(RSE). Each Technical Specification change and a discussion of the appropriate l

accident analysis are provided in Attachment 3.

i Several changes which are not addressed in the RSE deal with the addition of the

]

Boron Dilution Mitigation System.

In particular, Specifications 4.1.1.1.3, 4.1.1.1.4, 4.1.1.2.2, Table 3.3-1; item 6.b, Table 3.3-1; Action 5, Table 4.3-1; Note (9), 3/4.3.3.12, 4.9.1.3, and 3/4.9.2 reflect the addition of this system to Unit 2.

It is requested that these Specifications not apply to Unit 2 until prior to startup to allow calibration and testing of the system so that it can be l

declared operable.

In the interim between issuance of the License Amendment and I

the unit entering Mode 2, the requirements of the deleted Specifications l

concerning the source range monitors will be administratively imposed to ensure j

that there will always be adequate protection in the event of a boron dilution I

accident.

l l

It is requested that Surveillance 4.3.3.12.1(b) be deleted. This surveillance is I

required prior to startup but the Specification itself is not applicable in Modes 1 or 2.

Therefore, it makes no sense to test the channels prior to making them

)

inoperable.

The change to Specification 3.9.2.1, Action (a)(2) is an editorial correction.

The addition of Action (d) will allow the plant to change modes if the Boron Dilution Mitigation System is inoperable. This omission of this statement from the original Specification was an oversight. 'This statement already appears in Specification 3.3.3.12 which covers all other applicable modes.

The proposed changes to the Catawba, Units 1 and 2 Technical Specifications have been reviewed pursuant to 10 CFR 50.91.

The following analysis provides a determination that the proposed amendments do not involve any Significant Hazards Considerations, as defined in 10 CFR 50.92.

l 10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:

l (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 amendment does not involve an increase in the probability or consequences of any previously evaluated accident. The Westinghouse RSE (Attachment 3) provides a discussion of each affected accident analysis (except for the boron dilution accident). The boron dilution accident is addressed in Section 15.4.6 of the Catawba FSAR. As long as the unit is operated within the l

parameters specified, the previously acceptable safety limits will not be exceeded.

s

JUSTIFICATION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION (Cont.)

The proposed amendment does not create the possibility of a new or different kind l

of accident from any accident previously evaluated.

The RSE concludes that the amendment will not introduce any changes that will fall outside of the previously evaluated accidents.

The proposed amendment does not involve a significant reduction in a margin of i

i safety. The RSE concludes that operation with the proposed amendments will not result in a plant condition outside of the already established safety analysis.

i Almost all of these changes are making Unit 1 specific requirements applicable to I

Unit 2.

The Unit 1 changes were previously reviewed and approved by the NRC Staff. Those changes were issued October 1, 1986 as amendments 14 and 6 to the Catawba Units 1 and 2 Technical Specifications.

Based upon the preceding discussion, Duke Power Company concludes that the l

proposed amendments do not involve a Significant Hazards Consideration.

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ATTACHMENT 3 CATAWBA UNIT 2/ CYCLE 2 RELOAD SAFETY EVALUATION 1

1

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