Text

Amends 14 & 6 to Licenses NPF-35 & NPF-52,respectively, Modifying Tech Specs Re Application of Positive Moderator Temp Coefficient Reflecting Cycle 2 Refueling for Unit 1
	ML20215E521
Person / Time
Site:	Catawba
Issue date:	10/01/1986
From:	Jabbour K; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20215E523	List: ML20215E521; ML20215E529;
References
	NUDOCS 8610150353
	Download: ML20215E521 (43)
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'o,i, UNITED STATES NUCLEAR REGULATORY COMMISSION 9y WASHINGTON, D. C. 20555

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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.

i DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 License No. NPF-35 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Caro'.ina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) dated July 15, 1986, and supplemented July 24, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR l

Chapter I; D.

The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 Cin Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 14, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

\\

\\b Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance: October 1, 1986 b

V PWR WR-A PWR#L/DPWR-A OGC-Beth

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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION PIEDM0NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. NPF-52 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

' e application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke 4

Power Company acting for itself, North Carolina Electric Membership Corporation and Piedmont Municipal Power Agency, (the licensee) dated July 15, 1986, and supplemented July 24, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; s

B.

The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read-as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

\\Y Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance:

october 1, 1986 Nrk MDunc/'hWR-A PWL#4 PWR# DPWR-A OGC-Beth WR#4/DPWR-A an/ rad KJabbour

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4 ATTACHMENT TO LICENSE AMENDMENT N0.

FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDMENT N0.

FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf pages is also provided to maintain document completeness.

Amended Overleaf Page Page 2-8 2-7 3/4 1-4 3/4 1-3 3/4 1-5 3/4 1-Sa 3/4 1-6 3/4 1-21 3/4 1-22 3/4 1-23 3/4 2-1 3/4 2-2 3/4 2-3 3/4 2-4 3/4 2-4a 3/4 2-4b 4

3/4 2-4c 3/4 2-5 3/4 2-6 3/4 2-7 3/4 2-7a 3/4 2-7b 3/4 2-7c 3/4 2-7d 3/4 2-7e 3/4 2-7f 3/4 2-8 B 3/4 1-2 B 3/4 1-1 B 3/4 2-1 8 3/4 2-2 B 3/4 2-2a B 3/4 2-3 B 3/4 2-4 B 3/4 2-Aa 6-19 6-20 w

<--e-g.- - - - - - - -

-w----

.r---,

-n-,----,-g

.--,----,vv

~-,---,-,---,,-r~r

.m- - - - -,-, -

r---,- - - -, -

O i

i TABLE 2.2-1 (Continued) n D.

TABLE NOTATIONS 25 NOTE 1: OVERTEMPERATURE AT (y 1 7a3) 5 AT, Mi - K U(1)7,3)-Il+K(P-P')-f(AI)}

AT 2

3 3

2 7

3 i'id Where:

AT Measured AT by RTD Manifold Instrumentation;

=

1 Lead-lag compensator on measured AT; e.

=

~

ti, 12 Time constants utilized in lead-lag compensator for AT, 11=8s,

=

i T2 = 3 s; 1

Lag compensator on measured AT;

=

1+1S 3

13 Time constant utilized in the lag compensator for AT, r3 = 0;

=

7 AT Indicated AT at RATED THERMAL POWER;

=

9 o

j K

=

3 1.411; 2

0.02401/*F; K

=

i j

1 The function generated by the lead-lag compensator for T,yg

=

dynamic compensation; I

Time constants utilized in the lead-lag compensator for T,yg, 14 = 28 s,

=

14, is j

15 = 4 s; I

j Average temperature, *F; T

=

1 Lag compensator on measured T,yg;

=

y.

i Time constant utilized in the measured T lag compensator, is = 0; ts

=

e avg i

d t

4 s

l TABLE 2.2-1 (Continued)

[]

TABLE NOTATIONS (Continued)

NOTE 1:

(Continued)

[

T' 5 590.8*F (Nominal T,,,g allowed by Safety Analysis);

5 3

0.001189; gj K

=

\\

w P

Pressurizer pressure, psig;

=

P' 2235 psig (Nominal RCS operating pressure);

=

Laplace transform operator, s 1; S

=

and f (AI) is a function of the indicated difference between top and bottom detectors of the t

power-range neutron ion chambers; with gains to be selected based on measured instrument j

response during plant STARTUP tests such that:

(i)

For q A between -22.5% and -6.5% (Unit 1) and between -43% and -6.5% (Unit 2),

t b

i oo f (AI) = 0, where q and q are percent RATED THERMAL POWER in the top and bottom t

t b

halves of the core respectively, and qt

9b is total THERMAL POWER in percent of RATED THERMAL POWER; l

g.g (ii)

For each percent that the magnitude of q

~9 is more negative than -22.5% (Unit 1) t b

and -43% (Unit 2), the AT Trip Setpoint shall be automatically reduced by 3.151% (Unit 1) 4 CL and 2% (Unit 2) of its value at RATED THERMAL POWER; and EE z2 (iii)

For each percent that the magnitude of qt q is more positive than -6.5%, the AT Trip oo b

Setpoint shall be automatically reduced by 1.641% of its value at RATED THERMAL POWER.

-s -,

5E NOTE 2:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by

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i more than 2.4%.

UC 1

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,yg 1 200*F 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 4

i 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 i

i MARGIN is restored.

SURVEILLANCE REQUIRiMENTS 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal j.

to 1% ak/ki I

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months "after detection of an inoperable control rod (s) and a.

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

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 untrippable i

control rod (s); and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 concentration, and 6)

Samarium concentration.

4.1.1.2.2 At least once per 18 months, each Reactor Makeup Water pump shall be demonstrated OPERABLE by verifying a flow rate of less than or equal to 120 gpm.

At least'once per 31 days, one Reactor Makeup Water pump shall be demonstratedinoperablebyverifyingthatthemotorcircuitbreap"rissecured in the open position.

l k

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

s REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1. 3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than the limits shown in Figure 3.1-0; b.

Less negative than -4.1 x 10 4 Ak/k/ F for all the rods withdrawn, l

end of cycle life (E0L), RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3.1.1.3a. - MODES 1 and 2* only#.

Specification 3.1.1.3b. - MODES 1, 2, and 3 only#.

ACTION:

a.

With the MTC more positive than the limits shown in Figure 3.1-0, l

operation in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than the limits shown in Figure 3.1-0 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6; 2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and 3.

A Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of Specification 3.1.1.3b.

above, be in HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With Keff greater than or equal to 1.

See Special Test Exceptions Specification 3.10.3.

4 -

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

Amendment No. 6 (Unit 2)

s REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:

a.

The MTC shall be measured and compared to the limit of Figure 3.1-0 prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading; and b.

The MTC shall be measured at any THERMAL POWER and compared to

-3.2 x 10 4 Ak/k/*F (all rods withdrawn, RATED THERMAL POWER l

condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.

In the event this comparison indicates the MTC is more negative than -3.2 x 10 4 Ak/k/*F, the MTC shall be l

remeasured, and compared to the EOL MTC limit of Specification 3.1.1.3b., at least once per 14 EFPD during the remainder of the fuel cycle.

4 CATAWBA - UNITS 1&2 3/4 1-5 Amendmer.t No.14 (Unit 1)

Amendment No. 6 (Unit 2)

i s

REACTIVITY CONTROL SYSTEttS CONTROL BANK INSERTION LIMITS LIMITING CONDITION FOR OPERATION l

3.1.3.6 The control banks shall be limited in physical insertion as shown in Figures 3.1-la (Unit 1) and 3.1-lb (Unit 2).

l APPLICABILITY:

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position 1

using the above figure, or c.

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

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

I"

With K,7f greater than or equal to 1.

CATAWBA - UNITS 1&2 3/4 1-21 Amendment No.14(Unit 1)

Amendment No. 6(Unit 2)

P (Fully Withdrawn) 228 29 %, 228 (79 %, 228) 200 BANK B 180 -

160 (0%,162) 45 140 BANK C c.

S vs I

120

.o 5

.100 g

E BANK D o

80 E

s0 -

(0%, 47) 40

~

3 (30%, 0)

I I

I

~I I

I 0

O 20 40 60 80 100 (Fully inserted)

Relative Power (Percent)

FIGURE 3.11a ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION (UNIT 1) r-CATAWBA UNITS 1 and 2 3/4122 Amendment No.14 (Unit 1)

Amendment No.

6 (Unit 2)

=*

9 (FULLY WITHDRAWN) 228

/ (20%,278.;)..

A 220 f

_- (76%, 228) 7 i

.i

,/ BANK B

,/

200 3

k 0%,187);

/

l180 f'

O z

./

r-160 f

f 5

(100%,162) ; _/

$ 140 f.,

BANK C '

,f S

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f H

en O

a 100 g

/

Z f

f 4

m 80 h

$i(0%,72) l

" 60 f'f f

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20 i

0

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O 10 20 30 40 50 60 70 80 90 100 (FULLY RELATIVE POWER (PERCENT OF RATED THERMAL POWER)

INSERTED) e*'

FIGURE 3.1-lb ROD BANK INSERTION LIMITS VERSUS THERMAL POWER l

FOUR LOOP OPERATION (Unit 2) l CATAWSA - UNITS 1 AND 2 3/4 1-23 Amendment No.14 (Unit 1)

Amendment No.

6 (Unit 2)

e

?

1.0 0.9 g

D 0.8

7 8

'o 0.7 Acceptable Unacceptable 0.6 Operation peration 3uj-0.5 8

0.4 E

f 0.3 a

j!

0.2 5

+;

0.1 b

t 0

l l

e 0

10 20 30 40 50 60 70 80 90 100

% of Rated Thermal Power FIGURE 3.1-0 l

MODERATOR TEMPERATURE COEFFICIENT VS. POWER LEVEL CATAWBA - UNITS 1 & 2 3/4 1-Sa Amendment No. 14 (Unit 1)

Amendment No.

6 (Unit 2)

(

m

REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY f

LIMITING CCNDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (Tavg) shall be greater than or equal to 551*F.

APPLICABILITY:

MODES 1 and 2#*.

ACTION:

With a Reactor Coolant System operating loop temperature (T,yg) less than 551*F, restore T,yg to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.1.1.4 The Reactor Coolant System Temperature (Tavg) shall be determined to

~ be greater than or equal to 551 F:

a.

Within 15 minutes prior to achieving reactor criticality, and b.

At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T,yg is less than 561 F with the T,yg-Tref Deviation Alarm not reset.

l 1

[ *

With K,ff greater than or equal to 1.

See Special Test Exceptions Specification 3.10.3.

JATAVBA - UNITS 1 & 2 3/4 1-6

s 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) (UNIT 1)

LIMITING CONDITION FOR OPERATION 3.2.1.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within:

a.

the allowed operational space defined by Figure 3.2-la for RAOC operation, or b.

within a 13% target band about the target flux difference during baseload operation.

APPLICABILITY:

MODE 1, above 50% of RATED THERMAL POWER (Unit 1).*

ACTION:

For RAOC operation with the indicated AFD outside of the Figure 3.2-la a.

limits, 1.

Either restore the indicated AFD to within the Figure 3.2-la limits within 15 minutes, or 2.

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

ND**

b.

For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target flux difference:

1.

Either restore the indicated AFD to within the target band limits within 15 minutes, or U

2.

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

c.

THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the Figure 3.2-la limits.

I

~

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.14 (Unit 1)

Amendment No. 6 (Unit 2)

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 4.2.1.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 50% of RATED THERMAL POWER by:

a.

Monitoring the indicated ~AFD for each OPERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status.

b.

Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

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

4.2.1.1.3 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.

4.2.1.1.4 When in Base Load operation, the target flux difference shall be updated at least once per 31 Effectiv> Full Power Days by either determining the target flux difference in conjunction with the surveillance requirements of Specification 3/4.2.2 or by linear interpolation between the most recently mea-sured values and the calculated value at the end of cycle life. The provisions of Specification 4.0.4 are not applicable.

g.

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

Amendment No. 6(Unit 2)

s 5

8 3 E 2 x

s4 u.

O E

E1

(-20, 100)

(10,100) g _

UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE

~

OPERATION GO 50

( 36, 50)

(21, 50) 40 20 I

I I

I 0

-50

-40 30

-20

-10 0

10 20 30 40 50 Flux Difference (All%

FIGURE 3.2-1a AXlAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL PQWER (UNIT 1)

CATAWB A - UNITS 1 and 2 3/423 Amendment,No. 14 (Unit 1)

Amendment'No. 6 (Unit 2)

s POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (UNIT 2)

LIMITING CONDITION FOR OPERATION 4

3.2.1.2 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within j

the following target band (flux difference units) about the target flux l

difference:

a.

15% for Cycle 1 core average accumulated burnup of less than or j

equal to 5000 MWD /MTU; b.

+3%, -9% for Cycle 1 core average accumulated burnup of greater l

than 5000 MWD /MTU; and i

c.

+3%, -12% for subsequent cycles.

The indicated AFD may deviate outside the above required target level at greater l

than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AFD is within the Acceptable Operation Limits of Figure 3.2-1b and the l

cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER (Unit 2).*

ACTION:

a.

With the indicated AFD outside of the above required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes, either:

l 1.

Restore the indicated AFD to within the target band limits, or 2.

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

b.

With the indicated AFD outside of the above required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation times during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits of i

Figure 3.2-lb and with THERMAL POWER less than 90% but equal to or l

greater than 50% of RATED THERMAL POWER, reduce:

1.

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

See Special Test Exceptions Specification 3.10.2.

CATAWBA - UNITS 1&2 3/4 2-4 Amendment No.14 (Unit 1) l Amendment No. 6 (Unit 2)

s POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 2.

The Power Range Neutron Flux * - High Setpoints to less than or 1.

equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c.

With the indicated AFD outside of the above required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time during the pre-vious 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER untii the indi-cated AFD is within the above required target band.

SURVEILLANCE REQUIREMENTS 4.2.1.1.2 The indicated AFD shall te determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status.

b.

Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

4.2.1.2.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outside the target band.

Penalty deviation outside of the above required target band shall be accumulated on a time basis of:

a.

One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and

Surveillance testing of the Power Range Neutron Flux Channel may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits of Figure 3.2-lb.

A total'of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the above re' quired target band during testing without penalty deviation.

CATAWBA - UNITS 1&2 3/4 2-4a Amendment ho.14 (Unit 1)

Amendment h. 6 (Unit 2)

r POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b.

One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

4.2.1.2.3 The target 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.

4.2.1.2.4 The target flux difference shall be updated at least once per l

31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.2.3 above or by linear interpolation between the most recently measured value and 0% at the end of cycle life.

The provi-sions of Specification 4.0.4 are not applicable.

l l

l g

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

Amendment No. 6 (Unit 2)

=,

o 1

4 f

140

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50 40 30 20

-10 0

10 20 30 40 50 FLUX DIFFERENCE (61) %

FIGURE 3.2-lb AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (Unit 2) n Amendment No.14 (Unit 1)

CATAWBA - UNITS 1 AND 2 3/4 2-4c Amendment No.

6 (Unit 2)

s l

POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z) (Unit 1)

LIMITING CONDITION FOR OPERATION 3.2.2.1 F (Z) shall be limited by the following relationships:

l q

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

P F (Z) $ [4.64] [K(Z)] for P $ 0.5 q

Where:

P _ THERMAL POWER

, and RATED THERMAL POWER K(Z) = the function obtained from Figure 3.2-2 for a given core 4

height location.

APPLICABILITY:

MODE 1 (Unit 1).

ACTION:

With F (Z) exceeding 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints (value of K ) have i

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

l b.

Identify and correct the cause of the out-of-limit condition prior j

to increasing THERMAL POWER above the reduced limit required by l

ACTION a., above; THERMAL POWER may then be increased provided F (Z) is demonstrated through incore mapping to be within its limit.

q g.

CATAWBA - UNITS 1 & 2 3/4 2-5 Amendment No.14(Unit 1)

Amendment No. 6 (Unit 2)

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 For RAOC operation, (F (z) shall be evaluated to determine if F (z) is within its limit by:

0 0

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 q

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

Verify the requirements of Specification 3.2.2.1 are satisfied.

c.

Satisfying the following relationship:

N 2

x K(z) q (z) $.32 F

for P > 0.5 P x W(z)

N x K(z) 0 (z) < 2.32 F

for P < 0.5 W(z) x 0.5 I

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

manufacturing tolerances and me'asurement uncertainty, 2.32 is the F limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL q

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.

i

During power escalation at the beginning of each cycle, power le/el'maf be increased until a power level for extended operation has been achieved and a power distribution map obtained.

CATAWBA - UllITS 1&2 3/4 2-6 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

+

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) e.

With measurements indicating fFM(z)\\

maximum

( K(z)

)

over z N

has increased since the previous determination of F9 (z) either of the following actions shall be taken:

N 1)

Fq (z) shall be increased by 2% over that specified in Specification 4.2.2.1.2c., or N

2)

Fq (z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that Fh(z) is not increasing.

maximum over z K(z) f.

With the relationships specified in Specification 4.2.2.1.2.c. above not being satisfied:

1)

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

expression:

5 (z) x W(z) \\

r

[ maximum F

1 1

x 100 for P > 0.5

,over z 2.32 x K(z)

P a

rF (z)xW(z))

[ maximum 1,x 100 for P < 0.5 over z 2.32 1,

x K(z) l

_ 0.5

)

2)

One of the following actions shall be taken:

a)

Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits of 3.2-la by 1% AFD for each percent F (z) exceeds its limits as deter-q mined in Specification 4.2.2.1.2f.1).

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints to these modified limits, or b)

Comply with the requirements of Specification 3.2.2.1 for F (z) exceeding its limit by the percent calculated.ebove, or q

c)

Verify that the requirements of Specification 4.2.2.1.3 for Base Load operation are satisfied and enter Base Load operation.

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

Amendment No. 6 (Unit 2)

~

,.~

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) g.

The limits specified in Specifications 4.2.2.1.2c., 4.2.2.1.2e., and 4.2.2.1.2f., above are not applicable in the following core plane regions:

1.

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

Upper core region from 85 to 100%, inclusive.

ND 4.2.2.1.3 Base Load operation is permited at powers above APL if the following conditions are satisfied:

a.

Prior to entering Base Load operation, maintain THERMAL POWER above ND APL and less than or equal to that allowed by Specification 4.2.2.1.2 for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Maintain Base Load operation surveillance (AFD within 13% of target flux difference) during this time period.

Base Load operation is then permitted providing THERMAL ND BL ND POWER is maintained between APL and APL or between APL and 100% (whichever is most limiting) and FQ surveillance is maintained BL pursuant to Specification 4.2.2.1.4.

APL is defined as:

APLBL = minimum g

] x 100%

(2.32 x K(Z) t over Z M

p (Z) x W(Z)BL q

N where:

F (z) is the measured F (z) increased by the allowances for 9

manufacturing tolerances and measurement uncertainty.

The F limit q

is 2.32.

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

W(z)BL is the cycle dependent function that accounts for limited power distribution transients encountered during base load operation. The function is given in the Peak Factor Limit Report as per Specification 6.9.1.9.

b.

During Base Load operation, if the THERMAL POWER is decreased below ND APL then the conditions of 4.2.2.1.3.a shall be satisfied before re-entering Base Load operation.

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

F (Z) is within its limit by:

g 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 g

by 3% to account for manufacturing tolerances and furtheir increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2.1 are satisfied.

CATAWBA - UNITS 1 & 2 3/4 2-7a Amendment No.14 (Unit 1) i Amendment No. 6 (Unit 2) n.n_.--

--.n.

...-,_.m.,.y

-. ~.

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) c.

Satisfying the following relationship:

(2.32 x K(Z)

ND F (Z) <

for P > APL P x W(Z)BL M

where:

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

The F limit is 2.32.

q q

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

P is the relative THERK;L POWER.

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

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

d.

Measuring F (Z) in conjunction with target flux difference deter-mination ac ording to the following schedule:

1.

Prior to entering BASE LOAD operation after satisfying surveil-lance 4.2.2.1.3 unless a full core flux map has been taken in the previous 31 EFPD with the relative thermal power having been ND maintained above APL for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to mapping, and 2.

At least once per 31 effective full power days.

e.

With measurements indicating maximum FM (z)

E K(z) 3 over z has increas,ed since the previous determination F (Z) either of the following actions shall be taken:

M 1.

F (Z) shall be increased by 2 percent over that specified in q

4.2.2.1.4.c, or M

2.

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

(z) is not increasing.

K(z) 3 over z f.

With the relationship specified in 4.2.2.1.4c above iot being satisfied, either of the following actions shall be takep:,,

1.

Place the core in an equilibrium condition where the limit in N

4.2.2.1.2c is satisfied, and remeasure F (Z), or CATAWBA - UNITS 1 & 2 3/4 2-7b Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 2.

Comply with the requirements of Specification 3.2.2.1 for F (Z) exceeding its limit by the percent calculated with q

the following expression:

F (Z) x W(Z)BL ] ) -1 ] x 100 for P > APL ND

[(max. over z of [ 2.32 x K(Z) p g.

The limits specified in 4.2.2.1.4c., 4.2.2.1.4e., and 4.2.2.1.4f.

above are not applicable in the following core plan regions:

1.

Lower core region 0 to 15 percent, inclusive.

2.

Upper core region 85 to 100 percent, inclusive.

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

of Specification 4.2 2.1.2 an overall measured F (z) shall be obtained from a power q

distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

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

Amendment No. 6 (Unit 2)

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR - Fn(Z) (Unit 2)

LIMITING CONDITION FOR OPERATION 3.2.2.2 F (Z) shall be limited by the following relationships:

q F (Z) 5 [2.32] [K(Z)] for P > 0.5 0

P F (Z) 5 [4.64] [K(Z)] for P $ 0.5 q

Where:

P _ THERMAL POWER

, and RATED THERMAL POWER K(Z) = the function obtained from Figure 3.2-2 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% 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints (value of K ) have 4

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

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

m POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS i.

4 4.2.2.2.1 The provisions of Specification 4.0.4 are not applicable.

l 4.2.2.2.2 F,y shall be evaluated to determine-if F (Z) is within its limit by:

q a.

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

b.

Increasing the measured F component of the power distribution map xy by 3% to account for manufacturing tolerances and further increasing l

the value by 5% to account for measurement uncertainties, c.

Comparing the F computed (F ) obtained in Specification 4.2.2.2.2b.,

above to:

xy i

1)

The F,y limits for RATED THERMAL POWER (FRTP) for the appropriate x

measured core planes given in Specification 4.2.2.2.2e. and f.,

below, and 2)

The relationship:

= F,RTP [1+0.2(1-P)],

Fx Where F is the limit for fractional THERMAL POWER operation l

RTP express as a function of F and P is the fraction of RATED x

THERMAL POWER at which F was measured.

xy j

d.

Remeasuring F,y according to the following schedule:

RTP 1)

When F is greater than the F limit for the appropriate x

x i

measured core plane but less than the F relationship, additional C

RTP powergistributionmapsshallbetaken d F,Y compared to FxY i

and F either:

xy

)

a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL C

POWER or greater, the THERMAL POWER at which F was yy last determined, or 1

k b)

At least cnce per 31 EFPD, whichever occurs first.

i 1

j s-l i

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

Amendment No. 6 (Unit 2)

4 i'

POWER DISTRIBUTION LIMITS I

SURVEILLANCE REQUIREMENTS (Continued)

C RTP l

2)

When the F is less than or equal to the F limit for the x

appropriate measured core plane, additional power distribution RTP L

j maps shall be taken and F compared to F and F at least x

x xy once per 31 EFPD.

e.

The F limits for RATED THERMAL POWER (F P) shall be provided for j

xy all core planes containing Bank "D" control rods and all unrodded j

core planes in a Radial Peaking Factor Limit Report per Specifica-i tion 6.9.1.9; f.

The F limits of Specification 4.2.2.2.2e.,,above, are not applicable xy in the following core planes regions as measured in percent of core height from the bottom of the fuel:

1)

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

Upper core region from 85 to 100%, inclusive, 3)

Grid plane regions at 17.8 i 2%, 32.1 1 2%, 46.4 1 2%, 60.6 i 2%

and 74.9

2%, inclusive, and I

4)

Core plane regions within i 2% of core height (i 2.88 inches) g about the bank demand position of the Bank "D" control rods.

WithF,fexceedingFxy, the effects of F b

on F (Z) shall be evaluated g.

xy 9

to determine if F (Z) is within its limits.

q l

4.2.2.2.3 When F (Z) is measured for other than F determinations, an overall q

xy measured F (Z) shall be obtained from a power distribution map and increased 9

by 3% to account for manufacturing tolerances and further increased by 5% to i

l account for measurement uncertainty.

I i

l J

l i

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

Amendment No. 6 (Unit 2) i I-.__-_,___-._,______.___

-_-,.c,-

+

P i.s0

.. _ _. r_ __..+

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2. _.

. _.~.._._ = _ =

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=.u

=

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w

_.:2.... _.

...~

_=-.=.x

+

. +.

__-.., +..._.

_... ~..

1.25

=

. _=

u..=

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=

1.00

~"~~

.:zn_..... - - -__

--~-^^

"-~ ~ ~ ~

~-..^~

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...... _ ~ "

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0.50

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

-.... CORE

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.=~.: r.._._

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_-.... _. -._.

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.__. 10.8 0.94. _

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4

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=-

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=

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=

~=._

=.

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z 0

2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT (FT)

~

FIGURE 3.2-2 K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT 9

CATAWBA - UNITS 1 AND 2 3/4 2-8

e 3/4.1 REACTIVITY CONTROL SYSTEMS BASES

)

3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that:

(1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, baron concentration, and T,yg.

The most restrictive condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled Reactor Coolant System cooldown.

In the analysis of this accident, a minimum SHUTOOWN MARGIN of 1.3% Ak/k is required to control the reactivity transient.

Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T less than 200*F, the reactivity transients resulting from a postulated steE9

(

line break cooldown are minimal and a 1% ak/k SHUTDOWN MARGIN provides adequate protection.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator teinperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other j

than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.

These corrections I

g...

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

REACTIVITY CONTROL SYSTEMS BASES 4

MODERATOR TEMPERATURE COEFFICIENT (Continued) involved subtracting the incremental change in the HDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions.

Th transformedintothglimitingMTCvalue-4.1x10{svalueoftheMDCwasthen Ak/k/*F.

The MTC value of -3.2 x 10 Ak/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibriumboronconcentrationand_jsobtainedbymakingthesecorrectionsto j

the limiting MTC value of -4.1 x 10 Ak/k/*F.

l l

The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains 4

within its limits since this coefficient changes slowly due principally to the j

reduction in boron concentration associated with fuel burnup.

1 i

)

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification enstres that the reactor will not be made critical with the Reactor Coolant System average temperature less than 551*F.

This i

limitation is required to ensure:

(1) the moderator temperature coefficient l

is within it analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the P-12 interlock is above its setpoint, l

(4) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (5) the reactor vessel is above its minimum RT temperature.

NOT i

3/4.1.2 BORATION SYSTEMS The Boron Injection System ensures that negative reactivity control is available during each mode of facility operation.

The components required to i

perform this function include:

(1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency I

power supply from OPERA 8LE diesel generators.

With the coolant average temperature above 200*F, a minimum of two baron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable.

The l

boration capability of either flow path is sufficient to provide a SHUTDOWN i

g..

CATAWBA - UNITS 1&2 B 3/4 1-2 Amendment No. 14(Unit 1) j Amendment No. 6 (Unit 2)

o 3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:

(1) maintaining the calculated DNBR in the core greater than or equal l 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 q

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 fuel pellets and rods; F

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

the integral of linear power along the rod with the highest integrated power to the average rod power; and 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 (Unit 2 only).

l 3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper 9

bound envelope of 2.32 times the normalized axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The full-length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels.

The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL. POWER value by the appropriate fractional THERMAL POWER level.

The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

CATAWBA - UNITS 1 & 2 8 3/4 2-1 Amendment No.14(Unit 1)

Amendment No. 6(Unit 2)

POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (Continued)

Although it is intended that Unit 2 will be operated with the AFD within the target band required by Specification 3.2.1.2 about the target flux differ-ence, 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 sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited. Accordingly, a 1-hour penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is provided for operation outside of the target band but within the limits of Figure 3.2-lb while at THERMAL POWER l

1evels between 50% and 90% of RATED THERMAL POWER.

For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less.significant. The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

For Unit 2, provisions for monitoring the AFD on an automatic basis are l

derived from the plant process computer through the AFD Monitor Alarm.

The computer determines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least two of four or two of three OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER.

During opera-tion 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

Figure B 3/4 2-1 shows a typical monthly target band for Unit 2.

0 For Unit 1 at power levels below APL, the limits on AFD are defined by Figure 3.2-la, i.e., that defined by the RAOC operating procedure and limits.

These limits were calculated in a manner such that expected operational tran-sients, e.g., load follow operations, would not result in the AFD deviating outside of those limits.

However, in the event such a deviation occurs, the 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 factors would change sufficiently to prevent operation in the vicinity of the ND APL power level.

ND For Unit 1 at power levels greater than APL, two modes of operation are permissible; 1) RAOC, the AFD limit of which are defined by Figure 3.2-la, and

2) Base Load operation, which is defined as the maintenance of the AFD within ND a 13% band about a target value.

The RAOC operating procedure aboye APL 93 ND the same as that defined for operation below APL 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 guprantee opera-tion with F (z) less than its limiting value.

To allow operation Bf thE maximum 9

permissible value, the Base Load operating procedure restricts the indicated CATAWBA - UNITS 1 & 2 B 3/4 2-2 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

o POWER DISTRIBUTION LIMITS BASES AXIAL FLUX DIFFERENCE (Continued)

AFD to relatively small target band and power swings (AFD target band of 13%,

ND OL APL power i APL or 100% Rated Thermal Power, whichever is lower).

For Base Load operation, it is expected that Unit 1 will operate within the target band.

Operation outside of the target band for the short 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 redistri-bution impact from past operation on the Base Load operation, a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months waiting ND period at a power level above APL and allowed by RAOC is necessary.

During i

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

the Base Load procedure.

After the waiting period extended Base Load operation is permissible, j

For Unit 1 the computer determines the one minute average of each of the j

OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are:

1) outside l

the allowed AI power operating space (for RA0C 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) APLND (for Base Load operation).

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.

3/4.2.2 and 3/4.2.3 HEAT 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 ilmit.

1 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 i 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; a

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

Amendment No. 6(Unit 2)

O 1.00

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INDICATED AXl AL FLUX DIFFERENCE g

FIGUP.E C 3/4 2-1 TYPICAL INDICATED AXI AL FLUX DIFFERENCE VERSUS THERM,L POWEP (Unit 2)

CATAWBA - UNITS 1 AND 2 B 3/4 2-3 Amendment No.14 (Unit 1)

Amendment No.

6 (Unit 2)

POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) c.

The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained; and i

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.

H above are maintained.

As noted on Figure 3.2-3, Reactor Coolant System flow rate andFhmaybe"tradedoff"againstoneanother(i.e.,alowmeasuredReactor N

Coolant System flow rate is acceptable if the measured F is also low) to ensure that the calculated DNBR will not be below the design DNN value.

The relaxation i

{

of F as a function of THERMAL POWER allows changes in the radial power shape H

for all permissible rod insertion limits.

R as calculated in Specification 3.2.3 and used in Figure 3.2-3, accounts

)j for F less than or equal to 1.49.

This value is used in the various accident H

i analyses where F influences parameters other than DNBR, e.g., peak clad temp-H erature,andthusisthemaximum"asmeasuged"valueallowed.

The rod bow pen-l w

alty as a function of burnup applied for F is calculated with the methods de-AH l

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, 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 j

a full-core map taken with the Incore Detector Flux Mapping System, and a 3%

j allowance is appropriate for manufacturing tolerance.

For Unit I the hot channel factor F (z) is measured periodically and in-creased by a cycle and height dependent power factor appropriate to either RAOC i

or Base Load operation, 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 9

operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)BL acco'unts for the g..

j more restrictive operating limits allowed by Base Load operation which result in less severe transient values.

The W(z) function for normal operation is i

provided in the Peaking Factor Limit Report per Specification 6.9.1.9.

J CATAWBA - UNITS 1 & 2 8 3/4 2-4 Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

For Unit 2 the Radial Peaking Factor, Fxy(Z), is measured periodically to provide assurance that the Hot Channel Factor, F (Z), remains within its limit.

9 The F limit for RATED THERMAL POWER (F RTP) as provided in the Radial Peaking xy Factor Limit Report per Specification 6.9.1.9 was determined from expected power control maneuvers over the full range of burnup conditions in the core.

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

Amendment No. 6 (Unit 2)

a ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Semiannual Radioactive Effluent Release Reports shall include a list and 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 Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP and to the ODCM, pursuant to Specifi-cations 6.13 and 6.14, respectively, as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Specification 6.15.

It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Speci fication 3.12.2.

The Semiannual Radioactive Effluent Release Reports shall also include the following:

an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.

MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 For Unit 1 the W(z) functions for RAOC and Base Load operation and the value for APLND (as required) shall be provided to the Director, Nuclear Reactor Regulation, Attention: Chief, Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555 at least 60 days prior to cycle initial criticality.

In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.

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.

For Unit 2 the F limit for RATED THERMAL POWER (FRTP) shall be provided to xy x

the Regional Administrator of the Regional Office of the NRC with a copy to the 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 coreiplanes and the plot of predicted (F.PRel) vs Axial Core Height with the limit envelope l

at least 60 days prior to each cycle initial criticality unless otherwise l

CATAWBA - UNITS 1 & 2 6-19 Amendment No.14 (Unit 1) l Amendment No. 6 (Unit 2)

p ADMINISTRATIVE CONTROLS l

RADIAL PEAKING FACTOR LIMIT REPORT (Continued) approved by the Commission by letter.

In addition, in the event that the limit should change requiring a new submittal or an amended submittal to the Radial Peaking Factor Limit Report, it will be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission RTP by letter.

Any information needed to support F will be by request from the x

NRC and need not be included in this report.

s-i i

l l

CATAWBA - UNITS 1 & 2 6-19a Amendment No.14 (Unit 1)

Amendment No. 6 (Unit 2)

ADMINISTRATIVE CONTROLS P

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

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

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

a.

Records and logs of unit operation covering time interval at each power level; b.

Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; c.

.Al.1 REPORTABLE EVENTS; d.

Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.

Records of changes made to the procedures required by Specification 6.8.1; f.

Records of radioactive shipments; g.

Records of sealed source and fission detector leak tests and results; and h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; c.

Records of radiation exposure for all individuals entering radiation control areas; d.

Records of gaseous and liquid radioactive material released to the environs; e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1; i --

f.

Records of reactor tests and experiments; g.

Records of training and qualification for current members of the unit staff; CATAWBA - UNITS 1 & 2 6-20

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