Text

Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P
	ML20155B211
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	10/22/1998
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20155B209	List: ML20155B207; ML20155B211;
References
	NUDOCS 9810300088
	Download: ML20155B211 (38)
	v • d • e

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l

. 1 1

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1 l

l l

Attachment la l

W roved Technical specifications for McGuire Units 1 and 2 Marked copy l

i l

d

~

'98i'03OOOB8 981022 PDR ADOCK 05000369 p PDR

l SLs 2.0 670 DO NOT OPERATE IN THIS ARE A i

660 f ,J ele I Lg 4 5 Sne- 6 b*; 1 6s0 -

2455 psio l

l

& l 2400 paio i b630 2280 pelo l I @ -

2100 psio '

i 1

610 -

i 1

1945 pse l

600 -

590 l

ACCEPTABLE OPERA 110N 880 O.0 0.2 0.4 0.6 0.8 1.0 la Fraction of Roted Thermal Power I

Figure 2.1.1-1 Reactor Core Safety Limits -

Four Loops in Operation i

l McGuire Units 1 and 2 2.0-2

! Amendment Nos.134 66 1

Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

l SR 3.2.1.2 -------

N OT E - ---- -

1. Extrapolate F"(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement, if F"o(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F"o(X,Y,Z) EXTRAPOLATED g Fb(X,Y,Z) " EXTRAPOLATED, and !

l E"o(X.Y.Z)ExTnAPOtATED > E"o(X.Y.Z)

Fb(X,Y,Z)P EXTRAPOLATED Fb(X,Y,Z) "

, p j then: O' Y ,. pd ,'y

a. Increase F*o(X,Y,Z) acto N reverify F%(X,Y,Z) s b@(X,Y,Z) "; or

b. Repeat SR 3.2.1.2 prior to the time at which F"o(X,Y,Z) s Fo'(X,Y,Z) " is extrapolated to not be met.

2. Extrapolation of F1(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F"a(X,Y,Z) s Fb(X,Y,Z) P 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"o(X,Y,Z) was last verified AND 31 EFPD thereafter (continued)

McGuire Units 1 and 2 3.2.1-4 Amendment Nos.1

Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY P

SR 3.2.1.3 -----------------

N OT E S------ - -

1. Extrapolate F%(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F%(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F"o(X,Y,Z)ExTn4PotATED 2F b(X,Y,Z)RPS EXTRAPOLATED, and E"o(X.Y.Z) EXTRAPOLATED > E"o(X,Y.Z)

Fb(X,Y,Z)RPSEXTRAPOLATED Pb(X,Y,Z)nes wclbt

.pe ##!

then: ,,,. ped ,.4 ft,e. C O L k j

a. Increase F"o(X,Y,Z) by factor and 1 reverify F"o(X,Y,Z) s Fb(X,Y,Z)"#8; or j

b. Repeat SR 3.2.1.3 prior to the time at j which F%(X,Y,Z) s Fb(X,Y,Z)sPs is 1 extrapolated to not be met.

2. Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F"o(X,Y,Z) s Fb(X,Y,Z)nes -

2 hou ter achieving equilibrium conditions after exceeding, by a i 10% RTP, the THERMAL l POWER at which l F"o(X,Y,Z) was last verified AND l 31 EFPD thereafter

'i McGuire Units 1 and 2 3.2.1 -5 Amendment Nos.18 66

l Fm(X,Y) l 3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1

SR 3.2.2.2 --

-NOTES-

1. Extrapolate F"m(X,Y) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"m(X,Y) is within limits and the 31 EFPD extrapolation indicates:

F"3s(X,Y) EXTRAPOLATED z Fh(X,Y)susv EXTRAPOLATED and E%(X.Y) EXTRAPOLATED >E (X.Y)

Fb(X,Y)sm XTRAPOLATED Fb(X,Y)se p

,,,,to then: Sjfe,-Qel.h a.

u Increase F m(X,Y) b e +4e col R actormi i .0- nd reverify F"as(X,Y) s Fh(X,Y)sm; or

b. Repeat SR 3.2.2.2 prior to the time at which F%(X,Y) s F'3s(X,Y)sm is extrapolated to not be met.

2. Extrapolation of F% (X,Y) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F%(X,Y) s Fh(X,Y)sm .

Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after l exceeding, by 2 l 10% RTP, the THERMAL POWER at which l F%(X,Y) was last i venfied l

AND 31 EFPD 1

thereafter l

McGuire Units 1 and 2 3.2.2-4 Amendment Nos.189t 6 l

l

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

Design Features i 4.0 1 2

4.0 DESIGN FEATURES 4.1 Site Location The McGuire Nuclear Station site is located at latitude 35 degrees,25 minutes,59 seconds north and longitude 80 degrees,56 minutes,55 seconds west. The Universal Transverse Mercator Grid Coordinates are E 504,669,256, and N 3,920,870,471. The site is in northwestern Mecklenburg County, North Carolina,17 miles north-northwest of Charlotte, North Carolina.

4.2 Reactor Core , guo# or g , g g_ o 4.2.1 Fuel Assemblies The rea r shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of ircalloy fuel rods with an initial composition of natural or slightly ;

enriched uran' ' oxide (UO2 ) as fuel material. Limited substitutions of -

l zirconium a oyjor st inless steel filler rods for fuel rods, in accordance with approved s of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable l NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

l l

4.2.2 Control Rod Assemblies l

The reactor core shall contain 53 control rod assemblies. The control material shall be silver indium cadmium (Unit 1) silver indium cadmium and boron carbide (Unit 2) as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality I 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum i:ominal U-235 enrichment of 4.75 weight percent;

b. kon s;0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

, (continued)

McGuire Units 1 and 2 4.0-1 Amendment Nos.18ptd

Reporting Requirements !

5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

5. DPC NE 2011PA, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March,1990 (DPC Proprietary).

6. DPC NE-3001PA, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November, 1991 (DPC Proprietary).

l i

7. DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station i Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June,1985.

8. DPC-NE-3002A, Through Rev. 2 "FSAR Chr'.er 15 System Transient Analysis Methodology," SER dateJ April 26,1996. !

l

9. DPC NE-3000P-A, Rev.1 " Thermal-Hydrauli: Transient Analysis !

Methodology," SER dated December 27,1995. l

10. DPC-NE-1004A, Rev.1, " Nuclear Design Methodology Using i CASMO-3/ SIMULATE-3P," SER dated April 26,1996.

11. DPC-NE-2004P-A, Rev.1, " Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," SER dated February 20,1997 (DPC Proprietary).

12. DPC-NE-2001P A, Rev.1," Fuel Mechanical Reload Analysis Methodology for Mark-BW fuel," October 1990 (DPC Proprietary).

13. DPC-NE-2005P-A, Rev.1, " Thermal Hydraulic Statistical Core Design Methodology," SER dated November 7,1996 (DPC Proprietary).

14. DPC-NE-2008P-A, " Fuel Mechanical Reload Analysis Methodology Using TACO 3," SER dated April 3,1995 (DPC Proprietary).

15. BAW-10183P-A, Fuel Rod Gas Pressure Criterion, B&W Fuel Company, Juiy,1995. /

pp(_ pg -zoo 9 PA , " U* SS' h* *SO~ Y*\ T*SI

^

~

jg' ge,po,.t, d 5 c. 4 c.) tc 2 (p #C A p We.iq d .

(continued)

McGuire Units 1 and 2 5.6-4 Amendment Nos.

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

Fo(X,Y,Z)

B 3.2.1 BASES f ,

SURVEILLANCE REQUIREMENTS Nntinued) Pke A// Y 5

~

')

than the measured factor i of the current li , ditional actions must be taken. These actions are meet the F ,Y,Z) limit with the last F"o(X,Y,Z) increased by actor @fJ42)or to evaluate Fo(X,Y,Z) prior to the projected point in time when trie extrapolated values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its lirnit for any significant period of time without detection using the best available data. F"o(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of F"o(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within *2% of the core height about the demand position of the rod tip.

Fo(X,Y,Z) is verified at power levels 210% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equil!brium conditions to ensure that Fo(X,Y,Z) is within its limit at higher power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of Fo(X,Y,Z) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. 10 CFR 50.46,1974.

2. UFSAR Section 15.4.8.

3. 10 CFR 50, Appendix A, GDC 26.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE 2011PA " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors", March 1990.

McGuire Units 1 and 2 B 3.2.1-11 Revision No.fl

_ _ __ ___ _ ~ .. _ _ _ _ . _ . _ _

l j Fas(X,Y) l B 3.2.2

! BASES SURVEILLANCE REQUIREMENTS (continued) l channel factor to the surveillance limit is likely to decrease belo b the value of that ratio when the measurement was taken, pi,e a I

Each of these extrapolations is applied separately to the entha)py rise hot channel factor surveillance limit. If both of the extrapolations re unfavorable, i.e., if the extrapolated factor is expected to ex ed the

, extrapolated limit and the extrapolated factor is expected t become a i larger fraction of the extrapolated limit than the measured actor is of the current limit, additional actions must be taken. These a ions are to meet the F"m(X,Y) limit with the last F"as(X,Y) increased by actorM or l to evaluate F"3s(X,Y) prior to the point in time when the extrapolated i

values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent F"m(X,Y) from exceeding its limit for any '

significant period of time without detection using the best available data.

F as(X,Y) is not required to be extrapolated for the initial flux map taken af ter reaching equilibrium conditions since the initial flux n::#'B^

the baseline measurement for future trending. '

5 cc.f N F"m(X,Y) is verified at power levels 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium I conditions to ensure that F"m(X,Y) is within its limit at high power levels.

l The Surveillance Frequency of 31 EFPD is adequate to monitor the l change of power distribution with core burnup. The Surveillance may be

done more frequently if required by the results of F"3s(X,Y) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. UFSAR Section 15.4.8

2. 10 CFR 50, Appendix A, GDC 26.

3. 10 CFR 50.46.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE-2005P, " Duke Power Company Thermal Hydraulic Statistical Core Design Methodology", September 1992.

McGuire Units 1 and 2 8 3.2.2-9 Revision No.[

i

'l Attachment 1b i Improved Technical specifications for catawba Units 1 and 2 Marked copy j

1

.a l SLs 2.0

. l 1

670 DO NOT OPERATE IN THt$ AREA M

l f /clefG 2.q SC Ps',%

I o'n L 650 -

2455psb om 1 2 0 0 psio C

L 630 2280psio I -

l h620 2100 pelo 610 -

1945 paio 600 -

1 590 -

ACCEPTA8U! OPERATION Seo i ,

l 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Roted Thermal Power Figure 2.1.1-1 (UNIT 1 ONLY) i i

Reactor Core Safety Limits -

Four Loops in Operation Catawba Units 1 and 2 2.0-2 Amendment Nos.173 1

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

SLs 2.0 670 00 NOT OPERATE IN THIS AREA.

dek fe-

~

l 24 5 psb~-

llw 650 - 2455 psia l l

l s l 64 -

240 psia i l

l

[a . M*

620 -

2100 psia 610 -

1946 pelo 590 -

ACCEPTABLE OPetA110N 580 O.0 0.2 0.4 0.6 0.8 1.0 1.2 Froction of Roted Thermol Power s

Figure 2.1.1-1 (UNIT 2 ONLY)

Reactor Core Safety Limits -

Four Loops in Operation Catawba Units 1 and 2 2.0-3 Amendment Nos.17 65

i Fo(X,Y,Z) 3.2.1 l SURVEILLANCE REQUIREMENTS (continued) ;

SURVEILLANCE -FREQUENCY SR 3.2.1.2 .----------- -

NOTE- --

i

1. Extrapolate F*o(X,Y,Z) using at least two '

measurements to 31 EFPD beyond the most recent measurement. If F1(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

1 F"o(X,Y,Z)exTaxeotAreo n F'o(X,Y,Z) "muma and l l

E"o(X.Y.Z)sXTRAPotATeo > E"a(X.Y Z)

Fb(X,Y,Z) "exTnApotArea Fo(X,Y,Z) " #

,f,Ag g,jg if,'<A id then:

5/"CoI g

a. Increase F1(X,Y,Z) by@ factor and reverify F%(X,Y,Z) s Fb(X,Y,Z) ; or

b. Repeat SR 3.2.1.2 prior to the time at I which F1(X,Y,Z) s Fo(X,Y,Z) " is extrapolated to not be met.

2. Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

Once within Verify F"o(X,Y,Z) s F'o(X,Y,Z) ".

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium ,

conditions after !

exceeding, by 2 l 10% RTP, the ;

THERMAL 1 POWER at which l F"o(X,Y,Z) was 3 last verified l

AND !

31 EFPD thereafter !

(continued) :

Catawba Units 1 and 2 3.2.14 Amendment Nos.1 165 )

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

l Fo(X,Y,Z) l 3.2.1 SURVEILLANCE REQUIREMENTS (continued) l l SURVEILLANCE FREQUENCY l SR 3.2.1.3 --------------.----

NOTE S - ------ -------------

1. Extrapolate F"o(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"o(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F"o(X,Y,Z)exrRAeOureo 2 F b(X,Y,Z)Res,x,g,ggL,,,,,

and 4 1

1

$(X.Y,Z)eXTRAPOurm > (X,Y.Z)

Fo(X,Y,Z)RPS EXTRAPOLATED a(X,Y,Z)RPS f-Ae c'A" 8 .

'd then: 7pec t'b#

q4e,COLb

a. Increase F"o(X,Y,Z) by$ factor and reverify F"o(X,Y,Z) s Fb(X,Y,Z)""*; or I b. Repeat SR 3.2.1.3 prior to the time at which F%(X,Y,Z) s Fb(X,Y,Z)""8 is extrapolated to not be met.

2. Extrapolation of F o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

l Once within Verify F"o(X,Y,Z) s Fb(X,Y,Z)Res ,

achieving equilibrium conditions after exceeding, by 2 10% RTP, the

( THERMAL l POWER at which l F"o(X,Y,Z) was l last verified l

l AND 31 EFPD thereafter l

t Catawba Units 1 and 2 3.2.1 -5 Amendment Nos.1 165 l

l l~

L

l i F3s(X,Y) l 3.2.2 SURVEILLANCE REQUIREMENTS (continued) l l

SURVEILLANCE FREQUENCY j 1

l SR 3.2.2.2 ---

- N OT E S------------ - ------- l l 1. Extrapolate F"m(X,Y) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"m(X,Y) is within limits and the 31 EFPD extrapolation indicates:

F"m(X,Y)exTaApoureo 2 Fh(X,Y)sm exTRAPo urEO 1

and I l

l E"m(X.Y)exTaxeotareo > F"m(X.Y) l Fh(X,Y)smexTn4potAreo Fh(X,Y)sm % l

. f M Y gg f .

l then: V ;ge de d i

l cot- D

a. increase F1(X,Y) bdfactor nd reverify F1(X,Y) s Fi(X,Y)s"; or l

b. Repeat SR 3.2.2.2 prior to the time at :

which F1(X,Y) s Fb(X,Y)sm is i extrapolated to not be met. )

2. Extrapolation of F1(X,Y) is not required for the initial flux map taken after reaching equilibrium i conditions.

l l Once within 12 l Verify F1(X,Y) s Fb(X,Y)s". hours after achieving equilibrium conditions after i exceeding, by 2 10% RTP, the THERMAL I POWER at which F1(X,Y) was last l verified AND 31 EFPD thereafter 1

i Catawba Units 1 and 2 3.2.2-4 Amendment Nos.1J3f

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location Catawba Nuclear Station is located in the north central portion of South Carolina approximately six miles north of Rock Hill and adjacent to Lake Wylie. The station center is located at latitude 35 degrees,3 minutes,5 seconds north and longitude 81 degrees,4 minutes,10 seconds west. The corretoonding Universal Transverse f.iercator Coordinates are E 493,660 and N 3,88. 558, zone 17.

A 4.2 Reactor Core or 7,,1 @

fl,tr b ,g t o 4.2.1 Fuel Assemblies l The reac r shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy fuel rods with an initial composition of natural or slightly enriched uran' dioxide (UO2) as fuel material. Limited substitutions of zirconium a yy or ainless steel filler rods for fuel rods, in accordance with ,

approved ppnc ns of fuel rod configurations, may be used. Fuel assemblies '

shall be lim e to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to :

comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver indium cadmium and boron carbide as approved by the NRC.

4.3 Fuel Storage I

4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

(continued)

Catawba Units 1 and 2 4.0-1 Amendment Nos.

Reporting Requirements

, 5.6 l

l l 5.6 Reporting Requirements l

5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) l

15. BAW-10183P-A, Fuel Rod Gas Pressure Criterion, B&W Fuel Company, July,1995.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, I l Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as i l SDM, transient analysis limits, and accident analysis limits) of the safety I

! analysis are met. I

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Ventilation Systems Heater Report l

l When a report is required by LCO 3.6.10," Annulus Ventilation System (AVS),"

LCO 3.7.10 " Control Room Area Ventilation System (CRAVS)," LCO 3.7.12, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," LCO 3.7.13,

" Fuel Handling Ventilation Exhaust System (FHVES)," or LCO 3.9.3,

" Containment Penetrations," a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.

5.6.7 PAM Report When a report is required by LCO 3.3.3, " Post Accident Monitoring (PAM) l Instrumentation," a report shall be submitted within the following 14 days. The I report shall outline the preplanned alternate method of monitoring, the cause of l the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

l 5.6.8 Steam Generator Tube Inspection Report

a. The number of tubes plugged in each steam generator shall be reported I to the NRC within 15 days following completion of the progr c

gg . A/E .- 2c> o7 P A , " Wes+.g oas . Fo i Tms&

ug " sea e<A Cbec Pv"cH -

4 (continued)

Catawba Units 1 and 2 5.6-5 Amendment Nos.

i Fo(X,Y,Z)

B 3.2.1 q BASES SURVEILLANCE REQUIREMENTS (continued) Y k 'Y gpecifjh i

%l g ,.

4 than the measured factor i of the current it, additional actions must be taken. These actions are meet the F ,Y,Z) limit with the last F"o(X,Y,Z) increased by actor (gfho2] or to evaluate Fo(X,Y,Z) prior to the projected point in time when the extrapolated values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its limit for any significant period of -

time without detection using the best available data. F"o(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of F"o(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within *2% of the core height about tho demand position of the rod tip.

Fo(X,Y,Z) is verified at power levels 210% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions to ensure that Fo(X,Y,Z) is within its limit at higher power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the 4

change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of Fo(X,Y,Z) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. 10 CFR 50.46,1974.

2. UFSAR Section 15.4.8.

, 3. 10 CFR 50, Appendix A, GDC 26.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC NE 2011PA " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors", March 1990.

t Catawba Units 1 and 2 B 3.2.1-11 Revision No./

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

Fm(X,Y)

B 3.2.2 BASES SURVEILLANCE REQUIREMENTS (continued) channel factor to the surveillance limit is likely to decrease belo the value of that ratio when the measurement was take e *WYJc, Each of these extrapolations is applied separately to t enthalpy rise hot channel factor surveillance limit. If both of the extrapol ations are unfavorable, i.e., if the extrapolated factor is expected ta exceed the extrapolated limit and the extrapolated factor is expecte d to become a larger fraction of the extrapolated limit than the measured factor is of the current limit, additional actions must be taken. These apions are to meet the F"m(X,Y) limit with the last F"m(X,Y) increased by@factorbf4-62 Lor to evaluate F"as(X,Y) prior to the point in time when the extrapolated values are expected to exceed the extrapolated limits.e These alte requirements attempt to prevent F"m(X,Y) from exceeding its limit for an significant period of time without detection using the best available data.

i F m(X,Y) is not required to be extrapolated for the initial flux map take after reaching equilibrium conditions since the initial flux man establis t es the baseline measurement for future trending. sgn.%f m

+Le CoLk F"m(X,Y) is verified at power levels 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter achieving equilibrium conditions to ensure that F"m(X,Y) is within its limit at high power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequentlyif required by the results of F"m(X,Y) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. UFSAR Section 15.4.8

2. 10 CFR 50, Appendix A, GDC 26.

3. 10 CFR 50.46.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE-2005P, " Duke Power Company Thermal Hydraulic Statistical Core Design Methodology", September 1992.

Catawba Units 1 and 2 B 3.2.2-9 Revision No.[

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

41 . .

4' i

k I

i i

4 I

i 1

s s

l Attachinent 2a t

l Reprinted Improved Technical Specifications for McGuiro Units 1 and 2 4

4 1

1 J

5 I

e i

4 1

1, e

4 k,

4 4

l, M

i

. v.i. .,,, - _- . _ - _ m , -. ___. ,.-,

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

SLs

! 2.0 I

i 670 l

DO NOT OPERATE IN THIS AREA i i

l l @

650 -

i l

I 640 2400 pelo bG M2 l

I l

9G -

2100 pelo l

610 -

l 1 l

1945 psio i I

600 -

l 590 ACCEPTA8LE OPERA!CN g f f f g

! 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Roted Thermal Power

Figure 2.1.1-1 i

i Reactor Core Safety Limits -

Four Loops in Operation McGuire Units 1 and 2 2.0-2 Amendment Nos.

l l

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

Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 ------------------------NOTE-------------------------------

1. Extrapolate F%(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"o(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

g F"o(X,Y,Z)enupourso a Fb(X,Y,Z)*enueourso, e

and F"n(X.Y.Z)snapourto > 6(X.Y.Z)

F'o(X,Y,Z)*snapoureo F'o(X,Y,Z)*

then:

a. Increase F"o(X,Y,Z) by the appropriate factor specified in the COLR and reverify F"o(X,Y,Z) s Fo(X,Y,Z)*; or ,

b.- Repeat SR 3.2.1.2 prior to the time at which F"o(X,Y,Z) s Fo'(X,Y,Z)* is )

.: extrapolated to not be met. j

2. Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

- Verify F"o(X,Y,Z) s Fb(X,Y,Z)". Once within

- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after f achieving equilibrium

-l l

conditions after ;

exceeding, by 2 l 10% RTP, the THERMAL ..

POWER at which F"o(X,Y,Z) was last verified AND 31 EFPD thereafter (continued)

McGuire Units 1 and 2 3.2.1 -4 Amendment Nos.

_ Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3 --------------------------NOTES-----------------------

, 1. Extrapolate F"o(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"o(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F"o(X,Y,Z)sxrn4pourso 2F'o(X,Y,Z)""8 sxra4potArso, and

$(X.Y.Z)sxin4potArso > $(X.Y.Z)

F'o(X,Y,Z)nessXTRAPoureD F'o(X,Y,Z)nes then;

a. Increase F"o(X,Y,Z) by the appropriate factor specified in the COLR and reverify F"o(X,Y,Z) s F'o(X,Y,Z)nes; or

b. Repeat SR 3.2.1.3 prior to the time at which F"o(X,Y,Z) s F'o(X,Y,Z)nes is extrapolated to not be met.

2. Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F%(X,Y,Z) s F'o(X,Y,Z)nes .

Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"o(X,Y,Z) was last verified AND 31 EFPD 4

thereafter McGuire Units 1 and 2 3.2.1 -5 Amendment Nos.

'gi--t v -rup y __ u y--- - ,a-- - - - - ~ , - -

--t.m

Fm(X,Y) 3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.2.2 - - - - - - . . - - - - - - -

N OT E S.--- ----------------------

1. Extrapolate F"m(X,Y) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"m(X,Y) is within limits and the 31 EFPD extrapolation indicates:

F"m(X,Y)sunwourso F2 h(X,Y)sm enneoureo and E"m[Xa Ylennyourso > F"m(X,Y)

Fh(X,Y)smEnRAPOLATEo AH(X,Y)sm then:

a. Increase F"m(X,Y) by the appropriate factor specified in the COLR and reverify F"3a(X,Y) s Fb(X,Y)se; or

b. Repeat SR 3.'2.2.2 prior to the time at which F"3s(X,Y) s Fh(X,Y)se is extracolated to not be met.

2. Extrapolation of F"6s (X,Y) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F"as(X,Y) s Fb(X,Y)sm .

Or.ce within 12 1

, hours after achieving equilibrium !

conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"m(X,Y) was last verified AND 31 EFPD thereafter McGuire Units 1 and 2 3.2.2 4 Amendment Nos.

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

D sign Featurcs 4.0

, 4.0 DESIGN FEATURES i l

4.1 Site Location The McGuire Nuclear Station site is located at latitude 35 degrees,1. rMutes,59 l seconds north and longitude 80 degrees,56 minutes,55 seconds wem. The Universal Transverse Mercator Grid Coordinates are E 504,669,256, and N 3,920,870,471. The site is in northwestern Mecklenburg County, North Carolina,17 miles north-northwest of Charlotte, North Carolina.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of either ZlRLOS or Zircalloy fuel rods with an initial composition of l natural or slightly enriched uranium dioxide (UO2 ) as fuel material. Limited substitutions of ZlRLOS, zirconium alloy, or stainless steel filler rods for fuel l rods, in accordance with approved applications of fuel rod configurations, may be l

used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number l of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

j 4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material I shall be silver indium cadmium (Unit 1) silver indium cadmium and boron carbide (Unit 2) as approved by the NRC.

l 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

i

a. Fuel assemblies having a maximum nominal U-235 enrichment of 4.75 weight percent; L

! b. ka 5 0.95 if fully fboded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; (continued)

McGuire Units 1 and 2 4.0-1 Amendment Nos.

I

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

5. DPC-NE-2011PA, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March,1990 (DPC Proprietary).

6. DPC-NE-3001PA, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," November, 1991 (DPC Proprietary).

7. DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station

! Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June,1985.

8. DPC-NE-3002A, Through Rev. 2 "FGAR Chapter 15 Systsm Transient Analysis Methodology,' SER dated April 26,1996.

( 9. DPC-NE-3000P-A, Rev.1 " Thermal-Hydraulic Transient Analysis Methodology," SER dated December 27,1995.

10. DPC-NE-1004A, Rev.1, " Nuclear Dec!gn Wthodology Using CASMO-3/ SIMULATE-3P," SER dated April 26,1996.

11. DPC-NE-2004P-A, Rev.1, " Duke Power Cvmpany McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," SER dated February 20,1997 (DPC Proprietary).

12. DPC-NE-2001P-A, Rev.1, " Fuel Mechanical Reload Analysis Methodology for Mark-BW fuel," October 1990 (DPC Proprietary).

13. DPC-NE-2005P-A, Rev.1, " Thermal Hydraulic Statistical Core Design Methodology," SER dated November 7,1996 (DPC Proprietary).

14. DPC-NE-2008P-A, " Fuel Mechanical Reload Analysis Methodology Using TACO 3," SER dated April 3,1995 (DPC Proprietary).

15. BAW-10183P-A, Fuel Rod Gas Pressure Critorion, B&W Fuel Con,pany, July,1995.

16. DPC-NE-2009P-A, " Westinghouse Fuel Transition Report," SER dated (DPC Proprietary).

(continued)

McGuire Units 1 and 2 5.6-4 Amendment Nos.

l l

E _ _

l Fo(X,Y,Z)

B 3.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than the measured factor is of the current limit, additional actions must be

, taken. These actions are to meet the Fo(X,Y,Z) limit with the last l

F"o(X,Y,Z) increased by the appropriate factor specified in the COLR or l to evaluate Fo(X,Y,Z) prior to the projected point in time when the l extrapolated values are expected to exceed the extrapolated limits.

These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its limit for any significant period of time without detection

, using the best available data. F"o(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of F"o(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within i2% of the core height about the demand position of the rod tio.

l Fo(X,Y,Z) is verified at power levels 210% RTP above the THERMAL l DOWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions to ensure that Fo(X,Y,Z) is within its limit at higher power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of Fo(X,Y,Z) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors betwaen 31 day surveillances.

REFERENCES 1. 10 CFR 50.46,1974.

2. UFSAR Section 15.4.8.

3. 10 CFR 50, Appendix A, GDC 26.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE-2011PA " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse l Reactors", March 1990.

McGuire Units 1 and 2 B 3.2.1-11 Revision No.1

.. .. 1 Fm(X,Y)

B 3.2.2 BASES SURVEILLANCE REQUIREMENTS (continued) channel factor to the surveillance limit is likely to decrease below the value of that ratio when the measurement was taken.

Each of these extrapolations is applied separately to the enthalpy rise hot channel factor surveillance limit. If both of the extrapolations are

. unfavorable, i.e., if the extrapolated factor is expected to exceed the i extrapolated limit and the extrapolated factor is expected to become a 1 larger fraction of the extrapolated limit than the measured factor is of the I current limit, additbnal actions must be taken. These actions are to meet !

the F"m(X,Y) limit with the last F"m(X,Y) increased by the appropriate U factor specified in the COLR or to evaluate F"m(X,Y) prior to the point in time when the extrapolated values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent F"m(X,Y) from exceeding its limit for any significant period of time without detection using the best available data. F"m(X,Y) is not required to be ;

extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline n.easurement for future trending.

F"m(X,Y) is verified at power levels 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions to ensure that F"m(X,Y) is within its limit at high power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of F"m(X,Y) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. UFSAR Section 15.4.8

2. 10 CFR 50, Appendix A, GDC 20.

3. 10 CFR 50.46,

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE-2005P, " Duke Power Company Thermal Hydraulic Statistical Core Design Methodology", September 1992.

- McGuire Units 1 and 2 B 3.2.2-9 Revision No.1

s. .

l-l l

1 l

i I

l i

I Attachment 2b Reprinted Improved Technical Specifications for Catawba Units 1 and 2 i

1 1

i i

b i

l i

t

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

SLs 2.0 670 00 NOT OPEftATE N THIS AREA 660 650 -

640 2400 pelo C

t, 630 2280 pelo I

h620 2100 psia 610 -

1945 paio 600 -

590 -

ACCEPTA84.E OPERATION 580 ' ' ' '

O.0 0.2 0.4 0.6 0.8 1.0 t.2 Fraction of Roted Thermal Power Figure 2.1.1-1 (UNIT 1 ONLY)

Reactor Core Safety Limits -

Four Loops in Operation Catawba Units 1 and 2 2.0-2 Amendment Nos.

SLs 2.0 \

6'70 00 NOT OPERATE IN THIS AREA.

660 -

650 -

640 -

2400 psia b630 - 22a0 m I 620 -

2100 psia 610 -

1946 pelo 600 -

590 -

ACCEPTABLE OPERATION 580 O.0 0.2 0.4 0.6 0.8 1.0 1.2 Froction of Roted Thermol Power Figure 2.1.1-1 (UNIT 2 ONLY)

Reactor Core Safety Limits -

Four Loops in Operation Catawba Units 1 and 2 2.0-3 Amendment Nos.

Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 ------------------------------NOTE--------------------------------

1. Extrapolate F"o(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F%(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F%(X,Y,Z)exrupoureo a F'o(X,Y,Z) "EXrMPouTEo, and E"(X,Y.Z)EXTMPOurEo > E (X.Y.Z)

Fb(X,Y,Z) "exrmeourso Fb(X,Y,Z) "

l then:

a. Increase F"o(X,Y,Z) by the appropriate factor specified in the COLR and reverify F"o(X,Y,Z) s Fb(X,Y,Z) "; or

b. Repeat SR 3.2.1.2 prior to the time at l which F"o(X,Y,Z) s Fo(X,Y,Z) "is extrapolated to not be met, i 2. Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F%(X,Y,2) s Fb(X,Y,Z) ". Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"o(X,Y,Z) was i

last verified AND 31 EFPD thereafter l _

(continued) l Catawba Units 1 and 2 3.2.1 -4 Amendment Nos.

l

1 Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.3 --------------------------------NOTES-----------------------------

1. Extrapolate F"o(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"c(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:

F"o(X,Y,Z)sxrnu.oureo F2 b(X,Y,Z)nes, and EWX.Y.Z)sxinu,ourso > F"o(X Y.Z)

Fb(X,Y,Z)RPS ExTRAPOLATEo Fo(X,Y,Z)nes then:

1

! a. Increase F"o(X,Y,Z) by the appropriate i factor specified in the COLR and reverify l F"o(X,Y,Z) s F'o(X,Y,Z)nes or

b. Repeat SR 3.2.1.3 prior to the time at which F"o(X,Y,Z) s Fb(X,Y,Z)nes is extrapolated to not be met.

2. Extrapolation of F"o(X,Y,Z) is not required for the l

initial flux map taken after reaching equilibrium conditions.

I Verify F"(X,Y,Z) s Fb(X,Y,Z)"" . Once within l 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after l exceeding, by 2 l- 10% RTP, the THERMAL i POWER at which l l F*o(X,Y,Z) was j last verified AND 31 EFPD i

thereafter t

Catawba Units 1 and 2 3.2.1 -5 Amendment Nos.

s. .

Fm(X,Y) 3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.2.2 ----------------------------NOTES---------------------------------

1. Extrapolate F"m(X,Y) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"m(X,Y) is within limits and the 31 EFPD extrapolation indicates:

F"m(X,Y)mneouTEo > F'm(X,Y)sunvmnw,u,,D and E" mixm YlEXTRAPOLATED > mM F'm(X,Y)suavEXTRAPOLATED a(X,Y)suav then;

a. Increase F1(X,Y) by the appropriate factor specified in the COLR and rrverify l

F1(X,Y) s Fh(X,Y)sunv; or

b. Repeat SR 3.2.2.2 prior to the time at which F1(X,Y) s Fh(X,Y)sunv is extrapolated to not be met.

2. Extrapolation of F1(X,Y)is not required for the initial flux map taken after reaching equilibrium conditions.

Verify F1(X,Y) s Fh(X,Y)sunv . Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after ;

excoeding, by > l 10% RTP, the THERMAL POWER at which F1(X,Y) was last verified AND 31 EFPD thereafter l

Catawba Units 1 and 2 3.2.2-4 Amendment Nos.

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location Catawba Nuclear Station is located in the north central portion of South Carolina approximately six miles north of Rock Hill and adjacent to Lake Wylie. The station center is located at latitude 35 degrees,3 minutes,5 seconds north and longitude 81 degrees,4 minutes,10 seconds west. The corresponding Universal Transverse Mercator Coordinates are E 493,660 and N 3,878,558, zone 17, 4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of either ZlRLO or Zircalloy fuel rods with an initial composition of l natural or slightly enriched uranium dioxide (UO2 ) as fuel material. Limited substitutions of ZlRLO , zirconium alloy, or stainless steel filler rods for fuel l rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been l analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver indium cadmium and boron carbide as approved by the NRC.

l 4.3 Fuel Storage i 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained l with:

I 1

(continued)

Catawba Units 1 and 2 4.0 1 Amendment Nos.

Reporting Requirements 5.6 1

. 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

15. BAW-10183P-A, Fuel Rod Gas Pressure Criterion, B&W Fuel Company, July,1995.

16. DPC-NE-2009P-A, " Westinghouse Fuel Transition Report," SER dated (DPC Proprietary).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Ventilation Systems Heater Report When a report is required by LCO 3.6.10, " Annulus Ventilation System (AVS),"

LCO 3.7.10,

Control Room Area Ventilation System (CRAVS)," LCO 3.7.12, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," LCO 3.7.13,

" Fuel Handling Ventilation Exhaust System (FHVES)," or LCO 3.9.3,

" Containment Penetrations,* a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.

5.6.7 PAM Report When a report is required by LCO 3.3.3, " Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.8 Steam Generator Tube inspection Report

a. The number of tubes plugged in each steam generator shall be reported to the NRC within 15 days following completion of the program; (continued) l Catawba Units 1 and 2 5.6-5 Amendment Nos.

Fo(X,Y,Z)

B 3.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the Fo(X,Y,Z) limit with the last F"o(X,Y,Z) increased by the appropriate factor specified in the COLR or l to evaluate Fo(X,Y,Z) prior to the projected point in time when the extrapolated values are expected to exceed the extrapolated limits.

These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its limit for any significant period of time without detection using the best available data. F"o(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of F"o(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within 2% of the core height about the demand position of the rod tip.

Fo(X,Y,Z) is verified at power levels 210% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions to ensure that Fo(X,Y,Z) is within its limit at higher power levels.

1 The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of Fo(X,Y,Z) evaluations.

The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. 10 CFR 50.46,1974.

2. UFSAR Section 15.4.8.

3. 10 CFR 50, Appendix A, GDC 26,

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE-2011PA " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors", March 1990.

Catawba Units 1 and 2 B 3.2.1-11 Revision No.1

.. c.

Fm(X,Y)

B 3.2.2 BASES SURVEILLANCE REQUIREMENTS (continued) channel factor to the surveillance limit is likely to decrease below 4

the value of that ratio whea the measurement was taken.

Each of these extrapolations is applied separately to the enthalpy rise hot channel factor surveillance limit. If both of the extrapolations are unfavorable, i.e., if the extrapolated factor is expected to exceed the extrapolated limit and the extrapolated factor is expected to become a larger fraction of the extrapolated limit than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the F"m(X,Y) limit with the last F"m(X,Y) increased by the appropriate factor specified in the COLR or to evaluate F"m(X,Y) prior to the point in time when the extrapolated values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent F"m(X,Y) from exceeding its limit for any significant period of time without detection using the best available data. F"m(X,Y)is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending.

F"m(X,Y) is verified at power levels 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions to ensure that F"m(X,Y) is within its limit at high power levels.

The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of F"m(X,Y) evaluations.

3 The Frequency of 31 EFPD is adequate to monitor the change of power I distribution because such a change is sufficiently slow, when the plant is l operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.

REFERENCES 1. UFSAR Section 15.4.8

2. 10 CFR 50, Appendix A, GDC 26.

I

3. 10 CFR 50.46.

4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

5. DPC-NE 2005P, " Duke Power Company Thermal Hydraulic Statistical Core Design Methodology", September 1992.

Catawba Units 1 and 2 B 3.2.2-9 Revision No.1

_

ML20155B211

Text

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