Text

Cycle 7 Core Operating Limits Rept.
	ML20012E832
Person / Time
Site:	North Anna
Issue date:	03/26/1990
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20012E826	List: ML20012E825; ML20012E828; ML20012E831; ML20012E832;
References
	NUDOCS 9004060388
	Download: ML20012E832 (25)
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l North Anna Unit 2 Cycle 7 Core Operating Limits Report March 26, 1990

/*i 9004060388 9003:29 "

PDR ADOCK 05000338 P ppc

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's i COLR for North Anna Unit 2 Cycle 7

i. .

I 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for North Anna Unit 2 Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7.

The Technical Specifications affected by this report are listed below:

3/4.1.1.4 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axlal Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4.9.1 Boron Concentration f

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i COLR for North Anna Unit 2 Cycle 7 i

I 2.0 OPERATING LIMITS t

The cycle specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.1.7.

2.1 Moderator Temoerature Coefficient (Specification 3/4.1.1.4) 2.1,1 The Moderator Temperature Coefficient (MTC) limits are:

The BOC/ARO MTC shall be less positive than or equal to +0.6E 4 Ak/k/ F below 70 percent of RATED THERMAL POWER.

The BOC/ARO MTC shall be less positive than or equal to 0.0E 4 Ak/k/ F at or above 70 percent of RATED THERMAL POWER.

The EOC/ARO/RTP MTC shall be less negative than -5.0E 4 Ak/k/ F.

2.1.2 The MTC Surveillance limits are:

The 300 ppm /ARO/RTP MTC should be less negative than or equal to

-4.0E 4 Ak/k/ F.

The 60 ppm /ARO/RTP MTC should be less negative than or equal to l

-4.7E-4 Ak/k/ F.

I where: BOC stands for Beginning of Cycle ARO stands for All Rods Out !

EOC stands for End of Cycle f

RTP stands for RATED THERMAL POWER l

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Page 2 of 12 )

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i COLR for North Anna Unit 2 Cycle 7 2.2 Shutdown Rod insertion Limit (Specification 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to at least 228 steps, i

2.3 Control Rod Insertion Limits (Specification 3/4.1.3.6)

I 2.3.1' The control rod banks shall be limited in physical insertion as shown in i Figure 1.

2.4 Axial Flux Difference (Specification 3/4.2.1) 2.4.1 The AXIAL FLUX DIFFERENCE Limits are provided in Figure 2.

Note - These limits may be modified in the Control Room Reactor Data Book in accordante with Specification 4.2.2.2.f.2.a.

t 2.5 Heat Flux Hot Channel Factor- Fo(Z) (Specification 3/4.2.2)

Fo(Z) s p

K(Z) for P > 0.5 Fo(Z) s0.5CFO

K(Z) for P s 0.5 3 l

THERMAL POWER where: P = RATED THERMAL POWER I

2.5.1 CFO = 2.19 2.5.2 K(Z) is provided in Figure 3. l I

2.5.3 N(Z) values are provided in Figures 4 through 7.

Page 3 of 12 ,

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COLR for North Anna Unit 2 Cycle 7 i N ?

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( 2.6 Nuclear Enthalov Rise Hot Channel Factor F3 (Specification 3/4.2.3) l

[

N' l .FAH s CFDH * (1 + PFDH * (1 P)) f i '

t I"> THERMAL POWER !

l. where: P " RATED THERMAL POWER i L ;' 2.6.1 CFDH = 1.49

. i 2.6.2 PFDH = 0.3 n

f 2.7 Boron Concentration (Specification 3/4.9.1)

. t.

The refueling boron concentration shall be 2 2300 ppm. l i

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Page 4 of 12

v COLR for North Anna Unit 2 Cycle 7 3.0 REFEFlEblCES

1. VEP FRD 42, Rev.1 A,

Reload Nuclear Design Methodology, September 1986.

(Methodology for LCO 3.1.1.4 Moderator Temperature Coefficient, LCO 3.1.3.5 Shatdown Bank Insertion Limit, LCO 3.1.3.6 - Control Bank Insertion Limits, LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 - Boron Concentration).

2a. WCAP 9220 P A, Rev.1," WESTINGHOUSE ECCS EVALUATION MODEL -

1981 VERSION", February 1982 (W Proprietary).

(Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor.)

2b. WCAP 9561 P A, ADD. 3, Rev.1 "BART A 1: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS SPECIAL REPORT: THIMBLE MODELING IN W ECCS EVALUATION MODEL", JULY, 1986, (W Proprietary).

(Methodology for LCO 3.2.2 Heat Flux Hot Channel Factor.)

3. VEP NE 2 A, " Statistical DNBR Evaluation Methodology", June 1987.

(Methodology for LCO 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor.)

4. K. L. Basehore et al., "Vepco Relaxed Power Distribution Control Methodology and Associated FO Surveillance Technical Specifications,"

g VEP NE 1 A, March 1986.

(Methodology for LCO 3.2.2 - Heat Flux Hot Channel Factor and LCO 3.2.1 Axial Flux Difference.)

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l COLR for 16erth Anna UNIT 2 CYCLE 7 L t 228 l

l l , (54, tit) !

V 200 '

)

t (100. 194) .

a 150 / /

i SAIK C I

(0,118) 1100 ,

.E, -

8 w i 50 f ;

l (4.8 ,0) j 0 to 40 to to 100 Percent of RATED THElBEL POWER 1

Figure 1 Control Rod Bank Insertion Limits vs Percent RATED THERMAL POWER Pace 6 of 12

, . =

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l COLR for North Anna UNIT 2 CYCLE 7 120 i l

l(+4100) i

( 12 100) 100 l

UECLEPTAtl.E :

OPERAT10N .UECCEP"ABLE OPEMT' ON '

s !'

( l* ( .

(

L ls !

Eu E >

ACCEP"ASLE !

) OPERA"10N

'3w (27,00)

(+20 50) 40

)

i f

to .

0 .

50 30 10 10 30 50 40 -20 0 20 40 AXIAL FLUX O!FFERENCE (5 AI)

Figure 2 Axial Flux Difference Lietts as a Function of RATED THERMAL POWER from 150 MWO/NTU Burnup to E0C l' age 7 of 12

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COLR for North Anna UNIT 2 CYCLE 7 1

- 1.2 ;

I I J j 00 NOT.0PERATE IN THIS AREA !

1

,(4.0,1.0) ;

1.0 N I

-(10.93,0.9373) l

, 1 t

0.4 ;

C )

} l 1 l

" 0.6 ;

l- .

=

y (12.0,0.4564) :

0.4 y

t l 0.2 N l

i O

ft 0 2 4 4 8 10 12

(*) 5 14.6 33.3 50.0 64.7 83.3 100 Core Height For core height of 12 feet FIGURE 3 ,

K(Z) Normalized Fg as a function of Core Height Page 8 of 12

o.

, f COLR FOR NORTH ANNA UNIT 2 CYCLE 7gggggy ggg l 10.20 1.191 10.00 1.184 )

9.40 1.180 1 9.60 1.175 l 9.40 1.173 J 9.20 1.179 l 9.00 1.188 i l.22+88 4.80 1.199 8.60 1.207 ,

7N

4.40.

8.20 1.213 1.217

)

1.20+44 / \

\

8.00 7.80 1.219 1.219 :

l- / \ 7.60 1.217 !

l .:

/ \ 7.40 1.214 !

i 2 1.1g+ts f r 7.20 1.204 I E / \/ 7.00 6.80 1.202 I i

if 1.196 :

/. V 6.60 1.187 g 6.40 1.177 E.'+"

f 6.20 6.00 1.164 1.155

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i

.!2 ; I 5.80 l.60 1.145 1.139 t

3 1.14+H \ / 5.40 1.132 3

E ( S /

5.20

~5.00 4.80 1.120 1.110 1.106 S

/ 4.60 1.109 l 1.12+n \ / !

4.40 1.115 f

/

~

\v f 4.20 4.00 1.122 1.126 i L 3.80 1.130 ;

1.10Hs 3.60 1.132 L s.n+n 3.40 1.133

.une e.n+n s.um s.n+n i. uni 3.20 1.133 i

CettN[18NT(ft[T) 3.00 1.133 '

2.80 1.132 2.60 1.132 2.40 1.135 .

N2C7/JU N(Z) TUICil08 AT 5000-7000 ut0/Wiu IUtuYP 2.20 1.140 .

2.00 1.147 1.80 1.152 i FIGURE 4 N(Z) FUNCTION F(R N2C7 AT 2893 MW REDUCED TEMPGATlRE OPRATION FROM 5000 to 7000 MWO/MTU BlRWP TOP AW BOTTOM 15 P9 CENT EXC1.tCED AS PR TECH SPEC 4.2.2.2.G Page 9 of 12

4 i-l 1

COLR FOR NORTH ANNA l. NIT 2 CYCLE 7 HEIGHT {

NZ6 i i

10.20 1.131 I 10.00 L'

9.80 1.184 1.180 I

9.60 1.175 9.40 1.173 l 9.20 1.179 (

9.00 1.184 L 1.!!+08 8.40 1.199 I l

8.60 1.207 !

8.40 1.213 !

4.20

(

l 1.2O+0e / \

\

s 00 7.80 1.21,7 1.21 1.219 I / \ 7.60 1.217

=

/ ) 7.40 1.214 :

/ r 7.20 1.208 i 3 1.18+es . / ( ) 7.00 1.202 J t ) / \f 6.80 1.196

( / v 6.60

)

1.147 g g j 6.40 '1.177 B

i,te,se \ f 6.20 1.166

\ r 8.00 1.155 t 3

- \ j l.80 1.145 5.60 2

/ 1.239 :

3 l 5 1.14+se ( 5.40 1.132 W l.20 1.120 i i 3 ( [ 5.00 4.80 1.110 1.106 I

1. title T

/ 4.60 1.109

\ I 4.40 1.115 i

\[

V 4.20 4.00 1.122 1.126 -

1 3.00 1.130 .

1.10+0e 3.60 1.132 8.80608 I.00+49 3.40 1.134 4.00+44 0.00+00 1.00600 1.00+01 3.20 -1.139 CORENElCNT(FEET) 3.00 1.146 2.80 1.112 2.60 1.114 2.40 1.164 N2C7/JUN(Z)FUICil0EAi7000-9000N00/NTUIURNUP 2.20 1.164 2.00 1.174 -

~

1.80 1.142 FIGURE 5 ~

N(Z) FUNCTION FOR N2C7 AT 2893 MW REDUCE 0 TEMPERATtRE OPERATION FROM 7000 to 9000 MWD /MTU BtRNUP TOP AW BOTTOM 15 PERCENT EXCLLDED AS PER TECH SPEC 4.2.2.2.G Page 10 of 12

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e COUt POR NORTH ANNA lMT 2 CYCLE 7 Nf!GHT N27 i 10.20 1.191 i 10.00 1.186 !

9.40 1.100 (

9.60 1.175 +

9.40 1.173 i 9.20 1.179 i 9.00 1.148 1.34+08 8.80 1.199 !

4.60

~

1.207 8.40 1.213 8.20 1.217 :

1.II+0e / \T 4.00 7.40 1.219 1.221 as '

/ T 7.60 7.40 7.20 1.224 1.227 .

1.230

~

2 \

E' 1.20+09 ) \ 7.00 1.230 t

= f g 6.40 1.230 ;

p g / ) 6.60 1.226 ;

, , 6.a 1.u2 L t,ig,se / 6.20 E '

( ) 1.214 !

6.00 1.207 V

g- I

' 5.80 1.1M ,

2 l.60 1.185 5 1 18+ \ 5.40 1.169 l.20 1 \ ) j 5.00 4.80 1.147 1.133 1.130 1.14+49 (

4.60 1.129 l '

i 4.40 1.125

\ 4.20 1.125

\ ;

4.00 1.126 !

1.11,30 T f 3.80 1.129 3.60 1.131 !

0.00+49 3.40 1.133 i 1.00+00 4.00+44 0.00+00 8.00+00 1.00+01 3.20

1.139 CettNtitNT(Fl[T) 3.00 1.145 2.s0 1.ist '

2.60 1.158 2.40 1.164 N2C7/JUN(2)FUNCil05Af9000-15600W50/51UIUINUP 2.20 1.164 2.00 1.174 FIGURE 6 1.40 1.182 N(2) FUNCTION FOR N2C7 AT 2893 MW ,

REDUCED TEMPERATLRE OPERATION FRCM 9000 to 15600 MWD /MTU BtRNUP TOP AE 80TTOM 15 PERCENT EXCL M AS PER TECH SPEC 4.2.2.2.G Page !I of 12

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. i CCUt FOR NORTH ANNA UNIT 2 CYCLE 7 HEIGHT NZ8 10.20 1.150 l 10.00 1.147 9.80 1.142 9.60 1.140 9.40 1.147.

9.20 1.162~ ;

9.00 1.175 8.80 1.188 4.60 1.199 8.40 1.207 8.20 1.214 1.22+08 [ \ ,

8.00 7,30 1.218 1.221 i

j 7.60 1.224 :

. 7.40 1.228

= J 7.20 1.230 i g 7.00 1.230 ;

- 6.80 1.230 a

-- 1.11+00 6.50 1.226 t 3

4.40 1.222 :

g. 6.20 1.214

- 6.00 1.207 i E 5.80 1.196 t O' 5.60 1.145 I

j- g .

/

5.40 5.20 1.169 t'

1 - 1.144 I1.14+gt r 5.00 1.134 :

4.80 1.131

)

/ 4.60 4.40 4.20 1.130 1.127 1.123 3

t

4'.00 1.118 .

3.80 1.112 1.1960s 3.60 1.107 0.00+64 1.46669 3.40 1.105 i 4.99600 8.00+00 8.00+44

' 1.99+41 3.20 1.109 ,

CONENElCNT(ftET) 3.00 1.113 2.00 1.120 '

2.60 1.125 2.40 1.130 N2c7/JUN(Z)FUNCilesAt 15600-17700NT8/NTUBURNUP j.2 g.]

1.30 1.149 N(!) FUNCTION Ff1R N2C7 AT 2893 lef REDUCED TEMPBATLRE OPRATION FROM 15600 MWD /NTU 8tRNUP TO EOL -

TOP A W BOTTOM 15 PGCENT EXCL WED AS PB TECH SPEC 4.2.2.2.G ,

Page 12 of 12 .

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Attachment 7 i I

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Markup of the North Anna MERITS Technical Specifications >

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Virginia Electric and Power Company i l

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o F MTC t 3.1.3 L

3.1 REACTOR ,

3.1.3 Moderator Temnerature Coefficient (MTC) , ,

^

i LCO 3.1.3 The MTC shall be within the limits (: ".d:d in the COR I

OPERATING.LIMITSREPORT(COLR).

.............................. NOTE ------- - - --- ------ --

The maximum upper limit shall be s 0.6E-4 Ak/k/'F' for THERMAL POWER 70%

g

[ 5;bii5 W Es h ?*f'd6Nhii ~ lff [RTP Q&

N &Idi'$i'i 9]d' APPLICABILITY MODE 1, MODE 2 with k,ff h 1.0 for Beginning of Cycle (BOC) limit, MODES 1, 2, and 3 for End of Cycle (EOC) limit.

..........................--N0TE--------- -- ---------------

LCO 3.0.4 is not applicable. l ACTIONS 1

L CONDITION REQUIRED ACTION COMPLETION TIME A. MTC outside BOC limit. --------- NOTE----------

Subsequent operation is permitted. The requirements of LCO i

' 3.1.6, Control Bank Insertion Limits, remain

j. applicable, i A.1 Establish administrative 24. hours L

withdrawal limits for l control banks to maintain MTC within limit.

9.8 A.2 Be in MODE 2 with 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months !

Kerr < l.0.

B. MTC outside E0C limit. B.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months North Anna Units 1 & 2 3.1-6 Amendment Nos. xxx & yyy ;

I MTC o

3.1.3 SURVE!LLANCE REQUIREMENTS SURVEILLANCE FREQUENCY'

-.................N0TE--- -----------...--

SR 3.0.4 is not applicable for SR 3.1.3.1, SR 3.3.3.2 and SR 3.3.3.3.

SR' 3.3.3.1 -

Verify BOC MTC within limit. After each refueling prior to entering MODE 1 SR 3.1.3.2 -----

NOTES-- ----- ----- ---- ----NOTE-- --

1. If the MTC is more ne ativeythanthe Required once 300 ppm surveillance imit rr;id:d in within 7 EFPD the COLR, SR 3.1.3.2 shall be repeated after reaching once per 14 Effective Full Power Days the equivalent (EFPD) during the remainder of the fuel of an cycle, equilibrium RTP ARO

2. SR 3.3.3.2 need not be repeated if the. boron MTC measured at the equivalent of concentration equilibrium RATED THERMAL POWER - All of 300 ppm Rods Out (RTP-ARO) boron concentration ------ -------

of 5 60 ppm is more positive than the 60 ppm surveillance limit err;id:d i the COLR. f. '

Verify EOC MTC within limit. Each cycle (continued)

North Anna Units 1 & 2 3.1-7 Amendment Nos. xxx & yyy

L l

[_ *'

MTC 3~1.3 1

i SURVEILLANCE REQUIREMENTS- (continued) i SURVEILLANCE FREQUENCY l SR 3.1.3.3 Verify MTC within 300 ppm surveillance ---- NOTE--- - i limit,;. .. : f:f ' .^t: ^^1" Required once ;

within 7 EFPD ,

after reaching j the equivalent :

of an :

equilibrium RTP-ARO l boron concentration -

of 300 ppm. 4 Each cycle 4

i CROSS-REFERENCES '

TITLE NUMBER MODE 2 Physics Tests Exceptions 3.1.13 Startup Reports 5.10 r

s s

i North Anna Units 1 & 2 3.1-8 Amendment Nos. xxx & yyy i

y g

Shutdown Bank Insertion Limit 3.1.5

,, 3.1 REACTOR 3.1.5 Shutdown Bank Insertion Limit LCO 3.1.5 Shutdown banks shall be within the physical insertion limit peev4ded in the CORE OPERATING LIMITS REPORT.

(

APPLICABILITY: MODE 1, MODE 2 with keff 1 1.0, Within 15 minutes prior to initial control bank withdrawal during an approach to criticality.

............................ NOTE------..---.-------.---.---.

This LCO is not applicable while performing SR 3.1.4.2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1 Restore shutdown banks 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months banks outside limit, to within limit.

0.B B. Required Action not met B.1 Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within required keff s 1.0.

Completion Time.

i

, North Anna Units 1 & 2 3.1-15 Amendment Nos. xxx & yyy i

y _ _ _ .__ . __ _

g ,

Control' Bank Insertion Liaits f 3.1.6 j i

l 3.1 REACTOR 3.1.6 Control Bank Insertien Limits :

asllaY -- l LCO 3.1.6 Control banks shall be within the limits (puow4dee 73 in the !

CORE OPERATING LIMITS REPORT.for: i

a. Physical insertion limits, and '

b. Sequence and overlap requirements.

APPLICABILITY: MODE 1.

MODE 2 with korf 1 1.0.

............................N0TE--- --------~~-------------~~

This LCO is not applicable while performing SR 3.1.4.2.

]

-i ACTIONS -

l' CONDITION REQUIRED ACTION COMPLETION TIME A. Control banks below A.1 Restore control banks 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months !

insertion limits.

i above insertion limits. i 1

i B. Control banks sequence B.1 Restore control banks 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or overlap requirements sooy;. ice or overlap to j not met. :ovet requirements. -

1 L l C. Required Actions not C.1 Be in MODE 2 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months met within required keff < 1.0.

Completion Times.

1 t

--w I

North Anna Units 1 & 2 3.1-17 Amendment Nos. xxx & yyy .

9

y 1

t

. Heat Flux Hot Channel Facter . Fg(Z) , ,I-3.1.7- -l 3.1 REACTOR 3,1.7 Heat Flur Hot Channel Factor - Fnf2) i LCO 3.1.7 The Heat Flux Hot Channel Factor,QF (Z), shall be limited {

by the following relationships

i

. i Fg (Z) s (f.Q

K(2) for P_ > 0.5 l P

i F(Z) g s CfD

K(Z) for -P s 0.5 l' 0.5 where: CFQ is the F g limit at RATED TilERMAL POWER (RTP) j

->provWed in the CORE OPERATING LIMITS REPORT l (COLR),

l I

K(Z) '

is the normalized Fq as a function of core ;

height peev4ed n the COLR, and !

THERMAL POWER Y

P= i RATED THERMAL POWER -)

APPLICABILITY: MODE 1.

ACTIONS

~ CONDITION REQUIRED ACTION ~ COMPLETION TIME A. FgC (Z) exceeds limit. A.1 Reduce THERMAL POWER at 15 minutes least.1% of RATED THERMAL. POWER (RTP) for 4 each 1% FQ C(Z) exceeds limit.

AtiQ (continued)

North Anna Units 1 & 2 3.1-19 Amendment Nos. xxx & yyy '

n

-c Heat Flux Hot Channel Factor Fg (Z)

, 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY' SR 3.1.7.2 - ~~----- ------ NOTES--- ----- ---------

N

1. Fg (Z) evaluations are not 6 applicable for the following axial core regions, measured in percent of core height:

a. Lower core region, from 0 to 15%

inclusive, and

b. Upper core region, from 85 to 100%

inclusive.

2. N If Fg (2) is within limits and measurements indicate maximum over Z

, K(Z) .

has increased since~the previous evaluation of FQ (Z):

a. N Increase Fg (Z) by 2% and N

reverify that Fg (Z) is within limits.

QB

b. SR 3.1.7.2 shall be repeated once per 7 EFPD until 2 successive flux maps indicate maximum over Z has not increased. ,

t N C '

3. Fg (7) , pq (Z) x N(Z

4. N(Z)andK(Z)are;--[)tdintheCOLR.

.......................................... l (continued) .

I i

North Anna Units 1 & 2 3.1-22 Amendment Nos. xxx & yyy l

)

Nuclear Enthalpy Rise Hot Channel FactoroFagN j

' 3.1.8 l

, .j 3.1 REACTOR 3.1.8 Nuclear Enthalov Rise Hot Channel Factor FAHN j l

E LCO 3.1.8 The Nuclear Enthalpy Rise Hot Channel Factor, F N j shall be limited by the following relationship.AH ,

1 FAHN s CFDH * (1 + PFDH * (1 P)) {

F ;

where CFDH (RT =%senddedi The_P)AuN limit at RATED THERMA W

REPORT (COLR),t.n the CORE OPERATING LIMITS N

[

!: !5! in*k k Cg g AH j THERMAL POWER 4

p. -

RATED THERMAL POWER-APPLICABILITY: MODE 1.

i

. ACTIONS ,

CONDITION REQUIRED' ACTION- COMPLETION TIME-A. --

NOTE--------- 'I Required Actions A.2 .

and A 3 must be '

completed whenever Condition A is entered. '

FAHN outside limit. A.I.1 Restore FAH N to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i limit.

QB 4 A.1.2.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 50% of RATED THERMAL POWER (RTP). ;.

MD i (continued)

North Anna Units 1 & 2 3.1-24 Amendment Nos. xxx & yyy

c_

y .,F g

l, o, AFD l L

3.1.9 l i s L1;

[

/ , 3.1 REACTOR ,

3.1.9 Axial Flux Difference i.

L LCO 3.1.9 The AXIAL FLUX DIFFERENCE (AFD) shall be maintained within o the limits ; m if,:f-i,n he CORE OPERATING LIMITS REPORT.

g .

t P .........N0TE---------------------- -----

.The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits. i r APPLICABILITY: MODE 1 with THERMAL POWER 2 50% of RATED THERMAL POWER (RTP).

ACTIONS '

CONDITION '

REQUIRED ACTION COMPLETION TIME A. AFD outside limits. A.1 Restore AFD to within 15 minutes limits.

DB

..........N0TE--------- !

Required Action A.2.2

must be completed if ,

Required Action A.F.1 is completed.

A.2.1 Reduce THERMAL POWER to 30 minutes i

< 50% of RTP.

AtiD A.2.2 Reduce Power Range 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and Neutron Flux-.High trip 30 minutes setpoints to 1 55% of i RTP.

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V North Anna Units 1 & 2 3.1-27 Amendment Nos. xxx & yyy

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o. Boron Concentration 3.8.1 3.8 ' REFUELING OPERATIONS .

'3.8.1 Boron Concentration LC0 .3.8.1 The boron concentration of all filled portions of the Reactor Coolant System (RCS), the refueling canal, and the refueling-cavity shall be maintained within the Itmit ; = 'd d in the CORE OPERATING LIMITS REPORT.

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APPLICABILITY: RCS - MODE 6.

Refueling Canal - MODE 6 with reactor head removed.

Refueling Cavity - MODE 6 with reactor head removed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE 15 minutes outside limit. ALTERATIONS and positive reactivity additions. i 8HQ A.2.1 Initiate boration to 15 minutes i restore concentration, b8R A.2.2 Continue action as Until boron required in A.2.1. concentration is restored 4

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify Loron concentration within limit. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CROSS-REFERENCES - None.-

North Anna - Units 1 & 2 3.8-1 Amendment Nos. xxx & yyy

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o Ad31nistrative Contr61s !

5.0 !

5.0 ADMINISTRATIVE CONTROLS f 5.10 REPORTING REQUIREMENTS 5.10.7 Soecial Recorts (continued) -

e. Emergency Core Cooling Systems (ECCS). LCOs 3.4.2 and 3.4.3. :

In the event the ECCS is actuated and injects water into the Reactor Coolant System prepare and submit a Special Report to the Commission within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to >

date. The current value of the usage factor for each affected !

safety injection nozzle shall be provided in this Special Report ,

whenever its'value exceeds 0.70.

5.10.8 CORE OPERATING LIMITS REPORT '

5.10.8.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any :

remaining part of a reload cycle for the following:

1. Moderator ' Tom erature Coefficient B and E (dMd66M MO surveillance imitsfor Specification 3.1.3 limit:3 and 300 ppm '

2. Shutdown Bank Insertion Limit for Specification 3.1.5,

3. Control Bank Insertion Limits for Specification 3.1.6, j

-4. Axial Flux Difference limits for Specification 3.1.9,

5. Heat Flux Hot Channel Factor, K(Z) and N(Z) for Specification 3.1.7

6. Nuclear Enthalpy Rise Hot Channel Factor and Power Factor Multiplter for Specification 3.8.1, and

7. Boron Concentration for Specification 3.8.1. o 5.10.8.b The analytical methods used to determine the core operating limits i 5.10.8.c

$1 Y $ $ Y LI hYY The core operating limits shall be determined so that all applicable Yl'5# -

i limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

(continued) ,

North Anna Units 1 & 2 5-35 Amendment Nos. xxx & yyy ;

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ML20012E832

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