ML20012E831

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Cycle 8 Core Operating Limits Rept.
ML20012E831
Person / Time
Site: North Anna Dominion icon.png
Issue date: 03/26/1990
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20012E826 List:
References
NUDOCS 9004060387
Download: ML20012E831 (13)
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North Anna Unit 1 Cycle 8 i Core Operating Limits Report -

i March 26 1990  !

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i 9004060387 900329 PDR s P ADOCK 05000338 t FDC i i

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t l COLR for North Anna Unit 1 Cycle 6 l

1.0 CORE OPERATING LIMITS REPORT This Core Operating L1rnits Report (COLR) for North Anna Unit 1 Cycle 8 has been prepared in accordance with the requirements of Technical Specification l 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 Axial 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 Page 1 of 11

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l COLR for North Anna Unit 1 Cycle 8 l 2.0 OPERATING IJMITS The cycle specific parameter limits for the speelfications 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/kFF below 70 percent of RATED THERMAL POWER.

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

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

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/kFF.

The 60 ppm /ARO/RTP MTC should be less negative than or equal to 4.7E 4 Ak/kFF.

where: BOC stands for Beginning of Cycle ARO stands for All Rods Out EOC stands for End of Cycle RTP stands for RATED THERMAL POWER Page 2 of 11

m COLR for North Anna Unit 1 Cycle 8 2.2 Shutdown Rod Intertion Limit (Specification 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to at least 228 steps, i

t 2.3 Control Rod insertion Limits (Specification 3/4.1.3.6)

! 2.3.1 The control rod banks shall be limited in physical insertion as shown in Figure 1, 2.4 Avial 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 accordance with Specification 4.2.2.2.f.2.a.

2.5 Heat Flux Hot Channel Factor FO(Z) (Specification 3/4.2.2)

Fo(Z) s p O,K(Z) for P > 0.5 for P s 0.5 Fo(Z) s 05

  • K(Z)

THERMAL POWER where: P = RATED THERMAL POWER 2.5.1 CFO = 2.19 2.5.2 K(Z) is provided in Figure 3.

2.5.3 N(2) values are provided in Figures 4 through 6.

Page 3 of 11

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l l COLR for North Anna Unit 1 Cyclo 8 i 1

l l 2.6 Nortear Enthainv Rise Hot Channel Factor F3 (Specification 3/4.2.3)

N l FAH s CFDH ' (1 + PFDH ' (1 P))  :

l' i THERMAL POWER .

where: P = RATED THERMAL POWER  !

l 2.6.1 CFDH = 1.49 2.6.2 PFDH = 0.3 2.7 Boron Concentration (Specification 3/4.9.1)

The refueling boron concentration shall be 2 2300 ppm.

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COLR for North Anna Unit 1 Cycle 8

3.0 REFERENCES

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1. VEP FRD 42, Rev.1 A,
  • Reload Nuclear Design Methodology, September i 1986.

i (Methodology for LCO 3.1.1.4 Moderator Temperature Coefficient, LCO 3.1.3.5 Shutdown 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 - l Nuclear Enthalpy Rise Hot Channel Factor, and LCO 3.9.1 Boron i 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 i 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," l 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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Page 5 of 11 i

I COLA for NoMh Anne WN!T 1 CYCLE 4

  1. 88 (54. ISS) 200

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(100. IM) j E '

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8 (0, lit) i 100 0 I

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0 (4.4.,0) e 0 N 40 N 80 100 i

PeMont of MTG THEWIRL PWtt  !

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Figure 1 Cutrel Red Sank Insertion Limits vs Penent uitD TH(lWEL POWER  :

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COLA for herth Anne Wulf 1 CYCLt t

> lit IM UMCLIPTABLE

( 18 IM) l (+4100) USCttp"ASLt I

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i OPtMT10N t SPtMT. ON '

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/ mt,.

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( .27,14)  !

i 40 (+tt W) '

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0 30  !

30 10 le 30 50 40 30 0 20 40 t M!AL FLUI OlFFERDEt (5 41) i i

Figure t Asial Flum Otfference Lietts as a Function of MitO I

' THtlWEL POWtt free 0 MS/NTU Surnup to E0C r

..__ ,__.-. _-. ._...__-- -- _____-----__--_.--.4.---..-,,_.-.-,_m,-y - . - - - - - , -

u ,;y cola tw nonn aa** Wif i GYCLE a I'I I i i

80 NDT Opt 44TE IN TNIS AREA

' (. 0. 1.0) i.e (10.93,0.9873) 0.8 C

2 .

1 0..

C E (18.0,0.4564) 0.4 0.t O

ft 0 8 4 6 8 10

(*) 5 16.6 33.8 80.0 06.7 88.3 It 100 Core Neight o

For core height of la feet FIGURE 3 K(!) Nonnallaed Fg as a Funettom of Core Height Page 8 of 11 i

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.g W M MTH ANNA UNIT 1 CYC1.E e p ,y HEIGHT N(2)

(FEET) 10.20 1.198 10.00 1.193 9.80 1.186 1.2.+ . 9.60 1.180 i 9.40 1.177 l h 9.20 ,1.181 l

q 9.00 1.188 j 8.80 1.198 i 8.60 1.204  !

1*!!. 9 8.40 1.208  !

. 8.20 1.210 l g 8.00 1.210 l g

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[] 7.60 7.60 1.208 1.205 I

E } / 7.40 1.200 l E'+"

( \/

V 7.20 7 00 1.199 1 194 I

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/ 6.60 1.188 -

E / 6.60 1.184 3  ;

6.40 1.179 is 6.20 1.172 r S k 6.00 1.164  !

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  • 1.14... \ 5.80 1.154  ;

5.60 1.142  ;

5.40 1.130  !

5.20 1.119 5 5.00 1.120  !

4.80 1.126 i

  • jg,,, 4.60 1.134 4.40 1.142 i

....... i...... ....... ....... ....... 1.....i 4.20 1.150 COREH[lCHT(f((T) 'j f;{y ,

3.60 1.171  !

PnURE 4  !$

3.00 l'!$

1.194 i

l 16(!) MSCT!W PR NICS AT 2H3 41 2.80 1.206 i RERE E TB D RAf1RE OPRAT! M 2.60 1.218 i PRtBI SOM to FDM ftEVIffU OLAltaP 2.40 1.228 i TOP AIO 30f7(3415 PRCOff EXCt.WE 2.20 1.238 i AS PB TECM $PEC 4.2.2.2.G 2.00 1.246  ;

1.80 1.254  :

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

1 W FOR NORTH ANNA UNIT 1 CYCLE 4 t

j HEIGHT N(2)  !

r (FEET)  ;

i 10.20 1.200  ;

10.00 1.196  ;

9.80 1.100 l l'H+" 9.60 1.184 s

9.40 1.178 9.20 1.185 9.00 1.198 i

^ 8.80 1.213  !

\ 8.60 1.225  !

8.40 1.234 1.24 00 \- 8.20 1.242 5 / 8.00 1.249 l

-,  ; 7.80 1.255  !

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7.60 1,250 5 7.40 1.263

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i 3 7.20 1.265 i 1 .2...e 7,00 ~ 1.264 l

! r 6.40 1.262  !

= h / 6.60 1.256  !

\ / 6.40 1.250 l

v 6.20 1.240 .

=

W 6.00 1.231  !

E l'N'N 5.80 5.60 1.216 1.202

\ .' 20 .1 8 i V 5.00 1.141 1 4.80 1.135 l 4.60 1.136 5 1.12 00

' 4.40 1.139  !

....... 2...... ....... ....... ....... i.....i

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COREH[lCHT(T((i) 3.80 1.150  !

3.60 1.151 l MGURE5 ljg };}!! [

N(Z) FUNCT!W FM NICS AT 2 93 Mg 3.00 1.154  !

R TEMPe 2.80 1.161 40,euc.e 2 . 1 tA.nas. - OPRAT!0.N, 0. . 2.60 1.168 l i

TOP A4 00TTM il PRCENT EXCLISED 2.40 1.175 -

A5 PM TECH $PEC 4.2.2.2.G 2,;l ;jg2 (

1.80 1.193 i Page 10 of 11 i

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COLR FOR NORTH ANNA UNIT 1 CYCLE 8 L t I

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' HEIGHT N(Z)

(FEET)  ;

10.20 1.200 10.00 1,196 i 9.80 1.190 l 1.20+00 9.60 1.184 7 9.40 1.175  !

9.20 1.185 '

A 9.00 1.198

\ 8.80 1.21? i

T 8.60 1.225 I O 1.24+00

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( 8.40 1.234 *

. g 8.20 l'.242  ;

$  ! 8.00 1.249  ;

g 7.80

) 7.60 1.255  ;

'1.260.  ;

g 7.40 1.263 i

=

7.20 1.265' g 1.20+00 7 7.00- 1.264

. 6.80 ,1.262 5 6.60 1.256' e 6.40 l'250 i

g V 6.20 1.240' *

g. 6.00 1.231 i g 1.?I+00 \' 5.80 1.-216 5.60 1.202 '

k 5.40 1.183 '

\ m 5.20 1.158

l. \ / N/ 5.00 1.141 i

1.12+00

(/ 4.80 4.60 1.135 1.136 4.40 1.139 O.0G+00 2.00+00 4.00+00 6.00+00 B.00+00 1.00+01 4.20 1.142 L 4.00 1.142 1 COREHEICHi'(FEET) 3.80 1.140 3.60 1.138 .,

FIGURE 6 3.40 1.133 1 3.20 1.129 N(Z) RadCTION FGt N1C8 AT 2393 MW 3.00 1.126 REDUCE TD99tATLftE OPGLATION 2.80 1.128 1 F1tm 16000 MWD /MTU BLftMJP TO E0L 2.60 1.132 l l' TOP A2 00TTOM 15 PGtCENT EXCLLDED 2.40 1.141 AS PDt TECH SPEC 4.2.2.2.G 2.20 1.148

( 2.00 1.157 1.80 1.166 )

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' l Attachment 6  !

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North Anna Unit 2, Cycle 7  !

Core Operating Limits Report .l i

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Virginia Electric and Power Company '

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