ML19324B013

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Forwards Core Surveillance Rept Containing Specific Power Distribution Limits Applicable for Cycle 7 Operation W/Temp Reduction
ML19324B013
Person / Time
Site: North Anna Dominion icon.png
Issue date: 10/20/1989
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-001A, 89-1A, NUDOCS 8910300175
Download: ML19324B013 (9)
v • d • e


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r VIRGINIA ELECTRIC AMD POWER COMPANY RICHMONU, VIRGINIA 23261 s

Q6 y-October 20, 1989 U.S. Nuclear Regulatory Commission Serial No. 89-001A-Attn: Document Control Desk PES /JYR:cdk 4

Washington, D.C. E0555 Docket No. 50-339-License No. NPF-7 E . Gent 1einen:

VIRGINIA ELECTRIC AND POWER COMPANY M TEMPERATURE REDUCTION

-North Anna Unit 2 is currently scheduled to implement a 6*F RCS average temperature reduction between 5000 MWD /MTU and 7000 MWD /MTU of burnup. The.

purpose of this letter is to transmit to you the Core Surveillance Report I containing- specific power distribution limits applicable for Cycle 7 operation '

with this temperature reduction.

The'. Cycle 7 core with the temperature reduction was analyzed in accordance with the methodology documented in the ap3 roved topical report VEP-FRD-42, Revision 1-A, " Reload Nuclear Design Met hodology," using NRC approved codes as referenced in the topical. The information in the report was developed in accordance with our topical report VEP-NE-1-A, " Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications. " ~

These analyses were performed and reviewed by our technical staff. The results of these analyses indicated that no key analysis parameters would become more limiting during Cycle 7 operation with the reduced temperature conditions than i the values assumed in the applicable safety analyses.

A review has been performed by both the Station Nuclear Safety and Operating Consnittee and the Safety Evaluation and Control Staff. It has been determined that no unreviewed safety question as defined in 10 CFR 50.59 will exist as a result of the 6 F RCS average temperature reduction implementation.

The Core Surveillance Report, which consists of the Cycle 7 N(z) function and the Axial Flux Difference Limits for operation past 5000 MWD /MTV, is included as Attachment 1. These limits are based upon the current total peaking factor (F)limitof2.19. Technical Specification 6.9.1.7 requires that the Report be 0 provided to the NRC 60 days prior to cycle criticality unless a written waiver has been granted by the Staff. For reasons noted in our letter Serial No.89-646, dated September 14, 1989, we were unable to meet the 60 day requirement. A written waiver was requested at that time, and this letter transmits the Core Surveillance Report for the temperature reduction as promised.

8910300170 891020

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[ . This letter is provided for your information and planning. However, should you have questions, pleasef contact us at your earliest convenience.

L f'- 1 Very truly yours.

E h (_ \[' s s t W. . Stewart P Senior Vice President - Power

' Attachment

1. Core Surveillance-Report For North Anna 2, Cycle 7 cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street.~ N. W.

Suite 2900' Atlanta, Georgia' 30323

'Mr. J.-L. Caldwell NRC Senior Resident Inspector North Anna Power Station I

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Core Surveillance Report for North Anna 2 Cycle 7-With 6*F RCS Average Temperature Reduction ,

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{ NORTH ANNA UNIT 2 CYCLE 7 CORE SURVEILLANCE REPORT FOR REDUCE 0 TEMPERATURE OPERATION I This Core Surveillance Report is provided in accordance with Section 6.9.1.7 of the North Anna Unit 2 Technical Specifications.

The burnup-dependent Cycle 7 N(z) function for Technical Specification 4.2.2.2.C is shown in Figures 1-4. N(z) was calculated according to the procedure of VEP-NE-1-A.

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The N(z) function

  • will'be used to confirm that the heat flux hot channel factor, FQ(z), will be limited to the Technical Specifications values of f

2.19 K(z)

FQ(z) s ---------- , P > 0.5 and P

FQ(z) s 4.38 K(Z), P 5 0.5.

The Cycle 7 Axial Flux Differcnce (AFD) limits for Technical Specification 3.2.1 are shown in Figure 5. These limits were calculated according to the methods of VEP-NE-1-A and are comparable to the previous Cycle 7 limits. r The limits on Axial Flux Difference assure that the FQ(g) upper bound envelope is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

  • The N(z) function, when applied to a power distribution measured under equilibrium conditions, demonstrates that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10CFR50.46.

FIGURE 1 - N(Z) FUNCTION FOR N2C7 AT 2893 MW HEIGHT NZ5 REDUCED TEMPERATURE OPERATION FROM 5000 to 7000 MWD /MTU BURNUP TOP AND BOTTOM 15 PERCENT EXCLUDED 10.20 1.191 -

AS PER TECH SPEC 4.2.2.2.G 10.00 1.186 9.80 1.180 9.60 1.175 '

9.40 1.173 9.20 1.179 9.00 1.188 8.80 1.199 1.22+00 8.60 1.207 f\ 8.40 1.213

/ \ 8.20 1.217 1.20+00 / \

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8.00 7.80 1.219 1.219 7.60 1.217 as j

/ \

r 7.40 7.20 1.214 1.208

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.f 1.18+00 j

/ \

g f

/ 7.00 6.80 1.202 1.195.

V 6.60 1.187 d / 6.40 1.177 j ,

6.20 1.166

=. .

1.16+00 / 6.00 1.155  ;

7

5.80. 1.145 S l

\ 5.60 1.139  !

d g 1.14+00 \ / 5.40 5.20 1.132 1.120

.W E ( m [ 5.00 4.80 4.60 1.110 1.106

\

/ 1.109 1.12+00 \ / 4.40 1.115

\V / f 4.20 4.00 3.80 1.122 1.126 1.130 1.10+00 3.60 1.132 3.40 1.133 0.00+00 2.00+00 4.00+00 5.00+00 8.00+00 1.00+01 3.20 1.133 COREHEIGHT(FEET) 3.00 1.133

! 2.80 1.132 2.60 1.132 2.40 1.135 N207/JUN(Z)fyNCil0NAT5000-7000 llWD/nlTU BURNUP 2.20 1.140 2.00 1.147 l 1.80 1.152 9

a-eem--*,._-.s. ,g-, w - - + - - - , , r--r---,---r-e g- -vr w - ----v,,-,---,wer-.-=w-*w , ++,,-v

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l FIGURE 2 - N(Z) FUNCTION FOR N2C7 AT 2893 MW HEIGHT 'NZ6-REDUCED TEMPERATURE OPERATION ,

FROM 7000 to 9000 MWD /MTU BURNUP

' TOP AND BOTTOM 15 DERCENT EXCLUDED 10.20 1.191 ,

AS PER TECH SPEC 4.2.2.2.G 10.00' 1.186 9.80 1.180 ,

9.60 1.175 9.40 1.173 9.20 1.179 9.00 .1.188 8.80 1.199 ,

1.22+30 8.60 1.207 8.40 '1.213 TN 8.20 1.217 1.20+00

/ '\

8.00 7.80 1.219 1.219

\ 7.60 1.217

\ 7.40 1.214

  • E / 7.20 1.208
1.1I+00 ' f \) 7.00 6.80 1.202 1.195 3

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i f Y 6.60 6.40 1.187 1.177 E

=, 1 15+00 \. f 6.20 6.00 1.166 1.155

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h 5.40 1.132

= 1.14+00 \ 5.20 1.120 S' \ / 5.00 1.110 E

  • \ / 4.80 1.106

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/ 4.60 1.109 1.12+00 \ / 4.40 1.115

\y f

/ 4.20 4.00 3.80 1.122 1.126 1.130 j ,gg,gg 3.60 1.132 3.40 1.134 0.00+00 2.00+00 4,00+00 6.00+00 8.00+00 1.00+01 3.20 1.139 COREHEIGHT(FEET) 3.00 1.146 2.80 1.152 2.60 1.158 2.40 1.164 N2C7/JUN(Z)FUNCil0NAT7000-9000 HD/WTUBURNUP 2.20 1.168 2.00 1.174 1.80 1.182 1

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FIGURE 3 - N(Z) FUNCTION FOR N2C7 AT'2893 MW HEIGHT NZ7 i REDUCED TEMPERATURE OPERATION FROM 9000 to 15600 MWD /MTU BURNUP TOP AND BOTTOM 15 PERCENT EXCLUDED 10.20 1.191 l AS PER TECH SPEC 4.2.2.2.0 10.00 1.186 f 9.80 1.180 i 9.60 1.175 s 9.40 1.173 .

9.20 1.179 9.00 1.188 8.80 1.199 .

1.24+00 8.60 1.207 8.40 1.213 8.20 1.217 8.00 1.219 1

1.22+00

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/ \T 7.80 7.60 1.221

-1.224

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as r

\ 7.20 1.230 ,

d 1.20+00 / \ 7.00 1.230 '

2 j g 6.80 1.230 C / \ 6.60 1.226 g 7 6.40 1.222

  • 6.20 E'1'11+00

' / k/ 6.00 1.214 1.207 E

h k f V 5.80 5.60 1.196 1.185 i 5.40 1.169 l d.

g 1.11+00 \ f 5.20 1.147 W

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f 5.00 4.80 4.60 1.133 1.130 1.129

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1.14+00 \ I 4.40 1.126

\ f 4.20 1.125

\ j 4.00 1.126

%f 3.80 1.129 1.12+00 3.60 1.131 3.40 1.133 0.00+00 2.00+00 4.00+00 5.00+00 1.00+00 1.00+01 3.20 1.139 i COREHEIGHT(FEET) 3.00 1.145 ,

l 2.80 1.152 1 2.60 1.158

1. 2.40 1.164 N207/JUN(Z)FUNCil0NAT9000-15600 WWD/MTUBURNUP 2.20 1.168 l

2.00 1.174 1.80 1.182 l

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i FIGURE 4 - N(Z) FUNCTION FOR N2C7 AT 2893 MW HEIGHT NZ8 REDUCED TEMPERATURE OPERATION FROM 15600 MWD /MTU BURNUP TO EOL TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G f,'

$'h 9.80 1.142 9.60- 1.140 9.40 1.147 9.20 1.162 9.00 1.175 8.80- 1.188 l 8.60 1.199 8.40 1.207 8.20 1.214 I- 1.22400 [\ ,

8.00 7.80 1.218 1.221~

7.60 1.224 7.40 1.228 5 ) 7.20 1.230 7.00 1.230 t' 6.80 1.230 0 6.60 1.226 g 1.11+00 -

6.40 1.222

  • i 6.20 1.214 E' ( 6.00 1.207
) 5.80 1.196 5 5.60 1.185 d 5.40 1.169 E \' / 5.20 1.148

= 1.14+00 - 5.00 1.134 i E I 4.80 1.131 i / 4.60 4.40 1.130 1.127 j l

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/ 4.20 1.123 '

\ 4.00 1.118 3.80 1.112 1.10f00 3.60 1.107 3.40 1.105 1 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 3.20 1.109 i

COREHEIGHT(FEET) 3.00 1.113  ;

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2.80 1.120 I 2.60 1.125 i 2.40 1.130 i N207/JUN(2)FUNCil0NAT15600-17700 WWD/WTUBURNUP 2.20 1.135 2.00 1.141 1.80 1.149

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i K FIGlRE 9 - AXIAL FLUX DIFFERENCE LIMITS .-

AS A FUNCTION OF RATED THERMAL POWER I FROM 150 MWD /MTU BURNUP TO EOC FOR NORTH ANNA UNIT 2 CYCLE 7 REDUCED TEMPERATURE OPERATION ,

j 1.20402-(6 ,100) 1.00+02 (-12, 100)

=

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  • 0.00+01 / \ Unnecept.able E j

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-5.00+01 -3.00+01 -1.00+01 1.00401 3.00+01 5:00+01 l-

l. PERCENTTLUXDIFFERENCE(DELTA-l)

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