ML19327B320

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Forwards Cycle 8 Core Surveillance Rept for Reduced Temp Operation.No Key Analysis Parameters Would Become More Limiting During Cycle 8 Operation W/Reduced Temp Conditions than Values Assumed in Applicable Safety Analysis
ML19327B320
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
89-318B, NUDOCS 8910300173
Download: ML19327B320 (9)
v • d • e


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I VIRGINIA El.EcrmlC AND power CoMrANY RICHMOND, VIRGINIA 23MI e

October 20, 1989 i

U.S. Nuclear Regulatory Commission Serial No. 89-318B -

Attn: Document Control Desk PE5/JYR:cdk i Washington, D.C. 20555 Docket No. 50-330 (

License No. NPF-4 '

Gentlemen: J VININIA ELECTRIC AND POWER COWANY -

WMWlWE713Er5TKf7F WsT1 l

.' Tf@_TQQUICLF~el T_~EMMRATURf; REDUCTJ_0N,  ;

Forth Atoa Unit 1 fr currently scheduled to inplement a 6"F RCS average  !

temparctura redacti n betwecn 3003 MWD /MTU and S000 MWD /MTU of burnpr. Tne  ;

purpose cf this letter is to transmit to you the Core Surveillance heport .

containing specific power oistribution limits hoplictbie for Cycle 8 oporntico with this temperature re6 ction. l The Cycle 8 ore with the temperateve rehetion was antlyzed in accord <nce with l the mthecology docemented in the ap)reved topical report VEP FRD-42, Revi r. ion [

1-A, " Reload huclear Design Metiocology," using HRC approved co6es 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 i Control Methodology and Associated FQ Surveillance Technical Specifications." l 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 8 operation with the reduced temperature conditions than  !

the values assumed in the applicable safety analyses. I A review has been performed by both the Station Nuclear Safety and Operating t Committee 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 l l-result of the 6"F RCS average temperature reduction implementation.

The Core Surveillance Report, which consists of the Cycle 8 N(z) function and the Axial Flux Diffeience Limits for operation past 3000 MWD /MTV, is included as Attachment 1. These limits are based upon the current total peaking factor '

(F0 ) limit of 2.19. Technical Specification 6.9.1.7 requires that the Report be 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 1-transmits the Core Surveillance Report for the temperature reduction as promised.

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This letter is provided for your information and planning. However. should you  ;

have questions, please contact us at your. earliest convenience.

  • i Very truly yours, i i

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{ W. L. Stewart .

l. ' Senior Vice President - Power j l Attachment l'

( 1. Core Surv6111ance Report For North Anna 1. Cycle 8 f' '

cc: U.S.' Nuclear Regulatory Comission

- Pegion.II

". 301 m rfetta Street d. H.

4: '

Suitt 2900 Atlanta, Georgia 30123

@ Mr. J. l.. CaltNell-NRC Senior Ret.fdent Inspector

-'Y - North Arsna rewer Static'n l 's F

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Attachment 1 .

Core Surveillance Report for North Anna 1 Cycle 8 -

With 6*F RCS Average Tenperature Reduction t

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l NORTH ANNA UNIT 1 CYCLE 8 CORE SURVEILLANCE REPORT FOR REDUCED TEMPERATURE OPERATION 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 8 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.

i 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

,' 2.19 K(z)

FQ(4) 5 ---------- , P > 0.5 and P

fr/(z) s 4.38 K(Z), P s 0.5.

The Cycle 3 Axial Flu Of fference (AfD) limits for Technical Specification 0.2.1 are shown iti Figura 5. These limits were calculatec, according te the r.iethods of VEP-NE-1-\ and are comparable to the prtyious C3cle 7 ,

limits.

The limits on Axial Flux Differnnce assure that the FQ(z) 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.

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i, FIGlRE 1 - N(Z) FUNCTION FOR NIC8' AT 2893 W [

REDUCED TEMPERATlRE OPERATION  :

i FROM 3000 to 5000 MWD /MTU BLRNUP i TOP AIO BOTTOM 15 PERCENT EXCLlDED  !

AS PER TECH SPEC 4.2.2.2.G ,

i HEIGHT N(Z) i (FEET) l 10.20 1.173  !

10.00 1.169  ;

9.80 1.163 '

9.60 1.158  :

9.40 1.153  !

I'II'N 9.20 1.154  !

9.00 1.161  !

8.80 1.173 -;

8.60 1.180  ;

.. _.. 5.40 1.185  :

8.20 1.159 1.!!400 \ i m...

8.00 7.80 7,,,

1.192 1,1 3,l,95 7

-,  ! 7.40 1.199 a-4

~~

7.20 1.199 ,

i! '3 7.00 1.194

= l

)  ;

rQ~~ ~ i 5.60 1,188  ;

[ ;,jg4g) \ i  ;

s,\ 6.50 1.179 I a "i 6.40 1.166 E

1

/ 6.20 1.153 5 6.00 1.145 l d / 5.80 1.140  !

E V 5.60 1.130 i Ili 5.40 1.123 E l'14+88 /

5.20 1.118  !

5.00 1.119

  • 4.80 1.125
  • 4.60 1.133 1 4.40 1.142 ,

4.20 1.150  !

1.10400 4.00 1.158 3.80 1.165 0.00400 2.00600 4.00600 6.00+00 8.00+00 1.00401 3.60 1.171 i COREHEIGHT(FEET) 3.40 1.176  !

3.20 1.182 3.00 1.192 1 2.80 1.203 2.60 1.212 2.40 1.221 P 20 1.230 2.00 1.237 1.80 1.245

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I FIGURE 2 - N(Z) FUNCTION FOR NIC8 AT 2893 MW REDUCED TD9PERATLRE OPERATION FROM 5000 to 7000 MWD /MTU BLRNUP TOP AND BOTTOM 15 PERCENT EXCLWED AS PER TECH SPEC 4.2.2.2 G HEIGHT N(Z)

(FEET)

I 10.20 1.173 7 10.00 1.169 L

9.80 1.163 9.60 1.158-1.28+00 9.40 1.153 9.20 1.154

\ 9.30 1.161 1

8.80 1.173

! ) _. 8.60 1,180

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l 8.40 1.185 8.20 1.189 1.27400 l \, 3 8.00 1.192 3

g 7.80 1.195 C \ 7.60 1. iM

) 7.40 1.199

$ ._ __.l _.. \ _ _ _

7.20

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l

' (3 g 7.00 1 19's 1.194

= 1.16+00 \ 6.80 s 1.188 2 9 ,

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6.60 1.179

$ } / 6.40 1.166 3 i j 6.20 1.153 '

.G 6.00 1.145 S

\ /

f M 5.80 1.140 E

  • 1.14400 \ j 5.60 1.130 5.40 1.123 5.20 1.118 5.00 1.120 x 4.80 1.126 4.60 1.134 1.10+00 4.40 1.142 4.20 1.150 0.00+00 2.00+00 4.00+00 6.00+00 6.00+00 1.00+01 4; 3

f; COREHEIGHT(FEET) 3.60 1.171 3.40 1.176 3.20 1.182 3.00 1.194 2.80 1.206 2.60 1.218 2.40 1.228 2.20 1.238 2.00 1.246 1.80 1.254

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FIGURE 3 - N(Z) FUNCTION FOR N1C8 AT 2893 MW  !

REDUCED TEMPERATLRE OPERATION FROM 7000 to 16000 MWD /MTU BLRNUP  :

TOP AW BOTTOM 15 PERCENT EXCLLDED i AS PER TECH SPEC 4.2.2.2.G 1

'l HEIGHT N(Z) {

(FEET) l 10.20 1.200 i 10.00 1.196 i 9.80 1.190 l' 9.60 1.184 1.24+00 9.40 1.175 i 9.20 1.171 9.00 1.174  !'

3 8.80 1.185 1.22,00 ~

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/ \ 3 8.60 8.40 1.105 1.204 j

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g-

\ 8.20 8.00 1.212 1.217 t;

g' 1*20+00 -

= -,c

'\ 7.80 7.60 1.221 1.224 i

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=

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j

\ [ ,I 7.40.

7 Z's 1.227 1.230 i

i \

M l ' ! 80't - \ ,

It [. _

T 00 6.80 1.230 11.29

,  ; I,- { j 6.60 1.225 .

5 4 .4 v 6.40 1.221

-t g 1.18+00

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l 6.20 6.00 1.212  !

1.205 i

= ) / 5.80 1.194 l g (_ I -

5.60 1.182 ,

5.40 1.166 j 1.14+00 \  ! 5.20 1.145 5.00 1.131

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v 4.80 1.128  :

4.60 1.132 )

1.12+0g 4.40 1.138 I 4.20 1.144 ,

0.00+00 2.00100 4.00100 6.00400 1.00+00 1.00401 4.00 1.147 -

3.80 1.150 COREHEICHT(TEET) ,

3.60 1.151 3.40 1.150 3.20 1.151 4 3.00 1.154 2.80 1.161 2.60 1.168 2.40 1.175 2.20 1.182 2.00 1.187 1.80 1.193

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! FIGLRE 4 - N(Z) FUNCTION FOR N1CS AT 2893 MW REDUCED TD4PfflATLRE OPERATION

' FROM 16000 MWU/Miu BLRNUP TO EOL TOP AM) BOTTOM 15 PERCENT EXCLLDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)

(FEET) 10.20 1.200 10.00 1.196 9.80 1.190 9.60 1.184 9.40 1.175 9.20 1.171 9.00 1.174 f'N 8.80 1.185 1.22400 / \ 8.60 1.196 8.40 1.204

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\ 8.20 1.212 5  ;

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8.00 7.80 1.217 1.221 3 / 7.60 1.224 2 / 7.40 1.227 O i.tsoo / 7.20 1.230 2 3 j 7.00 1.230 t

=2  ! V 6.80 1.229  ;

E 6.60 1.225 -r

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

I 6.40 1.721

.7 \'. .~f 6.20 1.212

's ) 6.00 1.205 i

, S 1*14+00 ( 5.80 1.194  !

3 5.60 1.183 t

" l 5.40 1.167 I

/ 5.20 1.145 s / 5.00 1.131 r

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\ 4.80 1.129 ,

T 4.60 1.128 t 4.40 1.125 t 1.10100 4.20 1.121 0.00100 2.00400 4.00100 6.00+00 8.00+00 1.00401 COREHEIGHT(FEET) 3.60 1.105 i 3.40 1.102

  • 3.20 1.106 3.00 1.110 2.80 1.117 ,
2. r50 1.121 2.40 1.127 2.20 1.136 i

i 2.00 1.147 l 1.80 1.157

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l FIGlRE 5 - AXIAL FLUX DIFFERENCE LIMITS i AS A FUNCTION OF RATED THERMAL POWER i FROM.3000 MWD /NTU BlRNUP TO EOL i FOR NORTH Al#4A UNIT 1 CYCLE 8 REDUCED TEhPERATlRE OPERATION i

i.20+0, i

l 1.00+02 ,-12. LOO) (6.1(10 )

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1.00+01 / _

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9.00+00  ;

-5.00+01 -3.00+01 -1.00+01 1.00+01 3.00+01 5.00+01 PERCENTFLUXDiffERENCE(DELTA-1)

NIC8/ANAfDLIMITSFORREDUCEDTEWPERATUREOPERAil0N NIC8/AN Axial Flux Difference Limits

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