ML20245J317
| ML20245J317 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/28/1989 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-318, NUDOCS 8905040094 | |
| Download: ML20245J317 (10) | |
Text
- _ - - _ - _ _ - - _ _ _ _
VINGINIA ELECTHIC AND POWEH COMPANi RICIIMOND, VIROINIA 20261.
w.n.c^"'"*""'
April 28,- 1989
' Vaca Pass: Dant'
'Nuctuam U. S. Nuclear Regulatory Commission Serial No.89-318 Attn: Document Control Desk.
PES /JYR:cdk Washington, D.C.
20555 Docket No.
50-338 License No. NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 1 RELOAD INFORMATION FOR CYCLE 8 North = Anna Unit No. 1 completed its seventh cycle of operation on February 25, 1989, and went.into an outage for refueling. The purpose of this letter is to transmit to you the Core Surveillance Report containing specific. power distribution limits applicable for Cycle 8 operation and to. advise you of our plans for Cycle 8 operation.
1 The Cycle 8 reload core was analyzed in accordance with the methodology documented in the approved topical report VEP-FRD-42, Revision 1-A,
" Reload Nuclear Design Methodology," 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 Specification."
These analyses were performed and reviewed by our technical staff.
The results of these analyses indicated that no key analysis parametern would become more limiting during Cycle 8 operation than the values assumed in the currently applicable safety analyses.
A review has been performed by both the Station Nuclear Safety and Operating 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 result of the Cycle 8 reload core.
The Core Surveillance Report,.which consists of the Cycle 8 N(z) function and the Axial Flux Differerce Limits, is included as Attachment 1.
These limits are based upon the current total peaking factor (F ) limit of 2.19.
Technical O
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 No.89-192, dated April 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 t*3 redesigned Cycle 8 core.
u \\
~ 8905040094 890428 PDR ADOCK 05000338 P
1 l
l i
' This letter is provided for your information and planning. However, should you have questions, please contact us at your earliest convenience.
l Very truly yours, l
$nA
. R. Cartwright Attachment 1.
Core Surve111atv:e Peport For North Anna 1, Cycle 8 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
i
______._____.____.___m._
f.
NORTH ANNA UNIT 1 CYCLE 8 CORE SURVEILLANCE REPORT This Core Surveillance Report is provided in accordance with Section i
6.9.1.7 of the North Anna Unit 1 Technical Specifications.
l The burnup-dependent Cycle 8 N(z) function for Technical Specification 4.2.2.2.C is shown in Figures 1-6.
N(z) was calculated according to the procedure of VEP-NE-1-A.
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(z) s ----------,
P > 0.5 and P
FQ(z) s 4.38 K(Z),
P s 0.5.
The Cycle 8 Axial Flux Difference (AFD) limits for Technical Specification 3.2.1 are shown in Figure 7.
These limits were calculated according to the methods of VEP-NE-1-A and are comparable to the Cycle 7 limits.
The limits on Axial Flux Difference assure that the FQ(z) upper bound envelope is not exceeded during either normal cperation 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 tne ECCS acceptance criteria of 10CFR50.46.
1
FIGURE 1 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 0 to 1000 M4D/MTU BURNUP.
TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)
(FEET) 1.80 1.283 2.00 1.274 2.20 1.265 2.40 1.254 2.60 1.242 1'30+00 2.80 1.229 3.00 1.217-3.20 1.207 1
3.40 1.202
\\
3.80 1.192 3.60 1.198 1.26+00
\\
4.00 1.185 5
4.20 1.177
\\
4.40 1.167 S:
\\
4.60 1.157 1.22+00 4.80 1.144 5
f g
\\
j 5.00 1.131
\\
/
5.20 1.117
\\
/
5.40 1.108
==
g
\\
/]
/
5.60 1.104 1.18+00 5.80 1.108 3
f
/
6.00 1.114 6.20 1.124 g
g
/
6.40 1.133
/
6.60 1.144
=
1.14+00 6.80 1.155
/
7.00 1.164
\\
/
7.20 1.172
/
\\,
7.40 1.179
\\/
7.60 1.184 1.10+00 7.80 1.188 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 8.00 1.191 8.
1 COREHEIGHT(IEET) 8.60 1.189 8.80 1.185 9.00 1.179 9.20 1.178 9.40 1.185 9.60 1.196 9.80 1.203 10.00 1.211 10.20 1.217 l
J
4 FIGURE 2 - N(Z) FUNCTION FOR NIC8 AT 2893 HW FROM 1000 to 3000 MWD /MTU BURNUP TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)
(FEET) 1.80 1.283 2.00 1.274 2.20 1.265 2.40 1.254 2.60 1.242.
2.80 1.229 3.00 1.217 3.20 1.207 3.40 1.202 1.28+00 3.60 1.198 s
h 3.80 1.192
\\
4.00 1.185 4.20 1.176 4.40 1.167 m
4.60 1.156 w
2 1.24+00 4.80 1.142 5.00 1.129 g
5.20 1.124 5.40 1.129
=
g f
g
\\
_\\
5.60 -
1.136 j
j
- 1.20+00-
\\
/
\\
/
5.80 1.148
\\
j /
6.00 1.156
=
T 6.20 1.166 a
E V
(
6.40 1.180 S
6 60 1.194 5
6.80 1.205
- 1.16+00 7.00 1.212 7.20 1.217
/
7.40 1.218 7.60 1.217
\\ /
7.80 1.214 v
8.00 1.215 1.12+00 8.20 1.215 0.00+00 2.00+00 4 00+00-6.00+00 0.00+00 1.00401 8.40 1.212 COREHEIGHT(FEET) 8.60 1.208 8.80 1.201 9.00 1.189 9.20 1.183 9.40 1.186 9.60 1.195 9.80 1.203 10.00 1.211 10.20 1.217 L
+
FIGURE 3 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 3000 to 5000 MWD /MTU BURNUP TOP At() BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)
(FEET)
.1.80 1.187 2.00 1.180
'2.20 1.173 2.40 1.165 2 60 1.156 2.80.
'1.148 3.00 1.137 Oh 3.20 1.129 1.21+00 3.40 1.128
/
\\
.3.60 1.132 3.80 1.133
/
j 4.00 1.134-4.20 1.134 1'1H00 L
5 4.40 1.132 3
\\
4.60 1.129 i~
/
4.80 1.123 5
(
j 5.00.
1.118 g; 1.17+00
\\
. /
5.20 1.120
\\
/
V 5.40 1.129 52
\\
/
5.60 1.138
=
i r
5.80 1.149 s
,*,3
\\
j 6.00 1.156 6.20 1.166 f
6.40 1.180 5
6.60 1.194 g
/
6.80 1.205
=
1.13+00 kA
/
7.00 1.212 v
\\
/
7.20 1.217
\\,e/
7.40 1.218 7.60 1.217 7.80 1.215-1.11+00 8.00 1.215 8.
1 0.00+00 2.00+00 4.00+00 6.?D+00 8.00+00 1.00+01 COREHEfGHT(EEET) 8.60 1.208 8.80 1.201 9.00 1.193 9.20 1.183 9.40 1.169 9.60 1.167 9.80 1.172 10.00 1.177 10.20 1.182
t
~
FIGURE 4 - N(Z)~ FUNCTION FOR'NIC8'AT 2893 MW
.FROM 5000 to 7000 MWD /MTU BURNUP TOP A W BOTTOM 15 PERCENT EXCLl0ED
'AS PER TECH SPEC 4.2.2.2.G HEIGHT.
N(Z)
(FEET) 1.80' 1.187 2.00 1.180 j
2.20-1.173 i
2.40 1.165 2.60 1.156 2.80 1.148 pN 3.20 1.129.
3.00
'1.137-
'I.21+00
/
\\
3.40, 1.128 3.60 1.132
\\
3.80 1.133
/
1 4.00 1.134.
5
- 1. m 00 4.20 1.134 f
4.40 1.132
\\
c' 1
4.60 1.129' E ~ "
~
(
f
}/
4.80 1.123 bl.17f00
\\
I l
5.00 1.118 1
i l
V 5.20 1.120 l
\\
/
5.40 1.129
==
.E i
5.60 1.138 5
5.80 1.149 d 1.15+00
)
6.00 1.156 5
6.20 1.166 E
6.40 1.180 E
6.60 1.194
~
1.13+00 A
6.80 1.205
~~
v
\\
/
7.00 1.212
\\ /
7.20 1.217 7.40 1.218 m
7.60 1.217 1.11+00 7.80 1.215-0.00+00 2.00+00 4.00+00 6.00+00 8.0C+00 1.00+01 fl COREHEISHI(FEET) 8.40 1.212 8.60 1.208 8.80 1.201 9.00 1.193 9.20 1.183 9.40 1.169 9.60 1.167 9.80 1.172 10.00 1.177 10.20 1.182 j
l l
m--
4 FIGURE 5 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 7000 to 16200 MWD /MTU BURNUP l
TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G l
HEIGHT N(Z)
(FEET) 1.80 1.187 2.00 1.180 2.20 1.173 2.40 1.165 2.60 1.156 2.80 1.148 1
3.00 1.136 3.20 1.129
/
3.40 1.128 i
1.24+00 3.60 1.131 3.80 1.133 i
4.00 1.135 4.20 1.136 l
o, bi 4.40 1.135 J
-d 4.60 1.134 4.80 1.135 f
gg 1.20+00 5.00 1.142
)
5.20 1.159
==
=g 5.40 1.181
\\
5.60 1.198 5.80 1.209 ao
-d 6.00 1.221
==
6.20 1.228
$$1.16+00
\\
6.40 1.236 6.60 1.241 c=
6.80 1.249 7.00 1.253 7.20 1.256 sl 7.40 1.256 ks/
7.60 1.254 1.12+00 7.80 1.251 8.00 1.245 0.00+00 2.00+00 4.00+00 6.00+00 8.00+00 1.00+01 8.20 1.238 COREPEIGHT(FEET) 8.40 1.228 8.60 1.216 I
8.80 1.204 9.00 1.192 9.20 1.183 9.40 1.182 9.60 1.192 9.80 1.197 10.00 1.202 10.20 1.206
'I
~
4 4
FIGURE 6 - N(Z) FUNCTION FOR NIC8 AT 2893 MW FROM 16200 MWD /MTU BURNUP TO EOL TOP AND BOTTOM 15 PERCENT EXCLUDED AS PER TECH SPEC 4.2.2.2.G HEIGHT N(Z)
(FEET) 1.80 1.174' 2.00 1.167 2.20 1.161
/T 2.40 1.154
/
\\
2.60 1.146 1.24+00
(
2.80 1.138 3.00 1.128 3.20 1.123 3.40 1.124 5
3.60 1.130 3
3.80 1.132 4.00
'1.135 a 1.20+00
/
4.20 1.136 E
=
4.40 1.135
=
4.60 1.134 E
4.80.
1.135 5
5.00 1.142 3
5.20 1.159 E
\\
5.40 1.181 S
1.16+00
\\
5.60 1.198 5
5.80 1.209 6.00 1.221 6.20 1.228 6.40 1.236
\\
/
6.80 1.249 Q
6.60 1.241 V
l 7.00 1.253 1.12f00 7.20 1.256 1
0.00+00 2.00+00 4.00+00 6.00+00 0.00f00 1.00+01 l
fl COREHEIGHT(FEET) 7.80 1.251
'8.00 1.245 8.20 1.238 8.40 1.228 8.60 1.216 8.80 1.204
'9.00 1.187 9.20 1.180 9.40 1.182 l
9.60 1.192 9.80 1.197 I
10.00 1.202 10.20 1.206 l
i 1
- _ - _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i l
FIGURE 7 - AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER FROM 150' MWD /MTU BURNUP TO E0C~
FOR NORTH ANNA UNIT 1 CYCLE 8
'l 1
1.20+02
.I.
1.00+02
(_'12.10 3)
(+i.100 I
)
/
\\
==
s Unacceptable
" 8.00+01
/
\\
- g
/
\\
Operation Accepta al.e
\\
5 j
\\
Operati m 6.00+01 s
/
\\
4.00+01
(-2 7,50)
( +2 ),50) ti5
- 2.00+01 0.00+00
-5.00+01
-3.00+01
-1.00+01
.1.00+01 3.00+01 5.00+0'l PERCENTFLUXDiffERENCE(DELTA-l) i e
O