ML20040C908
| ML20040C908 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/26/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 029, 29, NUDOCS 8201290362 | |
| Download: ML20040C908 (19) | |
Text
. _ -
VinotwrA ELECTHIC AND Powna COMPANY Ricuxown, Vruots:A 2026i H.H.Laammuno January 26, 1982 Vacs Pasesommt Necs. nan Ormaatsown Mr. Harold.R. Denton, Director Serial No. 029 Office of Nuclear Reactor Regulation N0/NAS JHL:acm Attn:
Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing
'U. S. Nuclect Regulatory Commission Washington, D. C. 20555.
Gentlemen:
NORTH ANNA POWER STATION UNIT 2 SUBMITTAL OF ADDITIONAL INFORMATION PURSUANT TO LICENSE CONDITION 2.C (14)
The attached information provides some. of the plant specific information for North Anna 2, appropriate for the development of input information for system transient analysis computer codes as recently requested by your letter to Mr.
R.
H.
Leasburg (December 29, 1981).
This information is intended to supplement the data provided by our previous letter (B.
R.
Sylvia to H.
R.
Denton, Serial No. 107, February 19, 1981) and the data gathered'by' members of the E.
G.
C.
Idaho staff during their July, 1981 trip to' Vepco headquarters.
This information. includes representative point kinetics reactivity. coef ficients, data on the auxiliary feedwater system performance, Reactor Coolant Pump (RCP) data, and core average axial power profiles for several core conditions.
The latter data _were requested of us informally by E.
G.
G.
The remaining information requested by your letter of December 29, 1981 is proprietary.
We are pursuing the release of this information with Westinghouse and will forvard it as soon as it is released to us.
Very truly ou l' /
. Leasburg Attachments.
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s 8201290362 820126 PDR ADOCK 05000339
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P PDR
Item Ib, North Anna Point Kinetic Reactivity Feedback Coefficients i
1 1
?
--..._._m
__._z_._.._
__,, ~ _. _ _. _ _.. _., _ _ _ - _ - _ _...
lb.
Point Kinetic Racctivity Feedbeck Coefficients, North Anna 2, Cycle 1 I
(1)
(1)
Condition Hot Full Power, End of Cycle Hot Zero Power, End of Cycle
~
Rodded Less Most Parameter Rodded Unrodded Rodded Reactive Rod (N-1)
(3)
- 26.9
- 39.3
- 28.4 Moderator Temp.
( C + D in, 0 ppm, (0 ppm, 530 F) pcm/ F
( 0 ppm boron, Coefficient,Sak/k)
(pcm = 1x10-550 F) 550 F) 0 (3)
Moderator Density
+ 0.28
+ 0.26
+ 0.385 Coefficient, (hultiply MTC, pcm/0F (Analynis Value + 0.43) delta k/k/(gm/cc) by - 9.8x10-3)
Doppler Temperature Coefficient, pcm/ F
-1.60
-1.60
-2.35
-2.35 8968 (NoXe) 7920 (2000 pcm, NoXe)
Control' Rod trip reactivity (tyP cal reload) 9030 (Eq.Xe) i Worth, pcm
= 6100 pcm (Analynis Value 4000pcm) 1
~
Worth, pcm/ ppm
-10.1
-9.8
-10.9
-10.9 l
Differential Boron (12 ppm boron, A-D in)
(1) Some values are (2) Based on (3) Point values at approximate, based on 550 F water at 5500F. Values decrease
~
Notes hand extrapolations 2250 psia.
(inabsolutevalueg y[Qo[deggging g,-
of available data.
See F gure__1_.
m NIF
,FIC,15.2-44 5-5-75 y*
F.'s t
\\
ZERO POWER 1000 PSI A EMD OF LIFE RODDED CORE WITH ONE RCCA STUCK IN THE FULL OUT POSITION AND ZERO 80 ROM CONCENTRATION l.06 1.05 1.04 w
sU 2 1.03 E
c_
gi.02 (O
i 1.01 i.00
.ss i
I I
I I
I 200 '
250 300 350 160 0 450 500 550 CORE AVERAGE TEMPERATURE (*F)
Figure 15.2-44 Variation of K with Core Tempemtures EFF
(@
S
7-Item 2b.
North Anna Auxiliary Feedwater Flow As a function of Operating Pumps Note: Flows for various operating pump combinations may be obtained by addition of individual pump values l
, ~.
- l1F 10.4-9 2 b-1-3-73 O
10.4.3 Condensate and Feedw. ster 5 ste s 10.4.3.1 Design Basis See Section 10.1.
The pumps, drives, piping and 110,000 gal condensate storage tank of the Auxiliary Feedvater System have all been designed to seis ic C1 css I criteria (Section 3.2.1).
The auxiliary feedwater pumps are designed, fabricated, and tested in accordance with Class III requirements of the Draf t ASME Code for Pu ps and Valves for Nuclear Power (dated November,1968).
The auxiliary feedvater piping is designed in accordance with the Code for Nuclear Power Piping, KISI B31.7-1969.
The turbine driven auxiliary feedwater pu=o is rated at 735 ren and 2.806 l
l f t TDii, and the two notor driven au: ciliary feedvater euros are rated at 17a l
gpm at 2.806 ft TDH. The above ratines include recirculation flev. The design is based on the following conditions:
l 1.
Integrated residual heat release from a full power equilibrium Core.
s (a?h a hwhom e= =msmo s-a.
-===
._;___.-r___
,=--.ee
. ww w
.. ~
e.
G.
f1F Id.4-10 9-28-77 2.
Water inventory of the steam generators operating at nor:al minirum feedwater level.
3.
Minicum allowable steam generator feedvater level per=itted to 21 Prevent thermal shock or other damage.
4.
Automatic starting of auxiliary feedwater pt=ps to deliver full flow within one minute of fault.
5.
The temperature of the feedwater, supplied from the condensate storage tank, was assumed to be 35 F when considering thermal shock and 120 F when considering feedwater enthalpy.
6.
The pumps have continuous minimum flow recirculation whenever operating. Pune net ratings af ter recirculation losses are 700 gpm and 350 apc for the turbine-driven and motor-driven otmos.
respectivelv m 10.4.3.2 System Description The Condensate and Feedwater Syste=s are sl>own on Figs.10.4.3-1 through 64 10.4.3-4.
Condensate is normally withdrawn from the condenser hotwells by two of the three half-size =otor-driven condensate pumps. The pu=ps discharge into a coccon 24 in, header which carries the condensate through two parallel steam jet air ejector condensers and through one gland stern condenser.
O
__-__--_-----_---n
Item 3a.
North Anna Reactor Coolant Pumps Rated Information and Single-phase Head Curve f
f NIF 5.5-19 1-3-73 TABLE 5.5.1-1
.]
1 a.
REACTOR COOLANT PUMP DESICI PARAMETERS Design pressure, psig 2485 Design temperature. *F 650 Capacity / pump, gpm 92.800 Developed head, ft 312 NPSH required, ft 170 Suction temperature, 'F 546.5 RPM nameplate rating 1200 Discharge uozzle, ID, in.
27-1/2 Suction nozzle, ID, in.
31 Overall unit height, f t-1,1 25-6 3
Water volume, ft 56 Moment of inertia, ft-lb 95,000 Weight, dry, Ib 179,500 Motor Type AC induction single speed, air cooled Power, HP.
7000 Voltage 4000 Insulation class B Thermalastic Epoxy Phase 3
Frequency 60 S tarting Current, (hot) amp 1071 Current, (cold) amp 809 Input (hot reactor coolant), kw 5163 l
Input (cold reactor coolant), kw 6839 Motor air to water coolers 2
l Seal Water injection, gpm 8
Seal water return, gpm 3'
l l
NIF Fig. 5.5.1 2 9-28-77 0
600 00 TOTAL HEAD g.
y 400
=k E
300 au h
200 O
REQUIRED NET POSITIVE SUCTION HEAD 100 i
I I
I I
I I
I I
I I
l o
0 10 20 30 40 50 60 70 80 90 100 110 120 FLOW (THOUSANDSOFGFM)
Reactor Coolant Pump Es:imated Performance Char 3cteristic e
n.
l l
North Anna Core Average Axial Power Distributions Contents:
Case 1: BOC, Hot Zero Power, All Rods Out (ARO)
No Xenon i-Case 2: BOC, Hot Full Power, ARO, Equilibrium Xenon Case 3:
EOC, Hot Zero Power, ARO, No Xenon Case 4:
EOC, Hot Full Power, ARO, Equilibrium Xenon
FutSOPet - FLAM3 SOURCE Aec BURNUP 2017 - 9/93/81 - TMS 10/22/81 PAGE 0001
' CASE o N1C3, Ife tseOn mJ, NLP BO C,, A A O, A/O Xf.
l-AVERAGE AX1At. 30L5tCE DISTRIBUTION FOR CASE 1
~
(-
AX1AL NODE HEIGliT SOURCE l
1 2.25 1.23311E-01 1
6.75 2.31762E-01 3
11.25 3.24911E-01 l-l 4
15.75 4.27131E-01 5
20.25 4.8314cE-01 lf
,6 24.75 S.56625E-01 c7 19.f5 6.19914E-01 8
33'75 7.0427eE-01
.. 9 3S.25 7.801SSE-01
- 10. I 42.75 S.57403E-01 11
' 47.25 9.35757E-01 12 51.75 1.01422E*00 13 '
56.25 1.09189E*00 t
14 60.75 1.16764E*00
',/
15 65.25 1.24919E*00 16 69.75 1.30014E+00
.f
. !g 17 74.25 1.33101E+00 73.75 1.s2425E*00' 3G v
19.
83.25 1.46917E+00 20 07.75 1.50350E*00,
/
21 92.25 1.52542E+00' 9
22 /
96.75 1.53360E+00 4
23 101.25 1.52665E+00 24 It5.75 1.50320E+00 25i 113.25 1.4:173E+00
'I 26 114.15
,1.40027E+00 8
27 119.25,
1.315CSE+00 26 123.75 el.20445E+0!
i 29 128.25
- 25941E+00' 30 132.75 8.72219E-01 31 137.25 4.33081E-01 32 141.75
- 3.39607E-01 AX1AL O'F5ET. = 25.9e i
EE.
EE ED m
8 6
J FLn50 Pet - FLAtG SOURCE Ape muutJP EDIT - 9/03/81 - TWS 10/22/81 H1C), 9 0 t1MC/MTU, NZ9 DOC, 440, AJO gr.
FLAME AXIAL SOURCE DISTRIBUTION FOR CASE 1 SOURCE STRENGTH 1.8 1.5
+
1*.2 0.9 0.6
~
0.3 0.0 1
I I
I l
i I
~l
~
120 144 0
20 40 60
' 80 100 80TTort OF CORE HEIGHT * (INCHES)
PAGE 0001 putsopot - Ft.Afts sounCE AM: suRNUP EDIT - 9/03/81 - TMS 10/22/81
~
WTn N1C3, Agt it W NTU, MFP, DOC, A Ad, E4 Xf.
AYERAGE AXIAL SOLRCE DISTRIBUTION FOR CASE &
~
. AXIAL N00E HEIGHT SOURCE 1
2.25 2.55564E-01 2
6.75 4.71204E-01 3
11.25 6.41607E-01 4
15 75 7.74692E-21 5
20.25 8.79767E-31 i
6 24.75 9.64764E-01 7
29.25 1.03502E+00 F
8 33.75 1.09397E*00 9
38.25 1.14372E+00 10 42.75 1 10557E+00 11 47.25 1.22033E+00 12 51.75 1.24360E+00 13 56.25 1.27070E+00 14 60.75 1.28725E+00 15 65.25 1.29829E+00 16 69.75 1.30407E+00 17 74.25 1.30457E+00
' 18 78.75 1.29966E*00 19 83.25 1.28910E+00 20 87.75 1.27257E+00 21
.92.25 1.24976E+00 22 96.75
'1.22036E+00 23 101.25 1.10392E+00 24 105.75 1.13906E+00 25 110.25 1.03720E+00 26 114.75 1.02479E+00 27 119.25 9.50105E-01 28 123,75
- 8.60116E-01 29 128.25 7.49310E-01 30 132.75 6.3.2976E-01 31 137.25 4.43123E-01 32 141.75 2.36596E-01 AXIAL OFFSET =
-0.47 O
W e
W
A p
y-4 4
9 O
4 N"
-1 li b
5
- =
-.N.
e N
k 0
g
~
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h Eo Ee
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3
.O DT SR s
NO 8_:
o W
8 8
u w.
3 0
5 9
2 gt
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gi
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PAGE 4001 PLMsepet. PLApp SOURCE Ase gunHUP 201T = 9/03/81 - TMS 10/22/41 case o M1C3,15500 tes/MTU, NZP C E4 (-), A A d, Nd XF.
j AVERAGE AXIAL SOLRCE DISTRIBUTION FOR CASE 3 AXIAL N00E HFIGHT SOURCE g
)
1 2.25 -
3.50544E-02 2
6.75 6.13507E-42 3
11.25 7.97940E-02 4
15.75 9.30950E-02 5
20.25 1.06956E-01 6
24.75 1.21459E-01 7
29.25 1.39157E-01 8
33.75 1.61376E-01 9
30.25 1.89210F-01 10 42.75 2.236662-01 11 47.25 2.65730E-01 12 51.75 3.16409E-01 r
13 56.25 3.76739E-01 14 60.75 4.47792E-01 15 65.25 5.30664E-01 16 69.75 6.26463E-01 17 74.25 7.36273E-01 l
18 78.75 8.61090E-01 19 83.25 1.00177E*00 20 87.75 1.15362E+00 21 92.25 1.33232E+00 22 96.75 1.52158E+00 23 101.25 1.72472E+00 24 105.75 1.93793E+00 25 110.25 2.15426E+00 26 114.75 2.36145E+00 27 119.25 2.53893E*00 28 123.75 2.65343E+00 29 128.25 2.65227E+00 30 132.75 2.45706E*00 31 137.25 1.03114E+00
=
32 141.75 1.'t5342E+f0 AXIAL OFFSET e 76.40 M
FLMSOPS2 - FLAM3 SOURCE De SURNUP EDIT - 9/03/31 - TWS 10/22/81 H1C3,15500 tsJo/nTU, NZ9,(foC), ARD, Ajo gg',
FLAME AXIAL SOURCE DISTRIBUTION FOR CASE 3 SQLRCE STRENGTM 1.0 1
f 2.5 e
I 1.0
.=
4 1.5 i
\\
~
1.0 k
Y e
0.5 3,
l.
8.0 I
I I
I I
I I
I O
to 40 60 40 100 120 144 BOTTON OF CORE HEIGHT (INCHES)
~
m*
PutSopet - PLAM3 SOURCE AND SURNUP EDIT - 9/03/01 - TWS 10/11/81 PASE 0003
&SE o N1!3, M ARO, MFP.
1 PPM (Eoc.)
EQ XE.
3 7
AVERASE AXIAL SOURCE DISTRIBUTION FOR CASE 8/
AXIAL N00E HEIGHT 50U1CE 1
2.25 4.96182E-01
. 2 6.75 8.34665E-01 3
11.25 1.02295E+00 4
15.75 1.1101SE+00 5
20.25 1.13997t+00 6
24.75 1.14115E+00 7
29.25 1.12983E+00 8
33.75 1.11440E+00 9
38.25 1.09082E+00 10 42.75 1.03473t*00 i
11 47.25 1.07273E+00 12 51.75 1.06285E*30 13 56.25 1.0548%E+00 14 60.75 1.04057E+00 15 65.25 1.04385E+00 16 69.75
- 1. 04 n 5 **E
- 00 17 74.25 1.0365%E*00 18 78.75 1.03783E+00 19 83.25
- 1. 0 334 0E+00 20 87.75 1.04033E+00 21 92.25 1.04353E+00 22 96.75 1.04022E+00 23 101.25 1.05399E+00 24 105.75 1.06029E+00 25 110.25 1.06573E+00 26 114.75 1.06735E+00 27 119.25 1.06013E+00 28 123.75 1.0352%E+00 29 128.25 9.7852bE-01 30 132.75 4.68401E-01 31 137.25 6.79161E-01 32 141.75 3.'8793tE-01 LXIAL OFFSET a
-3.10 e
e e
8 9W6 9
.)
e D
- 9 i
Ou
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5 Cx O
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