ML20040A054
| ML20040A054 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 04/11/1977 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200267 | |
| Download: ML20040A054 (10) | |
Text
e a,
UNITED 5TATES NUCLEAR REGULATORY COMMISSION
[
(
)D y
WASHINGTON. D. C. 29666 g,*.... [
11 GR DOCKET N0.
STN 50-561 VENDOR:
BABC0CK & WILC0X COMPANY (B&W)
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS B&W'S STATISTICAL TREATMENT OF DATA FROM THE VESSEL MODEL FLOW TEST, BSAR-205 On March 25, 1977, representatives of B&W and the NRC staff met to discuss B&W's response to date concerning the subject statistical treatment of data.
The object of the meeting was to determine what information, in addition to that documented by B&W in response to l
request number 221.54, is needed by the staff to complete the review An of the thermal-hydraulic analysis of the BSAR-205 design.
attendance list is enciosad.
R. Gribble (B&W) described the Vessel Model Flow Test (V' AFT) including the instrumentation techniques and devices and the data acquisition Flow through individual model fuel assemblies was measured equipment.
using venturi meters at inlet and outlet ends of the model fuel assemblies.
Pressure differentials proportional to flow through the venturis
(
}
were transmitted via nylon tubing to a remote differential pressure
- ^ transducer. The VMFT test equipment and program are described in detail in a B&W Topical Report, BAW-10025P, " Reactor Vessel Model Flow Tests for 205 Fuel Assembly Cores". The objective of the testing was to support the design of a flow distribution plate located directly underneath the reactor core inlet. This plate contains a number of holes of varying size and location. The pattern of holes distributes core inlet flow such that all assemblies receive nearly the same amount of coolant flow.
J. Pegraia (B&W) discussed the statistical treatment of data taken during the VMFT program. The objective of this analytical wcrk was to demonstrate, at the 95% confidence level, that at least 95% of the time the lowest flow received by any of the fuel assemblies within a certain interior region of the core is 0.99 times the average flow per assembly in that region.
B&W asserted (in the VMFT Topical submitted December 1976) that this
" minimum flow factor" had been demonstrated. The staff has made a series of information requests on the BSAR-205 docket during 1977, in pursuit of an acceptable demonstration of the validity of the B&W " minimum flow factor".
These requests have been responded to on the BSAR-205 docket under request number 221.54.
8201200267 810403 PDR FOIA MADDEN 80-515 PDR
-. ~
t.
2
/
J. Pegram described the current B&W statistical treatment of the VMFT He stated that flow data used is from each of the 161
\\
test data.
interior fuel assemblies. Data was taken in eight separate tests in which a vessel model flow was set, and then the flow was measured in each of the 205 model assemblies. B&W cested the data from the 161 interior assemblies to determine whether it was normally distributed. They used the method of ANSI Standard Number 15.15 (1974) " Assessment of the Assumption of Nomality (Implying Individual Observed Values)".
B&W concluded that the probability that the data is nomally distributed is high, and also observed that the variability of the data among the D. Rubinstein (NRC) noted that the ANSI test referenced eight tests was low.
could only establish with high confidence that A hypothesis of nomality could not be rejected. There followed an extensive discussion of the number of data points that could be considered independent.
B&W argued that 8(161) = 1288 observations were independent. The staff demurred, stating that only 161 points, representing the number of different assemblies in different locations, were independent, since the eight test runs were essentially repetitions of flow measurements on an identical model set-up. J. Pegram then revised the B&W data summary prepared for this meating, basing the revised summary on an assumption of only 161 independent observations.
He showed that the resultant minimum flow factor was 0.9876, which the staff agread was equivalent to 0.99.
While the staff agreed in general with the current B&W method as described by J. Pearam, they felt that it was necessary to examine the overall presentation in the fom of a comprehensive written description, documented in BSAR-205. Staff and B&W agreed that the following would be submitted for staff review as soon as possible:
(1) As-recorded dats for each model fuel assembly, for one of the eight test runs.
(2) The lowest measured flow factor for any model assembly in any of the eight test runs. Location of this assembly should be indicated on a map of the model reactor core.
e (3) Calculations of the 3rd and 4th moment of the mean of the distribution of data, for (a) the average of the flow factors (over eight tests) for each of the 161 interior assemblies, and j
(b) the group of 1288 individual flow factors.
(4) The variances over eight test runs for each of the 161 interior assemblies.
i l
(
)
v
-~ ~ ~ -
o s
3-(
(5) A rewritten response to request number 221.54 to document i
the B&W approach presented at this meeting.
Thomas H. Cox, Project Manager i
Light Water Reactors Branch No. 3 Division of Project Management
Enclosure:
Attendance List cc:
See page 4 i
P 4
1
\\
e b
r f
i 5
i k
e i
4 I
i I
i 1
I.
g v
l t"
- '" =g-e *
- ' "'" ] %1 " *4N g
j
~
-4 x
f
't cc: Babcock & Wilcox Company ATTN: Mr. James H. Taylor Manager of Licensing Nuclear Power Generation Division P. O. Box 1260 Lynchburg, Virginia 24505 Washington Public Power Supply System ATTN: Mr. N. O. Strand Managing Director (Acting)
P. O. Box 968 3000 George Washington Way l
Richland, Washington 99352 Mr. Robert Borsum Bethesda Representative Nuclear Power Generation Division Suite 5515, 7735 Old Georgetown Road l
Bethesda, Maryland 20014 l
l l
B. G. Schultz Project Engineer Stone & Webster Engineering Corporation l
P. O. Box 2325 Boston, Massachusetts 02107 l
4 Mr. W. E. Kessler Commonwealth Associates, Inc.
209 East Washington Jackson, Michigan 49201 Robert J. Kafin, Esq.
115 Maple Street Glen Falls, New York 12801 Mr. B. M. Miller Ohio Edison Company 76 South Main Street Akron, Ohio 44308
-v 6 Tg - -
eg
,q,w...sg.,
e s
0 7 3, ENCLOSURE i
ATTENDANCE LIST 3/25/77 MEETING, B&W AND NRC Babcock & Wilcox Company Nuclear Regulatory Comission r
J. Pegram T. Cox e
R. Hiatt G. Kelly R. Gribble D. Rubinstein J. Hamilton J. Happell i
R. Davis i
,I f
I i
k l
l 4
1
/
x 1
x_. )
t 3
..,,_m...,,m-
~
,y- -w.
-+,v.,m-;,. m,vy s--y
.e,77 -.* ;..
- h..r e
I r.,
}
MEETING
SUMMARY
DISTRIBUTION Docket File I. Sihweil NRC PDR P. Check Local POR T. Novak TIC Z. Rosztoczy NRR Reading IE (7)
LWR 3 File G. Lainas B. C. Rusche V. Benaroya E. G. Case T. Ippolito R. S. Boyd V. Moore R. C. DeYoung R. Vollmer D. B. Vassallo M. Ernst D. Skovholt F. Rosa J. Stolz W. Gamill K. Kniel EP Branch Chief
- 0. Parr L. Dreher l
S. Varga ACRS (16)
R. Denise NRC Participants R. Clark G. Kelly T. Speis D. Rubenstein P. Collins C. Heltemes R. Houston L. Crocker J. Miller
/
F. J. Williams R. Heineman H. Denton D. Muller Project Manager Attorney, OELD M. Ruschbrook J. Knight D. Ross R. Tedesco R. Bosnak S. Pawlicki
+
1 i
4 L
w
=m...ee,'
_p y...,,,,,
w
a
~.
- 3hW'7 Mr9 ni vaufrpes em a:ecur Chkch (M Fi'>
cada mer f aJJ,m,8.~ waA. /.
t.
ki p AA__.
c~ A a b,b.
nM uJin M-sa'J g & M~y ga mz si+ viuf kp Sy.
M / i. y " wl.
1Ldd 3svo y
<- a p in. L f < o.
[% la'U d A i~5h + 4* "
3Ak Jentpuyx fr$ %.
~ e&, & cm)p La < u 9,+
N' s n s u s s r~ u Objeh ; 4 & 9sfr 4% f mtxtuaL.
a py
( 99).
Msz irts -1974 W <f Q 4.f %
B(td 8ef& a d*& m mM L SM 4 J 6 a n 4 r d.c a 4 %
cLGh&J & 4-n-4.-- m 4
(>
tw.
o3 psf 77 W D@
i.owJL w A-9
- s. e6)L d d mk gLA A A 14 sp.<.
py
% e y a(A~ n w..of A A p & a 3.
w a m ( & O & =.r. p) d n9 sy si M 9 an M kes &.
D% b ?!a Aok y
p wunL&aL waxn +.uw Mc wik D d.
.nu C & J A iu
(
'~
y dA.
J a y +
-99 c'
s y. it.-fue M ALAw w.
d l
I b.
t
)
r r- -
O
.O O
l l
y
> nws u t p pq p,,4 das~.
=> 3 Panile 5% 4 0 ><& caluMr 9 p /4/ d n 4 m m /z f~4 1 Se4 ym so z u s y.,/. g * /
mt 94+ Mk/1M f k, l% W [ w h ca.</ of /$/ s=I
~j 5
u f
(
')
l
(
)
u-j l
.,,,,.,....7.,
o w
I 205 FA VESSEL MODEL FLOW TEST TOPICAL l
l
- 1.
- Introduction..........................Rf B. Davis f
II.
Core Inlet Flow Acceptance l
Criteria
..............................R. M. Gribble l
III.
Model, Test Loop, Instrumentation, Procedures.............................R. M. Gribble l
t IV.
Core Inlet Development Program.........RP M. Gribble
[
V.
General Data Analysis.................JT*W.
Pegram VI.
Summary...............................Rf"B.
Davis 7__
i b
k p
5 i
,_s i
h hc t
a w
a