ML20112B533
| ML20112B533 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/08/1985 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8503190228 | |
| Download: ML20112B533 (10) | |
Text
__ __ _____.______________
.w O one First National Pl7z3, Chicigo. Illinoi Commonwealth Edison Address Reply to: Post Office Box 767 Chicago, Illinois 60690 March 8, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 FSAR Changes NRC Docket Nos. 50-454/455 and 50-456/457
Dear Mr. Denton:
The letter provides advance copies of revised pages for the Byron /Braidwood FSAR.
These pages are being revised to incorporate the results of revised reactor transient analyses.
These pages will be incorporated into the FSAR at the earliest opportunity.
NRC review is required:
Attachment A to this letter lists the revised FSAR pages which are enclosed.
These pages document the Westinghouse reanalysis of the reactor's transient response to a complete loss of forced reactor coolant flow.
The reanalysis demonstrates that the minimum DNBR will remain above 1.3, considering the as-built reactor coolant pump performance.
The characteristic of the reactor coolant flow decay is an important input to this transient analysis.
The startup test described in FSAR Table 14.2-70 is conducted to verify that the FSAR analysis is conservative with respect to flow coastdown.
Startup testing has determined that adequate margin exists for Byron 1.
Future testing is expected to confirm the margin for the other three units.
Use of the as-built pump data resulted in a revision to a startup test acceptance criterion after the test review was completed.
At the direction of I&E Region III personnel, this change was reviewed as a change to the Post-Fuel-Loading Initial Test Program in accordance with Condition 3 of the Byron 1 Operating Licensing NPF-37.
A report of this change will be submitted to Region III in accordance with 50.59(b) and Condition 3.
l0 hDk3190228850308ADOCK 05000454
/
i I p
H. R. Denton March 8, 1985 Please address further questions this matter to this office.
One signed original and fifteen copies of this letter and the enclosure are provided for NRC review.
Very truly yours,
% /2 /[h T. R. Tramm Nuclear Licensing Administrator 1m
^
cc:
J. G. Keppler - Region III Byron Resident Inspector AttEchment s.
A
}g 9860N ng t
8 h
l s
l
O '
ATTACHMENT A LIST OF REVISED FSAR PAGES v
Page 15.3-15, Table 15.3-1 time sequence of events Figure 15.3-9 flow vs. time Figure 15.3-10(a) power vs. time Figure 15.3-10(b) pressure vs. time Figure 15.3-11(a) heat flux vs. time (aug. channel)
Figure 15.3-ll(b) heat flux vs. time (hot channel)
Figure 15.3-12 DNBR vs. time i
r 9860N A
3 L_
l
(
B/B-FSAR AMENDMENT 37 MARCH 1982 TABLE 15.3-1 (Cont'd)
TIME SEQUENCE OF EVENTS FOR INCIDENTS WHICH RESULT IN A DECREASE IN REACTOR COOIANT SYSTEM FLOW ACCIDENT EVENT TIME (sec) l Four Loop Three Loop Operation Operation Reactor cool-0.0 /
0.0 ant pump under-I voltage trip point reached Rods begin to drop
- 1. 5 /
1.5 l
F Minimum DNDR 3.7 l
g 3.5 occurs I
r' or Coolant Pump Shaft-ure (Locked Rotor) l
?
I Rotor on on mp i
i locks 0.0 0.0
- 'Lo w trip point r d
0.04 0.03 Rods begin to drop 1.
1.03 15.3-15 i
l
t I
i i
conn og i
l 4000'8 I
i i
I e
3 O
b i
d 4000 9 c
l g-m W
=
w o
i 4/1 O
L J
W 4
Z M
4000~t P
u O
W J
4 A
U i
I
[
4000 ~2 I
i l
i i
i i
i i
_u n.a
' r T
W W
Y W
r W W j
O O
O O
O O
O O
O O
O O
O O
O O
O O
N O
O O
O O
O
\\
i S
to e
N O
e e
1 i
OYNIHON.40 '3V83) M013 3803 1
I l
l I
fi f 0R E /.T. 3 ~ 9
f l
[
5
[
- 000'01 l
i k
0000*8 i
i t
I
- n o
4000'S c
[
a[g-W
=
m t
m S
w x
4000't P
I E
r-w S
a.
j u
?
0000'2 l
i i
9 i
i 0 *0
^
o o
o o
o o
i o
o o
o o
o o
o o
8 8
o o
o o
o, eu cu e
is
.o OVN! HON 30 '3YuS H3M0d HY373nN A4urc Is* 3 -19
N.
s I
l 0
0 0
0 0
-000'01 7
r I
i t
0000'8 i
r t
e m
f o
L d
0000*S c
l g"
w r
uo a:
M m
mo a
w l
Z 0000'4 P
l N
4 w
a a.
u
?
0000'2 l
1 4
i i
0*0
^
l o
o o
o o
o o
o o
o e
o o
o o
o i
o.
o o
o o
o o,
o m
N o
e n
N N
N N
N N
m e
(VISd) 3HnSS3Hd S3Hd l
\\
l l
A(ve /r. 3 -/q'A)
I E
,000'01 i
-0000'8 l
t 3-v d
L 0000'S c
l
,g-3 W
o
=
~
w w
O J
w x
8.-
4000't P
i S
w<
a.
u l
0000'2 i
3 4
0*0 O
O O
O O
O O
O O
O O
o O
O O
O O
O O
O O,
N O
O O
m O
OVNIHON 30 '3YB.D XfYlj 1Y3H l
Aquae-IS. 3 - II0th
i t
4
+
+
4 00'01 0000'8 i
m t
o N
u d
z-t 0000'S u
u 3
w o
a w
r w=
oa I
y E-0000'%
P w
S a.
v
-0000'2 n.n y y I
'~
T T
T T
r-o o
o o
o o
o o
o o
o o
o o
o o
o o
m o
o o
o o
o.
.i co w
e m
O m
e OYNIHON 30 '3YH3) Xn131Y3H i
i i
fifup.6-Ib~.3-LIf(k
a 000'01 0000'8 t
m Od i
-0000*9 c
l z-W o oc m
m Oa l
8*-
4000't P
s ia S l
a.
i u
i 4000*2
= >
0
?
?
?
0'0 C
O O
O O
O I
O O
O O
O O
O O
O O
O O
O N
O (D
e N
h h
h M
M M
M 88NO fl4 UM' /S'. 3 - l2