ML20117D851
| ML20117D851 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/06/1985 |
| From: | Danni Smith COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 0049K, 49K, NUDOCS 8505100245 | |
| Download: ML20117D851 (5) | |
Text
I
'N Commonwealth Edison
/
) ona First Nationil Pixzt, Chicago, lihnois
~7 Acfdress Reply to: Post Offica Box 767
,/ Chicago. Illinois 60690 s.
May 6, 1985 Mr. Harold R. Denton U.S. Nuclear kegulatory Commission Ofc. of Nuclear Reactor Regulation Washington, DC.
20555
Subject:
Braidwood Station Units 1 and 2 Reactor Vessel Materials NRC Docket Nos. 50-456 & 50-457
Dear Mr. Denton:
Enclosed is information concerning the Braidwood Unit 2 reactor vessel material surveillance capsules.
In addition there is a withdrawal schedule for both Braidwood Units 1 and 2.
This information is provided for your review in order to close safety evaluation report confirmatory Issue Part A Item 5.
Please address any additional questions regarding this matter to this office.
One signed original and fifteen copies of this letter are provided for your use.
truly youys,
?
David H. Smith Nuclear Licensing Administrator
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8505100245 850506 13 1 PDR ADOCK 05000456
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BRAIDWOOD UNIT 2 REACTOR YESSEL BELTLINE MATERIAL E
Component Material Heat No.
Code No.
Melting Process Upper Shell A508 CL.3 490963/49C904-1-1 MK 24-2 Basic Elect. Furnace (Yac. Treated)
Lower Shell A508 CL.3 50D102/50C97-1-1 MK 24-3 Basic Elect. Furnace (Vac. Treated)
Weld Wire Flux I
~
Weld location Weld Process Weld Qual. No.
Type lleat No.
Type Lot No.
Upper to Lower Submerged Arc WF 562 Linde MnMoNi-4420ll Linde 80 0344 Shell Girth Weld Seam CHEMICAL COMPOSITION (Wt %)
Component Weld or Code No C Mn P
S Si Ni Cr Ho Cu V
Co Upper Shell Mk 24-2 N T.T N N 3 M
~0H TJ 4.01
.012 Lower Shell Mk 24-3 22 1.30 006 004.28
.75 08
.49 06 7.01 011 Upper to Lower Shell WF 562
.066 1.44.01 5.012.48
.67
.10
.44
.04
.005.011 i
Weld i
Surveillance Material Heat Treatment Lower Shell MK 24-3 1598-1652 F-6)HR-Water Quench 1202-1224 F-121HR-Air Cool 1100-1150 F-121/5 HR-Furnace Cool Weld Metal (WF 562) 1100-1150 F-121HR-Furnace Cool l
SURVEILLANCE CAPSULE CONTENTS I
Capsules U,V,W,X,YaZ Material Orientation Charpy Tension IT-Compact Lower Shell (Mk 24-3)
Axial 15 3
4 Lower Shell (Mk 24-3)
Tangential 15 3
4 Weld Metal (WF 562)
Transverse 15 3
4 Haz Metal (Mk 24-3)
Axial 15 l
0*
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REACTOR VESSEL CORE BARREL NEUTRON PAD 2
CAPSULE U
- "58.5
- L I
58.5*
61*
270*
90*
l W
REACTOR VESSEL 180*
l PLAN VIEW l
l 9[ VESSEL
- )
WALL
)
[
CAPSULE s/
ASSEMBLY lll !
5 h[W CORE f.
- j q MIDPLANE l
E b MKA4-3
(
l FIGURE 1-1.
LOCATION OF THE IRRADIATION l
s NE N N l
TEST CAPSULES IN THE UNIT NO. 2 d
6 REACTOR VESSEL f
" CORE BARREL f
1 l
l ELEVATION VIEW 4
D 9
m
Es l
SURVEILLANCE CAPSULE LOCATIONS & LEAD FACTORS Capsule Vessel Lead Ident.
Location Factor U
58.5
- 4. 0f>
X 238.5 4.05 Y
61.0 3.37 Y
241.0 3.37 W
1 21. 5 4.05 Z
301.5 4.05 (a) Factor by which Capsule Neutron Fluence lead the maximum fluence on the Vessel Inner Wall.
\\
l l
S p-r v
w w
,~-
r
-m
-m.
---ww.nm
- t-r--
t<~m--
-e'-.,
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Braidwood Reactor Vessel Material Surveillance Program Withdrawal Schedule Unit 1 Cap'sule Number Vessel Location Withdrawal Time (EFPY)*
U 58.50
, 1st refueling X
238.50 6
V 610 10 Y
2410' 15 W
121.50 standby Z.
301.50 standby Unit 2 U
58.50 1st refueling W
121.50 4.5 X
238.50 8.0 V.
610 15.0 Y
2410 standby Z
301.50 standby Withdrawal time may be modified to coincide with those refueling outages or reactor shutdowns most closely approaching the withdrawal schedule.
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