ML20032A265
| ML20032A265 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/29/1978 |
| From: | William Cahill CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8110290135 | |
| Download: ML20032A265 (10) | |
Text
Willism J. Cthiti,.
1 vo Preuent Q-
+-
I Me4b b h k Censchdated Edison Company of New York. Inc.
4 trwng Place. New York N Y 10003 Telephone (212) 460-3819 l
March 29, 1978 Re: Indian Point Unit No. 2 Docket No. 50-247 U
~
inl l
4; J
U.
i;;,1 C
ks Director of Nuclear Reactor Regulation ATTN:
Mr. Robert W. Reid, Chief
- jiy>
[Q Operating Reactors Branch No. 4 U
c 50 Division of Operating Reactors
[j w
U. S. Nuclear Regulatory Commission Q
g.
g Washington, D. C.
20555 m
Dear Mr. Reid:
The information requas :ed by your letter of May 18, 1977 regarding the Indian Point Unit No.
'e Reactor Vessel Material Surveillance Program is forwarded herewith as Attachment A to this letter.
This submittal supersedes our parcisi response of July 26, 1977.
Should you or your staff have any Curther questions, we will be pleased to discuss them with you.
Forty (40) copies of WCAP-7323, " Indian Point Unit No. 2 Reactor Vessel Radiation Surveillance Program," which describes the reactor vessel material surveillance program is provided as attachment B to this letter.
Very truly yours, h
N f
s' William J. Cahill, Jr Vice President 8110290135 780329 PDR ADOCK 05000247 701040154
\\
l I@
P PDR P
ee (q,jAttachment A
(_j IllDIAtl POINT UNIT ':C. 2 REACTOR VESSEL MATERIAL SURVEILLANCEPP.03PA3 I
1.) The estimated naximua fluence (E > 1 liev) at the innce surface of the reactor vessel wall as of l-tarch 31,1977 is 8.51x 10I7 n/cm2, 2.) The effective full power years (EFPY) of operation accumulated as of
!! arch 31,1977 is lJ 4 EFPY.
3.) Fabrication of the reactor vessel was performed by Cemb'istion Engineering.
Inc.
4.) a.) Sketch of the reactor vessel chowing all materials in the beltline region is shown in Figure 1.
b.)
Information on eaci, of the weids in the bcitiine region is shov.n in Tables 1 through 4.
c.)
Infort.;ation on each of the plates in the beltline region is shown in Tables 4 through 7.
S.)
Information relative to weld and plate material included in the tatorial surfeillance progran is shown in Tables 1 through 3 and 5 through 7.
O 5
4 6
h
U
/
FIGURE 1
{}
IDErlTIFICAh!0:1 A:1D LOCATIO:10F BELTLIiE REGIO:t MATERIAL FOR THE IllDIAri POIrlT UilIT 110, 2 REACTOR VESSEL o
90 0200)-lm
,e-- i- 0 4 2 C w
7 7 '~ s =
~
3y o -
0
/
J A.
/
d I-Uf D ~h.J. '
t O'
/OO a
\\\\
)
\\
u w
f(
B col-2.
BAcci-3j\\
M j,
E-G -ora
- t. j. c.f; 4 A70 90 f
4 1.- OYJB
+
d O AC OA-3.
g t
o b
N b20C).-l % g
/ go
\\
o.
{
2-Q
~'? A C' GonC sy
,,1 zg-9-c v2
- ~~ /
B ACC A-3 f.- O*/2A-l A70 J
h 9[
g Bicos-/
ss y
2:
e 3 -cVid gg\\,en n? I ij
' i.c":
o l
IS,', /
- h 3.osjjA.
- D \\
~
HI
's\\
4
\\ .' -
/ u g;t,co3.y b
N-A70
TABLE 1 IDENTIFICATION OF IflDIAN POINT UNIT f;0. 2 REACTOR VESSEL BELTLINE REGION WELD METAL Weld Utre Flux
- l eld Welding Weld g ation Process Control tio.
Tyne Heat !!o.
Tyce Lo t !;o.
Post Weld Heat Treatment f:c::lc Shell Submerged RACO 3 W5214 Linde 1092 3600 1125 + 25 F-25 HR-F0 Vertical Seam Arc
+Ni 200 ti7043A 1-W.2 A, S~C No.::le Shell Submerged RAC0 3 W5214 Linde 1092 3600 1125 f_ 25 F-25 HR-FC to Irter. Shell Arc
+tii 200 i;7040A Circle Sea" 8-04?
Inte. Shell Submerged RAC0 3 W5214 Linde 1092 3600 1125 + 25 F-25 HR-FC Ver-Ocal Se u Arc
+ili 200
!!7048A g
2-r:2 A, C&C Inte. 5Sall Sutnerged M1.03 RAC0 3 343009 Linde 1092 3708 1150* + 25 F-40 HR-FC
~
t o '_ t.. e c.h el l Arc
+1:i 200 t'9057A Ci rc'.e Ser:
3-2'E RT,CO 3 W5214 Linde 1092 3576 1150 + 25 F-40 HR-FC Lo.er Shell Submerged
~
Vertical Seems Arc
+ili 200 2-C 2 A!.3 Surveillance Submerged RAC0 3 W5214 Linde 1092 3600 1150 + 25*F219 3/4 HR-FC tiel d Arc
+tti 200 il7048A 9
o
-m e=-
a Table 2 Chemical Concesition of Vessel Beltline Region Held Metal Ue'd Wire Flux Weight Percent Ty;:a
[ pat No.
_Tyn Lot No.
C Mn P
S Si Mo Cr Ni Cu EACU 3 U5214 Linde 1092 3600
.11 1.20
.C21
.012
.19
.52 F.*C 0 3 3 CC09 Linde IC92 3708
.14 2.01
.01 0
.01 7
.04
.51 1
P.ACC 3
'45214 Linde 1092 3576
.12 1.15
.021
.012
.21
.56 Surveillance Weld - Not Performed
- Chemical analysis of bare wire - tio as deposited analysis is available Table 3 Mechanical Procerties of Vessel Beltline Region Weld Metal l
Energy Shelf g,'.
Weld Mira Flux TNDT*
at 10 F ftDT Energy YS UTS Elong RA T.vc 2 Heat No.
Type Lot No.
F Ft-Lbs F
Ft-Lbs KSI KSI 65.5 80.0 31.0 71.5 RAC0 3 U5214 Linde 1092 3000 0
103,93,95 0
67.9 84.2 31.0 69.8 $
P_'C0 3 343003 Linde 1092 3708 0
C4,71,90 0
T.ACO 3 u5214 Linde 1092 3575 0
57,51,69 0
68.5 85.0 27.5 68.5 Surveillance Weld 0
78,74,81 0
121 64.75 80.85 27.7 72.7
' Estimated per flRC Standard Review Plan Section 5.3.2 a
. ~.,
Table 4 Maximum End-of-Life Fluence at Vessel Inner 'Jall Locations Seam or Fluence Plate or l' eld Location Plate !!o.
I'/C!12 17 Nozzle Shell Vertical Seam 1-042A 6.6 x 10 I7 l-042B 4.4 x 10 l-042C 1.1 x 10 IO 18 Nozzle Shell to Inter. Shell Circle Seam 8-042 1.3 x 10 l0 Inter. Shell Vertical Seam 2-042A 8.8 x 10 2-0!i23 l0 2-042C 5.0 x 10 I9 Inter. Shell to Lo..ter Shell Circle Seam 9-042 1.6 x 10 18 Leuer Shell Vertical Secm 3-042A 7.0 x 10 3-C42B 18 Nozzle Shell Plate B20Gl-1 1.3 x 10 B2001-2 32001-3 I9 Inter. Shell Plate B2002-1 1.6 x 10 32002-2 BP.002-3 Leuer Shell Plate-82003-1 B2003-2
T Table 5 Identification of Reactor Vessel Beltline Region Plate Material Heat Treatment nat,1 C c~o 0",33 Plate i,0.
veat t:0, spec ;;o.
Supolier Aus teni ti ze Temoer Stress Relief
- le SP.cIl D2001-1 B4679 A302B Mod.
Lukens 1550-1650 F 4 Hrs-WQ 1200-1250 F-4Hr-AC 1125-1175 F-60Hr-FC B2001-2 C4701 1125-1175 F-50Hr-FC E2001-3 A9370 In*
N il 32:02-1)
S4f23 1125-1175F-40Hr-FCg Ff cN-E !
- B.1701 i
Co922 B2t92.c#
Lc..er Shell L2CO3-l C 791 0203-2 B4782
- c. surveillance IR:erial Table 6 Chemical Cencosition of Reactor Vessel Beltline Region Plate Material
':eight Percent Plate !!c.
C l'.n P
S Si iti Mo Cu B2031-1 0.2 1.35
.010
.022
.24
.50 46
.20 m
B2001-2
.23 1.27
.011
.021
.23
.43
.47
.14 W
B2001-3
.23 1.35
.012
.025
.26
.50 48
.19 02G02-li
.20 1.23
.010
.019
.25
.53
.46
.25 02002-2h*
.22 1.30
.014
.020
.22
.46
.50
.14 B2002-3)
.22 1.29
.011
.018
.25
.57
.46
.14 B2003-1
.23 1.33
.011
.025
.23
.65 48
.20 BE003-2
.21 1.30
.01 0
.021
.23
.48
.45 19
" Surveillance Material - tio analysis performed other than reported by supplier.
.__m._-m___
i Table 7 hchanical Prcaerties cf Reactor Vessel Beltlir.e Region Plate Material Shelf e,'.
' t;0 4
- DT Energy
- YS UTS Elone RA Pl c. t a 'M.
'F
F Fi-Lb "SI KSI Y,
'A B2:31-1 10 24 69 67.25 C7.75 26.00 64.45 C T:C l-2
-10 1B 63.5 63.25 85.25 27.25 65.75 B2001-3
-10 25 69 65.25 86.75 25.00 63.75 9
EE"02-1
-20 34 70 70.75 91.50 25.00 64.75 E."1 ? 2-2
-30 21 73 65.00 C5.25 26.50 67.00 L10 B-3
-10 21 73.5 68.95 90.50 26.75 67.75 CECJ3-1
-20 20 71 65.75 37.25 27.75 65.50
'J.rC3-2
-20
-20 83 61.25 81.60 30.75 70.50
^
?E002-1 34 76 67.17 83.40 25.20 67.6 '}
Surveillance B2002-2 34 75 64.55 87.15 27.65 69.8 Test Data 39 72.5 65.32 87.32 26.30 67.0 BECC2-3
Estin ated from longitudinal data ocr l'RC Standard Review Plan Section 5.3.2
.--e-
- .---..,-.e.-
f
?
Yl i
I l
Attachment'B WCAP-7323 l
Indian Point Unit No. 2 Reactor Vessel Radiation Surveillance Program l
t l
l t
f l
i 4
9 e
i f
I 1
=
k I
4
b REGULWlONY INFORNATION DISTRIBUTION SYSTEM (RIDS)
DIPTRINTION FOR INCnt11NG MATERIAL 50-247 f
kEC: F E lli R W ORG: CAHILL 14 J DOCDATE: 03/29/78 NPC CONSOL EDI5ON OF NY DATE RCVD: 04/13/78 40CTYPE:
- 1. L I TER NOTARIZED. NO COPIES RECEIVED k.UUJECT.
LTR 1 ENCL 40 h E'f.F ON 5E FO NGC LTR I!TD 05/1::/77.
FORWARDING INFO RE UNIT 2 REACTOR VESSEL HATFR I AL C URVEII.LANF E PROGRA!1.
14/ATT t4 CAP-7323 ENTITLED. " CONSOLIDATED
[UTOON CO INIII AN POINT LINIT NO 2 REACTOR VESSEL RADIATION SURVEILL.ANCE PRnGRA11" DTD 11AY 1%9 SCC pL(
REVIEWER INITIAL:
XJM
[L At1T I!ANL INDIAN P1 - UNIT 2 DISTHIEUTOR INITIAL:
- 1,44 itaul**4*+n DISTRIEUTION OF THIS MATERIAL IS AS FOLLOWS *************** o*
REACTOR VEEDEL MATERIAL SURVEILLANCE
( DISTRII':i tT ION COli A021 )
l FOR ACTInN; I m r n T r r-
-=mH C FNCL ZWETZIO**W/ ENCL INTERNAL 4.QL.1;- W/1 E 6JC-L NRC PDR**W/ ENCL I
E 4
- W / 2 EiEC-*~=-
OELD*4LTR ONLY N1PCr+W/ ENCL HANAUERrwW/ENCt.
l PAlil ICKI 4*lUENCL EISENHUT**W/ ENCL l
'?.HAn H W/ ENCL BAEReW/ ENCL BU1LER44W/ENCt.
EEB**W/ ENCL HAZ FL tonia-W/E NCl HOGEnW/ ENCL R G AMT.LF- * *tUENCI.
RANDAL.L**W/ ENCL EXTERNAi LPDR'-
WHITE PLAINS, NYsW/ ENCL T I C**tJ / ENCL M5104mW/ ENCL ACR9 CAT B4*tJ/16 ENCL l
l l
1.T R 40 ENCL 19 CONIROL NBR:
781040154
- 17 E. IP+OPid6P
+tverattoisivrrrr pen-F4rbrut*FOpun THE END
- r-* n u n
- n u n rr* " " '-o
- He e q
. _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _