ML20086S922
| ML20086S922 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/17/1995 |
| From: | Stephanie Coffin, Jeffrey Poehler BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20086S832 | List: |
| References | |
| NUDOCS 9508020178 | |
| Download: ML20086S922 (16) | |
Text
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ATTACilMENT (2) 4 t
BEST ESTIMATE CIIEMISTRIES FOR CALVERT CLIFFS REACTOR VESSEL BELTLINE WELDS t
l
[
r t
Baltimore Gas & Electric Company Docket Nos. 50-317 and 50-318 July 21,1995 i
9508020178 950721 PDR ADOCK 05000317 P
^
i BEST ESTIMATE CHEMISTRIES FOR CALVERT CLIFFS REACTOR VESSEL BELTLINE WELDS (Revision 1) l l
Prepared by:
r
_ NU 7 ITfV S. i. CofEn Materials Engineer Independently R viewed by:
J.C. Phhhler D%
\\ W t
Matekals Engineer MEIUJob # 95-34-15-0040
t 1
Calvert Cliffs Reactor Vessel Beltline Materials The reactor vessels for Calvert Cliffs Unit 1 and Unit 2 were fabricated by Combustion Engineering of formed and welded SA 533, Grade B, Class I plates. Tables 1 and 2 provide a general description of the beltline materials. The copper and nickel contents of the beltline plates were well characterized, l
Table 1. The copper and nickel contents of the beltline welds are best estimate values for the weld wire i
heat (s) obtained from various sources using the following rules:
Conner Content BGE determined the copper content for a particular weld wire heat from deposited weld metal chemical analyses. Wire chemical analyses were not used since they do not accurately reflect the copper content of the weld deposit. For each weld, all analyses at a spot were averaged to determine a value for the i
spot. All the values for each spot were averaged to arrive at an average for the weld (an example is provided in Table 3 for the Shoreham vessel weld seam 1-308-A). Values obtained from weld repair areas or backgroove areas were not included since these values were not representative of the general i
weld chemistry and in all cases provided low copper values. The number of coils the average for each weld represented was based on:
- 1) the number of coils used to fabricate the weld, and
- 2) the number of chemistry values obtained from the weld.
Each weld average was then multiplied by the number of coils the average represented. All these values were then added and divided by the total number of coils apresented to arrive at the final best estimate value.
Nickel Content BGE determined the nickel content for a particular weld wire heat from deposited weld metal and wire chemical analyses. Wire chemical analyses were used since the nickel content of the wire is very similar to the weld deposit. All values were simply averaged to arrive at the final best estimate value for nickel
- content, l
Tables 3 - 7 contain all the weld wire chemistry information available to BGE at this time.
j l
Weld Wire llent A8746 iltCC-2 Weld Seam 2-203-A.B.C The Combustion Engineering Owners Group provided the basis for the copper and nickel content of welds fabricated using weld wire heat A8746. These values were reported previously [1,2] and are summarized in Tab!: 8.
Table 8 summarizes the best estimate copper and nickel contents for Calvert Cliffs Unit I and Unit 2 reactor vessel beltline welds.
i ME1UJob # 95-34-13-0040 Page 2 of14
Table 1 Reactor Vessel Beltline Plates Unit Plate IIcat Cu Ni Location Description Code Number (w/o)
(w/o) 1 D-7206-1 C-4351-2 0.11 0.55 Intermediate Shell SA 533, Grade B, Class 1 1
D-7206-2 C-4441-2 0.12 0.64 Intermediate Shell SA 533, Grade B, Class 1 1
D-7206-3 C-4441-1 0.12 0.64 Intermediate Shell SA 533, Grade B, Class 1 1
D-7207-1 C-4420-1 0.13 0.54 Lower Shell SA 533, Grade B, Class 1 1
D-7207-2 B-8489-2 0.11 0.56 Lower Shell SA 533, Grade B, Class 1 1
D-7207-3 B-8489-1 0.11 0.53 Lower Shell SA 533, Grade B, Class 1 2
D-8906-1 A-4463-1 0.15 0.56 Intermediate Shell SA 533, Grade B, Class 1 2
D-8906-2 B-9427-2 0.11 0.56 Intermediate Shell SA 533, Grade B, Class 1 2
D-8906-3 A-4463-2 0.14 0.55 Intermediate Shell SA 533, Grade B, Class 1 2
D-8907-1 C-5804-1 0.15 0.60 Lower Shell SA 533, Grade B, Class 1 2
D-8907-2 C-5286-1 0.14 0.66 Lower Shell SA 533, Grade B, Class 1 2
D-8907-3 C-5803-3 0.11 0.74 Lower Shell SA 533, Grade B, Class 1 Table values from References [3,4].
Table 2 Reactor Vessel Beltline Welds Wire Heat (s)
Location Process Detail Welding Procedure Linde Flux Type Unit Weld Code Description Wire Type WPQR Flux Lot 1
2-203-A,B,C Intermediate Shell Submerged Arc TSAA-2-(l) ALT.
12008/20291 Axial MIL B4 - Modified SAA-33-27 1092 Tandem Arc 3833 1
3-203-A,B,C lxwer Shell Submerged Arc TS AA-2-1 21935 Axial MIL B4 - Modified SAA-33-27 1092 Tandem Arc 3869 1
9-203 Intermediate / Lower Submerged Arc SAA-MA-502-0 33A277 Circumferential MIL B4 SAA-33-34 0091 Single Arc 3922 2
2-203-A,B,C Intermediate Shell Submerged Arc SAA-4-0 A8746 Axial MIL B4 SAA-33-29 124 Single Arc 3878 2
3-203-A,B,C Lower Shell Submerged Arc TSA A-501-0 33A277 Axial MIL B4 SAA-33-36 0091 Tandem Arc 3922 2
9-203 Intermediate / lower Submerged Arc TSA A-501-0 10137 Circumferential MIL B4 SAA-33-36 0091 Tandem Arc 3999 Table values from References [3,4].
WPQR = Welding Procedure Qualification Record MEIUJob u 95-34-15-0040 Page 3 of14
Table 3 CC-1 Weld Scam 2-203-A,lI,C Weld Wire Ileats: 12008/20291 3pL13mmfi.... J.' gg;en M M
M 4(s###$ac4Homere $Neimbodilifi$lig MX> 7. T..
31ctinite - I SurrcMance II'etti 1
0.21 0.88 tandem 5,6 2
0.20 0.91 CVN Specimen DW-15 6,7 3
0.I95 0.87 5,6 4
0.191 0.848 5
0.193 0.863 Average 0.20 s.M u coils = 1 tandem l'ilgritn - 1 Surteillance wen l
0.14 0.81 CVN Specimen Y4A tandem 8,9 2
0.16 0.81 CVN Specimen Y45 3
0.17 0.78 CVN Specimen Y5M 4
0.17 0.81 CVN Specimen Y6U 5
0.16 0.77 CVN Specimen Y6Y 6
0.16 0.79 CVN Specimen Y61 7
0.17 0.80 CVN Specimen Y65 8
0.16 0.77 CVN Specimen Y66 9
0.16 0.79 CVN Specimen Y67 10 0.16 0.81 CVN Specimen Y5T 1I 0.17 0.98 ID, Weld Centerline 9,10 12 0.16 0.94 ID, Off Centerline 13 0.16 0.96 T/4, Weld Centerline 14 0.13 0.72 T/4, Off Centerline 15 0.19 0 86 T/4, Weld Centerline 16 0.17 0.76 T/2. Weld Centerline l7 0.16 0.79 T/2, Off Centerline 18 0.18 0.93 3TJ4, Weld Centerline to 0.17 0.95 3T/4, Off Centerline 20 0.19 0.83 3'l/4, Weld Centerline 21 0.17 0.97 OD, Weld Centerline 22 0.13 0.74 OD,0ff Centerline
.trerage 0.16 a cm/s = 1 tandem AIEIUJob n 95 34 15 0040 l' age 4 of14
Table 3, Continued CC-1 Weld Seam 2-203-A,II,C Weld Wire IIcats: 12008/20291
. g.x.ye,==_-=_=,a - - - _. m _ a yf%amn. u.n..~.,
, _y y.. _...
7%
m=m w._
, m-w wi ;
.w,,___
_m as Silitidat!Lih1d Weld 1-30ft-:t 1
0.20 0.87 ID, Weld Centerline tandem 10.11,12 2
0.18 0.97 ID, Off Centerline 3
0.20 0.87 ID, Weld Centerline 4
0.19 0.88 ID,0ff Centerline 5
0.33 0.73 T/4, Weld Centerline 6
0.27 0.78 T/4, Off Centerline 7
0.33 0.74 T/4, Weld Centerline 8
0.27 0.80 T/4, Off Centerline 9
0.30 0.73 T/4, Weld Centerline 10 0.30 0.73 T/4, Weld Centerline 11 0.16 0.69 T/2, Weld Centerline 12 0.17 0.73 1/2, Off Centerline 13 0.17 0.73 T/2, Weld Centerline 14 0.17 0.73 T/2, Off Centerline 15 0.25 0.86 3T/4, Weld Centerline 16 0.23 0.85 3T/4,0fT Centerline 17 0.26 0.90 3T/4, Weld Centerline 18 0.23 0.86 3T/4, Of1 Centerline 19 0.23 0.87 3T/4, Weld Centerline 20 0.23 0.87 3T/4, Weld Centerline 21 0 23 0.84 OD, Weld Centerline 22 0.23 0.86 OD, Off Centerline 23 0.24 0.86 OD, Weld Centerline 24 0.24 0.87 OD, Off Centerline Average 0.23
- cods = 5 tandem lixample: Determining Average Percent Copper for a Weld with Multiple Values Nu mlier(s)
% Cu
( 1 + 2 + 3 + 4 )'4 0.19 (5+6+7+8+9+10)6 0.30
( 11 + 12 + 13 + 14)'4 0.17 (15 + 16417+ 18 + 19 + 20) 6 0.24 (214 22 + 234 24 )'4 0.24 Total!5 0.23 The c:stimated size for this weld is 1-11/16 x 5-55/64 x 450 inches. This corresponds to approximately 1425 pounds of weld wire. liach coil of wire weighs 150 pounds. Therefore, this weld contains at least 9 coils (1425 divided by 150). Since five discreet measurements were taken through the thickness of the weld, the as erage obtained is representative of 5 coils.
AfEIUJob u 95-34-15-0040 l'a.ee 5 of14
Table 4 CC-1 Weld Seam 3-203-A,ll,C Weld Wire IIcat: 21935
. q w; (7: 7.,-
77.;7 meumummmesammmmmmuummmmmmmmmmmmmmmmmmmmmmmumunu
,.c; w wwm.+
., >,. ww Hlie and li' eld Deposit Analyses R-2546 1
0.70 single 13 l
R-2503 2
0.68 l
single l
l R-2495 3
0.71 l
single l
3 l
D-7279 4
0.20 l
single l
l D-7569 5
0.13 0.68 l
single l
l D-7524 6
0.21 l
single l
13 l.
Average 0.18 l
- cods = 3
.l S112Lelintn l'essel li' eld 5 306 1
0.15 0.70 ID, OIT Centerline single 10,11,12 2
0.17 0.70 T/4, Off Centerline 3
0.17 0.72 T/2, Centerline 4
0.17 0.70 T/2, Off Centerline 5
0.18 0.77 3T/4, Centerline 6
0.23 0.72 3T/4, Centerline 7
0.18 0.75 3T/4,0ff Centerline 8
0.17 0.76 OD, Centerline 9
0.15 0.73 OD, Off Centerline Average 0.17 l
- coils = $
l AfEll) Job u 95-34-15-0040 l' age 6 of 14
4 Table 5 CC-1 Weld Seam 9-203 and CC-2 Weld Seam 3-203-A,II,C Weld Wire IIcat: 33A277 rgy-m3.gpe: gwgg
<mmge en
. cy m a.
3 ge:'9.,
. z::q, 7: c
,, m
.2 t r::.
y ;% -
kW;A;QA;; mas.>d, uMatt.r s au. ~...;;
g,g sg
~^
'..ws,,;;:
s q,%
.% n ;,. >
ILkid.Det>ositArini.o.gs D-7947 1
0.30 single 3
D-7948 2
0.23 tandem D-9217 3
0.23 single D-7986 4
0.29 0.16 tandem D-7985 5
0.29 0.16 tandem D-7629 6
0.29 single D-9711 7
0.18 0.19 tandem D-7565 8
0.32 single 14 D-Il326 9
0.18 single D-7417 10 0.32 single D-7514 11 0.27 single D-7416 12 0.32 single D-8583 13 0.27 single A verage 0.27 n coils = 17 CBirert Clllfs - 1 Sitrycillgncg_il'gid 1
0.24 0.18 tandem 3,15 2
0.28 0.16 TOP, Weld Centerline 16 3
0.27 0.15 between TOP and T/4 4
0.24 0.15
- b. tween TOP and T/4 5
0.26 0.14 between TOP and T/4 6
0.23 0.20 T/4, Off Centerline 7
0.26 0.16 T/4, Off Centerline 8
0.25 0.16 T/4, Weld Centerline 9
0.24 0.15 T/4, Off Centerline 10 0.24 0.16 T/4, Off Centerline lI 0.25 0.15 betw een T/4 and T/2 12 0.26 0.16 betw een T/4 and T/2 13 0.25 0.16 T/2 14 0.28 0.14 between T/2 and 3T/2 15 0.20 0.15 3T/4 16 0.19 0.14 between 3T!4 and BOTTOM 17 0.18 0.14 between 3T/4 and BOTTOM 18 0.18 0.15 between 3T!4 and BOTTOM 19 0.22 0.16 T/4, Weld Centerline 10 20 0.22 0.16 T/4, Weld Centerline 21 0.21 0.21 T/4, Off Centerline 22 0.17 0.18 T/2, Weld Centerline 23 0.20 0.22 T/2, Off Centerline 24 0.16 0.17 3T/4, Centerline 25 0.16 0.16 3T/4, Centerline 26 0.16 0.21 3T/4. Off Centerline Average 0.22 e,\\Q ti ca:Is = 4 Sillli. lob n 95-34-1.5-0040 l' age 7 of 14
Table 5, Continued CC-1 Weld Seam 9-203 and CC-2 Weld Seam 3-203-A,B,C Weld Wire IIcat: 33A277 Maine Yankee Surveillance Weld 1
0.15 0.15 TOP, Weld Centerline tandem 16 2
0.15 0.15 between TOP and T/4 3
0.16 0.15 between TOP and T/4 4
0.16 0.14 betwecn TOP and T/4 5
0.15 0.15 T/4, Off Centerline 6
0.15 0.15 T/4, Off Centerline 7
0.15 0.14 T/4, Weld Centerline 8
0.15 0.16 T/4, oft Centerline 9
0.14 0.17 T/4, Off Centerline 10 0.15 0.14 between T/4 and T/2 11 0.19 0.17 between T/4 and T/2 12 0.21 0.14 T/2 13 0.21 0.14 between T/2 and 3T/2 14 0.21 0.14 3T/4 15 0.21 0.14 between 3T/4 and BOTTOM 16 0.22 0.15 between 3T/4 and BOTTOM 17 0.21 0.15 between 3T/4 and BOTTOM
. Average '
l
'l,0.17~l-l'
> # coils = 4
.l Farlev - 1 Surveillance Weld l l
l l
l tandem 17 l
1 l 0.14 l 0.19 Average
-l
-l ^ 0.14 'l l.
- M coils = 2 : :1 i.
i 1
MElUJob n 95-34-15-0040 Page 8 of14
Table 5, Continued CC-1 Weld Seam 9-203 and CC-2 Weld Scam 3-203-A,ll,C Weld Wire IIcat: 33A277 JNM
[.((j
. ;.[j q M I,[
- Mfg l
Sitggham l'essel ll' eld 4-308A 1
0.24 0.15 ID, Weld Centerline single 10,11,12 2
0.22 0.18 ID, Off Centerline 3
0.23 0.14 ID, Weld Centerline 4
0.22 0.17 ID, Off Centerline i
5 0.25 0.16 ID, Weld Centerline 6
0.24 0.20 ID, Off Centerline 7
0.22 0.15 T/4, Weld Centerline 8
0.21 0.17 T/4,0ff Centerline 9
0.19 0.13 T/4, Weld Centerline 10 0.20 0.18 T/4, Off Centerline i
11 0.23 0.16 T/4, Weld Centerline 12 0.23 0.19 T/4, Off Centerline 13 0.22 0.15 T/4, Weld Centerline 14 0.21 0.15 T/4, Weld Centerline 15 0.21 0.15 T/4, Weld Centerline 16 0.23 0.15 T/2, Weld Centerline 17 0.19 0.19 T/2, Off Centerline 18 0.25 0.15 T/2, Weld Centerline 19
- 0. ! 8 0.17 T/2, Off Centerline 20 0.28 0.16 T/2, Weld Centerline 21 0.20 0.19 T/2, Off Centerline 22 0.21 0.16 3T/4, Weld Centerline 23 0.19 0.20 3T/4, Off Centerline 24 0.18 0.15 3T/4, Weld Centerline 25 0.18 0.18 3T/4, Off Centerline 26 0.21 0.16 3T/4, Weld Centerline 27 0.20 0.20 3T/4, Off Centerline 28 0.18 0.14 3T/4, Weld Centerline 29 0.19 0.14 3T/4, Weld Centerline 30 0.19 0.14 3T/4, Weld Centerline 31 0.21 0.16 OD, Weld Centerline 32 0.20 0.17 OD, Off Centerline 33 0.17 0.14 OD, Weld Centerline 34 0.15 0.22 OD, Off Centerline 35 0.20 0.16 OD, Weld Centerline 36 0.18 0.25 OD, Off Centerline Average 0 21
- coils # 3 J
AfEIUJob :: 95-34-15-0040 l' age 9 of /4
Table 6 CC-2 Weld Seam 9-203 Weld Wire 11 cat: 10137
- L,;$,..AY $h A
$h$ ${b
$M$
5('?N' eld Deposit Analyses D-10600 1 0.23 single 18 ~ D-10596 2 0.22 0.02 tandem 4 3 0.21 Average 0.22
- coils = 3 31Illstone - 2 Surveillanct.ll'gid 1
0.21 0.06 single 19 2 0.23 0.065 CVN Specimen 317 3 0 24 0.071 CVN Specimen 31L Average 0 23
- coils = 2 Calvert Cliffs - 2 Surveillance Weld 1
0.20 0.04 tandem 15 2 0.24 0.06 between T/2 and 3T/4 20,21 3 0.24 0.05 just below 3T/4 4 0.17 0.09 TOP, Weld Centerline 16 5 0.20 0.07 between TOP and T/4 6 0.17 0.06 between TOP and T/4 7 0.17 0.05 betw een TOP and T/4 8 0.19 0.06 T/4, Off Centerline 9 0.19 0.06 T/4,0ff Centerline 10 0.18 0.05 T/4, Weld Centerline ll 0.18 0.05 T/4, Off Centerline 12 0.18 0.06 T/4, Off Centerline 13 0.18 0.05 between T/4 and T/2 14 0.21 0.06 between T/4 and T/2 15 0.22 0.05 T/2 16 0.23 0.06 between T/2 and 3T/4 17 0.24 0.06 3T/4 18 0 24 0.07 between 3T/4 and IlOTTON1 19 0.27 0.07 between 3T/4 and IlOTTON1 20 0.25 0.07 betueen 3T/4 and BOTION1 21 0.18 0.05 HOTTON1 22 0.19 0.087 TOP, Weld Centerline 10 23 0.26 0.059 T/4, Weld Centerline 24 0.24 T/4, Centerline 25 0.26 0.077 T/4, Off Centerline 26 0.24 0.068 T/2, Weld Centerline 27 0.23 0.091 T/2, Off Centerline 28 0.19 0.052 3T/4, Centerline 29 0.18 3T/4, Centerline 30 0.18 0.067 3T/4. Off Centerline 31 0.23 0.045 IlOTION1, Centerline 32 0.18 0.081 IlOTTON1, Off Centerline Arcrage 0 21 n,OD
- coils = 4 AIEIU Job 12 95-34-15-0040 Page10of14
Table 6, Continued CC-2 Weld Seam 9-203 Weld Wire IIcat: 10137 G ra me %Id entlResties t h
- tNa abec 4% Ces eMM0 4$MLocationu WliNunnberofAres (Rafe.% ce bhoreham VesseLSCHOL3-318-1 l
1 0.20 0.053 ID, Centerline single 10,11,12 2 0.19 0.064 ID, Off Centerline 3 0.21 0.076 T/4, Centerline 4 0.20 T/4, Centerline 5 0.20 l " s88 T/4, Off Centerline 6 0.20 0.048 T/2, Centerline 7 0.20 0.076 T/2, Off Centerline 8 0.18 0.051 3T/4, Centerline 9 0.19 3T/4, Centerline 10 0.18 0.11 3T/4, Off Centerline 11 0.28 0.024 OD, Centerline 12 0.20 0.071 OD, Off Centerline itverage U.:0
- coils = 4 9
\\lElli.loh # Y.5-34-l.5-0040 Page!Iof14
Table 7 Suminary of Source Chemistry Values for Calvert Cliffs lleltline Welds M s-,. - #% i @@8omme : U D ~#R % Cun s:$1s MofCailsW$(j fretalR4WNtif 1 12008/20291 McGuire Surveillance \\\\ citi 0.20 1 l 0.20 P<! grim Surveillance Weld 0.16 1 { 0.16 Shoreham Vessel Weld 0.23 5 1.15 Sum: 7 1.51 Weighted Average 1.51/7 = 0.22 Unweighted Average 0.20 0.83 Standard DeWation 0.05 0.07 21935 Weld Deposits 0.18 3 0.54 Shoreham Vessel Weld 0.17 5 0.85 Sum: 8 1.39 Weighted Ascrage 1.39/8 = 0.17 Unweighted Ascrage 0.18 0.72 - Standard Deviation 0.03 0.03 33A277 Weld Deposit 0.27 17 4.59 CC Surveillance Weld 0.22 4 0.88 Maine Yankee Surveillance Weld 0.17 4 0.68 Farley Surveillance Weld 0.14 2 0.28 Shoreham Vessel Weld 0.21 5 1.05 Sum: 32
- 7. -IN Weighted Average 7.48/32 = 0.23 Unweighted Average 0.21 0.16 -
Standard Deviation 0.04 0.02 10137 Weld Deposits 0.22 3 0.66 Millstone Surveillance Weld 0.23 2 0.46 CC Surveillance Weld 0.21 4 0.84 Shoreham Vessel Weld 0.20 4 0.80 Sum: 13 2.76 Weighted Average 2.76/13 = 0.21 Unweighted Average 0.21-0.06 Standard Deviation 0.03 0.02 AIEIUJob n 95-34-15-0040 l'ay 12 of14
~ Table 8 Best Estimate Copper and Nickel Contents for Calvert Cliffs Reactor Vessel Beltline Welds Wire Heat (s) Location Linde Flux Type Cu Ni Unit Weld Code Description Flux Lot (w/o) (w/o) 1 2-203-A,B,C Intermediate Sheli 12008/20291 0.22 0.83 Axial 1092 Tandem Arc 3833 1 3-203-A,B,C Lower Shell 21935 0.17 0.72 Axial 1092 Tandem Arc 3869 I 9-203 Intermediate / Lower 33A277 0.23 0.16 Circumferential 0091 Single Arc 3922 2 2-203-A,B,C Intermediate Sheil A8746 0.16 0.10 Axial 124 Single Arc 3878 2 3-203-A,B,C Lower Shell 33A277 0.23 0.16 Axial 0091 Tandem Arc 3922 2 9-203 Intermediate / Lower 10137 0.21 0.06 i Circumferential 0091 Tandem Arc 3999 Table values from References [3,4]. WPQR = Welding Procedure Qualification Record i J i MElUJob # 95-34-15-0040 Page 13 of14
i-i } Referencec i 1. Letter from R.E. Denton (BG&E) to NRC Document Control Desk, dated February 16,1993, i " Response to NRC's Request for Additional Information Regarding Baltimore Gas & Electric i Company's Response to the 1991 Pressurized Thermal Shock (PTS) Rule, dated July 15,1992." 4 2. Letter from D.G. Mcdonald (NRC) to R.E. Denton (BG&E), dated May 24,1993, " Response to . the 1991 Pressurized Thermal Shock (PTS) Rule,10 CFR 50.61, Calvert Cliffs Nuclear Power Plant, Unit No. 2." 3. "The Reactor Vessel Group Records Evaluation Program Phase II Draft Report for the Calvert Cliffs 1 Reactor Pressure Vessel Plates, Forgings, Welds and Cladding," Combustion Engineering, l. B-PENG-ER-006, January 1995. j 4. "The Reactor Vessel Group Records Evaluation Program Phase 11 Draft Report for the Calvert P Cliffs 2 Reactor Pressure Vessel Plates, Forgings, Welds and Cladding," Combustion Engineering, ) B-PENG-ER-007, January 1995. 4 5. Peter, P.A.," Evaluation of Pressurized Thermal Shock for McGuire Unit 1," WCAP-13948, 3. ~ February 1994. - 6. Yanichko, S.E., et al.," Analysis of Capsule X from the Duke Power Company McGuire Unit I Reactor Vessel Radiation Surveillance Program," WCAP-12354, August 1989. r 7. " Reactor Vessel Weld Materials for Calvert Cliffs Unit i Supplemental Surveillance Program," i Combustion Engineering, CEN-612-P, November 1993. 8. Perrin, J.S., et al.," Evaluation of Mechanical Properties of Unirradiated Specimens from Pilgrim I Unit No.1," Battelle Columbus Laboratories, October,1979. 9. " Pilgrim Surveillance Program Weld Documentation," Combustion Engineering, Report No. B- [; PENG-ER-002, February 1994. i 10. " Reactor Vessel Weld Metal Chemical Composition Variability Study for Baltimore Gas & Electric Company," B&W Nuclear Technologies, BAW-2220, June 1995. 11. "Shoreham and Calvert Cliffs Units 1 and 2 Equivalent Welds," Combustion Engineering, B- ~ PENG-ER-004, July 1994. 12. Shoreham Drawings 234-235-5,234-237,234-485-2. 13. Letter from P.W. Kruse (CE) to E. Titland (BG&E), dated January 11,1982,"C-E Chattanooga Metallurgical Records Search." 14. Letter from J.D. Shiffer (PG&E) to S.A. Varga (NRC), dated January 17,1986," Pressurized Thermal Shock Information Pursuant to 10 CFR 50.61." 15. " Testing and Evaluation of Calvert Cliffs, Units 1 & 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples for the Baltimore Gas & Electric Company," Combustion Engineering, TR-ESS-001, January 31,1975. I 16. " Quantitative Evaluation of Chemical Composition Variability in Reactor Pressure Vessel Welds," Combustion Engineering, CE NPSD-944-P, January 1995. 17. Shogan, R.P., et al.," Analysis of Capsule X from the Alabama Power Company Joseph M. Farley Unit i Reactor Vessel Radiation Surveillance Program," Westinghouse Electric Corporation, WCAP-11563, September 1987. 18. " Baltimore Gas & Electric Unit 11 Reactor Vessel Master Index with Welding Procedures, PQR's, Weld Material Test Reports, and Base Material Test Reports," Combustion Engineering Contract No. 73167. 19. Letter from W.G. Counsil (Northeast Nuclear Energy Company) to J.R. Miller (NRC), dated January 4,1984, " Millstone Nuclear Power Station, Unit No. 2, Proposed Revisions to Technical j Specifications, Pressure-Temperature Limit Curves." 20. Norris, E.B.," Reactor Vessel Material Surveillance Program for Calveit Cliffs Unit 2 Analysis of 263' Capsule," Southwest Research Institute, SwRI Project 06-7524. 21. Calvert Cliffs Drawings; Document Nos.12140-07 and 13140-03. 1 4-MElUJob H 95-34-13-0040 Page 14 of14 P
ATTACIIMENT (3) BWNT REPORT BAW-2220, " REACTOR VESSEL WELD METAL CHEMICAL COMPOSITION VARIABILITY STUDY FOR BALTIMORE GAS AND ELECTRIC COMPANY," JUNE 1995 Baltimore Gas & Electric Company Docket Nos. 50-317 and 50-318 July 21,1995 .}}