ML030990293
| ML030990293 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/27/2003 |
| From: | Gresham J Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2005-0108 WCAP-16001, Rev 0 | |
| Download: ML030990293 (141) | |
Text
C-0 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Appendix C
C-1 Contained in Table C-1 are the upper shelf energy values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 4.1. The definition for Upper Shelf Energy (USE) is given in ASTM E185-82, Section 4.18, and reads as follows:
"uppershelfenergy level - the average energy value for all Charpy specimens (normally three) whose test temperature is above the upper end of the transition region For specimens tested in sets of three at each test temperature, the set having the highest average may be regarded as defining the upper shelf energy."
If there are specimens tested in set of three at each temperature Westinghouse reports the set having the highest average energy as the USE (usually unirradcated material). If the specimens were not tested in sets of three at each temperature Westinghouse reports the average of all 100% shear Charpy data as the USE.
Hence, the USE values reported in Table C-1 and used to generate the Charpy V-notch curves were determined utilizing this methodology.
The lower shelf energy values were fixed at 2.2 ft-lb for all cases.
Table C-I Upper Shelf Energy Values Fixed in CVGRAPH [ft-lb]
Material Unirradiated Capsule X Capsule V Capsule Y Lower Shell Plate C4339-1 128 122 121 111 (Longitudmal Orientation)
Lower Shell Plate C4339-1 104 94 94 94 (Transverse Orientation)
Weld Metal 91 71 60 58 (heat 4 0227)
HAZ Material 116 101 94 94 Correlation Monitor 123 103 102 100 Material Appendix C
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 090819 on 07-19-2002 Page 1 Coefficients of Curve 1 I A = 65.09 B = 62.9 C = 8957 T0 = 55.31 Equation is CVN = A + B
- I tanh((T - TO)/C) I Upper Shelf Energy: 128 Fixed Temp. at 30 ft-lbs: -L1 Temp. at 50 ft-Ibs 33.3 Lower Shelf Energy: 219 Fixed Material: PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: UNIRR Total Fluence 3007 --
U] 250-la
"-- 20f 1
tW 150 1007 U
0 0 0 111 -- - - -
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: PLATE SA533BI OrL LT H(lat I C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-40 11 15.58 -4 58
-40 9.5 15.58 -6.08
-40 25 15.58 941
-15 22 2386 -[86
-15 31 7.13
-15 21 2386 -2.86 10 38.5 35.74 275 10 43 35.74 725 10 37 35.74 125
- ,* Data continued on next page '*"
C-2
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: LT Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 40 57 54.45 254 40 50 54.45 -4.45 40 44.5 54.45 -9.95 75 84 78.7 529 75 79 78.7 29 75 76 7937 -2.7 110 96 9934 -334 110 965 99.34 -2.84 110 98 9234 -1.34 160 119 11692 2.07 160 119 116.92 a07 160 121 116.92 4.07 210 126 12414 185 210 129 12414 485 210 127.5 12414 o.35 JM of RESIDUALS =142 C-3
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at O9:O819 on 07-19-2002 Page 1 Coefficients of Curve 2 A = 609 B = 59.9 C = 78.88 TO = 10517 Equation is CVN = A + B I tanh((T - TO)/C) ]
Upper Shelf Energy: 122 Fixed Temp. at 30 ft-lbs 57.9 Temp. at 50 ft-lbs. 89 Lower Shelf Energy: 2.19 Fixed Material: PLATE SA533BI Heat Number C4339-1 Orientation: LT Capsule: X Total Fluence:
W 250'
.Q I
200 10 150 zM Vo 100 100-U-0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 OrL LT Heat ffC4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-25 10 6.45 3.54
-5 12 92 2.88 20 20 1459 5.4 75 41 4024 .75 90 46 50.71 -4.71 125 71 76.84 -5.84 155 102.5 95.59 6.9 215 120.5 115.03 5.46
- Data continued on next page *4 C4
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: X Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 300 120 12114 -114 345 124 121.72 227 SUI of RESIDUALS = 15.53 C-5
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 09f0819 on 07-19-2002 Page 1 Coefficients of Curve 3 A = 61.59 B = 59.4 C = 103.62 TO = 139.45 Equation is: CVN = A+ B I [ tanh((T - TO)/C) ]
Upper Shelf Energy- 121 Fixed Temp. at 30 ft-lbs: 78 Temp. at 50 ft-lbs 118.9 Lower Shelf Energy: 2.19 Fixed Material PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: V Total Fluence:
30--
I) 250 P-O 200F 0
s4 1500 CD '00 V7 5 - = r A
U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material PLATE SA53311 Ori LT Heat if C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0 11 9.74 125 50 20 2014 -14 75 39 28.78 10.21 76 27 2918 -2.18 100 38 40.01 -2.01 150 62 67.62 -5.62 200 89 92.83 -3.83 250 117 108.42 8S7
- "I Data continued on next page ***
C-6
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orienta tion' LT Capsule: V Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 350 138 118.99 19 425 109 120.52 -11.52 SiJM of RESIDUALS = 13.74 C-7
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09:08:19 on 07-19-2002 Page 1 Coefficients of Curve 4 l A = 56.59 B = 54.4 C = 10788 TO = 170.8 Equation is CVN = A + B * [ tanh((T - T0)/C) I Upper Shelf Energy: 111 Fixed Temp. at 30 ft-lbs: 113.1 Temp. at 50 ft-lbs 157.6 Lower Shelf Energy: 219 Fixed Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: LT Capsule: Y Total Fluence:
3007s-co~ 2507 M
la 2007 1507Y 5F 0 0 II - - _ _ _ _ _I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material PLATE SA533B1 Ori: LT Heat f: C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0 8 6.6 139 10 12 7.45 4.54 100 33 2527 7.72 125 37 34.79 22 175 52 58.71 -6.71 200 60 70.97 -10.97 250 100 90.63 936 em Data continued on next page **
C-8
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
Page 2 MateriaL PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 300 105 101.91 3.08 325 111 10509 59 350 116 10721 8.78 SUM of RESIDUALS = 25.33 C-9
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 10:02:49 on 07-11-2002 Page 1 Coefficients of Curve 1 A = 458 B = 44.8 C = 84.91 T0 = 47.81 Equation is LE = A+ B I [ tanh((T - TO)/C) I Upper Shelf L.E. 90.61 Temperature at LE 35: 26.9 Lower Shelf LE- I Fixed Material: PLATE SA533BI Heat Number C4339-1 Orientation: LT Capsule: UNIRR Total Fluence:
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degree s F Data Set(s) Plotted Plant: SU2 Cap: UNIRR Material: PLATE SA533BI QrL LT Heat #: C4339-1 Charpy V-Notch Data Tempera ture Input Lateral Expansion Computed LE Differential
-40 7 1L05 -4.05
-40 6 11.05 -5.05
-40 17 1105 5.94
-15 16 17.62 -1.62
-15 21 17.62 3.37
-15 14 17.62 -3.62 10 30 27.07 2.92 10 32 27.07 4.92 10 28 27.07 .92
- " Data continued on next page ~*
C-1O
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orientation- LT Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 40 43 41.69 1.3 40 39 41.69 -2.69 40 36 41.69 -5.69 75 65 59.68 531 75 62 59.68 2.31 75 58 59.68 -1.68 110 73 73.78 -.78 110 72 73.78 -1.78 110 72 73.78 -178 160 85 84.65 .34 160 84 84.65 -.65 160 86 84.65 L34 210 87 8869 -169 210 89 8869 .3 210 90 8869 L3 SUM of RESII )UAIS = -X1 C-lI
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 10:02.49 on 07-11-2002 Page 1 Coefficients of Curve 2 A = 46.41 B = 45.41 C = 97.66 TO = 93.94 Equation is LE = A + B I [ tanh((T - TO)/C) I Upper Shelf LE. 91.83 Temperature at L.E. 35: 68.8 Lower Shelf LE 1 Fixed Material: PLATE SA533BI Heat Number: C4339-1 Orientation: LT Capsule: X Total Fluence:
Ml
- _1-a)..
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533BI Ori: LT Heat ff: C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential
-25 11 831 2.68
-5 12 1L58 .41 20 195 17.37 2.12 75 37.5 37.71 -21 90 40 44.58 -4.58 125 595 60.39 -.89 155 74 7161 138 215 89 8481 4.18
'*** Data continued on next page **
C-12
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: LT Capsule: X Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 300 87.5 9052 -3.02 345 90.5 913 -.8 SUM of RESIDUALS = 2.29 C-13
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at lIH249 on 07-11-2002 Page 1 Coefficients of Curve 3 A 42.09 B = 4109 C = 93.82 TO = 116.71 Equation is: LE = A + B * [ tanh((T - TO)/C) I Upper Shelf LE: 83.19 Temperature at LE 35: 100.3 Lower Shelf L.E- 1 Fixed Material: PLATE SA533BI Heat Number. C4339-1 Orientation: LT Capsule: V Total Fluence n I ,
LUU CI)
+I. 4I. I- I. IIII 1tb X
4 100- .
"--i (z
-q Q) e ___
n ___ ___ ___ ___ ___ ___ ___ __ _ _ _ _ _ _ _
4-)
z 4 W 0
__=
,z UI I I _I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: PLATE SA533B1 Ori LT Heat I C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 0 6 7.3 -13 50 16 16.97 -.97 75 30.5 24.93 556 76 20 25.3 -53 100 38. 34.84 365 150 54 56.08 -208 200 665 71.28 -4.78 250 86 78.65 7.34
'** Data continued on next page *"*
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: LT Capsule V Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 350 89 8262 637 425 74.5 8307 -8.57 SUMI of RESIDUALS = -.09 C-15
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1002:49 on 07-11-2002 Page 1 Coefficients of Curve 4 A = 4037 B = 39.37 C = 118.31 TO = 177.77 Equation is: LE. = A + B t I tanh((T - TO)/C) I Upper Shelf LE. 79.75 Temperature at L.E. 35: 161.5 Lower Shelf L.E 1 Fixed Material: PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: Y Total Fluence:
201,rU r- I 1 1i 1i 1 1 WU
-4 I n II 5aq 1U l l I
In, 50 U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: PLATE SA533B1 OrL LT Heat #: C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 0 2 4.71 -2.71 10 4 5.36 -1.36 100 22 17.67 4.32 125 26 23.89 21 175 38 39.45 -1.45 200 40 47.68 -7.68 250 69 6L81 718 F** Data continued on next page ****
C-16
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Materi al: PLATE SA533B1 Heat Number C4339-1 Ori entation LT Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 300 74 7089 31 325 71 73.71 -271 350 74 75.68 -168 SUMl of RESIDUALS = -.89 C-17
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 10.30:09 on 07-11-2002 Page 1 Coefficients of Curve I A = 50 B = 50 C = 93.52 TO = 57.63 Equation is Shear/ = A + B I [ tanh((T - TO)/C) I Temperature at 50; Shear 57.6 Material PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: UNIRR Total Fluence 1007 8F
/0 607 C) 40F a) 00 0
0 20 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL PLATE SA533B1 Ori: LT Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-40 9 1L02 -2.02
-40 7 1L02 -4.02
-40 17 ML02 5.97
-15 17 17.46 -.46
-15 25 17.46 753
-15 18 17.46 .53 10 33 2652 6.47 10 33 2652 6.47 10 29 2652 2.47
- ' Data continued on next page ****
C-18
UNIRR LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orientati on- LT Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Difjferential 40 41 4068 .31 40 40 40.68 -.68 40 33 4068 -7.68 75 57 59.17 -2.17 75 55 59.17 -417 75 52 5917 -7.17 110 77 75.39 16 110 73 7539 -2.39 110 67 7539 -8.39 160 100 89.92 1007 160 100 89.92 1007 160 100 8992 1007 210 100 9629 37 210 100 9629 3.7 210 100 9629 3.7 SU)[M of RESIDUALS = 33.5 C-19
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 10.30f19 on 07-11-2002 Page 1
- Coefficients of Curve 2 A = 50 B = 50 C = 6L52 TO = 134.17 Equation is: Shear/. = A + B * [ tanh((T - TO)/C) I Temperature at 50z. Shear 1341 Material: PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: X Total Fluence:
Q.)
0C
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 Ori: LT Heat #: C4339-1 Charpy V-Notch . Data Temperature Input Percent Shear Computed Percent Shear Differential
-25 3 .56 2.43
-5 3 107 1.92 20 5 2.38 2.61 75 15 12.74 225 90 20 1921 .78 125 40 42.59 -2,59 155 65 66.3 -13 215 100 9325 6.74
- Data continued on next page **m C-20
CAPSULE X LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientat ion: LT Capsule: X Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 300 100 99.54 .45 345 100 9989 I SUN1of RESIDUALS = 13.42 C-21
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 10.3009 on 07-11-2002 Page 1 Coefficients of Curve 3 1 A = 50 B = 50 C = 120.87 T0 = 13L83 Equation is Shearx = A + B
- I tanh((T - TO)/C) I Temperature at 5P/. Shear 131.8 Material: PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: V Total Fluence:
C10 CID 0~
0 0-
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: PLATE SA533B1 OrL LT Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 0 15 10.14 4.85 50 20 2052 -52 75 30 2808 191 76 30 28.41 L58 100 40 37.12 2.87 150 45 57.45 -12.45 200 75 7554 -54 250 100 87.59 12.4 ar Data continued on next page "
C-22
CAPSULE V LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material:: PLATE SA533B1 Heat Number C4339-1 Orientat ion: LT Capsule: V Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 350 100 97.36 2.63 425 100 99.22 .77 SUMof RESIDUALS = 13.51 C-23
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 10.3009 on 07-11-2002 Page 1 Coefficients of Curve 4 A = 50 B = 50 C = 75.01 TO = 183.75 Equation is: Shear/ = A + B
- I tanh((T - To)/C) ]
Temperature at 50/. Shear 183.7 Material: PLATE SA533B1 Heat Number: C4339-1 Orientation: LT Capsule: Y Total Fluence:
10fF7-U) 6 r 0
a)
C) 40~
"I.'
4, I I UI I I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: Y Material: PLATE SA533B1 Ori: LT Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 0 2 .73 126 10 .96 403 100 15 9.68 5.31 125 20 17.27 2.72 175 45 44.19 .8 200 50 6066 -1066 250 95 85.4 9.59
"** Data continued on next page t***
C-24
CAPSULE Y LOWER SHELL PLATE C4339-1 (LONG)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: Y Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 300 100 95.68 431 325 100 97.73 226 350 100 98.82 1.17 SUM of RESIDUALS = 20.83 C-25
UNIRR LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 4.1 Hyperbolic Tangent Curve Prnted at 0924:33 on 07-19-2002 Page 1 Coefficients of Curve I A= 53.09 B = 50.9 C= 94.36 T0 = 57.65 Equation is CVN = A + B
- I tanh((T - T0)/C)
Upper Shelf Energy: 104 Fixed Temp. at 30 ft-lbs 114 Temp. at 50 ft-lbs 519 Lower Shelf Energy: 2.19 Fixed MateriaL PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: UNIRR Total Fluence:
3007 co 2507 2007 10 150-r-
zz4 a?.
CU L) 100- --
50 0F I _ I__ - - I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL PLATE SA533B1 OrL TL Heat F: C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-40 135 136 -1
-40 10 136 -3.6
-40 9 136 -4.6
-15 20 20.17 -17
-15 24 20.17 3.82
-15 24 20.17 3.82 10 33 29.37 3.62 10 32 29.37 2.62 10 31 29.37 L62
' Data continued on next page mx C-26
UNIRR LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 40 44.5 43.68 .81 40 46 43.68 2.31 40 41 43.68 -2.68 75 62 62.35 -.35 75 60.5 62.35 -185 75 57 62.35 -5.35 110 81 78.75 224 110 73 78.75 -5.75 110 72 78.75 -6.75 160 101 93.55 7.44 160 99 93.55 5.44 160 95 93.55 1.44 210 106 100.12 5.87 210 10L5 100.12 L37 210 105 100.12 4.87 SUM of RESIDUALS = 16.09 C-27
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 092433 on 07-19-2002 Page I Coefficients of Curve 2 A = 45.9 B = 45.9 C = 97.48 TO = 100.78 Equation is CVN = A + B I [ tanh((T - TO)/C) I Upper Shelf Energy: 94 Fixed Temp. at 30 ft-lbs 601 Temp. at 50 ft-lbs 104.8 Lower Shelf Energy 2.19 Fixed Material: PLATE SA533B1 Heat Number: C4339-1 Orientation: TL Capsule X Total Fluence:
3007-- . -- . -
MI 2507 20 0o z-- 1507-100 IG i 50f U i0 I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: X Material: PLATE SA533B1 OrL TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-25 9.5 866 .83
-5 11 11.6 -.6 20 245 16.9 7.59 75 32 36.23 -423 80 31.5 38.46 -6.96 90 485 43.04 5.45 155 70.5 71.28 -.78 215 9L5 85.95 5.54
- Data continued on next page C-28
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: X Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 300 89 92.48 -3.48 345 100 9339 6.6 SUM of RESIDUAIS = 9.96 C-29
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 0924:33 on 07-19-2002 Page 1 Coefficients of Curve 3 A= 48.09 B = 45.9 C = 106.92 TO = 119.64 Equation is CVN = A+ B * [ tanh((T - TO)/C) I Upper Shelf Energy: 94Fixed Temp. at 30 ft-lbs 75 Temp. at 50 ft-lbs 124 Lower Shelf Energy: 2.19 Fixed Material: PLATE SA533BI Heat Number C4339-1 Orientation: TL Capsule: V Total Fluence:
301Li r I 2507 Ul 200-FM a)
I~c z
W V7 50-
--2
- t >
U i
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap. V Material: PLATE SA533BI Ori: TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0 6 11.04 -5.04 50 19 21.81 -2.81 75 39 29.97 9.02 100 52 39.75 12.24 100 25 39.75 -14.75 150 62 60.79 12 200 69 7729 -829 250 93 86.62 6.37
- 1 Data continued on next page "**
C-30
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: V Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 350 99 92.78 621 425 89 9369 -4.69 SUM of RESIDUALS = -.55 C-31
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 0M2M.33 on 07-19-2002 Page 1 Coefficients of Curve 4 l A = 48.09 B = 45.9 C =12L77 TO = 169.04 Equation is CVN = A + B I I tanh((T - TO)/C) I Upper Shelf Energy- 94 Fixed Temp. at 30 ft-lbs 1182 Temp. at 50 ft-lbs: 174 Lower Shelf Energy: 2.19 Fixed MateriaL PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: Y Total Fluence
- 3007 co 2507
,0 "D-200 z 150 1007 .____=_
oU Iz
, I . I, ,
UI I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material PLATE SA533B1 OrL TL Heat L C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0 6 758 -158 10 11 847 2.52 100 28 24.54 3.45 125o 40 32.18 7.81 175 47 50.34 -334 200 46 59.52 -13.52 250 74 74.79 -.79
- Data continued on next page °~
C-32
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperatur e Input CVN Energy Computed CVN Energy Differential 300 95 84.42 10.57 325 95 87.42 757 350 93 8952 3.47 SUBI of RESIDUALS = 1616 C-33
UNIRR LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:0853 on 07-11-2002 Page 1 Coefficients of Curve 1 A = 41.98 B = 40.98 C = 9524 TO = 58.12 Equation is LE = A + B * [ tanh((T - TO)/C) ]
Upper Shelf LE 82.96 Temperature at LE. 35: 41.7 Lower Shelf LEw 1 Fixed MateriaL PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: UNIRR Total Fluence:
M P-4 a-.
P--
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL PLATE SA533B1 OrL TL Heat #: C4339-1 Charpy V-Notch Data Tempera ture Input Lateral Expansion Computed LE Differential
-40 8 1026 -226
-40 6 10.26 -4.26
-40 5 10.26 -5.26
-15 15 15.52 -.52
-15 18 15.52 2.47
-15 17 15.52 L47 10 24 2287 L12 10 27 22.87 4.12 10 25 22.87 212
- "* Data continued on next page '**'
C-34
UNIRR LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533BI Heat Number C4339-1 Orientation: TL Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 40 35 3427 .72 40 36 3427 172 40 32 3427 -227 75 50 4916 83 75 48 4916 -16 75 47 49.16 -2.16 110 65 6232 2.67 110 59 6232 -3.32 110 61 62.32 -1.32 160 80 74.32 5.67 160 75 74.32 .67 160 72 74.32 -2 32 210 83 79.72 3.27 210 77 79.72 -272 210 78 79.72 -172 SUtI of RESIDUALS =-2.45 C-35
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 14:08.53 on 07-11-2002 Page 1 Coefficients of Curve 2 l A = 37.23 B = 36.23 C = 109.95 TO = 7593 Equation is LE = A + B * [ tanh((T - TO)/C) I Upper Shelf LE. 73.46 Temperature at LE 35: 69.1 Lower Shelf LE. 1 Fixed Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: X Total Fluence:
2007 -
S) 151 100
"--.4 (Z
11-4 00 (L) 4..)
(Z 0
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant. SU2 Cap: X Material: PLATE SA533B1 OrL TL Heat I C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LK Differential
-25 14.5 10.6 3.53
-5 14 14.52 -52 20 225 20.24 225 75 33 3692 -3.92 80 315 38.57 -7.07 90 49 41.84 7.15 155 59 59.56 -.56 215 735 6811 5.38 ale Data continued on next page F***
C-36
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: X Total Fluence:
Charpy V-Notch Data (Continued)
Temperaturi eInput Lateral Expansion Computed LE. Differential 300 73 7225 .74 345 68.5 7292 -4.42 SUM of RESIDUALS = 2.56 C-37
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:08:53 on 07-11-2002 Page 1 Coefficients of Curve 3 A = 37.47 B = 36.47 C = 103.4 TO = 129.37 Equation is LE. = A + B * [ tanh((T - TO)/C) I Upper Shelf LLE 73.94 Temperature at LE 35: 122.3 Lower Shelf LE I Fixed Material: PLATE SA533BI Heat Number C4339-1 Orientation: TL Capsule: V Total Fluence 20i1U
-co IIII I I I
"-4 1007 50
,\
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: PLATE SA533B1 Ori TL Heat " C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 0 4 6.52 -2.52 50 13 13.92 -.92 75 29.5 1988 9.61 100 28 27.38 61 100 185 2738 -8.88 150 47 44.65 2.34 200 55 59.11 -411 250 7.5 67.49 5
'*11 Data continued on next page F***
C-3 8
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule V Total Fluence Charpy V-Notch Data (Continued)
Temperaturi e Input Lateral Expansion Computed LE. Differential 350 74 72.93 1.06 425 70 73.7 -3.7 SUM of RESIDUALS = -1.51 C-39
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 14:08:53 on 07-11-2002 Page 1 Coefficients of Curve 4 A = 39.01 B = 38.01 C = 131.42 TO = 192.48 Equation is: LE = A + B [ tanh((T - T0)/C) I t
Upper Shelf LE: 77.03 Temperature at LE. 35: 178.5 Lower Shelf LE I Fixed Material: PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: Y Total Fluence:
co P-a ).
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: PLATE SA533BI Orn: Th Heat ;: C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 0 0 4.85 -4.85 10 2 5.45 -3.45 100 19 15.95 3.04 125 27 21.05 5.94 175 33 3399 -.99 200 34 4119 -7.19 250 57 54.67 2.32 FFFF Data continued on next page FPFF C40
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: Y Total Eluence Charpy V-Notch Data (Continued)
Temperatur e Input Lateral Expansion Computed LE Differential 300 68 64.64 3.35 325 69 68.1 .89 350 68 7069 -2.69 SUM of RESIDUAIS = -3.62 C-41
UNIRR INTER LOWER PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1491:48 on 07-11-2002 Page 1 Coefficients of Curve 1 A = 50 B = 50 C= 89.35 TO = 7218 Equation is Shear/ = A+ B
- I tanh((T - TO)/C) I Temperature at 50z Shear: 721 MateriaL: PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: UNIRR Total Fluence:
a)
(E)
C.)
0) a)
a)
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: UNIRR MateriaL PLATE SA533BI OrL TL Heat #: C,4339-1 Charpy V-Notch Data Tempera ture Input Percent Shear Computed Percent Shear Differential
-40 9 75 L49
-40 5 75 -2.5
-40 5 7.5 -2.5
-15 18 1243 5.56
-15 18 1243 5.56
-15 18 1243 5.56 10 29 19.91 9.08 10 19.91 7.08 10 29 1991 9.08
'**' Data continued on next page
- C42
UNIRR LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number- C4339-1 Orientation: TL Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 40 29 32.72 -3.72 40 29 32.72 -3.72 40 29 32.72 -372 75 47 5157 -4.57 75 47 5157 -4.57 75 42 51.57 -9.57 110 71 69.97 1.02 110 62 69.97 -7.97 110 63 69.97 -697 160 100 87.71 1228 160 100 87.71 1228 160 100 87.71 1228 210 100 95.62 4.37 210 100 95.62 4.37 210 100 95.62 4.37 1 of RESIDUALS = 44.56 C-43
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1421:48 on 07-11-2002 Page 1 Coefficients of Curve 2 l A = 50 B = 50 C = 49.04 TO = 121.1 Equation is: Shear/. = A + B * { tanh((T - T%)/C) I Temperature at 50. Shear 121.1 Material PLATE SA533BI Heat Number C4339-1 Orientation: TL Capsule: X Total Fluence:
Ca) 0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 OrL TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-25 2 25 1.74
-5 5 .58 4.41 20 5 1.9 a4 75' 15 1323 1.76 80 15 15.75 -.75 90 20 2L95 -195 155 80 .79.93 .06 215 100 97.87 212
- Data continued on next page Gus C-44
CAPSULE X LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule: X Total Fluence:
Charpy V-Notch Data (Continued)
Temperatun Input Percent Shear Computed Percent Shear Differential 300 100 9993 .06 345 100 99.98 .01 SUM of RESIDUALS = 10.89 C-45
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1421:48 on 07-11-2002 Page 1 Coefficients of Curve 3 A = 50 B = 50 C = 93.53 TO = 175.78 Equation iS Shearz = A + B * [ tanh((T - TO)/C) I Temperature at 50/ Shear: 175.7 MateriaL PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: V Total Fluence I I I II 101r'i IF -
80Y 6Y 404 0) 201
.. I UI I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: V MateriaL PLATE SA533B1 Ori: TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 0 10 27 7.72 50 15 6.35 8.64 75 15 1038 4.61 100 20 1651 3.48 100 20 16.51 3.48 150 25 3655 -1L55 200 55 62.66 -7.66 250 100 83.01 1698
- " Data continued on next page ***"
C46
CAPSULE V LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number. C4339-1 Orientation: TL Capsule V Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 350 100 97.64 2.35 425 100 99.51 .48 SUM of RESIDUALS = 28.54 C-47
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:21:48 on 07-11-2002 Page 1 Coefficients of Curve 4 A = 50 B = 50 C = 73.84 TO = 196.87 Equation is Shear/ = A + B
- I tanh((T - TO)/C) I Temperature at 50/ Shear 196.8 Material: PLATE SA533B1 Heat Number C4339-1 Orientation: TL Capsule: Y Total Fluence:
100 - - _ _ __ - _ _ _ _ _ _ _
80-0 AA CID 0
60 /
0) 0-40(F 20
,I U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: Y Material: PLATE SA533BI Ori: TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 0 2 .48 1.51 10 5 62 4.37 100 15 6.76 823 125 20 1249 7.5 175 35 356 -.6 200 40 52.11 -lall 250 90 80.82 917 FFFF Data continued on next page **"
C-48
CAPSULE Y LOWER SHELL PLATE C4339-1 (TRANS)
Page 2 Material: PLATE SA533B1 Heat Number C4339-1 Orientationr TL Capsule Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 300 100 9423 5.76 325 100 96.98 3.01 350 100 98.44 1.55 SUM of RESIDUALS = 28.42 C49
UNIRRADIATED WELD CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 09.3L31 on 07-19-2002 Page 1 Coefficients of Curve 1 A = 46.59 B = 44.4 C = 91.49 T0 = 15.46 Equation is CVN = A + B * [ tanh((T - TO)/C) ]
Upper Shelf Energy: 91Fixed Temp. at 30 ft-lbs: -20.4 Temp. at 50 ft-lbs 22.4 Lower Shelf Energy: 219 Fixed MateriaL WELD Heat Number WYIRE HEAT 0227 Orientation:
Capsule: UNIRR Total Fluence:
> 200-
- - 150-100 5fY
-30 0 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted PlanLt SU2 Cap: UNIRR Material WELD Ori: Heat #: WIF REHEAT 0227 Charpy V-Notch IData Temperature Input CVN Energy Computed CVN Energy Differential
-100 7 8.78 -L78
-100 7 8.78 -1.78
-100 75 8.78 -128
-40 34 22,55 1L44
-40 15.5 22.55 -7.05
-40 24 22.55 L44
-20 29 302 -12
-20 31 30.2 .79
-20 275 302 -2.7 F** Data continued on next page ****
C-50
- UNIRRADIATED WELD Page 2 Material Iflu Heat Number. WIRE HEAT 0227 Orii mntation:
Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 10 35 43.94 -6.94 10 53 43.94 905 10 47 43.94 305 40 50 5822 -822 40 555 5822 -Z72 40 535 5822 -4.72 73 75 7134 365 73 81 7134 9.65 73 78 7134 6.65 210 86 89.75 -3.75 210 69.5 89.75 -2025 210 72 89.75 -17.75 300 91 90.82 .17 300 91 9082 17 300 91 90.82 17 St3Mof RESIDUALS =-35.92 C-51
CAPSULE X WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 093131 on 07-19-2002 Page 1 Coefficients of Curve 2 A = 36.59 B = 34.4 C = 81.74 TO = 9L04 Equation is CVN = A+ B * [ tanh((T - TO)/C) ]
Upper Shelf Energy 71 Fixed Temp. at 30 ft-lbs 75.1 Temp. at 50 ft-lbs 124.6 Lower Shelf Energy: 2.19 Fixed Material: WELD Heat Number WIRE HEAT 0227 Orientation:
Capsule: X Total Fluence:
300-CI 2507
"-P I
200 100 50 U
-300 -200 -100 0 100 200 300 400 500 600 1 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: X MateriaL: WELD Ori: Heat i. WIRE HEAT 0227 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-5 11.5 818 3.31 20 14 1248 1.51 80 32 31.7 .02 90 33 36.15 -315 125 47.5 5011 -2.61 155 64 59.09 4.9 215 71 67.83 3.16 345 70 70.86 -.86 SUM1 of RESIDUALS = 626 C-52
CAPSULE V WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09:3131 on 07-19-2002 Page 1 Coefficients of Curve 3 l A= 31.1 B = 28.89 C= 125.54 TO = 124.51 Equation is CVN = A + B
- I tanh((T - TO)/C) I Upper Shelf Energy: 60 Fixed Teir ip.at 30 ft-lbs 119.7 Temp. at 50 ft-lbs 222.7 Lower Shelf Energy: 2.2 Fixed Material: WELD Heat Number WIIRE HEAT 0227 Orientation:
Capsule: V Total Fluence:
300- -
2507 Il 209=
- .1 Pa) 1507 0 1007=
Oj 5I~~ _ I
.11 I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap- V Material: IELD Ori Heat FLWIRI IEHEAT 0227 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 50 20 15.71 428 100 24 25.52 -152 125 27 3121 -421 150 39 36.88 211 250 53 531 -1 350 64 58.45 5.54 425 62 59.52 2.47 SUM of RESIDUALS = 8.58 C-53
CAPSULE Y WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09:31:31 on 07-19-2002 Page 1 Coefficients of Curve 4 A = 301 B =27.9 C = 99.63 TO = 1582 Equation is CVN = A + B
- I tanh((T - T0)/C) I Upper Shelf Energy: 58 Fixed Temp. at 30 ft-lbs 157.8 Temp. at 50 ft-lbs 2472 Lower Shelf Energy: 22 Fixed Material WELD Heat Number: WIRE HEAT 0227 Orientation:
Capsule: Y Total Fluence U) 10
"--4 1
nq 200-150 100-50 >
-,In, U'
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: WELD OrL Heat I WIRE HEAT 0227 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 72 11 10.6 .39 100 18 15.43 .56 150 24 27.8 -3.8 175 39 34.75 424 200 36 41.16 -516 250 54 50.36 3.63 350 54 56.83 -2.83
- 11 Data continued on next page ***
C-54
CAPSULE Y WELD Page 2 Material: TFELD Heat Number WirIRE HEAT 0227 Orientation:
Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN EEnergy Differential 375 66 5729 8.7 SUM of RESIDUAIS = 7.73 C-55
UNIRRADIATED WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:56:32 on 07-11-2002 Page 1 Coefficients of Curve I A = 395 B = 385 C79.87 TO =7.5 Equation is LE = A + B * [ tanh((T - T0)/C) I Upper Shelf LE. 78 Temperature at LE. 35: -18 Lower Shelf LE: I Fixed MateriaL: WELD Heat Number: WIRE HEAT 0227 Orientation:
Capsule: UNIRR Total Fluence:
20 -_
co)
S-.15f 100 5 v 1 I I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: WELD Ori: Heat I WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE. Differential
-100 3 588 -2.88
-100 15 5.8 -.88
-100 5 5.88 -.88
-40 31 1897 12.02
-40 15 1897 -3.97
-40 20 18.97 L02
-20 25 26.74 -174
-20 29 26.74 2.25
-20 25 26.74 -174
- Data continued on next page Ad C-56
UNIRRADIATED WELD Page 2 Material: MELD Heat Number. WYIRE HEAT 0227 Orientation:
Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 10 33 40.7 -7.7 10 47 40.7 629 10 40 407 -.7 40 50 54.36 -4.36 40 51 5436 -3.36 40 51 5436 -3.36 73 68 65.49 25 73 72 65.49 6.5 73 71 65.49 5.5 210 80 77.52 2.47 210 66 77.52 -11.52 210 70 77.52 -7.52 300 83 77.95 5.04 300 81 77.95 304 300 82 77.95 4.04 SUMI of RESIDUAIS = 0 C-57
CAPSULE X WELD CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 145632 on 07-11-2002 Page 1 Coefficients of Curve 2 A = 4022 B = 3922 C= 89.74 TO = 9902 Equation is LE. = A + B * [ tanh((T - TO)/C) I Upper Shelf L.E: 79.44 Temperature at LE 35: 86.9 Lower Shelf LE. 1 Fixed Material: WELD Heat Number. WIRE HEAT 0227 Orientation:
Capsule X Total Fluence
"-4 a)
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: WELD Or: Heat i WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential
-5 10.5 8.03 2.46 20 17 12.5 4.49 80 35 32.03 296 90 32 36.29 -429 125 43.5 5127 -7.77 155 65.5 6L94 3.55 215 86 7394 1205 345 70 7912 -912 SUM of RESIDUALS = 4.35 C-58
CAPSULE V WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14-56.32 on 07-11-2002 Page 1 Coefficients of Curve 3 l A = 28.85 B = 27.85 C = 133.08 TO = 135.46 Equation is LE = A + B * [ tanh((T - TO)/C) I Upper Shelf LE- 56.71 Temperature at LE 35: 165.3 Lower Shelf LEz I Fixed MateriaL WELD Heat Number. WIRE HEAT 0227 Orientation:
Capsule: V Total Fluence:
r -
- Uu I. 4 4 4 - 4-150 P.5q 100 0)
&- I D I
^
5-. .. ._ _
U I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: WELD Ori: Heat #: WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 50 16 13.07 2.92 100 17.5 21.6 -41 125 285 26.66 183 150 31.5 3188 -38 250 49 48.25 .74 350 55 5457 .42 425 55 56 -1 SUM of RESIDUALS = .42 C-59
CAPSULE Y WELD CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 14:652 on 07-11-2002 Page 1 Coefficients of Curve 4 A= 23.68 B = 2268 C = 92.31 T0 = 167.81 Equation is LE = A+ B * [ tanh((T - TO)/C) I Upper Shelf L.E 46.37 Temperature at L.E. 35: 218.3 Lower Shelf L.E I Fixed Material: WELD Heat NumberIWIRE HEAT 0227 Orientation:
Capsule: Y Total Fluence 150 P..E X
100
- 4 50-m- - 'In, z
, lI U
-300 -200 -100 0 100 200 300 400 500 600 1 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y MateriaL WELD Ori: Heat P WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE. Differential 72 4 6.05 -2.05 100 13 9.48 351 150 15 1936 -4.36 175 31 25.45 5.54 200 27 3129 -429 250 43 39.83 316 350 40 45.51 -5.51
- '* Data continued on next page ****
C-60
CAPSULE Y WELD Page 2 Material: WELD Heat Number. WIRE HEAT 0227 Orientation:
Capsule Y Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 375 50 45.87 412 SUAM of RESIDUALS = 13 C-61
UNIRRADIATED WELD CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 15017:3 on 07-11-2002 Page 1 Coefficients of Curve I I A = 50 B = 50 C = 73.51 TO = -6.56 Equation is: Shear/. = A + B * [ tanh((T - TO)/C) I Temperature at 50/ Shear -6.5 Material: WELD Heat Number WIRE HEAT 0227 Orientation:
Capsule: UNIRR Total Fluence l lI- I 101In Li I
80 C:
6 ~00 60 4 0 C) 00 0-2f 0 0
I2fFI0 U'0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: WELD Ork Heat I WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-100 5 729 -229
-100 9 729 1.7
-100 9 729 1.7
-40 33 2a, 429
-40 17 28.7 -11.7
-40 37 287 829
-20 33 4096 -7.96
-20 53 40.96 1203
-20 47 4096 6.03 ads Data continued on next page **"
C-62
. UNIRRADIATED WELD Page 2 Material WELD Heat Number. WIRE HEAT 0227 Orientation:
Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 10 47 61.07 -14.07 10 68 6LO7 6.92 10 58 61.07 -307 40 74 78.01 -4.01 40 74 78.01 -4.01 40 68 78.01 -10.01 73 100 89.7 1029 73 100 89.7 10.29 73 100 89.7 10.29 210 100 99.72 27 210 100 99.72 .27 210 100 9972 .27 300 100 99.97 .02 300 100 99.97 .02 300 100 99.97 .02 SUM of RESIDUAL'3 = 15.61 C-63
CAPSULE X WELD CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 15:0713 on 07-11-2002 Page 1 Coefficients of Curve 2 A= 50 B = 50 C = 68.85 TO =1179 Equation is Shearx = A + B * [ tanh((T - TO)/C) I Temperature at 50/ Shear 112.7 Material: WELD Heat Number WIRE HEAT 0227 Orientation:
Capsule: X Total Fluence:
Cd C.)
0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: WELD OrL Heat 11WIREEHEAT 0227 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-5 10 316 6.83 20 15 632 8.67 80 30 2783 2.16 90 35 34.02 .97 125 40 58.77 -18.77 155 95 77.31 1768 215 98 95.11 2.88 345 100 9988 .11 SUM of RESIDUAL'S= 20.56 C-64
CAPSULE V WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15)0713 on 07-11-2002 Page 1 Coefficients of Curve 3 l A= 50 B = 50 C = 100.78 TO = 14619 Equation is Shear/ = A + B * [ tanh((T - TO)/C) I Temperature at 50P Shear 146.1 Material WELD Heat Number. 'IRE HEAT 0227 Orientation:
Capsule: V Total fluence:
0 a-)
C) 0H
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material WELD OriL Heat I WIRE HEAT 0227 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 50 25 MI9 12.08 100 30 28.56 1.43 125 35 39.63 -4.63 150 45 51.88 -6.88 250 100 88.69 11.3 350 100 9827 1.72 425 100 99.6 .39 SUM of RESIDUALS = 15.41 C-65
CAPSULE Y WELD CVGRAPH 41 Hyperbolic Tangent Curve Printed at 15:07:13 on 07-11-2002 Page 1 Coefficients of Curve 4 l A = 50 B = 50 C = 69.41 T0 = 174.029 Equation is Shear. = A + B r [ tanh((T - TO)/C) I Temperature at 50z. Shear 174 Material WELD Heat Number WIRE HEAT 0227 Orientation:
Capsule: Y Total Fluence:
U 00n r0
-300 -200 -100 0 100 21DO 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: WELD OrL Heat A lYIRE HEAT 0227 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 72 5 5.02 -02 100 15 10.59 44 150 25 33.35 -835 175 65 50.7 1429 200 55 67.88 -1288 250 98 89.92 8.07 350 100 9937 62
- Data continued on next page "**
C-66
CAPSULE Y WELD Page 2 Material: IELD Heat Number. WIRE HEAT 0227 Orientation-Capsule Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Inpu t Percent Shear Computed Percent Shear Differential 375 100 99.69 .3 SUM of RESIDUALS = 6.44 C-67
UNIRRADIATED HEAT AFFECTED ZONE CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 09:3911 on 07-19-2002 Page 1 Coefficients of Curve I A = 59.09 B = 569 C = 116.82 TO = 1312 Equation is CVN = A+ B
- I tanh((T - TO)/C) I Upper Shelf Energy: 116 Fixed Temp. at 30 ft-lbs -52.8 Temp. at 50 ft-lbs: -5.7 Lower Shelf Energy- 219 Fixed Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: UNIRR Total Fluence:
30 - - -
co 2567
~- 15(
0 0 10(
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL HEAT AFFD ZONE Ori Heat I C433 9-1 SIDE OF WELD Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-100 165 1653 -.03
-100 16 16.53 -.53
-100 10 16.53 -6 53
-70 215 2429 -2.79
-70 19 2429 -529
-70 26 24.29 L7
-40 23 34.87 -1187
-40 38 34.87 312
-40 68 34.87 3312 11 Data continued on next page Gus C-68
UNIRRADIATED HEAT AFFECTED ZONE Page 2 Material: HEAT AFFD ZONE Heat Number. C4339-1 SIDE OF WELD Orientation:
Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 10 50 57.57 -7.57 10 50 57.57 -7.57 10 74 57.57 16.42 40 665 71.96 -5.46 40 54 71.96 -17.96 40 50 71.96 -21.96 73 100.5 85.95 14.54 73 97.5 85.95 1154 73 96 85.95 10.04 210 114 11=21 178 210 104 11221 -821 210 130 11221 17.78 300 120 115.16 483 300 100 11516 -1516 300 83 115.16 -3216 SUM of RESIDUALS =-2826 C-69
CAPSULE X HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09.3911 on 07-19-2002 Page 1 Coefficients of Curve 2 A = 51.59 B = 49.4 C = 62.37 TO = 5.62 Equation is: CVN = A + B I [ tanh((T - TO)/C) I Upper Shelf Energy: 101 Fixed Temp. at 30 ft-lbs: -236 Temp. at 50 ft-lbs 36 Lower Shelf Energy: 2.19 Fixed Material HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: X Total Fluence 2507 200 bH 150 V-. 4f%-"I - 0 __________
z 1UU 0 51I-Li
/ 4 I
- 1 i III U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: HEAT AFFD ZONE OrL Heat I/. C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input CVN Energy Computed CYN Energy Differential
-50 18 16.41 158
-25 24 29.12 -5.12
-25 31 2912 1.87
-5 45.5 4326 223 20 635 62.78 .71 90 92 94.8 -2.8 155 107 10018 6.81 215 95 100.88 -5.88 SUM of RESIDUALS = -.58 C-70
CAPSULE V HEAT AFFECTED ZONE CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at O9.39R on 07-19-2002 Page 1 Coefficients of Curve 3 l A = 48.09 B = 45.9 C = 152.25 TO = 61.87 Equation is: CVN = A + B
- I tanh((T - TO)/C) I Upper Shelf Energy: 94 Fixed Temp. at 30 ft-lbs -1.6 Temp. at 50 ft-lbs 681 Lower Shelf Energy. 2.19 Fixed Material: HEAT AFFD ZONE Heat Number- C4339-1 SIDE OF WELD - Orientation:
Capsule V Total Fluence:
300-Cin 250W
.1 200- _=
- 15=
CD) rOW
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: HEAT AFFD ZONE OriL Heat #: C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-50 20 19.36 .63 0 28 30.4 -2.4 25 33 3719 -419 75 62 52.04 9.95 150 69 72.05 -3.05 200 76 8113 -5.13 250 85 86.84 -1.84 350 103 9196 11.03 SUM of RESIDUALS = 4.98 C-71
CAPSULE Y HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09.39.ll on 07-19-2002 Page 1 Coefficients of Curve 4 A = 48.09 B = 45.9 C = 15L59 T0 = 13828 Equation is CVN = A + B
- I tanh((T - T0)/C) I Upper Shelf Energy: 94 Fixed Temp. at 30 ft-lbs 75 Temp. at 50 ft-lbs 1445 Lower Shelf Energy: 219 Fixed Material: HEAT AFFD ZONE Heat Number. C4339-1 SIDE OF WELD - Orientation:
Capsule: Y Total Fluence:
c) 0 a)
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: HEAT AFFD ZONE OrL Heat # C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-50 18 926 8.73
-25 25 1L74 1325 0 12 14.95 -2.95 100 32 36.74 -4.74 150 44 5R64 -7.64 200 66 65.81 .18 300 95 8428 10.71
'** Data continued on next page '*"
C-72
CAPSULE Y HEAT AFFECTED ZONE Page 2 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 325 93 86.79 62 SUM of RESIDUALS =23.75 C-73
UNIRRADIATED HEAT AFFECTED ZONE CYGRAPH 4.1 Hyperbolic Tangent Curve Printed at 14:1216 on 07-12-2002 Page 1 Coefficients of Curve 1 l A = 39.92 B = 38.92 C = 10558 TO = 4.68 Equation is: LK = A + B * [ tanh((T - T0)/C) I Upper Shelf LE- 7884 Temperature at LSE 35: -8.7 Lower Shelf LE I Fixed Material: HEAT AFFD ZONE Heat Number- C4339-1 SIDE OF WELD Orientation:
Capsule: UNIRR Total Fluence:
2007- -
150
~4 100
- _4 a) rr-r-O I I I I
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material HEAT AFFD ZONE Ori Heat #: C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input Lateral Expansion Computed LU Differential
-100 8 10.41 -2.41
-100 8 10.41 -2.41
-100 4 10.41 -6.41
-70 16 16.21 -21
-70 12 16.21 -421
-70 20 16.21 378
-40 18 2436 -636
-40 25 24.36 .63
-40 45 24.36 20.63
- Data continued on next page **FF C-74
UNIRRADIATED HEAT AFFECTED ZONE Page 2 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE. Differential 10 38 41.87 -3.87 10 40 4187 -187 10 52 41.87 1012 40 50 5247 -2.47 40 42 52.47 -1047 40 40 5247 -1247 73 69 6209 6.9 73 67 6209 4.9 73 66 6209 39 210 80 7727 2.72 210 75 7727 -2.27 210 84 7727 672 300 80 7855 .44 300 78 7855 -.55 300 70 7855 -855 SUM of RESIDUALS = -2.81 C-75
CAPSULE X HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:1216 on 07-12-2002 Page 1 Coefficients of Curve 2 A = 40.77 B = 39.77 C = 81.58 TO = 75 Equation is LE = A + B I [ tanh((T - TO)/C) I Upper Shelf LE 80.55 Temperature at LE 35: -4.4 Lower Shelf LE. 1 Fixed MateriaL HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: X Total Fluence 2007-.
p--CI)..
150 100 0
50 0*~~
~ - -- -
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: X Material: HEAT AFFD ZONE OrL Heat I C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential
-50 17 16.61 .38
-25 21 25.71 -4.71
-25 25 25.71 -.71
-5 40 34.72 527 20 47 46.82 .17 90 67.5 7125 -3.75 155 82 A8.46 353 215 79 80.06 -1.06 SUM of RESIDUALS = -.89 C-76
CAPSULE V HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:1216 on 07-12-2002 Page 1 Coefficients of Curve 3 A = 36.07 B = 35.07 C = 139.98 TO = 5625 Equation is LE = A + B I tanh((T - TO)/C) ]
Upper Shelf LE. 7115 Temperature at LE 35: 519 Lower Shelf LE. I Fixed Material: HEAT AFFD ZONE Heat Number. C4339-1 SIDE OF WELD Orientation:
Capsule V Total Fluence:
c) r---
CD Cd
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: HEAT AFFD ZONE OrL Heat #: C4339-1 SIDE OF 'WELD Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential
-50 17.5 13.6 3.89 0 14 22.69 -8.69 25 24.5 2837 -3.87 75 55 40.74 1425 150 51 56.58 -5.58 200 60 6317 -317 250 645 67 -2.5 350 75 70.11 4.88 SUM of RESIDUALS = -.8 C-77
CAPSULE Y HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 14:12:16 on 07-12-2002 Page 1 Coefficients of Curve 4 A= 39.04 B = 38.04 C = 169.94 TO = 162.17 Equation is: LE. = A+ B * [ tanh((T - T0)/C) I Upper Shelf LE 77.08 Temperature at LE 35: 144 Lower Shelf LE- 1 Fixed Material HEAT AFF'D ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: Y Total Fluence:
2f007S -
- _ 1507-
"C-
. H 50XL V
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: HEAT AFFD ZONE Ori: Heat A CC4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential
-50 7 6.78 21
-25 12 8.57 3.42 0 7 10.82 -3.82 100 27 25.71 128 150 35 3622 -L32 200 48 47.37 .62 300 66 6454 L45
- 11 Data continued on next page -
C-78
CAPSULE Y HEAT AFFECTED ZONE Page 2 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 325 66 67.32 -1932 SUM of RESIDUALS = .53 C-79
UNIRRADIATED HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 142032 on 07-12-2002 Page 1 Coefficients of Curve I A= 50 B = 50 C = 101.97 TO = -3.95 Equation is Shearx = A + B * [ tanh((T - T0)/C) I Temperature at 50z Shear -3.9 MateriaL HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule: UNIRR Total Fluence:
a) a)
4-H C)
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material HEAT AFFD ZONE Orh Heat : C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-100 17 1319 38
-100 13 13.19 -.19
-100 13 13.19 -.19
-70 23 21.49 15
-70 23 21.49 1.5
-70 27 2149 55
-40 23 33.02 -10.02
-40 33 33.02 -.02
-40 43 33.02 9.97
- F'* Data continued on next page F**
C-80
UNIRRADIATED HEAT AFFECTED ZONE Page 2 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Orientation:
Capsule UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 10 53 56.79 -3.79 10 53 56.79 -3.79 10 58 56.79 12 40 68 703 -2.3 40 58 70.3 -12.3 40 61 70.3 -9.3 73 96 81.89 141 73 91 8189 91 73 90 8189 8.1 210 100 98.51 L48 210 100 9851 1.48 210 100 9851 1.48 300 100 99.74 25 300 100 9974 .25 300 100 99.74 25 Afof RESIDUAL.S =1804 C-81
CAPSULE X HEAT AFFECTED ZONE CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1420.32 on 07-12-2002 Page 1 Coefficients of Curve 2 A = 50 B = 50 C = 75.03 TO = 31.37 Equation is Shear/ = A+ B
- I tanh((T - TO)/C) I Temperature at 50/ Shear: 313 Material: HEAT AFFI) ZONE Heat Number C4339-1 SIDE OF WYELDOrientation:
Capsule: X Total Fluence:
-4 U LI 0
Cn 6 0F' 4-
~- 4 2
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted PlantL SU2 Cap. X Material: HEAT AFFD ZONE Ori Heat # C4339-1 SIDE OF WELD Charpy V-Notch Data Tempera ture Input Percent Shear Computed Percent Shear Differential
-50 5 1025 -525
-25 10 182 -8.2
-25 25 182 6.79
-5 35 27.49 7.5 20 40 42.47 -2.47 90 80 8267 -2.67 155 100 96.42 3.57 215 100 9925 .74 SUMI of RESIDUALS .01 C-82
CAPSULE V HEAT AFFECTED ZONE CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1420.32 on 07-12-2002 Page 1 Coefficients of Curve 3 l A= 50 B = 50 C = 156.16 TO = 9L4 I Equation is: Shear/. = A + B I[ tanh((T - TO)/C) I Temperature at 50z Shear 91.4 Material: HEAT AFF'D ZONE Heat Number. C4339-1 SIDE OF WELD Orientation:
Capsule: V Total Fluence CL) 0
-300 -200 -100 0 100 200 300 400 500 600 1 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: HEAT AFFD ZONE OrL Heat # C4339-1 SIDE OF MELD Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-50 25 1405 10.94 0 25 23.67 L32 25 35 29.93 5.06 75 35 44.76 -9.76 150 50 67.92 -17.92 200 95 80.07 14.92 250 100 88.4 1159 350 100 96.48 3.51 SUM of RESIDUALS = 1969 C-83
CAPSULE Y HEAT AFFECTED ZONE CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1420-32 on 07-12-2002 Page 1 Coefficients of Curve 4 A= 50 B = 50 C = 17018 TO =82.96 Equation is Shear/. = A + B [ tanh((T - TO)/C) I Temperature at 50x Shear 82.9 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD - Orientation:
Capsule: Y Total Fluence:
1007 80-60 < A 0U C-)
0.. 4/
20) p p p
- U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: HEAT AFFD ZONE Ori: Heat #: C4339-1 SIDE OF WIELD Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-50 15 17.32 -2.32
-25 20 21.94 -1.94 0 35 2738 7.61 100 55 54.98 .01 150 65 68.73 -3.73 200 75 79.82 -4.82 300 100 92.76 7.23
" Data continued on next page ****
C-84
CAPSULE Y HEAT AFFECTED ZONE Page 2 MateriaL HEAT AFFD ZONE Heat Number: C4339-1 SIDE OF WELD Orientation:
Capsule Y Total Fluence Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 325 100 945 5.49 SUM of RESIDUAIS = 7.53 C-85
UNIRRADIATED CORRELATION MONITOR MATERIAL CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 09.48:20 on 07-19-2002 Page 1 Coefficients of Curve I I A = 62.59 B = 60.4 C = 8125 TO = 95.5 Equation is CVN = A + B * [ tanh((T - TO)/C)
Upper Shelf Energy: 123 Fixed Temp. at 30 ft-lbs 46.4 Temp. at 50 ft-lbs 783 Lower Shelf Energy: 219 Fixed Material: SRM SA533B1 Heat Number: HOT PLATE 02 Orientation: LT Capsule: UNIRR Total Fluence:
rirri1 '1 6uu
,+r 4 4 - .I Qr IC 1 I I 201J 4 4- + 4- -4. 4 1 IO I1007 I/o 501 I II U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR Material SRI SA533BI Ori: LT Heat 1I HSST PLATE 09 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential
-50 3 547 -2.47
-50 5 5.47 -.47
-50 5 5.47 -.47
-20 6 884 -2.84
-20 6.5 8.84 -2.34
-20 9 8.84 15 10 13.5 1532 -L82 10 12 1532 -332 10 14.5 1532 -.82
- Data continued on next page '*
C-86
UNIRRADIATED CORRELATION MONITOR MATERIAL Page 2 Material: SEM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input CYN Energy Computed CVN Energy Differential 40 35 26.74 825 40 22 26.74 -4.74 40 36 26.74 925 85 415 54.83 -13.33 85 52 54B3 -2.83 85 58.5 54.83 3.66 110 63.5 7325 -9.75 110 82.5 7325 924 110 85.5 7325 1224 160 109 102.49 65 160 108.5 102.49 6 160 81 102.49 -2L49 210 117 11619 .8 210 115 116.19 -L19 210 121 116.19 4.8 300 127 12221 4.78 300 1175 12221 -4.71 300 125 12221 2.78 Al of RESIDUALS = -417 C-87
CAPSULE X CORRELATION MONITOR MATERIAL CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 09:48:20 on 07-19-2002 Page 1 Coefficients of Curve 2 A=52.59 B = 50.4 C = 7414 T0 = 144.43 Equation is CVN = A + B * [ tanh((T - T0)/C) I Upper Shelf Energy: 103 Fixed Temp. at 30 ft-lbs 108.6 Temp. at 50 ft-lbs 1'10.6 Lower Shelf Energy: 219 Fixed Material SRM SA533B1 Heat Number: HSST PLATE 02 Orientation: LT Capsule X Total Fluence:
3007- S- _ _ _ _
250ff W
5.
15ff V--
0 1507_
10 0rI I I I I/
-30(O -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: SRM SA533B1 Ori: LT Heat ifHSST PLATE 02 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 20 4.5 5.59 -[09 80 24 1727 6.72 90 165 2107 -457 125 41 39.68 L31 155 575 59.73 -2.23 215 89 8992 -.92 300 117 1OL5 15.49 345 104 102.55 144 SUM of RESIDUAM£.S = 16.15 C-88
CAPSULE V CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09.4820 on 07-19-2002 Page 1 Coefficients of Curve 3 A = 5209 B = 49.9 C = 88.08 TO = 204.91 Equation is CVN = A + B
- I tanh((T - TO)/C) I Upper Shelf Energy: 102 Fixed Temp. at 30 ft-lbs 162.9 Temp. at 50 ft-lbs 2012 Lower Shelf Energy: 2.19 Fixed Material: SRM SA533B1 Heat Number. HSST PLATE 02 Orientation: LT Capsule: V Total Fluence:
3007- S -
250_
In 7
Pr-,
200 1507 V5H 10 500
- I U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: SRM SA533B1 Ori: LT Heat #: HSST PLATE 02 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 75 12 716 4.83 125 25 1618 8.81 150 32 24.48 7.51 175 32 35.77 -3.77 200 31 49.32 -18.32 250 89 75.62 13.37 350 103 98.43 4.56 425 100 10L33 -1.33 SUMI of RESIDUALS = 15.68 C-89
CAPSULE Y CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 09:4820 on 07-19-2002 Page 1 Coefficients of Curve 4 l A = 51.09 B = 489 C = 86.41 TO = 234.37 Equation is CVN = A+ B * [ tanh((T - TO)/C) I Upper Shelf Energy 100 Fixed Temp. at 30 ft-lbs 194.4 Temp. at 50 ft-lbs. 232.4 Lower Shelf Energy 2.19 Fixed Material SRM SA533M1 Heat Number: HSST PLATE 02 Orientation: LT Capsule Y Total Fluence nnr , i,..
%3uu
- 9) 250-
"n
"--4 1
-i- -3 P:q 20.
150 100 V
C.)
507 /
u'
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant S12 Cap: Y Material: SRM SA533B1 OrL LT Heat I HSST PLATE 02 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 72 7 4.42 2.57 125 25 9.4 15.59 175 22 21.95 .04 200 34 32.61 L38 225 32 45.81 -13.81 250 65 59.84 5.15 325 93 893 3.69
" Data continued on next page ado C-90
CAPSULE Y CORRELATION MONITOR MATERIAL Page 2 Material SPMI SA533B1 Heat Number. HSST PLATE 02 Orientation: LT Capsule: Y Total Fluence Charpy V-Notch Data (Continued)
Temperature Input CVN Energy Computed CVN Energy Differential 375 107 96.36 10.63 SUW of RESIDUALS = 2526 C-91
UNIRRADIATED CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at ILI03:00 on 07-15-2002 Page 1 Coefficients of Curve 1 A = 43.65 B = 42.65 C = 84.08 TO = 7627 Equation is LE = A+ B I tanh((T - TO)/C) ]
Upper Shelf LE 86.31 Temperature at LE 35: 58.9 Lower Shelf LE. I Fixed Material: SRM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: UNIRR Total Fluence:
20iLU r I I I I I M I I + I P-4 X 4 L _________
+ 4. ________
10 1)
UI WiI I !
"5- 0 0 0 W-C) 4-50-0 1 - _ -
n.
u
.~
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL SRM SA533B1 OrL LT Heat #: HSST PLATE 02 Charpy V-Notch Data Temperatur e Input Lateral Expansion Computed LE Differential
-50 4 5.03 -1.03
-50 3 5.03 -2.03
-50 5 5.03 -.03
-20 9 8.84 .15
-20 6 8.84 -264
-20 10 8B4 115 10 14 15.61 -L61 10 15 15.61 -.61 10 14 15.61 -1.61 Data continued on next page F*F C-92
UNIRRADIATED CORRELATION MONITOR MATERIAL Page 2 Material: SP.M SA533BI Heat Number ESST PLATE 02 Orientation: LT Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 40 32 26.31 5.68 40 23 2631 -3.31 40 32 26.31 5.68 85 42 48.06 -6.06 85 45 4806 -3.06 85 51 4806 2.93 110 54 59.9 -5.9 110 60 59. .09 110 71 59. 11.09 160 79 76.07 2.92 160 72 76.07 -4.07 160 69 76.07 -7.07 210 84 82.91 1.08 210 88 8291 5.08 210 87 82.91 4.08 300 84 85.9 -1.9 300 83 85.9 -2.9 300 87 85.9 1.09 SUM of RESIDUALS = -3.03 C-93
CAPSULE X CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1103.:00 on 07-15-2002 Page 1 Coefficients of Curve 2 A = 43.97 B = 42.97 C = 8038 TO = 130.66 Equation is LE. = A + B * [ tanh((T - T0)/C) I Upper Shelf LE: 86.95 Temperature at LE 35: 113.6 Lower Shelf LE. 1 Fixed Material: SRM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: X Total Fluence:
2007 U]
p-q 15 A
r 100 5W 0
50 U
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: SRM SA533B1 OrL ILT Heat . HSST PLATE 02 Charpy V-Notch Data Temperature Input Lateral Expansion Co] nputed L. Differential 20 5 614 -L14 80 25 19.98 5.01 90 22.5 23.91 -1.41 125 38 40.95 -a95 155 57 56.6 .39 215 79 7h56 1.43 300 89 85.7 329 345 825 86.54 -4.04 SUM of RESIDUAL' S=.56 C-94
CAPSULE V CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1103:00 on 07-15-2002 Page 1 Coefficients of Curve 3 A = 4375 B = 42.75 C = 121.68 TO = 213.75 Equation is: LE = A + B
- I tanh((T - T0)/C) I Upper Shelf L.E. 865 Temperature at LE 35: 188.4 Lower Shelf LE- 1 Fixed Material: SRMI SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: V Total Fluence:
2000 - _ =
U)
P-4
. P..j 150 X
W 100
"--4 (Z
- ..q 0) 4-)
ct
-4
/
0 la
. 1 +
U- I 2
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap- V Material SR1PSA533B1 Ori: LT Heat / HEST PLATE 02 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 75 17 8.93 806 125 19.5 1713 2.36 150 22 232 -12 175 28 30.58 -2.58 200 32.5 3894 -6.44 250 62 5612 5.87 350 81 7827 2.72 425 81 83.93 -2.93 SUM of RESIDUALS = 5.87 C-95
CAPSULE Y CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 11:03.00 on 07-15-2002 Page 1 Coefficients of Curve 4 l A = 39.52 B = 3852 C = 100.86 TO = 247.5 Equation is LE = A + B
- I tanh((T - TO)/C) I Upper Shelf LE- 78.05 Temperature at LE 35: 2355 Lower Shelf LE. I Fixed Material: SRM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: Y Total Fluence:
.C, Cd
-300 -200 -100 0 0oo 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: Y Materiah SRM SA533BI Ori: LT Heat L HSST PLATE 02 Charpy V-Notch Data Temperature Input Lateral Expansion Computed LE Differential 72 0 3.3 -33 125 15 724 7.75 175 15 15.78 -.78 200 25 22.61 2.38 225 23 31.07 -8.07 250 43 40.47 252 325 69 64.41 4.58 em Data continued on next page ***
C-96
CAPSULE Y CORRELATION MONITOR MATERIAL Page 2 Material: SRM SA533B1 Heat Number. HSST PLATE 02 Orientation: LT Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Lateral Expansion Computed LE Differential 375 69 725 -3.35 SUM of RESIDUAIS = 1.73 C-97
UNIRRADIATED CORRELATION MONITOR MATERIAL CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1247:42 on 07-15-2002 Page 1 Coefficients of Curve 1 A = 50 B = 50 C = 100.89 TO = 85.54 Equation is Shear/. = A + B * [ tanh((T - TO)/C) I Temperature at 5OX Shear 855 Material: SRM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: UNIRR Total Fluence:
0 C) 0~
0H 0D
-300 -200 -100 0 100 200 300 400 500 600 Temperature in A.
Degrees F
_ _ He _ _ _ _
Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: SRM SA533B1 Ori: LT Heat : HSST PLATE 02 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential
-50 9 6.37 262
-50 9 637 2.62
-50 9 6.37 2.62
-20 13 10.98 2o.
-20 9 10.98 -198
-20 13 10.98 2.01 10 23 1827 4.72 10 23 1827 4.72 10 23 1827 4.72 art Data continued on next page **
C-98
UNIRRADIATED CORRELATION MONITOR MATERIAL Page 2 Material: SRM SA53381 Heat Number HSST PLATE 02 Orientation- LT Capsule: UNIRR Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 40 29 28.84 15 40 33 28.84 415 40 29 28.84 .15 85 41 49.72 -8.72 85 42 49.72 -7.72 85 43 49.72 -6.72 110 55 61.88 -6 88 110 58 61.88 -3 88 110 67 61.88 5.11 160 87 8139 5.6 160 84 8L39 2a6 160 85 81.39 3.6 210 98 9217 5.82 210 98 9217 5.82 210 100 9217 7.82 300 100 98.59 1.4 300 100 9859 1.4 300 100 98.59 1.4 TMof RESIDUALS = 3518 C-99
CAPSULE X CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Prmted at 12:47:42 on 07-15-2002 Page 1 Coefficients of Curve 2 A = 50 B = 50 C = 56.91 TO = 15937 Equation is: Shear/. = A+ B * [ tanh((T - TO)/C) ]
Temperature at 50Y Shear 159.3 Material: SRM SA533B1 Heat Number: HSST PLATE 02 Orientation: LT Capsule: X Total Fluence:
cn 0)
CD 0-0D
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap. X Material: SRM SA533B1 Ori: LT Heat # HSST PLATE 02 Charpy V-Notch Data Tempera ature Input Percent Shear Computed Percent Shear Differential 20 3 .74 225 80 15 5.79 92 90 15 8.03 6.96 125 25 23 1.99 155 35 4616 -1L16 215 100 8759 124 300 100 9929 .7 345 100 99.85 .14 SUM of RESIDUALS = 22.52 C-100
CAPSULE V CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 12:47:42 on 07-15-2002 Page 1 Coefficients of Curve 3 A = 50 B = 50 C = 133.48 T0 = 217.54 Equation is: Sheari = A + B * [ tanh((T - TO)/C) I Temperature at 50v Shear. 217.5 Material: SRNI SAI331 Heat Number. HSSI PLATE 02 Orientation: LT Capsule: V Total Fluence:
0)
C)
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) PIotted Plant SU2 Cap: V MateriaL: SRM SA533B 1 Orin: LT Heat I HSSI PLATE 02 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 75 15 10.56 4.43 125 25 19.99 5 150 25 26.65 -1.65 175 35 3458 .41 200 45 43.46 153 250 50 61.92 -1192 350 100 87.91 12.08 425 100 95.72 427 SUll of RESIDUAL' S= 1416 C-101
CAPSULE Y CORRELATION MONITOR MATERIAL CVGRAPH 41 Hyperbolic Tangent Curve Printed at 12:47:42 on 07-15-2002 Page I
-- Coefficients of Curve 4 l A = 50 B = 50 C = 74.78 TO = 24L87 Equation is Shear/ = A+ B
- I tanh((T - TO)/C) I Temperature at 50; Shear 24L8 Material: SRM SA533B1 Heat Number HSST PLATE 02 Orientation: LT Capsule: Y Total Fluence:
0H a) n C0
-300 -200 -100 0 100 200 300 400 500 600 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: Y Material: SRM SA533BI Ori: LT Heat # HSST PLATE 02 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 72 10 1.05 8.94 125 15 42 10.79 175 20 14.32 5.67 200 25 24.6 .39 225 30 38.9 -8.9 250 55 55.41 -.41 325 100 9022 9.77
- '* Data continued on next page ***
C-102
CAPSULE Y CORRELATION MONITOR MATERIAL Page 2 Material: SiI1MSA533B1 Heat Number. HSST PLATE 02 Orien tation: LT Capsule: Y Total Fluence:
Charpy V-Notch Data (Continued)
Temperature Input Percent Shear Computed Percent Shear Differential 375 100 9723 2.76 Sul4 of RESIDUALS = 29.02 C-103
D-O APPENDIX D VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS Appendix D
D-1 D 1 Neutron Dosimetrv Comparisons of-measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at Surry Unit 2 Unit 2 are described herein. The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."[D'1 3 One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.
D. 1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the five neutron sensor sets withdrawn to date as a part of the Surry Unit 2 Reactor Vessel Materials Surveillance Program are presented. The capsule designation, location within the reactor, and time of withdrawal of each of these dosimetry sets were as follows:
.Capsule ID % Equivalent-, Withdrawal Irradiation Time, Azimuthal 'Timwe , I]EFPY]
Location X 150 End of Cycle 1 1.2 W 250 End of Cycle 4 3.8 V 150 End of Cycle 8 8.4 5 450 End of Cycle 13 15.0 Y 250/150 End of Cycle 17 20.3 The azimuthal locations included in the above tabulation represent the first octant equivalent azimuthal angle of the geometric center of the respective surveillance capsules.
Appendix D
D-2 The passive neutron sensors included in the evaluations of Surveillance Capsules X, W, V, S, and Y are summarized as follows:
Sensor Material ,..,.,`',Reaction I erest
, . AAf Copper 63 Cu(n,(X)60Co Iron 5Fe(np)s4Mn Nickel 58Ni(np) 58 Co Titanium 6E T(np)fSc Uranium-238 23U(n,f)137Cs Neptunium-237 237 Np(nf)13 7 Cs Cobalt-Aluminum 59Co(ny)6Co Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table D- 1. The use of passive monitors such as those listed above does not yield a direct measure of the energy dependent neutron flux at the point of interest. Rather, the activation or fission process is a measure of the integrated effect that the time and energy dependent neutron flux has on the target material over the course of the irradiation period. An accurate assessment of the average neutron flux level incident on the various monitors may be derived from the activation measurements only if the irradiation parameters are well known. In particular, the following variables are of interest:
- the measured specific activity of each monitor,
- the physical characteristics of each monitor,
- the operating history of the reactor,
- the energy resp6nse of each monitor, and
- the neutron energy spectrum at the monitor location.
The radiometric-counting of the neutron sensors from Capsules X and W was carried out by the Battelle Memorial Institute. The radiometric counting of the sensors from Capsules V, S, and Y was completed at the Pace Analytical Services Laboratory located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For Appendix D
D-3 the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples In the case of the uranium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.
The irradiation history of the reactor over the irradiation periods experienced by Capsules X, W, V, S, and Y was based on the reported monthly power generation of Surry Unit 2 from initial reactor criticality through the end of the dosimetry evaluation period. For the sensor sets utilized in the surveillance capsules, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations.
Having the measured specific activities, the physical characteristics of the sensors, and the operating history of the reactor, reaction rates referenced to full-power operation were determined from the following equation:
R= A No FY PX C, [I - e-J]l[e-'d]
Pref where.
R = Reaction rate averaged over the irradiation period and referenced to operation at a core power level of Prf (rps/nucleus).
A = Measured specific activity (dpslgm).
No = Number of target element atoms per gram of sensor.
F = Weight fraction of the target isotope in the sensor material.
Y = Number of product atoms produced per reaction.
P, = Average core power level during irradiation period j (MW).
Pf= Maximum or reference power level of the reactor (MW)
C, = Calculated ratio of sensor reaction rate during irradiation period j to the time weighted average sensor reaction rate over the entire irradiation period.
X= Decay constant of the product isotope (1/sec).
t, = Length of irradiation period j (sec).
td Decay time following irradiation period j (sec).
and the summation is carried out over the total number of monthly intervals comprising the irradiation period.
For capsules remaining in a single location for the entire irradiation period, the spectrum averaged reaction cross-section is essentially constant and, therefore, the cycle dependent neutron flux (E > 1.0 MeV) can be substituted for individual reaction rates in the computation of the C,term. However, for cases such as Appendix D
D-4 Capsule Y where relocation of the capsule resulted in significant changes in the relative neutron energy spectrum, the explicit sensor reaction rates must be used to compute the time history corrections.
In the equation describing the reaction rate calculation, the ratio [PJ]/[Pr,f] accounts for month-by-month variation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. The ratio C,, which was calculated for each fuel cycle using the transport methodology discussed in Section 6 2, accounts for the change in sensor reaction rates caused by variations in flux level induced by changes in core spatial power distributions from fuel cycle to fuel cycle. For a single-cycle irradiation, C,is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional C,term should be employed. The impact of changing flux levels for constant power operation can be quite significant for sensor sets that have been irradiated for many cycles in a reactor that has transitioned from non-low leakage to low leakage fuel management or for sensor sets contained in surveillance capsules that have been moved from one capsule location to another. The fuel cycle specific neutron flux values used in the time history corrections for Capsules X, W, V,and S as well as the individual sensor reaction rates used in the time history corrections for Capsule Y are listed in Table D-2. These values represent the cycle dependent results at the radial and azimuthal center of the respective capsules at the axial elevation of the active fuel midplane.
Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, corrections were made to the 2"U measurements to account for the presence of 235U impurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation Corrections were also made to the both the 23 8 U and 237Np sensor reaction rates to account for gamma ray induced fission reactions that occurred over the course of the capsule irradiations. The correction factors applied to the Surry Unit 2 fission sensor reaction rates are summarized as follows:
Correcti C'apsue X' Capsule WyS Capsule ,V- Caue S Capsule Y 235U Impurity/Pu Build-in 0.873 0.860 0.843 0 813 0.785 238U(y,f) 0.957 0.961 0.959 0.957 0.961 Net 238U Correction 0.835 0.826 0.808 0.778 0.754 23Np(Yf) 0.983 0.984 0.982 0.983 0 984 These factors were applied in a multiplicative fashion to the decay corrected uranium fission sensor reaction rates.
Appendix D
D-5 Results of the sensor reaction rate determinations for Capsules X, W, V, S, and Y are given in Table D-3.
In Table D-3, the computed reaction rates for each sensor indexed to the radial center of the capsule are 8
listed The fission sensor reaction rates as listed include the applied corrections for 2 U impurities, plutonium build-in, and gamma ray induced fission effects.
D 1.2 Least Squares Evaluation of Sensor Sets Least squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as +(E > 1.0 MeV) or dpa/s along with their uncertainties are then easily obtained from the adjusted spectrum In general, the least squares methods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within their respective uncertainties. For example, R -8R =Z(o-+/-g 6'e)(0+6,)
relates a set of measured reaction rates, R1, to a single neutron spectrum, 4 g,through the multigroup dosimeter reaction cross-section, aig, each with an uncertainty S. The primary objective of the least squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.
2 For the least squares evaluation of the Surry Unit 2 surveillance capsule dosimetry, the FERRET codeO ]
was employed to combine the results of the plant specific neutron transport calculations and sensor set reaction rate measurements to determine best-estimate values of exposure parameters (+(E > 1.0 MeV) and dpa) along with associated uncertainties for the two in-vessel capsules withdrawn to date.
The application of the least squares methodology requires the following input:
1 - The calculated neutron energy spectrum and associated uncertainties at the measurement location 2 - The measured reaction rates and associated uncertainty for each sensor contained in the multiple foil set.
3 - The energy dependent dosimetry reaction cross-sections and associated uncertainties for each sensor contained in the multiple foil sensor set.
For the Surry Unit 2 application, the calculated neutron spectrum was obtained from the results of plant specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section D. 1.1. The dosimetry reaction cross-sections and uncertainties were obtained from the Sandia National Laboratory Radiation Metrology Laboratory (SNLRML) dosimeter cross-section libraryID-31. The SNLRML library is Appendix D
D-6 an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard E1018, "Application ofASTM Evaluated Cross-Section Data File, Matrix E 706 (MB)".
The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum were input to the least squares procedure in the form of variances and covariances. The assignment of the input uncertainties followed the guidance provided inASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."
The following provides a summary of the uncertainties associated with the least squares evaluation of the Surry Unit 2 surveillance capsule sensor sets.
Reaction Rate Uncertainties The overall uncertainty associated with the measured reaction rates includes components due to the basic measurement process, irradiation history corrections, and corrections for competing reactions. A high level of accuracy in the reaction rate determinations is assured by utilizing laboratory procedures that conform to the ASTM National Consensus Standards for reaction rate determinations for each sensor type.
After combining all of these uncertainty components, the sensor reaction rates derived from the counting and data evaluation procedures were assigned the following net uncertainties for input to the least squares evaluation:
Reactinn, 5Uncrtainty 63Cu(n,a)f'Co 5%
4Fe(np) Mn 5%
5 Ni(n,p)"Co 5%
4Ti(n,p)6Sc 5%
23U(n,f)137Cs 10%
237Np(n,f)137Cs 10%
"Co(n,y) 'Co 5%
These uncertainties are given at the 1a level.
Dosimetry Cross-Section Uncertainties The reaction rate cross-sections used in the least squares evaluations were taken from the SNLRML library. This data library provides reaction cross-sections and associated uncertainties, including covariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are provided in a fine multigroup structure for use in least squares adjustment applications. These cross-sections were compiled from the most recent cross-section evaluations and they have been tested with respect to their accuracy and consistency for least squares evaluations. Further, the library has been empirically tested for use-in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.
Appendix D
D-7 For sensors included in the Surry Unit 2 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.
'I eaction Uncertainty 6Cu(na) 3 Co 4.08-4.16%
54 3.05-3.11%
Fe(n,p) Mn 5sNi(n,p) 58Co 4.494.56%
4Ti(n,pY Sc 4.514.87%
23U(n,f)137Cs 0.54-0.64%
237Np(n,f)' 37Cs 10.32-10.97%
59Co(n,'y)#Co 0.79-3.59%
These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.
Calculated Neutron Spectrun The neutron spectra input to the least squares adjustment procedure were obtained directly from the results of plant specific transport calculations for each surveillance capsule irradiation period and location. The spectrum for each capsule was input in an absolute sense (rather than as simply a relative spectral shape).
Therefore, within the constraints of the assigned uncertainties, the calculated data were treated equally with the measurements.
While the uncertainties associated with the reaction rates were obtained from the measurement procedures and counting benchmarks and the dosimetry cross-section uncertainties were supplied directly with the SNLRML library, the uncertainty matrix for the calculated spectrum was constructed from the following relationship:
Mgg =R2 +Rg *Rg, *Pgg, where R1, specifies an overall fractional normalization uncertainty and the fractional uncertainties Rg and Rg. specify additional random groupwise uncertainties that are correlated with a correlation matrix given by:
Pgg. = [I J gg, + O e-A where H = (g -g )
H=272 Appendix D
D-8 The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term).
The value of 6 is 1.0 when g = g', and is 0.0 otherwise.
The set of parameters defining the input covariance matrix for the Surry Unit 2 calculated spectra was as follows:
Flux Normalization Uncertainty (Rn) 15%
Flux Group Uncertainties (RF, Rs.)
(E > 0.0055 MeV) 15%
(0.68 eV < E < 0.0055 MeV) 29%
(E < 0.68 eV) 52%
Short Range Correlation (0)
(E>00055MeV) 0.9 (0.68 eV < E < 0.0055 MeV) 0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (y)
(E > 0.0055 MeV) 6 (0.68 eV < E < 0.0055 MeV) 3 (E<0.68eV) 2 D.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Surry Unit 2 surveillance capsules withdrawn to date are provided in Tables D4 and D-5. In Table D-4, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.
These ratios of M/C and M/BE illustrate the consistency of the fit of the calculated neutron energy spectra to the measured reaction rates both before and after adjustment. Also included in the tabulation are the results of the X2/Degree of freedom statistical test associated with each of the least squares evaluations. In Table D-5, comparison of the calculated and best estimate values of neutron flux (E > 1.0 MeV) and iron atom displacement rate are tabulated along with the BE/C ratios observed for each of the capsules.
Appendix D
D-9 The data comparisons provided in Tables D-4 and D-5 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of the least squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 12% at the Ic level. From Table D-5, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 6-7% for neutron flux (E > 1.0 MeV) and 6-8% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the lo level.
Further comparisons of the measurement results with calculations are given in Tables D-6 and D-7. These comparisons are given on two levels. In Table D-6, calculations of individual threshold sensor reaction rates are compared directly with the corresponding measurements. These threshold reaction rate comparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculated energy spectra. In Table D-7, calculations of fast neutron exposure rates in terms of ,(E > 1.0 MeV) and dpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.
In the case of the direct comparison of measured and calculated sensor reaction rates, the MWC comparisons for fast neutron reactions range from 0.80-1.16 for the 23 samples included in the data set. The overall average M/C ratio for the entire set of Surry Unit 2 data is 0.97 with an associated sample standard deviation of 10.5%.
In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.84-1.01 for neutron flux (E > 1.0 MeV) and from 0.85-0.98 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.95 with a sample standard deviation of 6.9% and 0.94 with a samole standard deviation of 6.0%, respectively.
Based on these comparisons, it is concluded that the calculated fast neutron exposures provided in Section 6.2 of this report are validated for use in the assessment of the condition of the materials comprising the beltline region of the Surry Unit 2 reactor pressure vessel.
Appendix D
D-10 Table D-1 Nuclear Parameters Used In The Evaluation Of Neutron Sensors Monitor RC.:\tion of Target
'1 9Q% Response, isso tomi t Rnge Product; ield Material, Interest Frato WMJ Half-life., (%
Copper 6 Cu(na) 0.6917 5.0- 12.0 5.271 y Iron -Fe (n,p) 0.0585 2.4 - 8.8 312.3 d Nickel 5 Ni (n,p) 0.6808 1.7 - 8.4 70.82 d Uranium-238 2Iu (nf) 1 0000 1.5 - 7.9 30.07 y 7
Neptunium-237 2 Np (n,f) 1.0000 0.45 - 5.0 30.07 y 6.02 Cobalt-Aluminurn 9Co (ny) 0 0017 non-threshold 5.271 y 6 17 Notes: The 90% response range is defined such that, in the neutron spectrum characteristic of the Surry Unit 2 surveillance capsules, approximately 90% of the sensor response is due to neutrons in the energy range specified with approximately 5% of the total response due to neutrons with energies below the lower limit and 5%of the total response due to neutrons with energies above the upper limit.
Appendix D
D-11 Table D-2 4(E > 1.0 MeV) [nlcn 2-s] at the Surveillance Capsule Center Core Midplane Elevation J
Cycl apsle V CapuleS 1 8.01e+10 2.79e+10 2
8.24e+10 3.03e+10 3
8.06e+10 3.01e+10 4
8.09e+10 2.81e+10 6.58e+10 2.44e+10 6
6.46e+10 2.34e+10 7
6.63e+10 2.29e+10 8
5.49e+10 2.20e+10 9
1.96e+10 10 1.99e+10 1.89e+10 12 1.83e+10 13 1.65e+10 14 15 16 17 Average 7.10e+10 2.27e+ 10 Appendix D
D-12 Table D-2 (Continued)
Sensor Reaction Rates [rps/a] at the Surveillance Capsule Center Core Midplane Elevation Bare Bare Bare Cd Cov. Cd Cov. Bare Cd Cov.
Cycle Cu-63(n,a) Fe-54(n,p) Ni-58(n,p) U-238(n,f) Np-237(n,f) Co-59(n,g) Co-59(n,g)
I 3.978E-17 4.133E-15 5.621E-15 1.901E-14 1.356E-13 2.048E-12 1.023E-12 2 4.114E-17 4.278E-15 5.819E-15 1.969E-14 1.406E-13 2.125E-12 1.062E-12 3 4.188E-17 4.362E-15 5.935E-15 2.010E-14 1.436E-13 2.171E-12 1.085E-12 4 4.018E-17 4.179E-15 5.684E-15 1.924E-14 1.374E-13 2.076E-12 1.037E-12 5 3.416E-17 3.457E-15 4.691E-15 1.566E-14 1.107E-13 1.654E-12 8.256E-13 6 3.428E-17 3.488E-15 4.736E-15 1.586E-14 1.123E-13 1.680E-12 8.390E-13 7 3.200E-17 3.222E-15 4.371E-15 1.457E-14 1.029E-13 1.539E-12 7.675E-13 8 3.037E-17 3.051E-15 4.139E-15 1.378E-14 9.724E-14 1.449E-12 7.234E-13 9 2.886E-17 2.887E-15 3.915E-15 1.301E-14 9.170E-14 1.365E-12 6.811E-13 10 3.047E-17 3.060E-15 4.151E-15 1.383E-14 9.759E-14 1.455E-12 7.266E-13 11 2.544E-17 2.519E-15 3.413E-15 1.130E-14 7.935E-14 1.177E-12 5.876E-13 12 2.611E-17 2.589E-15 3.509E-15 1.162E-14 8.165E-14 1 211E-12 6.045E-13 13 3.565E-17 3.756E-15 5.130E-15 1.771E-14 1.315E-13 2.155E-12 1.070E-12 14 3.305E-17 3.455E-15 4.716E-15 1.622E-14 1.201E-13 1.961E-12 9.728E-13 15 3.196E-17 3.346E-15 4.568E-15 1.573E-14 1.165E-13 1.906E-12 9.458E-13 16 3.211E-17 3.336E-15 4.551E-15 1.561E-14 1.153E-13 1.877E-12 9.312E-13 17 3.133E-17 3.247E-15 4.428E-15 1.517E-14 1.118E-13 1.813E-12 9.001E-13 Avg. 1-17 3.274E-17 3.356E-15 4.565E-15 1.541E-14 1.108E-13 1.708E-12 8.512E-13 Appendix D
D-13 Table D-3 Measured Sensor Activities And Reaction Rates
'easured Reaction Rate ? snucleusI-Sensor ReactioneX C CapsifleY Capsule CapsuleY Cu-63(n,a)Co-60 5.87E-17 4.70E-17 4.86E-17 2.20E-17 3.2 lE-17 Fe-54(n,p)Mn-54 6.56E-15 4.39E- 15 4.99E-15 1.69E-15 3 04E-15 Ni-58(n,p)Co-58 8.26E-15 5.92E-15 6.36E-15 2 29E-15 U-238(n,f)Cs-137 (Cd) 2.75E-14 1.79E-14 2.36E-14 6.81E-15 1.36E-14 Np-237(n,f)Cs-137 (Cd) 1.89E-13 1.75E-13 5.04E-14 1.28E-13 Co-59(n,y) Co-60 3.94E-12 3.12E-12 7.08E-13 1.53E-12 Co-59(n,y) Co-60 (Cd) 1.06E-12 Appendix D
D-14 Table D-4 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule X ( X2/DOF = 0 25)
Reactonl slaton ml Rection Measuired Calculted = Estimate , .
6 3 Cu(n,a)60Co 5.87E-17 5.23E-17 5.84E-17 1.12 1.01 5 Fe(n,p) Mn 6.56E-15 5.79E-15 6.29E-15 1.13 1.04 5sNi(n,p) 5 8Co 8.26E-15 7.96E-15 8.42E-15 1.04 0.98 23 8U(nf)' 37Cs (Cd) 2.75E-14 2.82E-14 2.90E-14 0.98 0.95 237Np(nf)13 7 Cs (Cd) 1.89E-13 2.14E-13 2.01E-13 0.88 0.94 5 9 Co(nY)60Co 3.94E-12 3.53E-12 3.93E-12 1.12 1.00 Capsule W ( X2/DOF = 0.27)
__________________ Reacton Rate [rps/tm ____
- Reacton Measured Calculated Estimaf. MIC MIRE 3Cu(n,a) 6"Co 4.70E-17 4.05E-17 4.56E-17 1.16 1.03 5Fe(np)54Mn 4.39E-15 4.21E-15 4.40E-15 1.04 1.00 5 Ni(n,p)"Co 5.92E-15 5.74E-15 5.95E-15 1.03 0.99 238 U(n,f)137Cs (Cd) 1.79E-14 1.95E-14 1.95E-14 0.92 0.92 Capsule V(X 2 /DOF= 0.16)
_ R , Raq
,,sctirn ' ?.teI ' ps/*,
' -': x , ? . >eaE R"eacdion Meeasured Cal, lidtd ,Estinate MIC MIRE 63 Cu(n,a)6Co 4.86E-17 4.76E-17 4.75E-17 1.02 1.02 "Fe(n,p) 4Mn 4.99E-15 5.19E-15 4.94E-15 0.96 1.01 5 8Ni(np) 5 Co 6.36E-15 7.12E-15 6.63E-15 0.89 0.96 23u(nf)13 7 CS (Cd) 2.36E-14 2.51E-14 2.33E-14 0.94 1 01 237 Np(nf) 3 7Cs (Cd) 1.75E-13 1.90E-13 1.75E-13 0.92 1.00
' 9Co(n,y)6Co 3.12E-12 3.1OE-12 3.12E-12 1.01 1.00 Appendix D
D-15 Table D-4 cont'd Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule S ( I2/DOF = 0.31)
'3lReattoniti , AI titt Reaction Measured Calculed '>Estimate C E' 63Cu(n,a)6Co 2.20E-17 2.14E-17 2.09E-17 1.03 1.05
'Fe(n,p)4Mn 1 69E-15 1.98E-15 1.74E-15 0.85 0.97 5 8Ni(n,p) 58Co 2.29E-15 2.66E-15 2.33E-15 0.86 0.98 238U(nf)137 Cs (Cd) 6.81E-15 8.47E-15 7.22E-15 0.80 0.94 237Np(nf)l 37Cs (Cd) 5.04E-14 5.73E-14 4.93E-14 0.88 1.02 59 Co(n,y)6°Co 7.08E-13 7.88E-13 7.09E-13 0.90 1.00 CapsuleY ( Xy2 /DOF = 0.36)
Reation.. Measured Calcfe,d Estimate MWC M'BE.
63 0.98 1.02 Cu(n,a)6Co 3.21E-17 3.27E-17 3.15E-17
'Fe(n,p)4Mn 3.04E-15 3.35E-15 3.12E-15 0 91 0.97 238U(nf) 1 37 Cs (Cd) 1.36E-14 1.54E-14 1.46E-14 0.88 0.93 237Np(nf) 137CS (Cd) 1.28E-13 l.llE-13 1.17E-13 1.15 1.09
'Co(n,y)wCo 1.53E-12 1.68E-12 1.57E-12 0 91 0.97 59 Co(ny)6OCo (Cd) 1.06E-12 8.19E-13 1.03E-12 1.29 1.03 Appendix D
D-16 Table D-5 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center
_ __ _ _ E > .O M V n c -Si ~
Be~t"" 'Unceratr Ca.sjlu Cak ' ' Estimite I' 4i ' BE/c, X 8.01E+10 8.11E+10 6% 1.01 W 5.37E+10 5.31E+10 7% 0.99 V 7.10E+10 6.59E+10 6% 0.93 S 2.27E+10 1.91E+10 6% 0.84 Y 4 27E+10 4.10E+10 6% 0.96
- ,onAtomaDisplaceiment Rate [dpatsi Capsule I. Calculated . Unce ia)__ . *E..
~dEstimate . __ _ __ __
X 1.34E-10 1.32E-10 7% 0.98 W 8.75E-11 8.52E-11 8% 0.97 V 1.19E-10 1.09E-10 7% 0 92 S 3.64E-11 3.08E-11 6% 0 85 Y 6.99E-11 6.72E-11 7% 0.96 Appendix D
D-17 Table D-6 Comparison of Measured/Calculated (MtC) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions ssss. .rC Rafio?
Reaction Capsule.X apsule W YCapsule Casue SW. Capsule Y 63 Cu(n,a)6°Co (Cd) 1.12 1.16 1.02 1.03 0.98 54Fe(n,p)54Mn 1.13 1.04 0.96 0.85 0.91 "Ni(n,p)"Co (Cd) 1.04 1.03 0.89 0.86 238 U(nf) 37 Cs (Cd) 0.98 0.92 0.94 0.80 0.88 237Np(nf)137Cs (Cd) 0.88 0.92 0.88 1.15 Average 1.03 1.04 0.95 0.89 0.98 Sample 10.2 9.5 5.1 9.6 12.4
% Standard Deviation Notes-
- 1. The overall average M/C ratio for the set of 23 sensor measurements is 0.97 with an associated sample standard deviation of 10.5%.
Table D-7 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios
<BE/C Ratio'
- ..Capsule ID A (§dpa E>a 10MeV)
X 1.01 0.98 W 0.99 0.97 V 0.93 0.92 S 0.84 0.85 Y 0.96 0.96 Average 0.95 0.94
% Standard Deviation 6.9 6.0 Appendcx D
D-18 Appendix D References D-1. Regulatory Guide RG- 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.
D-2. A Schmittroth, FERRETDataAnalysisCore, HEDL-TME 7940, Hanford Engineering Development Laboratory, Richland, WA, September 1979.
D-3. RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.
Appendix D
ATTACHMENT 2 EVALUATION OF APPLICATION OF SURRY UNIT 2 CAPSULE Y SURVEILLANCE DATA TO SURRY UNIT 2 LOWER SHELL PLATE MATERIAL C4339-1 AND INTERMEDIATE TO LOWER SHELL CIRCUMFERENTIAL WELD MATERIAL R3008
ATTACHMENT 2 EVALUATION OF APPLICATION OF SURRY UNIT 2 CAPSULE Y SURVEILLANCE DATA TO SURRY UNIT 2 LOWER SHELL PLATE MATERIAL C4339-1 AND INTERMEDIATE-TO-LOWER SHELL CIRCUMFERENTIAL WELD MATERIAL R3008 BACKGROUND Surry Unit 2 surveillance Capsule Y was withdrawn from the Surry Unit 2 reactor vessel on March 31, 2002. Capsule Y contains Surry Unit 2 lower shell plate material C4339-1 and intermediate-to-lower shell circumferential weld material R3008 (weld wire heat 0227).
This evaluation provides revised Surry Unit 2 data tables for the NRC's Reactor Vessel Integrity Database (RVID) and an evaluation of changes relative to the previous RVID update for Surry Unit 2 (1). The evaluation considers the impact of Surry Unit 2 Capsule Y surveillance data on (a) licensing basis reactor coolant system (RCS) pressure/temperature (P/T) limit curves, (b) the associated Low Temperature Overpressure Protection System (LTOPS) setpoints and enabling temperature, (c) 10 CFR 50.61 Pressurized Thermal Shock (PTS) screening calculations, and (d)
Charpy Upper Shelf Energy (CvUSE) values. The evaluation was performed in a manner consistent with applicable regulatory guidance. Specifically, the calculation of the Reference Temperature for the Nil Ductility Transition (RTNDT) is performed in accordance with Regulatory Guide 1.99 Revision 2 (3), and the regulatory guidance provided in the meeting minutes from the November 12, 1997 NRC/Industry meeting on reactor vessel integrity (5). PTS screening calculations were performed in accordance with 10 CFR 50.61 (2). CvUSE values were developed in accordance with Regulatory Guide 1.99 Revision 2 (3). Evaluation results are presented in a format consistent with the data requirements of the NRC's Reactor Vessel Integrity Database (RVID).
DISCUSSION OF CHANGES TO PREVIOUSLY REPORTED INFORMATION Surry Unit 2 revised RVID data tables are presented in Appendix A. Shaded cells in Appendix A indicate a changed value relative to those currently presented in RVID (Version 2.0.1, dated 7/6/00). The following changes have been incorporated into the revised tables:
Surry Unit 2 Lower Shell Plate material C4339-1 and Intermediate-to-Lower Shell Circumferential Weld Material R3008
- The RG 1.99 Revision 2 Position 2.1 chemistry factor (CF) calculation includes consideration of the capsule Y analysis results. The Capsule Y data are documented in Table 5-12 of Reference (4).
Page 1 of 5
- Because the surveillance capsules were irradiated in a single reactor and the surveillance material was derived from a single source, irradiation temperature and chemistry corrections are not applied in the credibility determination.
- The surveillance data applicable to C4339-1were determined to be non-credible.
However, the data were within 2a of the RG 1.99 Rev. 2 Position 1.1 curve based on a CF for the average surveillance material chemical composition. Therefore, the Position 1.1 CF value was applied to the C4339-1 beltline material with a full margin term. The surveillance data for the R3008 material were determined to be credible, so the RG 1.99 Rev. 2 Position 2.1 CF values were applied for this material.
EVALUATION OF EXISTING P/T LIMITS AND LTOPS SETPOINTS The existing Surry Units 1 and 2 P/T limits and LTOPS setpoints (7)(8) are based on a limiting 1/4-thickness (14-T) RTNDT of 228.4 0F. When the P/T limits and LTOPS setpoints were developed, this value of RTNDT was determined to bound all Surry Units 1 and 2 reactor vessel beltline materials at fluences corresponding to 28.8 EFPY and 29.4 EFPY for Surry Units 1 and 2, respectively (7)(8). RTNDT calculations have been performed for all Surry Unit 2 reactor vessel beltline materials at a neutron fluence value corresponding to 30.1 EFPY (1). The results are presented in Appendix A. After consideration of the aforementioned changes to previously reported information, the most limiting 1/-T RTNDT value for Surry Unit 2 is 208.8 0F at the fluence value corresponding to a cumulative core burnup of 30.1 EFPY (1). However, the P/T Limits and LTOPS Setpoints are based on a limiting '/-T RTNDT value of 228.4 0F. Therefore, the existing PIT Limits and LTOPS Setpoints remain valid and conservative.
EVALUATION OF PTS SCREENING CALCULATIONS PTS screening calculations have been performed for all Surry Unit 2 reactor vessel beltline materials at a neutron fluence value corresponding to 30.1 EFPY (1). The results of these calculations are presented in Appendix A. After consideration of the aforementioned changes to previously reported information, it is concluded that all Surry Unit 2 beltline materials continue to meet the 10 CFR 50.61 screening criteria.
REPORT OF CvUSE VALUES CvUSE data and calculations are presented in Appendix A. Although surveillance Capsule Y only contained Surry Unit 2 lower shell plate material C4339-1 and intermediate-to-lower shell circumferential weld material R3008 (weld wire heat 0227),
the CvUSE table reflects the following changes:
- The current listing in the RVID for weld material L737/4275 (nozzle-to-intermediate shell circumferential weld) identifies the material as Linde 80 material when in fact it consists of SAF 89 material.
Page 2 of 5
- The current listing in the RVID for weld material R3008/0227 (intermediate-to-lower shell circumferential weld) identifies the material as Linde 80 material when in fact it consists of Grau Lo material.
1/-T USE fluence values are calculated using the RG 1.99 Rev. 2 Position 1.1 attenuation equation. The RG 1.99 Rev. 2 Position 1.1 methodology includes the vessel clad material thickness in the fluence calculation (i.e., "...depth into the vessel wall measured from the inner (wetted) surface."):
f/fiur = exp (-0.24x), x = [0.25*vessel thickness] + [clad thickness]
For Surry Unit 2, the maximum allowable f/fsurf would be:
x = [0.25*8.079 in] + [0.157 in] = 2.177 in, f/fsu= 0.593 However, Surry Unit 2 attenuation was calculated by the more conservative approach of calculating wall depth by taking 25% of the total including the clad thickness:
x = [0.25*(8.079 in + 0.157 in)] = 2.059 in, f/fsur = 0.610 The higher f/fsuf produces a higher ARTNDT, so the 1/4-T fluences calculated for Surry Unit 2 are conservative with respect to the RG 1.99 Rev. 2 Position 1.1 methodology.
- The values for unirradiated USE for materials C4331-2 and C4339-1 appeared to have been mistyped in the RVID. Corrected values have been provided.
- The percentage drops in CvUSE values were calculated using the RG 1.99 Rev. 2 Position 1.2 methodology. CvUSE data obtained from surveillance capsules compares favorably with predictions. For those Rotterdam and Linde 80 materials that are below 50 ft-lbs, equivalent margin analyses (EMAs) have been previously approved in References (9) and (10).
CONCLUSIONS After consideration of the aforementioned changes to previously reported information, the most limiting 1/-T RTNDT value for Surry Unit 2 is 208.80 F at a fluence value corresponding to a cumulative core burnup of 30.1 EFPY. The existing Surry Unit 2 Technical Specification RCS P/T limits, LTOPS setpoints, and LTOPS enabling temperature are based upon a 1/4-T RTNDT value of 228.4 0F (7) (8). Therefore, the analyses supporting the Surry Unit 2 RCS P/T limits, LTOPS setpoints, and LTOPS enabling temperature remain valid and conservative (7) (8). In addition, after consideration of the aforementioned changes to previously reported information, all Surry Unit 2 reactor vessel beltline materials continue to meet the 10 CFR 50.61 PTS screening criteria for cumulative core burnups up to 30.1 EFPY. Finally, calculated Surry Unit 2 CvUSE values continue to be greater than the 50 ft-lb 10CFR50 Appendix G criterion.
Page 3 of 5
NRC REACTOR VESSEL INTEGRITY DATABASE Virginia Power requests that information presented in Appendix A be used to update the NRC Reactor Vessel Integrity Database (RVID).
FUTURE CAPSULE EXTRACTION PLANS The currently docketed reactor vessel materials surveillance program includes withdrawal of the final Surry Unit 2 surveillance capsule at a fluence value corresponding to a cumulative core burnup of 30.1 EFPY. As a result of Dominion's license renewal efforts for Surry Unit 2, a submittal is planned to change the capsule withdrawal schedule to reflect the recommendations of the Generic Aging Lessons Learned (GALL) report (6).
REFERENCES (1) Letter from L. N. Hartz to USNRC, "Virginia Electric and Power Company, North Anna Power Station Units 1 and 2, Surry Power Station Units 1 and 2, Evaluation of Reactor Vessel Materials Surveillance Data," Serial Number 99-452A dated November 19, 1999.
(2) Title 10, Code of Federal Regulations, Part 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."
(3) Regulatory Guide 1.99 Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," dated May, 1988.
(4) WCAP-16001, "Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program," dated February 2003.
(5) Memorandum from K. R. Wichman to E. J. Sullivan, "Meeting Summary for November 12, 1997 Meeting with Owners Group Representatives and NEI Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses," dated November 19, 1997.
(6) NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," dated July 2001.
(7) Letter from R. F. Saunders to USNRC, "Virginia Electric and Power Company, Surry Power Station Units 1 and 2, Request for Exemption - ASME Code Case N-514, Proposed Technical Specifications Change, Revised Pressure/Temperature Limits and LTOPS Setpoint," Serial No.95-197, June 8,1995.
(8) Letter from B. C. Buckley to J. P. O'Hanlon, "Surry Units 1 and 2 - Issuance of Amendments Re: Surry Units 1 and 2 Reactor Vessel Heatup and Cooldown Page 4 of 5
Curves (TAC Nos. M92537 and M92538)," Serial No.96-020, dated December 28, 1995.
(9) BAW-2178PA, "Low Upper Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Level C & D Service Loads," dated April 1994.
(10) BAW-2192PA, "Low Upper Shelf Toughness Fracture Analysis of Reactor Vessels of B&W Owners Group Reactor Vessel Working Group for Level A & B Conditions,"
dated April 1994.
Page 5 of 5
APPENDIX A REACTOR VESSEL MATERIALS DATA TABLES FOR SURRY UNIT 2 (11 pages)
Facility: Surry Unit 1 Vessel Manufacturer: B&W and Rotterdam Dockyard Best- Best- Assigned Estimate Estimate Material RPV Weld Wire Heat or Copper Nickel ID Fluence Chemistry Method of Initial Inner Surf. ART 0
Material ID Location (wt/6) (wt%) (xl El 9) Factor Determining CF RT(NDT) Sigma(l) Sigma(delta) Margin or RT(PTS) 1/4-T ART 122V109VA1 Nozzle Shell Forging 0110 0 740 0 307 761 Tables 40 00 17 0 34 0 125 5 1161 C4326-1 Intermediate Shell 0 110 0 550 3 530 73 5 Tables 10 00 17 0 34 0 141 6 132 8 C4326-2 Intermediate Shell 0110 0 550 3 530 73 5 Tables 0 00 17 0 34 0 1316 122 8 4415-1 Lower Shell 0 102 0 493 3 530 85 0 Surv Data 20 00 85 17 0 149 9 139 7 4415-2 Lower Shell 0 110 0 500 3 530 73 0 Tables 0 00 17 0 34 0 131 0 122 2 J726/25017 Nozzle to Int Shell Circ Weld 0 330 0 100 0 307 152 0 Tables 0 20 0 28 0 68 8 171 6 153 0 SA-1585/72445 Int to Low Sh Circ (ID 40%) 0 220 0 540 3 200 131 4 Surv Data -5 19 7 28 0 68 5 235 1 218 9 SA-1650/72445 Int to LowSh Circ (OD 60%) 0 220 0 540 3 200 131 4 Surv Data -5 19 7 28 0 68 5 235 1 218 9 SA-1494/8T1554 Int Shell Long Welds L3 & L4 0160 0 570 0 600 143 9 Tables -5 19 7 28 0 68 5 186 8 167 4 SA-1494/8T1554 Lower Shell Long Weld Li 0 160 0 570 0 540 143 9 Tables -5 19 7 28 0 68 5 182 6 163 4 SA-1526/299L44 Lower Shell Long Weld L2 0 340 0 680 0 540 220 6 1 Tables -7 20 6 28 0 69 5 245 1 215 7
- 1/4T ART value of 228 4 F was used In the determination of PIT limits Note Shaded cells indicate a changed value relative to the NRC's Reactor Vessel Integrity Database (RVID) Version 2 0 1 (Data Update on 7/6/00)
Facility: Surry Unit 2 Vessel Manufacturer: B&W and Rotterdam Dockyard Best- Best- Assigned Estimate Estimate Material RPV Weld WIre Heat or Copper Nickel ID Fluence Chemistry Method of Initial Inner Surf ART Material ID Location (wt%) (wt%) (xlEl9) Factor Determining CF RT(NDT) Sigma(l) Sigma(delta) Margin or RT(PTS) 1/4-T ART 123V303VA1 Nozzle Shell Forging 0110 0 720 0298 758 Tables 30 l 00 T 170 l 340 1147 1055 C4331-2 Intermediate Shell 0120 0600 3520 830 Tables -10 l 00 170 l 340 1342 1242 C4339-2 IntermediateShell 0110 0540 3520 734 Tables -20 00 170 340 111.5 1026 C4208-2 LowerShell 0150 0550 3520 1073 Tables -30 00 170 l 340 1464 1335 C4339-1 LowerShell 0107 0530 3520 708 Tables -10 00 170 340 1180 1095 L737/4275 Nozzle to Int Shell Circ Weld 0 350 0 100 0 298 160 5 Tables 0 20 0 28 0 68 8 176 1 156 6 R3008/0227 Int to LowerShell Cire Weld 0187 0545 3520 1324 Surv Data 0 200 140 l 488 2247 2088 WF-4/8T1762 Int Shell Long L4 (ID 50%) 0190 0570 0697 1524 Tables -5 l 197 l 280 l 685 2004 1796 SA-1585/72445 Int Sh L3 (100%), L4 (OD 50) 0 220 0 540 0 697 131 4 Surv Data -5 l 197 l 280 68 5 181 6 163_7 WF-4/8Tt762 LSL2(1D63%),L1 (100) 0190 0570 0697 1524 Tables -5 197 280 l 685 2004 1796 WF-8/8T1762 LS Long Weld L2 (OD 37%) 0190 0570 0697 1524 Tables -5 19.7 280 685 2004 1796
- 1/4-T ART value of 228 4 F was used In the determination of P/T limIts Note Shaded cells indicate a changed value relative to the NRC's Reactor Vessel Integrity Database (RVID) Version 2 0 1 (Data Update on 716/00)
Appendix A Page I of 11
CvUSE Values Facility: Surry Unit 2 Vessel Manufacturer: B&W and Rotterdam Dockyard
%Drop In RPV Weld Wire Heat or 1/4-T Fluence Unirradiated Unirradiated USE %Drop in USE Material ID Location Forging or Flux Type USE @1/4 T (xlE19) USE Method USE @1/4 T Method Cu %
123V303VA1 Nozzle Shell Forging SA508, Cl 2 89 5 0182 1040 MeasuredtMTEB 5-2 14 0% Pos 1 2 011 C4331-2 Intermediate Shell SA533,Gr B1 63 0 2147 84 0 -- Measured/MTEB 5-2 25 0% Pos 12 012 C4339-2 Intermediate Shell SA533, Gr. B1 63 2 2.147 83 0 Measured/MTEB 5-2 23 9% Pos 1 2 011 C4208-2 Lower Shell SA533, Gr B1 67 3 2147 94 0 Measured/MTEB 5-2 28 4% Pos 1 2 015 C4339-1 Lower Shell SA533,Gr B1 80 2 2147 105 0 Measured 23 6% Pos 1 2 011 L737/4275 Nozzle to Int Shell Circ Weld SAF 89 EMA 0 182 EMA Estimate EMA EMA 0 35 R3008/0227 Int to Lower Shell Circ Weld Grau Lo 55 0 -2 147 90 0 Measured 389% Pos 1.2 0 19 WF-4/8T1762 Int. Shell Long L4 (ID 50%) Linde 80 EMA 0 425 EMA Estimate EMA EMA 019 SA-1585/72445 Int Sh L3 (100%), L4 (0D 50) Linde 80 54 0 0 425 77 0 Measured 299% Pos 1 2 0 22 WF-4/8T1762 LS L2 (ID 63%), L1 (100) Linde 80 EMA 0 425 EMA Estimate EMA EMA 019 WF-8/8T1762 LS Long Weld L2 (OD 37%) Linde 80 EMA 0 425 EMA Estimate EMA EMA 019 Note Shaded cells indicate a changed value relative to the NRC's Reactor Vessel Integrity Database (RVID) Version 2 0 1 (Data Update on 7/6/00)
Appendix A Page 2 of II
Table 2: Surry Unit 2 Plate Material C4339-1 (Combined Longitudinal and Transverse Data)
Data Used In Irradiation Assessing Vessel?
Capsule ID (Including Source) Copper (wth) Nickel (wt%/) Temperature (F) Fluence (xl El 9) Measured Delta-RT(NDT) (F) (Yes or No)
Surry Unit 2 Capsule X (Long) 0 104 0 520 534 9 0 297 59 Yes Surry Unit 2 Capsule V (Long) 0 104 0 520 540 1 1 890 79 Yes Surry Unit 2 Capsule X (Trans) 0 104 0 520 534 9 0 297 49 Yes Surry Unit 2 Capsule V (Trans) 0.104 0 520 540 1 - 1 890 64 Yes Surry Unit 2 Capsule Y (Long) 0 104 0 520 543 7 2 730 114 Yes Surry Unit 2 Capsule Y (Trans) 0 104 0 520 5437 2 730 107 Yes Table 3: Surry Unit 2 Plate Material C4339-1 (Combined Longitudinal and Transverse Data)
Irradiation Adjusted Delta- Adjusted - Predicted Delta-0 Capsule ID (Including Source) Copper (wt !.) Nickel (wt%) Temperature (F) Fluence Factor Measured Delta-RT(NDT) (F) RT(NDT) (F) RT(NDT) (F)
Surry Unit 2 Capsule X (Long) 0 104 0 520 534 9 0 6677 - . 59 59 9 Surry Unit 2 Capsule V (Long) 0 104 0 520 540 1 1.1743 79 79 -10 Surry Uni 2 Capsule X (Trans) 0 104 0 520 534 9 0 6677 - 49 49 -2 Surry Unit 2 Capsule V (Trans) 0104 04 0 520 5401 1 1743 64 64 -25 Surry Unit 2 Capsule Y (Long) 0 104 0 520 543 7 12679 - 114 114
- 18 Surry Unit 2 Capsule Y (Trans) 0 104 0 520 543 7 12679 107 107 11
- For credibility check, measured shlft values are adjusted to average surveillance matenat chemistiy and irradiation temperature as required See Table 4 Appendix A Page 3 of 11
Table 4: Surry Unit 2 Plate Material C4339-1 (Combined Longitudinal and Transverse Data)
CF Determination Surveillance Data It Surv Data Non-Credible, Beltline Material Beltline Matenal Irradiation Credible or Non- Verify Conservatism of Chemistry Factor Applied to Beitline Beftline Material ID Copper (wt%) Nickel (wt%) Temperature (F) Position 1 1 Chemistry Factor Position 2 1 Chemistry Factor Credible? Position 1.1 CF Material*-
Plate C4339-1 0 107 0 530 543.7 70 8 75 7 Non-Credible 00 70 8
'Measured shift values are adjusted to the average surveillance matenal chemistry and irradiation temperature, and are venfied to be within 2 sigma of the trend curve based on RG 1 99 Rev 2 Position 11
- 'f surveillance data are non-credible but the Pos. 1 1 CF Is shown to be conservative, the lower of the Pos 1.1 and Pos 2. 1 chemistry factors Is applied to the beitline material wIth a full margin terrm If surveillance data are non-credible and the Pos 1 1 CF Is shown to be non-conservative, the greater of the Pos 1.1 and Pos 2 1chemistry factors Is applied to the belthlne matenal with a full margin term Credibility Assessment Conservatism Check for Pos 1.1 CF when Surv. Data Non-Credible (1) (2) (3)
Temperature Chemistry Temperature Correction (4)
Correction Correction Surveillance Data Applied to Surv Data for Chemistry Correction Applied Are adjusted surveillance data Applied for Applied for Credible or Non- Application to Beftline to Surv Data for Application Adjusted Delta- Adjusted - Predicted Delta- within 2 sigma of the applied CF Capsule ID (Including Source) Credibility? Credibility? Credible? Material? to Beltilne Material? RT(NDT) (F) RT(NDT) (F) trend curve?
Surry Unit 2 Capsule X (Long) No No Credible No No 59 13 Conservative Surry Unit 2 Capsule V (Long) No No Credible No No 79' .1 Conservative Surry Unit 2 Capsule X (Trans) No No Credible No No 49 3 Conservative Surry Unit 2 Capsule V (Trans) No No Non-Credible No No 64 '-17 Conservative Surry Unit 2 Capsule Y (Long) A No No Non-Credible No No 114 28 ConservatIve Surry Unit 2 Capsule Y (Trans) No No Credible N - No No 107 20 Conservative (1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift ifapplicable surveillance data were irradiated in a single reactor (i e , were irradiated at a similar temperature)
(2) For the credibility determination, a chemistry correction Is not applied to measured values of transition temperature shift If applicable surveillance data were obtained from a single source (I e, were machined from the same block of material)
(3) For determination of the beitline material chemistry factor, a temperature correction Is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i e
- were irradiated at a simiar temperature) A temperature correction is applied only In the conservative direction (4) For determination of the beltline material chemistry factor, a chemistry correction (I e ,ratio procedure) Is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data Is essentially Identical to the best-estimate chemical composition of the beltline material being evaluated Appendix A Page 4 of 11
Table 5: CvUSE Data Surry Unit 2 Plate Material C4339-1 (Combined Longitudinal and Transverse Data)
Capsule ID (Including Source) Fluence (x1 E19) Copper (wt%/) CvUSE (ft-lb) CvUSE - Drop Measured % CvtJSE - Drop Predicted % Delta-CvUSE %
Unirradiated Surv Material (Long) 0 00 0 10 128 00 .
Unirradiated Surv Matenal (Trans) 0 00 0 10 104 00 _
Surry Unit 2 Capsule X (Long) 0 30 0 10 122 00 4.7% 14 8% -10 1%
Surry Unit 2 Capsule V (Long) 1 89 0 10 121 00 5 5% 22 6% -171%
Surry Unit 2 Capsule X (Trans) 0 30 0 10 94 00 9 6% 14 8% -5 1%
Surry Unit 2 Capsule V (Trans) 1 89 0 10 94 00 9 6% 22 6% ,.-12 9%
Surry Unit 2 Capsule Y (Long) 2 73 0 10 11100 13 3% 24 4% -11.1%
Surry Unit 2 Capsule Y (Trans) 2 73 0.10 94 00 9 6% 244% -14 8%
Appendix A Page 5 of 11
Table 2: Surry Unit 2 Weld Material R3008 Data Used In Irradiation Assessing Vessel?
Capsule ID (Including Source) Copper (wt%/) Nickel (wt%/o) Temperature (F) Fluence (xl E19) Measured Delta-RT(NDT) (F) (Yes or No)
Surry Unit 2 Capsule X 0 187 0 545 534 9 0 297. - 96 Yes Surry Unit 2 Capsule V 0 187 0 545 540 1 1 890 140 Yes Surry Unit 2 Capsule Y 0 187 0 545 543 7 2.730 178 Yes Table 3: Surry Unit 2 Weld Material R3008 Irradiation Adjusted Delta- Adjusted - Predicted Delta.
Capsule ID (Including Source) Copper (wtO/.) Nickel (wt%) Temperature (F) Fluence Factor Measured Deita-RT(NDT) (F) RT(NDT) (F)* RT(NDT) (F)
Surry Unt 2 Capsule X 0 187 0 545 534 9 0 6677 96 96 7 Surry Unit 2 Capsule V 0 187 0 545 5401 - 1.1743 140 140 -15 SurryUnit 2 Capsule Y 0 187 0 545 543 7 12679 178 178 10
- For credibility check, rneasured shift values are adjusted to average surveillance matenal chemstry and irradiation temperature as required See Table 4 hAppl lmlix A hip1( fi '1 11
Table 4: Surry Unit 2 Weld Material R3008 CF Determination Surveillance Data If Surv Data Non-Credible, Beltline Material Beltline Material Irradiation Credible or Non- Verify Conservatism of Chemistry Factor Applied to Beltline Beltine Material ID Copper (wt%) Nickel (wt%/.) Temperature (F) Position 11 Chemistry Factor Position 2 1 Chemistry Factor Credible? Position 11 CF
- Matenal R3008 0 187 0 545 543 7 147 5 l 132.4 Credible 132 4
'Measured shift values are adjusted to the average surveillance material chemi1stry and Iradiatlon temperature, and are venied to be within 2 sigma of the trend curve based on RG 1 99 Rev 2 Position 1 1 If surveillance data are non-credible but the Pos 1.1 CFIs shown to be conservative, the lower of the Pos 1.1 and Pos 2 1 chemistry factors is appled to the beltline matenal with a ful nargin term f surveillance data are non-credible and the Pos I I CF is shown to be non-conservative, the greater of the Pos 1 and Pos 2 1 chemistry factors is applied to the beltline material with a ful margin term Credibility Assessment Conservatism Check for Pos 1 1 CF when Surv Data Non-Credible (1) (2) (3)
Temperature Chemistry Temperature CorrectIon (4)
Correction Correction Surveillance Data Applied to Surv. Data for Chemistry Correction Applied Are adjusted surveillance data Applied for Applied for Credible or Non- Application to Beitline to Surv. Data for Application Adjusted Delta- Adjusted - Predicted Delta- within 2 sigma of the applied CF Capsule ID (including Source) Credibility' Credibility? Credible? Material? to Beitline Material? RT(NDT) (F) RT(NDT) (F) trend curve?'
Surry Unit 2 Capsule X No No Credible No No . .
Surry Unit 2 Capsule V No No Credible No No Surry Unit 2 Capsule Y No No Credible No No. -
(1) For the credibility determination, a temperature correction Is not applied to measured values of transition temperature shift If applicable surveillance data were Irradiated In a single reactor (I e, were irradiated at a similar temperature)
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (i e, were machined from the same block of material).
(3) For determination of the beltline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift If applicable surveillance data were Irradiated in the reactor vessel which is being evaluated (i e were irradiated at a similar temperature) A temperature correction is applied only in the conservative direction (4) For determination of the beitline matenal chemistry factor, a chemistry correction (i e ,ratio procedure) is not applied to measured values of transition temperature shift if the chemical composition of applicable surveillance data Is essentially Identical to the best-estimate chemical composition of the beltline material being evaluated Appendix A Page 7 of 11
Table 5: CvUSE Data Surry Unit 2 Weld Material R3008 Capsule ID (Including Source) Fluence (x1E19) Copper (wt%) CvUSE (ft-tb) CvUSE - Drop Measured % CvUSE - Drop Predicted % Delta-CvUSE %
Unirradiated Surv Material 0 00 0 19 91 00 Surry Unit 2 Capsule X 0 30 0 19 71.00 22 0% 24 6% -2 7%
Surry Unit 2 Capsule V 1 89 0 19 60 00 34 1% 378%- . -37%
Surry Unit 2 Capsule Y 2 73 0 19 5800 36 3% 40 9% -46%
Appendix A Page 8 of 11
Table 2: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Data Used In Irradiation Assessing Vessel?
Capsule ID (Including Source) Copper (wth) Nickel (wt%) Temperature (F) Fluence (xl E19) Measured Delta-RT(NDT) (F) (Yes or No)
Point Beach Unit 1Capsule T 0 230 0 615 533 4 2 230 181 Yes Point Beach Unit 1 Capsule R 0 230 0 615 541 6 2 190 155 Yes Point Beach Unit 1 Capsule S 0 230 0 615 542 0 0 829 165 Yes Point Beach Unit 1 Capsule V 0 230 0 615 542 0 0 634 107 Yes Capsule CR3-LG2 (BWOG CR-3 Irrad) 0 220 0 590 556 0 1 670 164 No Capsule CR3-LG1 (BWOG CR-3 Irrad) 0 220 0 590 556 0 0 510 139 No Capsule W-1 (ANO-1 NBD) 0220 0590 5463 0660 138 No Table 3: Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach I Data Only)
Irradiation Adjusted Delta- Adjusted - Predicted Delta-Capsule ID (Including Source) Copper (wt%) Nickel (wt%) Temperature (F) Fluence Factor Measured Delta-RT(NDT) (F) RT(NDT) (F) RT(NDT) (F)
PoInt Beach Unit 1Capsule T 0 230 0 615 533 4 1 2173 181 181 7 Point Beach Unit 1 Capsule R 0 230 0 615 541 6 1 2126 155 155 -18 Point Beach Unit 1 Capsule S 0 230 0 615 542 0 0 9474 165 165 30 Point Beach Unit 1 Capsule V 0 230 0 615 542 0 0 8723 107 107 .17 For credibility check, measured shift values are adjusted to average surveillance mater'al chemistry and irradiation tempigerature as required See Table 4.
Appendix A Page 9 of 11
Table 4: Surry Unit 1and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
CF Determination Surveillance Data If Surv Data Non-Credible, Beftline Matenal BeItline Material Irradiation Credible or Non- Venfy Conservatism of Chemistry Factor Applied to Beltline Beltline Material ID Copper (wt/o) Nickel (wt%/) Temperature (F) Position 1 1 Chemistry Factor Position 2.1 Chemistry Factor Credible? Position 1.1 CF
- Material*
SA-1585172445 0 220 0 540 542 0 158 0 131 4 Non-Credible 00 131 4
'Measured shift values are adjusted to the average surveillance materlal chemistry and Irradiation temperature, and are venfied to be within 2 sigma of the trend curve based on RG 1 99 Rev. 2 Position 1.1.
If surveillance data are non-credible but the Pos 1 1 CF is shown to be conservative, the lower of the Pos 1.1 and Pos 2.1 chemistry factors is appbed to the be/itbne materIal with a full margin term If surveillance data are non-credible and the Pos I 1 CF Is shown to be non-conservative, the greater of the Pos 1.1 and Pos 2. 1 chemistry factors is applied to the beltil/ne material with a full margin temi Credibility Assessment Conservatism Check tor Pos 11 CF when Surv Data Non-Credible
()(2) (3)
Temperature Chemistry Temperature Correction (4)
Correction Correction Surveillance Data Applied to Surv Data for Chemistry Correction Applied Are adiusted surveillance data Applied for Applied for Credible or Non- Application to Beltline to Surv Data for Application Adjusted Delta- Adjusted - Predicted Delta- within 2 sigma of the applied CF Capsule ID (Including Source) Credibility? Credibility' Credible? Material? to Beitline Material? RT(NDT) (F) RT(NDT) (F) trend curve? -
Point Beach Unit 1 Capsule T No No Credible Yes Yes 181 -28 Conservative Point Beach Unit 1 Capsule R No No Credible Yes Yes 155 -53 Conservative Point Beach Unit 1 Capsule S No No Non-Credible Yes Yes 165 2 Conservative Point Beach Unit 1 Capsule V No No Credible Yes Yes 107 *43 Conservative Capsule CR3-LG2 (BWOG CR-3 Irrad) . . .
Capsule CR3-LG1 (BWOG CR-3 Irrad) . . . . . -
Capsule W-1 (ANO-1 NBD) . = = . .
(1) For the credibility determination, a temperature correction is not applied to measured values of transition temperature shift if applicable surveillance data were irradiated In a single reactor (I e , were irradiated at a similar temperature)
(2) For the credibility determination, a chemistry correction is not applied to measured values of transition temperature shift if applicable surveillance data were obtained from a single source (I e, were machined from the same block of material)
(3) For determination of the beitline material chemistry factor, a temperature correction is not applied to measured values of transition temperature shift it applicable surveillance data were irradiated in the reactor vessel which is being evaluated (i e ,were irradiated at a similar temperature) A temperature correction is appliLed only in the conservative direction (4) For determination of the beitIlne material chemistry factor, a chemistry correction (I e, ratio procedure) is not applied to measured values of transition temperature shift ifthe chemical composition of applicable surveillance data is essentially identical to the best-estimate chemical composition of the beitline material being evaluated.
Appendix A Page 10 of 11
Table 5: CvUSE Data Surry Unit 1 and 2 Weld Material SA-1585 (Point Beach 1 Data Only)
Capsule ID (Including Source) Fluence (x1 E19) Copper (wt%) CvUSE (ft-lb) CvUSE - Drop Measured % CvUSE - Drop Predicted % Delta-CvUSE %
Unirradiated Surv Matenal (Long) SA-1263 0 00 0 23 66 00 . .
Unirradiated Surv Material (Long) SA-1585 0 00 0 23 79 00 . .
Point Beach Unit 1 Capsule T 2 23 0 23 55 00 16 7% 44 3% -27.7%
Point Beach Unit 1 Capsule R 2.19 0 23 52 00 21 2% 44 2% -23 0%
Point Beach Unit I Capsule S 0 83 0 23 52 00 21 2% 35 3% -14 1%
Point Beach Unit 1 Capsule V 0 63 0 23 53 00 19 7% 33 3% -13 6%
Capsule CR3-LG2 (BWOG CR-3 Irrad) 1 67 0 22 53 00 32 9% 41 4% -8 5%
Capsule CR3-LG1 (BWOG CR-3 Irrad) 0 51 0 22 56 00 29 1% 31 8% -2 7%
Capsule W-1 (ANO-1 NBD) 0 66 0 22 51 00 35 4% 33 6% 1 8%
Appendix A Page 11 of 11