Text

WCAP-16001, Rev 0, Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program, Attachment 1, Appendix C and Attachment 2, Appendix a
	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)
	v • d • e

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:

"upper shelf energy 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 U]

la 1

tW U

3007 250-20f 150 1007 0 0 0

111

-300

-200

-100 0

100 200 300 Temperature in Degrees Data Set(s) Plotted Cap: UNIRR Material: PLATE SA533BI OrL LT H(

Charpy V-Notch Data Input CVN Energy Computed CVN Energy 400 F

500 600 Plant SU2 lat I C4339-1 Temperature

-40

-15

-15 10 10 10 11 9.5 25 22 31 21 38.5 43 37 15.58 15.58 15.58 2386 2386 35.74 35.74 35.74 Differential

-4 58

-6.08 941

-[86 7.13

-2.86 275 725 125

- ,* 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 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 Input CVN Energy 57 50 44.5 84 79 76 96 965 98 119 119 121 126 129 127.5 Computed CVN Energy 54.45 54.45 54.45 78.7 78.7 7937 9934 99.34 9234 11692 116.92 116.92 12414 12414 12414 Differential 254

-4.45

-9.95 529 29

-2.7

-334

-2.84

-1.34 2.07 a07 4.07 185 485 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

.Q 10 I

zM Vo 250' 200 150 100 100-U-0

-300 500

-200

-100 0

100 200 300 400 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 OrL LT Heat ff C4339-1 Charpy V-Notch Data Input CVN Energy Computed CVN Energy 600 Temperature

-25

-5 20 75 90 125 155 215 10 12 20 41 46 71 102.5 120.5 6.45 92 1459 4024 50.71 76.84 95.59 115.03 Differential 3.54 2.88 5.4

.75

-4.71

-5.84 6.9 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)

Input CVN Energy Computed CVN Energy Differential 120 12114

-114 124 121.72 227 SUI of RESIDUALS = 15.53 Temperature 300 345 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 Upper Shelf Energy-121 Fixed Material Equation is: CVN = A + B I [ tanh((T - TO)/C) ]

Temp. at 30 ft-lbs:

78 Temp. at 50 ft-lbs 118.9 Lower Shelf Energy: 2.19 Fixed PLATE SA533B1 Heat Number C4339-1 Orientation: LT Capsule: V Total Fluence:

30--

250 I)

P-O 0

CD s4 V7 200F 1500

'00 r

5

=

AU 0

100

-300

-200

-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 Input CVN Energy Computed CVN Energy Temperature 0

50 75 76 100 150 200 250 11 20 39 27 38 62 89 117 9.74 2014 28.78 2918 40.01 67.62 92.83 108.42 Differential 125

-14 10.21

-2.18

-2.01

-5.62

-3.83 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 Capsule: V Total Fluence:

Charpy V-Notch Data (Continued)

Input CVN Energy Computed CVN Energy 138 118.99 109 120.52 Si tion' LT Differential 19

-11.52 JM of RESIDUALS = 13.74 Temperature 350 425 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 co~M la Capsule: Y Total Fluence:

3007s-2507 2007 1507Y 5F 0

0 II

_I

-300

-200

-100 0

100 200 300 Temperature in Data Set(s) Plotted Plant SU2 Cap: Y Material PLATE SA533B1 400 F

500 600 Degrees Ori: LT Heat f: C4339-1 Charpy V-Notch Data Temperature 0

10 100 125 175 200 250 Input CVN Energy 8

12 33 37 52 60 100 Computed CVN Energy 6.6 7.45 2527 34.79 58.71 70.97 90.63 Differential 139 4.54 7.72 22

-6.71

-10.97 936 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 Lo Material: PLATE SA533BI Heat Number C4339-1 Capsule: UNIRR Total Fluence:

wer Shelf LE-I Fixed Orientation: LT

-300

-200

-100 0

100 200 300 Temperature in Degree Data Set(s) Plotted Plant: SU2 Cap: UNIRR Material: PLATE SA533BI QrL LT Charpy V-Notch Data ture Input Lateral Expansion Computed LE 400 500 600 s F Heat #: C4339-1 Tempera

-40

-15

-15 10 10 10 7

6 17 16 21 14 30 32 28 1L05 11.05 1105 17.62 17.62 17.62 27.07 27.07 27.07 Differential

-4.05

-5.05 5.94

-1.62 3.37

-3.62 2.92 4.92

.92

- " Data continued on next page ~*

C-1O

Temperature 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 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)

Input Lateral Expansion Computed LE 43 41.69 39 41.69 36 41.69 65 59.68 62 59.68 58 59.68 73 73.78 72 73.78 72 73.78 85 84.65 84 84.65 86 84.65 87 8869 89 8869 90 8869 Differential 1.3

-2.69

-5.69 531 2.31

-1.68

-.78

-1.78

-178

.34

-.65 L34

-169

.3 L3

)UAIS = -X1 SUM of RESII 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 Material: PLATE SA533BI Temperature at L.E. 35:

68.8 Heat Number: C4339-1 Lower Shelf LE 1 Fixed 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

-25

-5 20 75 90 125 155 215 11 12 195 37.5 40 595 74 89 Computed LE 831 1L58 17.37 37.71 44.58 60.39 7161 8481 Differential 2.68

.41 2.12

-21

-4.58

-.89 138 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)

Input Lateral Expansion Computed LE Differential 87.5 9052

-3.02 90.5 913

-.8 SUM of RESIDUALS = 2.29 Temperature 300 345 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 Material: PLATE SA533BI Temperature at LE 35: 100.3 Heat Number. C4339-1 Lower Shelf L.E-1 Fixed Orientation: LT Capsule: V Total Fluence n

I LUU CI)

+

4 I-I.

I.

IIII 1tb X

4

"--i (z-q Q) 4-)z4 100-e n W

0

,z

__=

_I UI I

I

-300

-200

-100 500 0

100 200 300 400 F

600 Temperature in Degrees 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

50 75 76 100 150 200 250 6

16 30.5 20 38.

54 665 86 7.3 16.97 24.93 25.3 34.84 56.08 71.28 78.65

-13

-.97 556

-53 365

-208

-4.78 7.34 Data continued on next page *"*

C-14

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)

Input Lateral Expansion Computed LE Differential 89 8262 637 74.5 8307

-8.57 SUMI of RESIDUALS = -.09 Temperature 350 425 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 Material: PLATE SA533B1 Temperature at L.E. 35:

161.5 Heat Number C4339-1 Lower Shelf L.E 1 Fixed Orientation: LT Capsule: Y Total Fluence:

201

,r r-I U

-4 5aq i

i 1

1 1

WU I

n II 1U l

l I

In, 50 U

-300

-200

-100 0

100 200 300 400 500 F

600 Temperature in Data Set(s) Plotted Plant SU2 Cap: Y Material: PLATE SA533B1 Degrees OrL LT Heat #: C4339-1 Charpy V-Notch Data Temperature 0

10 100 125 175 200 250 Input Lateral Expansion 2

4 22 26 38 40 69 Computed LE 4.71 5.36 17.67 23.89 39.45 47.68 6L81 Differential

-2.71

-1.36 4.32 21

-1.45

-7.68 718 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 Capsule: Y Total Fluence:

Charpy V-Notch Data (Continued)

Input Lateral Expansion Computed LE 74 7089 71 73.71 74 75.68 entation LT Differential 31

-271

-168 SUMl of RESIDUALS = -.89 Temperature 300 325 350 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 C) a)

1007 8F

/0 607 40F 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

-40

-15

-15 10 10 10 9

7 17 17 25 18 33 33 29 Computed Percent Shear 1L02 1L02 ML02 17.46 17.46 17.46 2652 2652 2652 Differential

-2.02

-4.02 5.97

-.46 753

.53 6.47 6.47 2.47

- - ' Data continued on next page ****

C-18

UNIRR LOWER SHELL PLATE C4339-1 (LONG)

Page 2 Temperature 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 Material: PLATE SA533B1 Heat Number C4339-1 Orientati Capsule: UNIRR Total Fluence Charpy V-Notch Data (Continued)

Input Percent Shear Computed Percent Shear 41 4068 40 40.68 33 4068 57 59.17 55 59.17 52 5917 77 75.39 73 7539 67 7539 100 89.92 100 89.92 100 8992 100 9629 100 9629 100 9629 SU) on-LT Difj

[M of RESIDUALS =

ferential

.31

-.68

-7.68

-2.17

-417

-7.17 16

-2.39

-8.39 1007 1007 1007 37 3.7 3.7 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 Capsule: X Total Fluence:

Orientation: LT Q.)

0C

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 Degrees F Ori: LT Heat #: C4339-1 Charpy V-Notch Input Percent Shear Temperature

-25

-5 20 75 90 125 155 215 3

3 5

15 20 40 65 100

. Data Computed Percent Shear

.56 107 2.38 12.74 1921 42.59 66.3 9325 Differential 2.43 1.92 2.61 225

.78

-2,59

-13 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 Capsule: X Total Fluence:

Charpy V-Notch Data (Continued)

Input Percent Shear Computed Percent Shear 100 99.54 100 9989 ion: LT Temperature 300 345 Differential

.45 I

N1 of RESIDUALS = 13.42 SU 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 0

50 75 76 100 150 200 250 Input Percent Shear 15 20 30 30 40 45 75 100 Computed Percent Shear 10.14 2052 2808 28.41 37.12 57.45 7554 87.59 Differential 4.85

-52 191 L58 2.87

-12.45

-54 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 Capsule: V Total Fluence:

Charpy V-Notch Data (Continued)

Input Percent Shear Computed Percent Shear 100 97.36 100 99.22 SU ion: LT Differential 2.63

.77 M of RESIDUALS = 13.51 Temperature 350 425 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:

U) 0 a)C) 10fF7-6 r 40~

"I.'

4, I

I UI I

I

-300

-200

-100 500 0

100 200 300 400 F

600 Temperature in Data Set(s) Plotted Plant: SU2 Cap: Y Material: PLATE SA533B1 Degrees Ori: LT Heat #: C4339-1 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature Differential 0

10 100 125 175 200 250 2

15 20 45 50 95

.73

.96 9.68 17.27 44.19 6066 85.4 126 403 5.31 2.72

.8

-1066 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 MateriaL PLATE SA533B1 Heat Number C4339-1 Capsule: UNIRR Total Fluence:

519 Lower Shelf Energy: 2.19 Fixed Orientation: TL co 10 z

CU r-z4 a?.

L) 3007 2507 2007 150-100-50 0 F I

I__

I

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL PLATE SA533B1 OrL TL H

Charpy V-Notch Data Input CVN Energy Computed CVN Energy F

eat F: C4339-1 Temperature

-40

-15

-15 10 10 10 135 10 9

20 24 24 33 32 31 136 136 136 20.17 20.17 20.17 29.37 29.37 29.37 Differential

-1

-3.6

-4.6

-17 3.82 3.82 3.62 2.62 L62 Data continued on next page mx C-26

Temperature 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 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)

Input CVN Energy Computed CVN Energy Differential 44.5 43.68

.81 46 43.68 2.31 41 43.68

-2.68 62 62.35

-.35 60.5 62.35

-185 57 62.35

-5.35 81 78.75 224 73 78.75

-5.75 72 78.75

-6.75 101 93.55 7.44 99 93.55 5.44 95 93.55 1.44 106 100.12 5.87 10L5 100.12 L37 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 Capsule X Total Fluence:

Orientation: TL MI 0o z--

3007--

2507 20 1507-100 IG i

50f U

I i0

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Data Set(s) Plotted Plant: SU2 Cap: X Material: PLATE SA533B1 Degrees OrL TL Heat #: C4339-1 Charpy V-Notch Data Temperature

-25

-5 20 75 80 90 155 215 Input CVN Energy 9.5 11 245 32 31.5 485 70.5 9L5 Computed CVN Energy 866 11.6 16.9 36.23 38.46 43.04 71.28 85.95 Differential

.83

-.6 7.59

-423

-6.96 5.45

-.78 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 Upper Shelf Energy: 94Fixed Material:

Equation is CVN = A + B * [ tanh((T - TO)/C) I Temp. at 30 ft-lbs 75 Temp. at 50 ft-lbs 124 Lower Shelf Energy: 2.19 Fixed PLATE SA533BI Heat Number C4339-1 Orientation: TL Capsule: V Total Fluence:

301 I

r Li Ul FM a) z W

V7 2507 200-I~c 50-

-- 2 t >

U i

0 100 400 500

-300

-200

-100 200 300 600 Temperature in Data Set(s) Plotted Plant SU2 Cap. V Material: PLATE SA533BI Degrees F Ori: TL Heat #: C4339-1 Charpy V-Notch Data Input CVN Energy Computed CVN Energy Temperature 0

50 75 100 100 150 200 250 6

19 39 52 25 62 69 93 11.04 21.81 29.97 39.75 39.75 60.79 7729 86.62 Differential

-5.04

-2.81 9.02 12.24

-14.75 12

-829 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 Capsule: Y Total Fluence Orientation: TL co

,0 z

"D-

3007 2507 200 150 1007

.____=_

oU Iz I,

I UI I

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: Y Material PLATE SA533B1 Degrees OrL TL Heat L C4339-1 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 0

10 100 125o 175 200 250 6

11 28 40 47 46 74 758 847 24.54 32.18 50.34 59.52 74.79

-158 2.52 3.45 7.81

-334

-13.52

-.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) e Input CVN Energy Computed CVN Energy 95 84.42 95 87.42 93 8952 SUBI of RESIDUALS Temperatur 300 325 350 Differential 10.57 757 3.47

= 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 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL PLATE SA533B1 OrL TL Charpy V-Notch Data ture Input Lateral Expansion Computed LE 400 500 F

600 Heat #: C4339-1 Tempera

-40

-15

-15 10 10 10 8

6 5

15 18 17 24 27 25 1026 10.26 10.26 15.52 15.52 15.52 2287 22.87 22.87 Differential

-226

-4.26

-5.26

-.52 2.47 L47 L12 4.12 212 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 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 Input Lateral Expansion 35 36 32 50 48 47 65 59 61 80 75 72 83 77 78 Computed LE 3427 3427 3427 4916 4916 49.16 6232 6232 62.32 74.32 74.32 74.32 79.72 79.72 79.72 Differential

.72 172

-227 83

-16

-2.16 2.67

-3.32

-1.32 5.67

.67

-2 32 3.27

-272

-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 Material: PLATE SA533B1 Temperature at LE 35:

69.1 Heat Number. C4339-1 Lower Shelf LE. 1 Fixed Orientation: TL S)

Capsule: X Total Fluence:

2007 151 100 00 0

0

"--.4 (Z

11-4 (L) 4..)

(Z

-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

-25

-5 20 75 80 90 155 215 14.5 14 225 33 315 49 59 735 Computed LK 10.6 14.52 20.24 3692 38.57 41.84 59.56 6811 Differential 3.53

-52 225

-3.92

-7.07 7.15

-.56 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) eInput Lateral Expansion Computed LE.

73 7225 68.5 7292 Temperaturi 300 345 Differential

.74

-4.42

= 2.56 SUM of RESIDUALS 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 Material: PLATE SA533BI Temperature at LE 35:

122.3 Heat Number C4339-1 Lower Shelf LE I Fixed Orientation: TL Capsule: V Total Fluence 20i1U co

"-4 IIII I

I I

1007 50

,\\

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: V Material: PLATE SA533B1 Degrees F Ori TL Heat " C4339-1 Charpy V-Notch Data Temperature Input Lateral Expansion 0

50 75 100 100 150 200 250 4

13 29.5 28 185 47 55 7.5 Computed LE 6.52 13.92 1988 27.38 2738 44.65 59.11 67.49 Differential

-2.52

-.92 9.61 61

-8.88 2.34

-411 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) e Input Lateral Expansion Computed LE.

74 72.93 70 73.7 SUM of RESIDUALS Temperaturi 350 425 Differential 1.06

-3.7

= -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 t [ tanh((T - T0)/C) I Upper Shelf LE: 77.03 Material: PLATE SA533B1 Temperature at LE. 35:

178.5 Heat Number C4339-1 Lower Shelf LE I Fixed Orientation: TL Capsule: Y Total Fluence:

co P-a ).

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: Y Material: PLATE SA533BI Orn: Th Heat ;: C4339-1 Charpy V-Notch Data Temperature 0

10 100 125 175 200 250 Input Lateral Expansion 0

2 19 27 33 34 57 Computed LE 4.85 5.45 15.95 21.05 3399 4119 54.67 Differential

-4.85

-3.45 3.04 5.94

-.99

-7.19 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) e Input Lateral Expansion Computed LE 68 64.64 69 68.1 68 7069 SUM of RESIDUAIS Temperatur 300 325 350 Differential 3.35

.89

-2.69

= -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 Temperature in Degrees F Data Set(s) Plotted Plant: SU2 Cap: UNIRR MateriaL PLATE SA533BI OrL TL Heat #: C, Charpy V-Notch Data ture Input Percent Shear Computed Percent Shear 500 600 4339-1 Tempera

-40

-15

-15 10 10 10 9

5 5

18 18 18 29 29 75 75 7.5 1243 1243 1243 19.91 19.91 1991 Differential L49

-2.5

-2.5 5.56 5.56 5.56 9.08 7.08 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 40 40 40 75 75 75 110 110 110 160 160 160 210 210 210 Input Percent Shear 29 29 29 47 47 42 71 62 63 100 100 100 100 100 100 Computed Percent Shear 32.72 32.72 32.72 5157 5157 51.57 69.97 69.97 69.97 87.71 87.71 87.71 95.62 95.62 95.62 Differential

-3.72

-372

-4.57

-9.57 1.02

-7.97

-697 1228 1228 1228 4.37 4.37 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 Capsule: X Total Fluence:

Orientation: TL Ca) 0

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: X Material: PLATE SA533B1 OrL TL Heat #: C4339-1 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature Differential

-25

-5 20 75' 80 90 155 215 2

5 5

15 15 20 80 100 25

.58 1.9 1323 15.75 2L95

.79.93 97.87 1.74 4.41 a4 1.76

-.75

-195

.06 212

- - - 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)

Input Percent Shear Computed Percent Shear 100 9993 100 99.98 SUM of RESIDUALS Temperatun 300 345 Differential

.06

.01

= 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 Capsule: V Total Fluence Orientation: TL 101r IF I

I I

'i 0) 80Y 6Y 404 201

.. I U I I

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Plant: SU2 Cap: V MateriaL PLATE SA533B1 Ori: TL Heat #: C4339-1 Charpy V-Notch Data Temperature Input Percent Shear 0

50 75 100 100 150 200 250 10 15 15 20 20 25 55 100 Computed Percent Shear 27 6.35 1038 1651 16.51 3655 62.66 83.01 Differential 7.72 8.64 4.61 3.48 3.48

-1L55

-7.66 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)

Input Percent Shear Computed Percent Shear 100 97.64 100 99.51 SUM of RESIDUALS Temperature 350 425 Differential 2.35

.48

= 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:

0 CID 0

0) 0-100 80-AA 60

/

40(F 20

,IU

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Plant: SU2 Cap: Y Material: PLATE SA533BI Ori: TL Heat #: C4339-1 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature Differential 0

10 100 125 175 200 250 2

5 15 20 35 40 90

.48 62 6.76 1249 356 52.11 80.82 1.51 4.37 823 7.5

-.6

-lall 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 Upper Shelf Energy: 91Fixed MateriaL Equation is CVN = A + B * [ tanh((T - TO)/C) ]

Temp. at 30 ft-lbs: -20.4 Temp. at 50 ft-lbs 22.4 Lower Shelf WELD Heat Number WYIRE HEAT 0227 Orientation:

Capsule: UNIRR Total Fluence:

Energy: 219 Fixed 200-150-100 5fY

-30 Temperature 0

-200

-100 0

100 200 300 400 500 600

-100

-40

-20

-20 Temperature in Data Set(s) Plotted PlanLt SU2 Cap: UNIRR Material WELD Charpy V-Notch I Input CVN Energy 7

775 34 15.5 24 29 31 275 Ori:

Heat #: WIF Data Computed CVN Energy 8.78 8.78 8.78 22,55 22.55 22.55 302 30.2 302 RE HEAT 0227 Differential Degrees F

-L78

-1.78

-128 1L44

-7.05 L44

-12

.79

-2.7 F** Data continued on next page ****

C-50

UNIRRADIATED WELD Page 2 Material I Temperature 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 flu Heat Number. WIRE HEAT 0227 Orii Capsule: UNIRR Total Fluence:

Charpy V-Notch Data (Continued)

Input CVN Energy Computed CVN Energy 35 43.94 53 43.94 47 43.94 50 5822 555 5822 535 5822 75 7134 81 7134 78 7134 86 89.75 69.5 89.75 72 89.75 91 90.82 91 9082 91 90.82 St mntation:

Differential

-6.94 905 305

-822

-Z72

-4.72 365 9.65 6.65

-3.75

-2025

-17.75

.17 17 17 3M of 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 Capsule: X Total Fluence:

Orientation:

CI

"-P I

300-2507 200 100 50 U

-300

-200

-100 0

100 200 300 400 F

500 600 1

Temperature in Degrees 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 20 80 90 125 155 215 345 11.5 14 32 33 47.5 64 71 70 818 1248 31.7 36.15 5011 59.09 67.83 70.86 3.31 1.51

.02

-315

-2.61 4.9 3.16

-.86

= 626 SUM1 of RESIDUALS 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 Upper Shelf Energy: 60 Fixed Material:

Teir WELD Equation is CVN = A + B

I tanh((T - TO)/C) I ip. at 30 ft-lbs 119.7 Temp. at 50 ft-lbs 222.7 Heat Number WIIRE HEAT 0227 Capsule: V Total Fluence:

Lower Shelf Energy: 2.2 Fixed Orientation:

Il Pa)

.1 0

300-2507 209=

1507 1007=

.11 5I~~

I I

Oj

-300 300

-200

-100 0

100 200 400 500 600 Temperature in Degrees Data Set(s) Plotted Plant: SU2 Cap-V Material: IELD Ori Heat FL WIRI F

IE HEAT 0227 Charpy V-Notch Data Input CVN Energy Computed CVN Energy Temperature Differential 50 100 125 150 250 350 425 20 24 27 39 53 64 62 15.71 25.52 3121 36.88 531 58.45 59.52 428

-152

-421 211

-1 5.54 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 F

500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: Y Material: WELD OrL Degrees Heat I WIRE HEAT 0227 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy Differential 72 100 150 175 200 250 350 11 18 24 39 36 54 54 10.6 15.43 27.8 34.75 41.16 50.36 56.83

.39

.56

-3.8 424

-516 3.63

-2.83

11 Data continued on next page ***

C-54

CAPSULE Y WELD Page 2 Material: TFELD Heat Number WirIRE HEAT 0227 Capsule: Y Total Fluence:

Charpy V-Notch Data (Continued)

Input CVN Energy Computed CVN E 66 5729 Orientation:

Temperature 375 Energy Differential 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 MateriaL: WELD Temperature at LE. 35:

-18 Lower Shelf LE: I Fixed Heat Number: WIRE HEAT 0227 Orientation:

Capsule: UNIRR Total Fluence:

co)S-.

20 15f 100 5

v 1

I I

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: WELD Degrees Ori:

Heat I WIRE HEAT 0227 Temperature Charpy V-Notch Data Input Lateral Expansion Computed LE.

-100

-40

-20

-20 3

15 5

31 15 20 25 29 25 588 5.8 5.88 1897 1897 18.97 26.74 26.74 26.74 Differential

-2.88

-.88

-.88 12.02

-3.97 L02

-174 2.25

-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 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 Input Lateral Expansion 33 47 40 50 51 51 68 72 71 80 66 70 83 81 82 Computed LE 40.7 40.7 407 54.36 5436 5436 65.49 65.49 65.49 77.52 77.52 77.52 77.95 77.95 77.95 Differential

-7.7 629

-.7

-4.36

-3.36

-3.36 25 6.5 5.5 2.47

-11.52

-7.52 5.04 304 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 Material: WELD Temperature at LE 35:

86.9 Lower Shelf LE. 1 Fixed Heat Number. WIRE HEAT 0227 Capsule X Total Fluence Orientation:

"-4 a)

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: X Material: WELD Or:

Heat i WIRE HEAT 0227 Charpy V-Notch Data Input Lateral Expansion Computed LE Temperature Differential

-5 20 80 90 125 155 215 345 10.5 17 35 32 43.5 65.5 86 70 8.03 12.5 32.03 36.29 5127 6L94 7394 7912 2.46 4.49 296

-429

-7.77 3.55 1205

-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 Upper Shelf LE-56.71 MateriaL WELD Equation is LE = A + B * [ tanh((T - TO)/C) I Temperature at LE 35:

165.3 Lower Shelf LEz I Fixed Heat Number. WIRE HEAT 0227 Orientation:

Capsule: V Total Fluence:

r

Uu P.5q 0)

I.

4 4

4 4-150 100

^

I D I

5-.

U I

-300

-200

-100 0

100 200 300 400 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: WELD Ori:

Heat #: WIRE HEAT 0227 500 600 Charpy V-Notch Data Input Lateral Expansion Computed LE Temperature 50 100 125 150 250 350 425 16 17.5 285 31.5 49 55 55 13.07 21.6 26.66 3188 48.25 5457 56 Differential 2.92

-41 183

-38

.74

.42

-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 Material: WELD Temperature at L.E. 35: 218.3 Lower Shelf L.E I Fixed Heat NumberI WIRE HEAT 0227 Capsule: Y Total Fluence Orientation:

P..E X

4 150 100 50-m-

'In, z

lI U

0 100

-300

-200

-100 200 300 400 F

500 600 1

Temperature in Degrees 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.

72 100 150 175 200 250 350 4

13 15 31 27 43 40 6.05 9.48 1936 25.45 3129 39.83 45.51 Differential

-2.05 351

-4.36 5.54

-429 316

-5.51

'* Data continued on next page ****

C-60

CAPSULE Y WELD Page 2 Material: WELD Heat Number. WIRE HEAT 0227 Capsule Y Total Fluence Charpy V-Notch Data (Continued)

Input Lateral Expansion Computed LE 50 45.87 Orientation:

Differential 412 SUAM of RESIDUALS = 13 Temperature 375 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 101In I

l l I-I Li C:

C) 0-80 6

~00 60 4

0 00 2f 0

0 I2fFI0 U'0

-300

-200

-100 0

100 Temperature in Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: WELD 200 300 Degrees 400 500 600 F

Ork Heat I WIRE HEAT 0227 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature Differential

-100

-40

-20

-20 5

9 9

33 17 37 33 53 47 729 729 729 2a, 28.7 287 4096 40.96 4096

-229 1.7 1.7 429

-11.7 829

-7.96 1203 6.03 ads Data continued on next page **"

C-62

. UNIRRADIATED WELD Page 2 Material WELD Heat Number. WIRE HEAT 0227 Capsule: UNIRR Total Fluence Orientation:

Charpy V-Notch Data (Continued)

Temperature 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 Input Percent Shear 47 68 58 74 74 68 100 100 100 100 100 100 100 100 100 Computed Percent Shear 61.07 6LO7 61.07 78.01 78.01 78.01 89.7 89.7 89.7 99.72 99.72 9972 99.97 99.97 99.97 SUM of RESIDUAL' Differential

-14.07 6.92

-307

-4.01

-10.01 1029 10.29 10.29 27

.27

.02

.02 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 Capsule: X Total Fluence:

Orientation:

Cd C.)

0

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: X Material: WELD OrL Heat 11 WIREE HEAT 0227 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature

-5 20 80 90 125 155 215 345 10 15 30 35 40 95 98 100 316 632 2783 34.02 58.77 77.31 95.11 9988 Differential 6.83 8.67 2.16

.97

-18.77 1768 2.88

.11 S = 20.56 SUM of RESIDUAL' 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 Capsule: V Total fluence:

Orientation:

a-)

0 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 50 100 125 150 250 350 425 Input Percent Shear 25 30 35 45 100 100 100 Computed Percent Shear Differential MI9 28.56 39.63 51.88 88.69 9827 99.6 12.08 1.43

-4.63

-6.88 11.3 1.72

.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 Capsule: Y Total Fluence:

Orientation:

U 00n r0

-300

-200

-100 0

100 21 Temperature in Data Set(s) Plotted Plant SU2 Cap: Y Material: WELD OrL DO 300 400 500 Degrees F 600 Heat A lYIRE HEAT 0227 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature 72 100 150 175 200 250 350 5

15 25 65 55 98 100 5.02 10.59 33.35 50.7 67.88 89.92 9937 Differential

-02 44

-835 1429

-1288 8.07 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) t Percent Shear Computed Percent Shear Differential 100 99.69

.3 SUM of RESIDUALS = 6.44 Temperature 375 Inpu 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 Material: HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Capsule: UNIRR Total Fluence:

30 co 2567

~-

15(

0 0

10(

Lower Shelf Energy-219 Fixed Orientation:

-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 Charpy V-Notch Data Temperature Input CVN Energy Computed CVN Energy 9-1 SIDE OF WELD Differential

-100

-70

-40

-40 165 16 10 215 19 26 23 38 68 1653 16.53 16.53 2429 2429 24.29 34.87 34.87 34.87

-.03

-.53

-6 53

-2.79

-529 L7

-1187 312 3312 11 Data continued on next page Gus C-68

Temperature 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 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)

Input CVN Energy Computed CVN Energy Differential 50 57.57

-7.57 50 57.57

-7.57 74 57.57 16.42 665 71.96

-5.46 54 71.96

-17.96 50 71.96

-21.96 100.5 85.95 14.54 97.5 85.95 1154 96 85.95 10.04 114 11=21 178 104 11221

-821 130 11221 17.78 120 115.16 483 100 11516

-1516 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 Orientation:

Material HEAT AFFD ZONE Heat Number C4339-1 SIDE OF WELD Capsule: X Total Fluence 2507 200 150 4f%-"I 0

bH z

V-.

1UU 0

51I-

/

4 I

Li

1 III iU

-300

-200

-100 0

100 200 300 400 500 F

600 Temperature in Data Set(s) Plotted Plant SU2 Cap: X Material: HEAT AFFD ZONE Degrees OrL Heat I/. C4339-1 SIDE OF WELD Temperature Charpy V-Notch Data Input CVN Energy Computed CYN Energy Differential

-50

-25

-5 20 90 155 215 18 24 31 45.5 635 92 107 95 16.41 29.12 2912 4326 62.78 94.8 10018 100.88 158

-5.12 1.87 223

.71

-2.8 6.81

-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 Material: HEAT AFFD ZONE Heat Capsule V 300-Cin 250W

.1 200-

_=

15=

CD) rOW Temp. at 50 ft-lbs 681 Lower Shelf Energy. 2.19 Fixed Number-C4339-1 SIDE OF WELD -

Orientation:

Total Fluence:

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: V Material: HEAT AFFD ZONE OriL Heat #: C4339-1 SIDE OF WELD 600 Charpy V-Notch Data Input CVN Energy Computed CVN Energy Temperature Differential

-50 0

25 75 150 200 250 350 20 28 33 62 69 76 85 103 19.36 30.4 3719 52.04 72.05 8113 86.84 9196

.63

-2.4

-419 9.95

-3.05

-5.13

-1.84 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 Input CVN Energy Computed CVN Energy Temperature Differential

-50

-25 0

100 150 200 300 18 25 12 32 44 66 95 926 1L74 14.95 36.74 5R64 65.81 8428 8.73 1325

-2.95

-4.74

-7.64

.18 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 Material: HEAT AFFD ZONE Temperature at LSE 35:

-8.7 Lower Shelf LE I Fixed Heat Number-C4339-1 SIDE OF WELD Orientation:

Capsule: UNIRR Total Fluence:

~4

_4 a) 2007-150 100 rr-r-O I

I I

I

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: UNIRR Material HEAT AFFD ZONE Ori Heat #: C4339-1 SIDE OF WELD Charpy V-Notch Data Temperature

-100

-70

-40

-40 Input Lateral Expansion 8

8 4

16 12 20 18 25 45 Computed LU 10.41 10.41 10.41 16.21 16.21 16.21 2436 24.36 24.36 Differential

-2.41

-6.41

-21

-421 378

-636

.63 20.63

- - - Data continued on next page **FF C-74

Temperature 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 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)

Input Lateral Expansion Computed LE.

Differential 38 41.87

-3.87 40 4187

-187 52 41.87 1012 50 5247

-2.47 42 52.47

-1047 40 5247

-1247 69 6209 6.9 67 6209 4.9 66 6209 39 80 7727 2.72 75 7727

-2.27 84 7727 672 80 7855

.44 78 7855

-.55 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 MateriaL HEAT AFFD ZONE Temperature at LE 35:

-4.4 Lower Shelf LE. 1 Fixed Heat Number C4339-1 SIDE OF WELD Capsule: X Total Fluence Orientation:

p--CI)..

2007-.

150 100 0

50 0*~~

~

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees 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

-25

-5 20 90 155 215 17 21 25 40 47 67.5 82 79 16.61 25.71 25.71 34.72 46.82 7125 A8.46 80.06

.38

-4.71

-.71 527

.17

-3.75 353

-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 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: V Material: HEAT AFFD ZONE OrL Heat #: C 400 500 600 F

4339-1 SIDE OF 'WELD Charpy V-Notch Data Input Lateral Expansion Computed LE Temperature

-50 0

25 75 150 200 250 350 17.5 14 24.5 55 51 60 645 75 13.6 22.69 2837 40.74 56.58 6317 67 70.11 Differential 3.89

-8.69

-3.87 1425

-5.58

-317

-2.5 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 "C-

. H 1507-50XL V

-300

-200

-100 0

100 200 300 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: Y Material: HEAT AFFD ZONE Ori:

Heat A C 400 F

500 600 C4339-1 SIDE OF WELD Charpy V-Notch Data Input Lateral Expansion Computed LE Temperature

-50

-25 0

100 150 200 300 7

12 7

27 35 48 66 6.78 8.57 10.82 25.71 3622 47.37 6454 Differential 21 3.42

-3.82 128

-L32

.62 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)

Input Lateral Expansion Computed LE Differential 66 67.32

-1932 SUM of RESIDUALS =.53 Temperature 325 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)

C) 4-H

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: UNIRR Material HEAT AFFD ZONE Orh Heat : C4339-1 SIDE OF WELD Temperature

-100

-70

-40

-40 Charpy V-Notch Data Input Percent Shear Computed Percent Shear 17 1319 13 13.19 13 13.19 23 21.49 23 21.49 27 2149 23 33.02 33 33.02 43 33.02 Differential 38

-.19

-.19 15 1.5 55

-10.02

-.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 10 10 10 40 40 40 73 73 73 210 210 210 300 300 300 Input Percent Shear 53 53 58 68 58 61 96 91 90 100 100 100 100 100 100 Computed Percent Shear 56.79 56.79 56.79 703 70.3 70.3 81.89 8189 8189 98.51 9851 9851 99.74 9974 99.74 Differential

-3.79

-3.79 12

-2.3

-12.3

-9.3 141 91 8.1 L48 1.48 1.48 25

.25 25 Af of 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

) ZONE Heat Number C4339-1 SIDE OF WYELD Capsule: X Total Fluence:

Material: HEAT AFFI Orientation:

-4 U

0 Cn 6

4-

~-

4 2

Tempera

-50

-25

-5 20 90 155 215 LI 0F'

-300

-200

-100 0

100 200 300 400 500 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 ture Input Percent Shear Computed Percent Shear Diff 5

1025 10 182 25 182 35 27.49 40 42.47 80 8267 100 96.42 100 9925 SUMI of RESIDUALS 600 erential

-525

-8.2 6.79 7.5

-2.47

-2.67 3.57

.74

.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 Capsule: V Total Fluence Orientation:

CL) 0

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 1

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 0

25 75 150 200 250 350 25 25 35 35 50 95 100 100 1405 23.67 29.93 44.76 67.92 80.07 88.4 96.48 10.94 L32 5.06

-9.76

-17.92 14.92 1159 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 Capsule: Y Total Fluence:

- Orientation:

1007 80-60 A

4/

0U C-)

0..

20) p p

p U

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Material: HEAT AFFD ZONE Plant SU2 Cap: Y Ori:

Heat #: C4339-1 SIDE OF WIELD Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature

-50

-25 0

100 150 200 300 Differential 15 20 35 55 65 75 100 17.32 21.94 2738 54.98 68.73 79.82 92.76

-2.32

-1.94 7.61

.01

-3.73

-4.82 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 201 1

I I

J 4

4-

+

4-

-4.

4 1

IO I1007 I/o 501 I

II U

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Data Set(s) Plotted Plant SU2 Cap: UNIRR Material SRI SA533BI Degrees Ori: LT Heat 1I HSST PLATE 09 Charpy V-Notch Data Temperature Input CVN Energy

-50

-20

-20 10 10 10 3

5 5

6 6.5 9

13.5 12 14.5 Computed CVN Energy 547 5.47 5.47 884 8.84 8.84 1532 1532 1532 Differential

-2.47

-.47

-2.84

-2.34 15

-L82

-332

-.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 40 40 40 85 85 85 110 110 110 160 160 160 210 210 210 300 300 300 Input CYN Energy 35 22 36 415 52 58.5 63.5 82.5 85.5 109 108.5 81 117 115 121 127 1175 125 Computed CVN Energy 26.74 26.74 26.74 54.83 54B3 54.83 7325 7325 7325 102.49 102.49 102.49 11619 116.19 116.19 12221 12221 12221 Differential 825

-4.74 925

-13.33

-2.83 3.66

-9.75 924 1224 65 6

-2L49

.8

-L19 4.8 4.78

-4.71 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' Material SRM SA533B1 Heat Number: HSST PLATE 02 Capsule X Total Fluence:

10.6 Lower Shelf Energy: 219 Fixed Orientation: LT W

5.

0 V--

3007-S-

250ff 15ff 1507_

10 0rI I

I I

I/

-30(

Temperature 20 80 90 125 155 215 300 345 O

-200

-100 0

100 200 300 400 Temperature in Degrees F Data Set(s) Plotted Plant SU2 Cap: X Material: SRM SA533B1 Ori: LT Heat if HSST PLATE 02 Charpy V-Notch Data Input CVN Energy Computed CVN Energy 4.5 5.59 24 1727 165 2107 41 39.68 575 59.73 89 8992 117 1OL5 104 102.55 SUM of RESIDUAM 500 600 Differential

-[09 6.72

-457 L31

-2.23

-.92 15.49 144

£.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 Temp. at 30 ft-lbs 162.9 Upper Shelf Energy: 102 Fixed

+ B

I tanh((T - TO)/C) I Temp. at 50 ft-lbs 2012 Lower Shelf Energy: 2.19 Fixed Number. HSST PLATE 02 Orientation: LT Total Fluence:

Material: SRM SA533B1 Heat Capsule: V In Pr-,

7 5H V

3007-S 250_

200 1507 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 Input CVN Energy Computed CVN Energy Temperature Differential 75 125 150 175 200 250 350 425 12 25 32 32 31 89 103 100 716 1618 24.48 35.77 49.32 75.62 98.43 10L33 4.83 8.81 7.51

-3.77

-18.32 13.37 4.56

-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 Capsule Y Total Fluence Orientation: LT nnr,

i,..

%3uu 9)

"n

"--4 1

-i- -3 P:q 250-20.

150 100 507

/

V C.)

u'

-300

-200

-100 500 0

100 200 300 400 F

600 Temperature in Degrees Data Set(s) Plotted Plant S12 Cap: Y Material: SRM SA533B1 OrL LT Heat I HSST PLATE 02 Charpy V-Notch Data Temperature 72 125 175 200 225 250 325 Input CVN Energy 7

25 22 34 32 65 93 Computed CVN Energy 4.42 9.4 21.95 32.61 45.81 59.84 893 Differential 2.57 15.59

.04 L38

-13.81 5.15 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)

Input CVN Energy Computed CVN Energy Differential 107 96.36 10.63 SUW of RESIDUALS = 2526 Temperature 375 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:

20i I r

I I

LU M

P-4 X

UI "5-0 W-C) 4-I I I

+

I 10

+

4.

4 L _________

1)

I W i I

0 0

50-0 1

n.

.~

u 300

-300

-200

-100 0

100 200 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: UNIRR MateriaL SRM SA533B1 OrL LT Heat Charpy V-Notch Data e

Input Lateral Expansion Computed LE

HSST PLATE 02 Differential Temperatur

-50

-20

-20 10 10 10 4

3 5

9 6

10 14 15 14 5.03 5.03 5.03 8.84 8.84 8B4 15.61 15.61 15.61

-1.03

-2.03

-.03

.15

-264 115

-L61

-.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 40 40 40 85 85 85 110 110 110 160 160 160 210 210 210 300 300 300 Input Lateral Expansion 32 23 32 42 45 51 54 60 71 79 72 69 84 88 87 84 83 87 Computed LE 26.31 2631 26.31 48.06 4806 4806 59.9 59.

59.

76.07 76.07 76.07 82.91 8291 82.91 85.9 85.9 85.9 Differential 5.68

-3.31 5.68

-6.06

-3.06 2.93

-5.9

.09 11.09 2.92

-4.07

-7.07 1.08 5.08 4.08

-1.9

-2.9 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 Material: SRM SA533B1 Temperature at LE 35:

113.6 Lower Shelf LE. 1 Fixed Heat Number HSST PLATE 02 Orientation: LT Capsule: X Total Fluence:

U]

p-q A -

r 5W 2007 15 100 0

50 U

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Plant SU2 Cap: X Material: SRM SA533B1 OrL I Charpy V-Notch Data LT Heat.

HSST PLATE 02 nputed L.

Temperature 20 80 90 125 155 215 300 345 Input Lateral Expansion 5

25 22.5 38 57 79 89 825 Co]

614 19.98 23.91 40.95 56.6 7h56 85.7 86.54 Differential

-L14 5.01

-1.41

-a95

.39 1.43 329

-4.04 S=.56 SUM of RESIDUAL' 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 Material: SRMI SA533B1 Temperature at LE 35:

188.4 Lower Shelf LE-1 Fixed Heat Number HSST PLATE 02 Orientation: LT Capsule: V Total Fluence:

U)

P-4

. P..j X

W

"--4(Z

..q 0) 4-)

ct

-4 2000

=

150 100 la

/

0 1

+

U-I 2

-300

-200

-100 0

100 200 300 400 F

500 600 Temperature in Degrees Data Set(s) Plotted Material SR1P SA533B1 Plant SU2 Cap-V Ori: LT Heat / HEST PLATE 02 Charpy V-Notch Data Input Lateral Expansion Computed LE Temperature Differential 75 125 150 175 200 250 350 425 17 19.5 22 28 32.5 62 81 81 8.93 1713 232 30.58 3894 5612 7827 83.93 806 2.36

-12

-2.58

-6.44 5.87 2.72

-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 Temperature in Degrees Data Set(s) Plotted Plant: SU2 Cap: Y Materiah SRM SA533BI Ori: LT Heat L 400 500 F

600 HSST PLATE 02 Temperature Charpy V-Notch Data Input Lateral Expansion Computed LE 72 125 175 200 225 250 325 0

15 15 25 23 43 69 3.3 724 15.78 22.61 31.07 40.47 64.41 Differential

-33 7.75

-.78 2.38

-8.07 252 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)

Input Lateral Expansion Computed LE Differential 69 725

-3.35 SUM of RESIDUAIS = 1.73 Temperature 375 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) 0H 0~

0D

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 A.

Data Set(s) Plotted Plant SU2 Cap: UNIRR Material: SRM SA533B1

_ He _

Ori: LT Heat : HSST PLATE 02 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature

-50

-20

-20 10 10 10 9

9 9

13 9

13 23 23 23 6.37 637 6.37 10.98 10.98 10.98 1827 1827 1827 Differential 262 2.62 2.62 2o.

-198 2.01 4.72 4.72 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 40 40 40 85 85 85 110 110 110 160 160 160 210 210 210 300 300 300 Input Percent Shear 29 33 29 41 42 43 55 58 67 87 84 85 98 98 100 100 100 100 Computed Percent Shear 28.84 28.84 28.84 49.72 49.72 49.72 61.88 61.88 61.88 8139 8L39 81.39 9217 9217 9217 98.59 9859 98.59 Differential 15 415

.15

-8.72

-7.72

-6.72

-6 88

-3 88 5.11 5.6 2a6 3.6 5.82 5.82 7.82 1.4 1.4 1.4 TM of 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 Capsule: X Total Fluence:

Orientation: LT cn CD 0) 0-0D

-300

-200

-100 0

100 200 300 400 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 ature Input Percent Shear Computed Percent Shear 500 600 Tempera Differential 20 80 90 125 155 215 300 345 3

15 15 25 35 100 100 100

.74 5.79 8.03 23 4616 8759 9929 99.85 225 92 6.96 1.99

-1L16 124

.7

.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 Capsule: V Total Fluence:

Orientation: LT 0)

C)

-300

-200

-100 0

100 200 300 400 500 600 Temperature in Degrees F Data Set(s) PI Plant SU2 Cap: V MateriaL: SRM SA533B otted 1

Orin: LT Heat I HSSI PLATE 02 Charpy V-Notch Data Input Percent Shear Computed Percent Shear Temperature 75 125 150 175 200 250 350 425 15 25 25 35 45 50 100 100 10.56 19.99 26.65 3458 43.46 61.92 87.91 95.72 Differential 4.43 5

-1.65

.41 153

-1192 12.08 427 S = 1416 SUll of RESIDUAL' 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 Capsule: Y Total Fluence:

Orientation: LT 0H a) n C0

-300

-200

-100 0

100 200 300 400 500 Temperature in Degrees F 600 Data Set(s) Plotted Plant SU2 Cap: Y Material: SRM SA533BI Ori: LT Heat # HSST PLATE 02 Charpy V-Notch Data Temperature 72 125 175 200 225 250 325 Input Percent Shear Computed Percent Shear Differential 10 15 20 25 30 55 100 1.05 42 14.32 24.6 38.9 55.41 9022 8.94 10.79 5.67

.39

-8.9

-.41 9.77

'* Data continued on next page ***

C-102

CAPSULE Y CORRELATION MONITOR MATERIAL Page 2 Material: SiI1M SA533B1 Heat Number. HSST PLATE 02 Orien Capsule: Y Total Fluence:

Charpy V-Notch Data (Continued)

Input Percent Shear Computed Percent Shear 100 9723 Sul tation: LT Differential 2.76 4 of RESIDUALS = 29.02 Temperature 375 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'13 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

,. AAf I erest Copper 63Cu(n,(X)60Co Iron 5Fe(np)s4Mn Nickel 58Ni(np)58Co Titanium E

6T(np)fSc Uranium-238 23U(n,f)137Cs Neptunium-237 237Np(nf)13 7Cs 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 238U 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 Wy S 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 listed The fission sensor reaction rates as listed include the applied corrections for 28U 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.

For the least squares evaluation of the Surry Unit 2 surveillance capsule dosimetry, the FERRET codeO2]

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 1 a 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 6 3Cu(na) Co 4.08-4.16%

54Fe(n,p) Mn 3.05-3.11%

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

'1 Target 9Q% Response, i sso tom i 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 Neptunium-237 2 7Np (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 Cycl J 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+1 0 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 ? snu cleusI-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)

Reacton l

slaton ml Rection M easui red Calculted

=

Estimate 6 3Cu(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)58Co 8.26E-15 7.96E-15 8.42E-15 1.04 0.98 238U(nf)' 37Cs (Cd) 2.75E-14 2.82E-14 2.90E-14 0.98 0.95 237Np(nf)137Cs (Cd) 1.89E-13 2.14E-13 2.01E-13 0.88 0.94 59Co(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(X2/DOF= 0.16)

R

?.

>eaE

,,sctirn Raq

' I te ' ps/*, x,

?

R"eacdion Meeasured Cal, lidtd

,Estinate MIC MIRE 63Cu(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 58Ni(np) 5Co 6.36E-15 7.12E-15 6.63E-15 0.89 0.96 23u(nf)13 7CS (Cd) 2.36E-14 2.51E-14 2.33E-14 0.94 1 01 237Np(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 58Ni(n,p)58Co 2.29E-15 2.66E-15 2.33E-15 0.86 0.98 238U(nf)137Cs (Cd) 6.81E-15 8.47E-15 7.22E-15 0.80 0.94 237Np(nf)l37Cs (Cd) 5.04E-14 5.73E-14 4.93E-14 0.88 1.02 59Co(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.

63Cu(n,a)6Co 3.21E-17 3.27E-17 3.15E-17 0.98 1.02

'Fe(n,p)4Mn 3.04E-15 3.35E-15 3.12E-15 0 91 0.97 238U(nf)1 3 7 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 59Co(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 Ca k

' 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

E..

~dEstimate

. ia)__

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 Capsule Y

Casue SW.

Capsule Y 63Cu(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 238U(nf) 37Cs (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

E>a 10MeV)

(§dpa 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, FERRETDataAnalysis Core, 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 228.40F. 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 208.80F 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 228.40F. 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 208.80F 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 228.40F (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 1 OCFR50 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 (1 1 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 Material ID Location (wt0/6)

(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 0 0 17 0 34 0 125 5 1161 C4326-1 Intermediate Shell 0 110 0 550 3 530 73 5 Tables 10 0 0 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 8 5 17 0 149 9 139 7 4415-2 Lower Shell 0 110 0 500 3 530 73 0 Tables 0

0 0 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 (1 00%), 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-Capsule ID (Including Source)

Copper (wt 0!.)

Nickel (wt%)

Temperature (F)

Fluence Factor Measured Delta-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 0 520 5401 04 1 1743 64 64

-25 Surry Unit 2 Capsule Y (Long) 0 104 0 520 543 7 1 2679 114 114 18 Surry Unit 2 Capsule Y (Trans) 0 104 0 520 543 7 1 2679 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 0 0 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 1 chemistry 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?

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 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 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 1 1 Chemistry Factor Position 2 1 Chemistry Factor Credible?

Position 1 1 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 1 Capsule 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)

PoInt Beach Unit 1 Capsule 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 1 and 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 0 0 131 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 if the 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

ML030990293

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