View source for DCL-03-052, Rev 0 to WCAP-15958, Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix a Through E

{{Adams
| number = ML031400347
| issue date = 01/31/2003
| title = Rev 0 to WCAP-15958, Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix a Through E
| author name = Oatley D
| author affiliation = Westinghouse Electric Co, LLC
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000275
| license number = DPR-080
| contact person = 
| case reference number = DCL-03-052, FOIA/PA-2005-0108
| document report number = WCAP-15958, Rev 0
| document type = Topical Report
| page count = 151
}}

=Text=
{{#Wiki_filter:A-0 APPENDIX A LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS
* Specimen prefix "E" denotes Intermediate Plate, Longitudinal Orientation
* Specimen prefix "R" denotes Correlation Monitor Material
* Specimen prefix "W" denotes Weld Material
* Specimen prefix "H" denotes Heat-Affected Zone material
* Load (1) is in units of lbs
* Time (1) is in units of milli seconds Appendix A

                                                ---       l :~~
A-i t5 3001II (a
0
           -j 2001cI 1001III 0 1 2          3     4 5     6 Time (1)
E52, -25&deg;F 5001 I.
4001 I-D   3001 0
           -J 2001I I-1001 I.
0 1 2          3     4 5     6 Time (1)
E49, 25&deg;F 500'I0 4001p.
            -s3W
           -J 0 1 2          3     4 5     6 Time (1)
E55, 75-F Appendix A

A-2 03 0
           -J Time (1)
E51, 110-F 0
           -J Time (1)
E53, 125&deg;F
           '0 0
           -J 0 1 2          3     4 5 6 Time (1)
E50, 175 0F Appendix A

A-3 5000 0
0      1   2           3     4 56 Time (1)
E54, 2500 F 1000 1 ,
5000-4000-\
             *~3000-2000 0
0      1   2           3     4 5  6 Time ()
n  3000 E56, 2750 F 2000     --   \
5000 4000 1000 0.
0      1   2           3     4 5  6 Time (1)
R49. 25F Appendix A

A-4 A
           -~ 300(
C
           -j 20C I
O     1                      2                        3                      4                5                     6 Time (1)
R51, 50&deg;F
                                    '~ ~ ~                ~..          .....             .......         ..
500C3.
400C3.
           *; 300C 0
           -J 200C3.
:~~     ~~       .......
1CC  3.
C     1                      2                        3                      4                 S                    6 Time (1)
R56, 100 0F I
2000 1000 0      1                     2                        3                      4                 5                    6 Time (1)
R55, 150&deg;F Appendix A

A-5 sooo       +            . . . ........
40007
           *3000I-o 2000 1000~
0   1   2          3                  4          S 6 Time (1)
R53, 200&deg;F sooo 2 4000+/-
4000, 3000 4.
2000i 1000-0   1   2          3                  4          5 6 Time (1)
R54, 250&deg;F 5000                            . . . .        . . .-
4000t T
i 3000 }                                 .......
2000+/-
10001 0
0   1   2          3                  4          5 6 Time (1)
R50, 300&deg;F Appendix A

A-6 50001            -.
4000+
3000X 20001 1000 -                                  ....      ....
0 0      1 2            3     4          S               6 Time (1)
R52, 325&deg;F 5000 4000
           *0 3000 2000 1000 0
0      1 2            3     4          5               6 Time (1)
WI ,25&deg;F sooo0                                ..             ..........
4000     1-                                 -   -..    .. ... .
X3 0 0 0 2000        . .
1000 0
0      1 2            3     4          S               6 Time (1)
W13, 100&deg;F Appendix A

A-7 0 1 2           3     4 5 6 Time (1)
W12, 150&deg;F 0 1 2           3     4 5 6 Time (1)
W9, 200&deg;F 0 1 2           3     4 5 6 Time (1)
W 10, 225&deg;F Appendix A

A-8 5000     . ..    .
sooo b     ~~.    . . .. .  . . . . .. .. . . . . . . ..
4000
           '3000                  \ -.
2000 . .               \  .
1000                                                             .. ...
0              1                2                       3                 4        5 6 Time (1)
W15, 300&deg;F 5000      ......
4000 .
3000 2000                                            .       .\
10 00                 l..                      .. . .. .\. ... .. . . .. . .. ... .
1000 0
0              1                 2                      3                 4        5 6 Time (1)
W14, 325&deg;F 5000 . .. ........          .......    .
4000 ..                                     \   .                   ......
3000               ..      ....                      ...
2000 1000 0
0              1                 2                      3                 4        5 6 Tine (1)
W 16, 350F Appendix A

A-9 0
300( ,1 200(
1lOOt V.
0  1 2           3     4 5 6 Time (1)
H14, -125-F 5001 4001
           *G 3001 0
           -J 200(
3-1001 0  1 2           3     4 5 6 Time (1)
H12, -50&deg;F
           -  3000-2           3     4 5 6 Time (1)
H 11, 0&deg;F Appendix A

A-10 0 1 2           3     4 S 6 Time (1)
IH10, 72&deg;F 0 1 2           3     4 5 6 Time (1)
H9, OO&deg;F 0 1 2           3     4 S 6 Time (1)
H15, 125&deg;F Appendix A

A-1l
           -J 0 1 2          3     4 S 6 Time (1)
H16, 175&deg;F 0
           -j 0 1 2          3     4 5 6 Time (1)
H13, 225&deg;F Appendix A

B-O APPENDIX B CHARPY V-NOTCH SHIFT RESULTS FOR EACH CAPSULE PREVIOUS FIT* VS. SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD (CVGRAPH VERSION 4.1)
*The previous fit was plotted by PG&E using the EPRI Hyperbolic Tangent Curve Fitting Routine.
Appendix B

B-1 TABLE B-I Changes in Average 30 ft-lb Temperatures for Intermediate Shell Forging B4106-3 (Longitudinal Orientation)
Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                  CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT30        Unirradiated       Irradiated  AT30 S             5               3              -2              5.14              3.36   -1.78 Y              5              52              47              5.14             53.81   48.66 V             -                                       1      5.14             39.46   34.32 TABLE B-2 Changes in Average 50 ft-lb Temperatures for Intermediate Shell Forging B4106-3 (Longitudinal Orientation)
Previous Fit vs. CVGRAPH 4.1 [F]
l_______          Previous Fit   _                              CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT50        Unirradiated      CVGRAPH      AT50 S            41              45              4              39.31             45.43    6.11 Y            41              94              53             39.31             91.82   52.51 V                                             -             39.31             77.51   38.19 TABLE B-3 Changes in Average 35 mil Lateral Expansion Temperatures for Intermediate Shell Forging B4106-3 (Longitudinal Orientation)
Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                  CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT35        Unirradiated       Irradiated  AT35
___               2_
29              29               0             28.65             28.92    0.27 Y            29              75              46             28.65             74.89   46.24 V               -               -             28.65             89.72   61.07 Appendix B

B-2 TABLE B-4 Changes in Average Energy Absorption at Full Shear for Intermediate Shell Forging B4106-3 (Longitudinal Orientation)
Previous Fit vs. CVGRAPH 4.1 [ft-lb]
Previous Fit*                                   (CVGRAPH 4.1 Fi t Capsule      Unirradiated     Irradiated           AE         Unirradiated       Irradiated        AE S             122             126                4             118               126             8 Y             122              119               -3             118               110            -8 (110)            (-12)
V                                -                              118               121             3
*Values in parenthesis were calculated per the definition of Upper Shelf Energy given in ASTM E185-82.
Note that the CVGRAPH USE values were also defined by ASTM E185-82.
TABLE B-5 Changes in Average 30 ft-lb Temperatures for Surveillance Weld Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                   CVGRAPH 4.1 Fit Capsule      Unirradiated     Irradiated          AT30        Unirradiated       Irradiated       AT30 5S            -67               43              110           -65.62             45.17        110.79 Y            -67              167              234           -65.62            166.97       232.59 V              -                                             -65.62            135.45       201.07 TABLE B-6 Changes in Average 50 ft-lb Temperatures for Surveillance Weld Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                   CVGRAPH 4.1 Fit Capsule      Unirradiated     Irradiated          AT5 o       Unirradiated       Irradiated       AT50 S            -23              125              148           -24.16            120.38       144.54 Y             -23              253              276           -24.16            255.73        279.9 V                                -                -           -24.16            219.26       243.43 Appendix B

B-3 TABLE B-7 Changes in Average 35 mil Lateral Expansion Temperatures for Surveillance Weld Material Previous Fit vs. CVGRAPH 4.1 [F]
q Previous Fit                                   CVGRAPH 4 Fit Capsule      Unirradiated     Irradiated          ATs         Unirradiated       Irradiated        AT 35 S              -46              96              142            46.52             95:28         141.81 Y              -46             195              241            -46.52           194.25        240.77 v                                                              -46.52           220.66        267.19 TABLE B-8 Changes in Average Energy Absorption at Full Shear for Surveillance Weld Material Previous Fit vs. CVGRAPH 4.1 [ft-lb]
Previous Fit*                                   CVGRAPH 4.1 Fit Capsule      Unirradiated     Irradiated           AE         Unirradiated       Irradiated        AE S               98              87              -II              91               81            -10 Y               98              66              -32              91               60            -31 (60)             (-38)
V                -               -                               91               66            -25
*Values in parenthesis were calculated per the definition of Upper Shelf Energy given in ASTM El 85-82.
Note that the CVGRAPH USE values were also defined by ASTM E185-82.
TABLE B-9 Changes in Average 30 ft-lb Temperatures for the Weld Heat-Affected-Zone Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                   CVGRAPH 4.1 Fit Capsule      Unirradiated     Irradiated          AT3 0       Unirradiated       Irradiated        AT>
S             -168             -91               77           -163.55           -91.24         72.31 Y             -168             -84               84           - 163.55          -83.77         79.77 V                                                             -163.55           -52.65         110.9 Appendix B

B-4 TABLE B- O Changes in Average 50 ft-lb Temperatures for the Weld Heat-Affected-Zone Material Previous Fit vs. CVGRAPH 4.1 [1F]
U Previos Fit                                     CVGRAPH 41 Fit Capsule      Unirradiated      Irradiated          AT, 0       Unirradiated      Irradiated        AT 50 s            11                 -55              56           -111.75           -55;29         56.46 Y             -111              -36              75           -111.75           -35.96         75.78 V               -                -                -           -111.75            -1.98         109.77 TABLE B-I I Changes in Average 35 mil Lateral Expansion Temperatures for the Weld Heat-Affected-Zone Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                   CVGRAPH 4.1 Fit Capsule      Unirradiatedl    Irradiated          AT35         Unirradiated      Irradiated        AT3s S             -107              -64              43            -107.5           -64.26         43.24 Y       1     -107              -36              71       1    -107.5           -36.47         71.03
                                                          -  -     -107.5            18.76         126.27 TABLE B-12 Changes in Average Energy Absorption at Full Shear for the Weld Heat-Affected-Zone Material Previous Fit vs. CVGRAPH 4.1 [ft-lb]
Previous Fit*                                   CVGRAPH 4.1 Fit Capsule      Unirradiated     Irradiated           AE          Unirradiated      Irradiated        AE S              147              125             -22              136              125           -11
    -Y             147              110             -37              136              109           -27 (109)           (-38)
V                                -                               136              116           -20
*Values in parenthesis were calculated per the definition of Upper Shelf Energy given in ASTM El 85-82.
Note that the CVGRAPH USE values were also defined by ASTM El 85-82.
Appendix B

B-5 TABLE B-13 Changes in Average 30 ft-lb Temperatures for the Correlation Monitor Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                  CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT30        Unirradiated      Irradiated          AT30 S            46              112             66            46.44            112.06           65.62 Y             46              158             112           46.44            162.23           115.79 V              -               -               -            46.44            163.05           116.61 TABLE B- 14 Changes in Average 50 ft-lb Temperatures for the Correlation Monitor Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                  CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT50        Unirradiated      Irradiated          AT50 S            78              146             68             78.3            143.42           65.11 y            78              190             112            78.3             188.9           110.59 V                             -               -             78.3            197.42           119.12 TABLE B-15 Changes in Average 35 mil Lateral Expansion Temperatures for the Correlation Monitor Material Previous Fit vs. CVGRAPH 4.1 [F]
Previous Fit                                  CVGRAPH 4.1 Fit Capsule    Unirradiated     Irradiated         AT35        Unirradiated      Irradiated          AT3 s S            59              124             65            58.96            124.49           65.53 Y            59              178             119           58.96            178.01           119.05 V             -               -               -            58.96            213.46           154.49 Appendix B

B-6 TABLE B-16 Changes in Average Energy Absorption at Full Shear for the Correlation Monitor Material Previous Fit vs. CVGRAPH 4.1 [ft-lb]
U Previous Fit*                                   CVGRAPH 4.1 Fit Capsule      Unirradiated      Irradiated l         AE         Unirradiated      Irradiated        AE S             124               123 _            -1             123               120    l       -3 Y             124               122              -2             123               112           -11 (112)           ( -2)       _
V               -                -                -             123               117            -6
*Values in parenthesis were calculated per the definition of Upper Shelf Energy given in ASTM El 85-82.
Note that the CVGRAPH USE values were also defined by ASTM E185-82.
Appendix B

C-O APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING SYMMETRIC HYPERBOLIC TANGENT CURVE-FITTING METHOD Appendix C

C-1 Contained in Table C-I 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:
         "ipper 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 unirradiated 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-I 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-1 Upper Shelf Energy Values Fixed in CVGRAPH ft-lb]
Nlaterial              Unirradiated       Capsule S        Capsule Y       Capsule V Intermediate Shell Plate             118               126              110             121 B4106-3 (Longitudinal Orientation)
Weld Metal                   91                81               60              66 (heat # 27204)
HAZ Material                   136              125               109             116 Correlation Monitor                123              120               112             117 Material
*The Charpy V-notch curves show a value of 2.19 ft-lb, rather then 2.2. This is an inconsistency with the CVGraph program; the value of 2.2 is entered into the program, however, the value of 2.19 appears on the plot. This inconsistency is not expected to alter the results.
Appendix C

INTER SHELL PLATE B4106-3 UNIRR (LONG)
CVGRAPI 4i lyperbolic Tangent Curve Printed at 11:11:43 on 0-19-2002 Page I Coefficients of Curve I F        A  = 60.09                   B = 57.9                     C = 85.44                     T = 54.37 Equation is. CVN = A + B
* I tanh((T - T)/C) I Upper Shelf Energy: 118 Fixed       Temp. at 30 ft-lbs:      5.1     Temp. at 50 ft-lbs        393       Lower Shelf Energy: 219 Fixed Material: PLATE SA533B1               Heat Number: B4106-3            Orientation: LT Capsule: UNIRR        Total Fluence:
300-250F 2001F P;%
0_
(I1 z__
150 100 I0            X                        I I           0 C) 50~~~~~~~~~            ooX t-~~~~~l/
u
            -300         -200         -100             0         100          200             300         400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: UNIRR        iaterial: PLATE SA533BI          Ori: LT        Heat  #: B4106-3 Charpy V-Notch Dakta Temperature                     Input CVN Energy                         Computed CVN Energy                       Differential
        -50                                 6                                            11.45                            -5.45
        -50                                 6                                            11.45                            -5.45
        -50                                 6                                            11.45                            -5.45
        -20                                215                                           19.47                              2.02
        -20                                 28                                           19.47                              8.52
        -20                                 22                                           19.47                              2.52 10                                37                                          32.46                               4.53 10                                46                                          32.46                              13.53 10                                29                                          3246                              -3.46
                                               *** Data continued on next page       'll C-2

INTER SHELL PLATE B4106-3 UNIRR (LONG)
Page 2 Material: PLATE SA533B1               Heat Number. B4106-3       Orientation: LT Capsule. UNIRR      Total Fluence Charpy V-Notch Data (Continued)
Temperature              Input CVN Energy                       Computed CVN Energy              Differential 40                          55                                     50.44                         4.55 40                          25                                     50.44                       -25.44 40                         53.5                                    50.44                         3.05 40                          50                                     50.44                        -.44 110                          77                                     9323                        -1623 110                          100                                     9323                         6.76 110                          107                                     9323                         13.76 210                         120.5                                   115.04                        5.45 210                          118                                    115.04                        2.95 210                         1145                                    115.04                       -.54 SUM of RDUALS = 5.13 I
I C-3

INTER SHELL PLATE B4106-3 CAPSULE S (LONG)
CVGRAPI! 4.1 yperbolic Tangent Curve Printed at 11:11:43 on 08-19-2002 Page I Coefficients of Curve 2 A= 64.09                    B 61.9                     C = 108.49                     TO = 70.58 Equation is CVN = A + B I tanh((T - T0)/C) I Upper Shelf Energy: 126 Fixed      Temp. at 30 ft-lbs:     3.3      Temp. at 50 f-lbs 45.4              Lower Shelf Energy: 2.19 Fixed Material: PLATE SA533B1                Heat Number: B4106-3         I)rientation: LT Capsule: Total Fluence: 2.84E+18 co
 "-q M
l 5H V
z4 0)
             -300       -200         -100             0         100          200          300           400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: S      Material: PLATE SA533BI         Ori: LT        Heat #: B4106-3 Charpy V-Notch Data Temperature                   Input CVN Energy                         Computed CVN Energy                      Differential
        -25                                 10                                       20.33                              -1033 25                                32                                       39.51                               -7.51 50                                59                                       5249                                  6.5 76                                92                                       6718                                 241 125                                97                                       92.78                                421 125                                59                                       92.78                              -33.78 200                               128                                       115.56                               12.43 350                               124                                       12528                               -128 SiUIM of RESIDUALS =-4.95 C4

INTER SHELL PLATE B4106-3 CAPSULE Y (LONG)
CVGRAPII 4.1 Hyperbolic Tangent Curve Printed at 11:11:43 on 08-19-2002 Page Coefficients of Curve 3 A = 56.09                    B = 53.9                      C = 91.63                        TO = 10224 Equation is. CVN = A + B          tanh((T - T0)/C) I Upper Shelf Energy: 110 Fixed      Temp. at 30 f-lbs       53.8        Temp. at 50 ft-lbs           91.8      Lower Shelf Energy: 19 Fixed Material: PLATE SA533BI                Heat Number.        4106-3           Orientation: LT Capsule: Y         Total Fluence: 1.05E+19 259fY In 20 150 1u z
I
                                                                    /7           4                4             +          +
e,0/
I                              .1            L 0
              -300      -200         -100               0         100          200               300           400        500          600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: Y       Material: PLATE SA533BI            Ori: LT             Heat : B4106-3 Charpy V-Notch Data Temperature                    Input CVN Energy                           Computed CVN Energy                           Differential
         -25                                 12                                             851                                  3.48 20                                20                                             17.55                                 244 50                                37                                            2831                                   8.68 75                               33                                            40.53                                -7.53 125                                63                                            6921                                -621 175                               96                                              91.7                                 4129 225                               113                                           103.07                                 9.92 275                               107                                           10757                                 -.57 SUM of RESIDUAIS = 14.5 C-5

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
CVGRAPH 41 Hyperbolic Tangent Curve Printed at 11:11:43 on 08-19-2002 Page I Coefficients of Curve 4 A = 61.59                   B = 59.4                     C = 9629                    TO = 96.56        l Equation is: CVN = A + B I anh((T - TO)/C) I Upper Shelf Energy 121 Fixed      Temp. at 30 ft-lbs      39.4       Temp. at 50 ft-lbs     77.5     Lower Shelf Energy: 2.19 Fixed Material: PLATE SA533BI                 leat Number. B4106-3        Orientation: LT Capsule: V       Total Fluence 137E+19 300-----_                                                                    __
250' 150 10                                                          In 50 0
             -300      -200         -100              0          100         200          300         400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: V       Material: PLATE SA533BI         Ori: LT       Heat #: 134106-3 Charpy V-Notch Data Temperature                   Input CVN Energy                          Computed CVN Energy                    Differential
        -25                               15                                           11                               3.99 25                              32                                          2411                              7.88 75                              33                                         48.51                            -15.51 110                              7Q                                         69.83                                .16 125                              92.                                        78.64                              13.35 175                              94                                         10152                            -752 250                              12                                         11628                               5.71
                                             >>'* Data continued on next page I"*
C-6

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
Page 2 Material: PLATE SA533B1           leat Number. B4106-3          Orientation: LT Capsule V     Total Fluence: 1.37E+19 Charpy V-Notch Data (Continued)
Temperature               Input CVN Energy                    Computed CVN Energy                    Differential 275                           119                                    118.15                           .84 SUM of RESIDUAIS = 8.91 I
i i
i C-7

INTER SHELL PLATE B4106-3 UNIRR (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 11:38.29 on 08-19-2002 Page I Coefficients of Curve I A= 45.01                      B = 44.01                     C = 88.8                     TO = 4921 Equation is LE = A+ B
* I tanh((T - T0)/C) I Upper Shelf LE- 89.02              Temperature a LE 35: 28.6                Lower Shelf LE I Fixed Material: PLATE SA533B1                 Heat Number. B4106-3           Orientation: LT Capsule: UNIER        Total Fluence.
       -300        -200         -100               0         100          200            300         400        500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DC]       Cap: UNIRR        liaterial PLATE SA533BI           Ori: LT       Heat : B4106-3 Charpy V-Notch Data Temperature                 Input Lateral Expansion                          Computed LE                         Differential
   -50                                  3                                           9.51                            -6.51
   -50                                  3                                           951                             -6.51
   -50                                  5                                           9.51                            -451
   -20                                  19                                          16.3                             2.69
   -20                                 24                                           16.3                              7.69
   -20                                 20                                           16.3                              3.69 10                                 31                                         26.74                              425 10                                 39                                          26.74                             1225 10                                23                                          26.74                            -3.74
                                          '** Data continued on next page C-8

INTER SHELL PLATE B4106-3 UNIRR (LONG)
Page 2 Material: PLATE SA533BI             Heat Number. 4106-3       Orientation: LT Capsule UNIRR      Total Fluence:
Charpy V-Notch Data (Continued)
Temperature           Input Lateral Expansion                     Computed LE                         Differential 40                          44                                      40.46                             3.53 40                          16                                      40.46                          -24.46 40                          45                                      40.46                              4.53 40                          40                                      40.46                            -.46 110                          60                                      71.17                           -11.17 110                          74                                      71.17                             2.82 110                          86                                      71.17                             14.82 210                          84                                      86.73                           -2.73 210                          85                                      86.73                           -1.73 210                          89                                      86.73                             226 SUNI of RESIDUALS =-327 I
i I
i I
It I
I C-9

INTER SHELL PLATE B4106-3 CAPSULE S (LONG)
CYGRAPH 41 Hyperbolic Tangent Curve Printed at 11:29 on 08-19-2002 Page 1 Coefficients of Curve 2 A = 3686                    B = 3536                    C = 75.79                   TO =3287 Equation is: LR = A B I anh((T - TO)/C) I Upper Shelf LE 72.72             Temperature at LE 35: 28.9            Lower Shelf LE I Fixed Material: PLATE SA533B1               Heat Number. B4106-3         Orientation: LT Capsule S       Total Fluence: 84E+18 200-U)
P-4
. .-    15F 100 0
 -5H Pa--                                                                                          0 Ct                                                         0 50                                                       0 U
             -300      -200         -100             0         100        . 200          300         400       500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: S       Material: PLATE SA533B1        Ori: LT      Heat #: B4106-3 Charpy V-Notch Data Temperature               Input Lateral Expansion                         Computed LE                       Differential
        -25                               105                                       13.79                           -329 25                               30                                       3315                             -3.15 50                               47                                       4483                               2.16 716                              68                                       553                               1Z67 125                              655                                       6692                             -1.42 125                              45.5                                      66.92                           -21.42 200                               79                                       7186                               7.13 350                              77.5                                      72.71                             4.78 SUM of RESIDUAIS = -2.54 C-10

INTER SHELL PLATE B4106-3 CAPSULE Y (LONG)
CVGRAPII 4.1 llyperbolic Tangent Curve Printed at I1:3829 on 08-19-2002 Page I Coefficients of Curve 3 l         A = 43.76                   B = 42.76                    C = 110.43                   TO = 97.85 Equation is LE = A + B tanh((T - TO)/C)
Upper Shelf LE- 86.52            Temperature at L 35: 74.8               Lower Shelf LE I Fixed Material: PLATE SA533BI                Heat Number. 131106-3         Orientation: LT Capsule Y        Total Fluence: 1.05E+19 AXU I
U) 15V ooL
'I 0a sr              -11X
                                            .~~~~~~~~~I u
           -300       -200         -100              0         100         200           300          400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: Y       Mlaterial: PLATE SA533BI         Ori: LT      lleat  : B4106-3 Charpy V-Notch Data Temperature                 Input Lateral Expansion                         Computed LR                         Differential
      -25                                  13                                        9.34                               3.65 20                                 18                                        17.78                               21 50                                 31                                        2631                               4.68 75                                29                                         35.03                            -6.03 125                                 50                                        54.06                            -4.06 175                                75                                         69.56                              5.43 225                                84                                         7M74                               525 275                                77                                         83.19                             -6.19 SUM of REiDUALS = 2.94 C-1l

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
CVGRAPH 4.1 lyperbolic Tangent Curve Printed at 11:3829 on 08-19-2002 Page 1 Coefficients of Curve 4 A = 41.48                   B = 40.48                   C = 106.09                    TO = 106.87 Equation is L = A + B I tanh((T- TO)/C) I .
Upper Shelf LE 81.97             Temperature at L 35:         89.7        Lower Shelf LE I Fixed llaterial: PLATE SA533BI              Heat Number3B4106-3             Orientation: LT Capsule V         Total Fluence 137E+19 204T Cl)
'--4 150[
0)r-100 4-,
50:
1)
             -300       -200         -100              0        100          200            300         400          500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: V       Material: PLATE SA533BI          Ori: LT        leat : B4106-3 Charpy V-Notch Data Temperature                 Input Lateral Expansion                         Computed LK                          Differential
        -25                                  5                                           722                             -222 25                                 19                                         1525                               3.74 75                                21                                          29.67                            -&67 110                                46                                          4Z68                               3.31 125                                57                                          48.33                              8.66 175                                56                                          64.41                            -8.41 250                                78                                          76.86                              113
                                               >> Data continued on next page         '
C-12

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
Page 2 Materi. a1: PLATE SA533BI           Heat Number: B4106-3       Ori enlation: LT Capsule V     Tolal Fluence 137E+19 Charpy V-Notch Data (Continued)
Temperature              Input Lateral Expansion                     Computed LE                     Differential 275                              80                                  78.71                  -         1,8 SUM of RESIDUALS = -1.18 C-13

INTER SHELL PLATE B4106-3 UNIRR (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 11:49.00 on 08-19-2002 Page 1 Coefficients of Curve I A = 50                        B = 50                      C = 10z2.68                  T0 = 77.35 Equation is Shear/. = A+ B I tanh{(T - TO)/C)]
Temperature at 50z. Shear. 773 Material: PLATE SA533B1                 Heat Number. B4106-3           Orientation: LT Capsule. UNIRR        Total Fluence:
       -300       -200         -100               0         100         200             300        400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR        Material: PLATE SA533B1           Or: LT       Heat #: 134106-3 Charpy V-Notch Data Temperature                 Input Percent Shear                       Computed Percent Shear                     Differential
   -50                                 9                                            7.72                              127
   -50                                 9                                            7.72                              127
   -50                                 9                                            7.72                              127
   -20                                14                                           13.05                              .94
   -20                                14                                           13.05                               .94
   -20                                14                                           13.05                               .94 10                                25                                           2121                               3.78 10                                20                                           2121                              -121 10                                25                                           2121                               378
                                         *-1 Data continued on next page I'l C-14

INTER SHELL PLATE B4106-3 UNIRR (LONG)
Page 2 Material: PLATE SA533131             Heat Number. B4106-3       Orientation: LT Capsule: UNIRR      Total Fluence Charpy V-Notch Data (Continued)
Temperature             Input Percent Shear                   Computed Percent Shear                Differential 40                           34                                     3257                              1.42 40                           29                                     32.57                           -3.57 40                           34                                     3257                              1.42 40                          30                                     32.57                           -2.57 110                          56                                     6538                            -9.38 110                          65                                     6538                             -.38 110                          65                                     65.38                            -.38 210                          100                                    92.98                             7.01 210                          100                                    92.98                             7.01 210                          100                                    92.98                             7.01 SUM of RESIDUAL 3 = 20.62 C-15

INTER SHELL PLATE B4106-3 CAPSULE S (LONG)
CVGRAPH 4.1 lyperbolic Tangent Curve Printed at 11:49:00 on 08-19-2002 Page I Coefficients of Curve 2 I         A=50                        B=50                        C=97                       T0=87.89 Equation is Shear/ = A+ B I tanh((T - TO)/C) I Temperature at Se!. Shear. 878 Mlaterial: PLATE SA533BI               Heat Number. B4106-3         Orientation: LT Capsule: S       Total Fluence: 2.84E+18
        -300      -200          -100            0          100         200           300         400      500          600 Temperature in Degrees F Data Set(s) Plotted Plant DCI        Cap: S     Material: PLATE SA533BI          Ori: LT      Heat : B4106-3 Charpy V-Notch Data Temperature                  Input Percent Shear                    Computed Percent Shear                  Differential
   -25                                 2                                         8.88                           -6.88 25                               20                                        21.47                           -1.47 50                               30                                         31.4                            -1.4 76                                60                                        43.9                            16.09 125                               70                                        6824                              1.75 125                               50                                        6824                           -1824 200                               100                                       90.98                             9.01 350                               100                                       99.55                              A4 SUM of RESIDUAIS = -.69 C-16

INTER SHELL PLATE B4106-3 CAPSULE Y (LONG)
CVGRAPH 4.1 llyperbolic Tangent Curve Printed at 11:9:00 on 08-19-2002 Page I Coefficients of Curve 3 F         A50                       B = 50                     C = 8724                      TO = 99.6 Equation is Shear = A + B         tanh((T - TO)/C)     I Temperature at 50z Shear:      99.6 Material: PLATE SA533BI              Ileat Number. 114106-3         Orientation: LT Capsule: Y      Total Fluence: 1.05E+19 100~~~~~~~~~~~~~~~~1 80-a)
CD       6(F 0) 0
  )
4CF 21r 0~~~~~
            -300     -200         -100            0          100        200             300         400        500         600 Temperature in Degrees F Data Set(s) Plotted Plantl DCI      Cap: Y      Material: PLATE SA533BI         Ori: LT       Beat #: B4106-3 Charpy V-Notch Data Temperature                Input Percent Shear                    Computed Percent Shear                    Differential
       -25                               10                                        5.43                              4.56 20                              15                                       13.8                                1.11 50                               30                                       2428                               5.71 75                              30                                       3625                             -625 125                              60                                       64.15                             -4.15 175                              90                                        1.91                              5.08 225                             100                                       94.65                              5.34 Z75                             100                                       9823                                1.76 SUM of RESIDUALS = 13.17 C-17

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 11:49:00 on 08-19-2002 Page 1 Coefficients of Curve 4 A = 50                       B = 50                      C = 7205                     TO = 117.18 Equation is: Shear = A+ B I tanh((T - TO)/C) I Temperature at 50. Shear. 117.1 Material: PLATE SA533BI                 Heat Number B4106-3            Orientation: LT Capsule V         Total Fluence 1.37E+19
        -300      -200         -100              0          100         200            300          400         500         600 Temperature                          in DeLrees F
                                                   .~~~~~~~~~~~~~~~~~~~~          ..
I Data Set(s) Plotted Plant DCI       Cap V        Mlaterial: PLATE SA533B1         Ori: LT        Heat #: B4106-3 Charpy V-Notch Data Temperature                 Input Percent Shear                       Computed Percent Shear                     Differential
   -25                                5                                           1.89                                 3.1 25                               10                                          7.18                                2.81 75                               15                                         23.66                              -8.66 110                              45                                          45.02                               -.02 125                               65                                         5539                                  9.6 175                               75                                         8326                               -826 250                              100                                         97.55                                2.44
                                         -" Data continued on next page *'1, C-18

INTER SHELL PLATE B4106-3 CAPSULE V (LONG)
Page 2 Mlaterial: PLATE SA533B1            Heat Number. B4106-3        Orientation: LT Capsule V     Total Fluence 1.37E+19 Charpy V-Notch Data (Continued)
Temperature                Input Percent Shear                 Computed Percent Shear                Differential 275                             100                                   98.76                           123 SUM of RESIDUALS = 223 C-19

WELD METAL UNIRRADIATED CVGRAPII 4.1 Hyperbolic Tangent Curve Printed at 12:2017 on 08-19-2002 Page I Coefficients of Curve I I         A = 4659                     R=   44.4                     C = 8827                         TO = -30.93 Equation is CVN = A + B I tanh((T - TO)/C) I Upper Shelf Energy: 91 Fixed        Temp. at 30 -lbs -65.6              Temp. at 50 f-lbs. -24.1               Lower Shelf Energy: 2.19 Fixed Material: ELD LINDE 1092                 Beat Number 27204 FLUX LOT 3714                  Orientation:
Capsule UNIRR         Total Fluence:
300-:
U)     25CFY la 0__
200 Is 15i V_
10  0                                                        03           _ _   _     _      _  _   _      _  _   _    _    _
50 I)
             -300         -200         -100               0        100           200              300           400          500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR       Material: WELD LINDE 1092           Ori.:           Heat #: 27201 FLUX LOT 3714 Charpy V-Notch Data Temperature                     Input CN Energy                            Computed CVN Energy                           Differential
        -150                                 19.5                                             7B                                    11.69
        -150                                  9                                               7.8                                    1.19
        -150                                 22.5                                             7.8                                  14.69
        -100                                 15.5                                            17.55                                -2.05
        -100                                 17.5                                            17.55                                 -.05
        -100                                  14                                             17.55                                -3.55
         -50                                 44.5                                            37.15                                  734
         -50                                  24                                             37J5                                 -13.15
         -50                                 295                                             37.15                                -7.65
                                                  *' Data continued on next page           '
C-20

VELD METAL UNIRRADIATED Page 2 Material: WELD LINDE 1092             Heat Number 27204 FLUX LOT 3714        Orientation:
Capsule, UNIRR       Total Fluence:
Charpy V-Notch Data (Continued)
Temperature                Input CYN Energy                        Computed CVN Energy                Differential
   -20                              50                                      52.07                        -2.07
   -20                             615                                      52.07                          9.42       Ij
   -20                             54.5                                     52.07                          2.42        ii 10                            63.5                                     65.83                        -2.33          I P
10                            59.5                                     65S3                         -6.33 10                             70                                      65.83                          4.16         I 40                             845                                      76.17                          832          i 40                              79                                      76.17                           2.82 40                              69                                      76.17                        -7.17 110                             83                                      87.49                        -4.49 110                            945                                      87.49                            7 110                             94                                      87.49                           65 UM of RESIDUALS = 26.7 II I
I ii I
C-21

WELD METAL CAPSULE S CVGRAP}I 4.1 lyperbolic Tangent Curve Printed at 122017 on 08-19-2002 Page 1 Coefficients of Curve 2 A = 41.59                   B = 39.4                    C= 144.65                 TO = 89.06 Equation is CVN = A      B
* I tanh((T - T0)/C) I Upper Shelf Energy: 81 Fixed       Temp. at 30 ft-lbs 45.1         Temp. at 50 ft-lbs 1203        Lower Shelf Energy: 219 Fixed Material: WiELD LINDE 1092            Heat Number. 27204 LUX LOT 3714           Orientation:
Capule S       Total Fluence 284E18 30tF 2507 200 150 50~~~~~                   -s--           ~     ~      - --
U'              I 300        -200        -100            0          100         200          300       400         500           600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: S      Material: ELD LINDE 1092          Ori:      leat #: 27204 FLUX LOT 3714 Charpy V-Notch Data Temperatt ire                   Input CVN Energy                        Computed CVN Energy                   Diflrerential 25                                21                                        252                              -42 60                                30                                       33.78                            -3.78 76                                49                                       38.05                              10.94 76                                43                                       38.05                              4.94 125                                42                                       5119                             -9.19 0
200                                63                                       67.01                            -4.01 250                                80                                       73.31                               6.68 350                                81                                       78.91                               2.08 SUM of RESIDUALS = 3.45 C-22

WELD METAL CAPSULE Y CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 12:20.17 on 08-19-2002 Page I Coefficients of Curve 3 l          A = 31.1                   B = 28389                   C = 10821                   TO = 171.09 Equation is CVN = A + B I tanh((T - T0)/C) I Upper Shelf Energy: 60 Fixed        Temp. at 30 ft-lbs 166.9        Temp. at 50 ft-lbs 255.7         Lower Shelf Energy: 22 Fixed Material: WELD LINDE 1092             Heat Number 27204 FLUX LOT 3714            Orientation:
Capsule: Y      Total Fluence: 1.05E+19 c) 7la 44)
 ~z-4 0) zV1 I
            -300         -200         -100            0          100         200           300        400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DC1       Cap: Y      Material: WELD LINDE 1092         Ori:        Heat # 27204 FLUX LOT 3714 I
Charpy V-Notch Data Temperature                     Input CVN Energy                        Computed CVN Energy                     Differential 25                                 16                                         5.83                              10.16 100                                 17                                        14.44                              2.55 150                                 24                                        25.53                            -1.53 185                                 26                                        34.79                            -8.79 215                                 42                                        4222                              -22 250                                 58                                        49.09                               8.9 350                                 63                                        57.95                              5.04        .i 400                                 60                                        59.17                               82           i SUM of RESIDUAIS = 16.94 i
i C-23                                                                i I

WELD METAL CAPSULE V CVGRAPII 4.1 lyperbolic Tangent Curve Printed at 12:20:17 on 08-19-2002 Page 1 Coefficients of Curve 4 l         A = 34.09                  B = 31.89                     C= 123.9                   TO = 151.46 Equation is: CVN = A+ B [ tanh((T - TO)/C) I Upper Shelf Energy: 65.99 Fixed       Temp. at 30 ft-lbs 135.4         Temp. at 50 ft-Ibs 2192         Lover Shelf Energy: 2.19 Fixed Material: WELD UNDE 092                Heat Number 04 FLUX LOT 3714               Orientation:
Capsule. V        Total Fluence: 137E+19 300F (I)   250 10 4-,4   200-15f Q) 10fF z
(-
50 U'I 300        -200        -100              0          100         200          300        400          500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI      Cap: V       Material: WELD LINDE 1092          Ori:       Heat #: 27204 FLUX LOT 3714 Charpy V-Notch Data Temperature                    Input CVN Energy                          Computed CVN Energy                    Differential 25                                 11                                         9.53                              1.46 100                                23                                        21.56                              1.43 150                                36                                        33.72                              227 200                                 37                                        45.99                            -8.99 225                                 52                                        51.08                               .91 300                                 71                                        60.68                             10.31 325                                 60                                        62.34                            -2:34
                                               *1'$Data continued on next page 'l C-24

WELD METAL CAPSULE V Page 2 Material: ELD LINDE 1092           Heal Number 27204 FLUX LOT 3714       Orientation:
Capsule. V      Total Fluence: 1.37E+19 Charpy V-Notch Data (Continued)
Temperature               Input CVN Energy                     Computed CVN Eneergy               Differential 350                           66                                      63.51                       2.48 SUM of RESIDUALS = 7.56 I I i
C-25                                                   ; 1 I

WELD METAL UNIRADIATED CVGRAPH 4.1 yperbolic Tangent Curve Printed a 1230:39 on 08-19-2002 Page I Coefficients of Curve I A= 44.58                    B = 43.58                     C = 94.87                  TO = -25.31 Equation is LE = A+ B
* I tanh((T - TO)/C) I Upper Shelf LE 88.17              Temperature at LE 35: -465              Lower Shelf LE. I Fixed Material: WELD LINDE 1092               Heat Number. 27204 FLUX LOT 3714            Orientation:
Capsule: UNIRR       Total Fluence
        -300         -200        -100               0         100         200            300        400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DC]      Cap: UNIRR      Material: ELD LINDE 1092             Ori:         Heat : 27204 FLUX LOT 3714 Charpy V-Notch Data Temper;3ture                Input Laleral Expansion                          Computed LE                         Differential
   -150                                15                                           6.86                              813
   -150                                 8                                           6.86                               1.13
   -150                                18                                           6.86                              11.13
   -100                                12                                          15.95                            -3.95
   -100                                15                                          15.95                             -.95
   -100                                14                                          15.95                             -1.95
    -50                                39                                          33.49                               5.5
    -50                                21                                          33.49                            -1249
    -50                                26                                          33.49                            -7.49
                                          '**1 Data continued on next page *'*
C-26

WELD METAL UNIRADIATED Page 2 Material: WELD LINDE 1092             ieat Number: Z7204 FLUX LOT 3714    Orientation:
Capsule: UNIRR       Total Fuence Charpy V-Notch Data (Continued)
Temperature              Input Lateral Expansion                       Computed LE                 Differential
   -20                              47                                     47.02                       -.02
   -20                              58                                     47.02                        10.97
   -20                              50                                     47.02                        2.97 10                               60                                     60.1                        -.1 10                              54                                      60.1                       -6.1 10                               62                                     60.1                         1.89 40                               77                                     70.6                        639 40                              74                                      70.6                        3.39 40                              64                                      70.6                       -6.6 110                              76                                    83.42                      -7.42 110                              88                                    83.42                        4.57 110                              84                                    83.42                         .57 SUM of RESIDUAIS = 9.55 C-27

WELD METAL CAPSULE S CVGRAPH 4.1 llyperbolic Tangent Curve Printed at 12.39 on 08-19-2002 Page I Coefficients of Curve 2 A=37.45                    B = 36.45                    C = 152.02                  TO = 10555 Equation. is: L = A        B I tanh((T - TO)/C) I Upper Shelf LE: 73.91             Temperature at LE 35:      952         Lower Shelf LE 1 Fixed Material: 1ELD LINDE 1092              Heat Number: 27204 FLUX LOT 3714            Orientation:
Capsule. S      Total Fluence: 284E+18
       -300         -200       -100              0         100         200            300        400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: S      Material: YELD LINDE 1092         Ori:         leat : 27204 FLUX LOT 3714 Charpy V-Notch Data Temperature               Input Lateral Expansion                          Computed LE                         Differential 25                                18                                        19.76                             -1.76 60                               28                                        26.85                               114 76                               33                                        30.45                               2.54 76                                32                                        30.45                               154 125                               37                                        42.09                             -5.09 200                               57                                        5758                               -.58 250                              685                                        64.43                               4.06 350                               69                                         71.1                              -21 SUM of RESiDUAIS = -25 C-28

WELD METAL CAPSULE Y CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1X.39 on 08-19-2002 Page 1 Coefficients of Curve 3 1        A = 31.12                   B = 30.12                      C = 115.87                 TO = 17924 Equation is: L = A + B
* I tanh((T - TO)/C) I Upper Shelf LE 6124               Temperature a LE 35: 1942                Lower Shelf LE I Fixed Material: WELD LINDE 1092               Heat Number 27204 FLUX LOT 3714              Orientation:
Capsule: Y          Total Fluence: 1.05E+19 20 0                                                                                                             __     __
15F
'--4 i0iY~~~~~~~~~~~
4-,
v I0 4              4.           .             I           I_
u
             -300        -200        -100               0          100          200          300         400         500           600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: Y      Material: WELD LINDE 1092            Ori:        1eat : 27204 FLUX LOT 3714 Charpy V-Notch Data Temperature                 Input Lateral Expansion                           Computed LE                         Differential 25                                 13                                          4.93                                8.06 100                                 15                                          1322                                1.77 150                                24                                           23.67                                .32 185                                24                                           32.61                            -. 61        I 215                                37                                           40.13                            -3.13 250                                60                                           47S52                              1247 350                                58                                           5823                               -23 400                                56                                           59.93                            -3.93 SUM of RESlDUAIS = 6.72 C-29

WELD METAL CAPSULE V CVGRAPH 41 }yperbolic Tangent Curve Printed at 1230.39 on 0-19-2002 Page I Coefficients of Curve 4 A=27.73                       B = 26.73                   C = 124.44                   TO   85.9 Equation i LE = A + B I tanh((T - T0)/C) I Upper Shelf LE 54.47               Temperature at LE 35: 220.6             Lower Shelf LE 1 Fixed Material: 'WELD LINDE 1092              Heat Number. 27204 FLUX LOT 3714            Orientation:
Capsule. V        Total Fluence: 137E+19 2007-
     -                                                         III Ib 50 U                            I       I                  I            I             I
        -300          ,200        -100              0         100          200           300        400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: V      Material: W'ELD LINDE 1092          Ori:        leat : 27?204 FUX LOT 3714 Charpy V-Notch Data Temperature                  Input Lateral Expansion                          Computed LE                        Differential 25                                   1                                         4.74                            -3.74 100                                  13                                         11.73                             126 150                                  25                                         2021                             4.78 200                                  24                                         30.73                           -6.73 225                                  37                                         35.85                             114 300                                  51                                         47.09                              3.9 325                                  50                                         49.3                               .69
                                           . >*Data continued on next page ""
C-30

WELD METAL CAPSULE V Page 2 Material: WELD LINDE 1092             Heat Number Z7204 FLUX LOT 3714     Orientation:
Capsule- V      Total Fluence. 1.37E+19 Charpy V-Notch Data (Continued)
Temperature              Input Lateral Expansion                       Computed LE                 Differential 350                             48                                       50.89                    -2.89 SUM of RESIDUALS = -1.56 c
I I
C-31

WELD METAL UNIRRADIATED CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 124450 on 08-19-2002 Page 1 Coefficients of Curve I A =50                         B = 50                      C =75.76                  T0    -1593 Equation is: Shear% = A + B       I tanh((T - TO)/C)  I Temperature at SOx Shear -15.9 Material: WELD LINDE 1092                Heat Number 27204 FLUX LOT 3714            Orientation:
Capsule: UNIRR       Total Fluence CZ 0
V)
Ca)
C) 0-
            -300        -200         -100               0         100         200          300         400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: UNI1RR      Material: WELD LINDE 1092           Or:        Heat #: 27204 FLUX LOT 3714 Charpy V-Notch Data Temperature                   Input Percent Shear                       Computed Percent Shear                  Differential
       -150                                 18-                                        282                               1517
       -150                                  9                                         2.82                               6.17
       -150                                 14                                         282                               11.17
       -100                                 14                                          9.8                              4.19
       -100                                 13                                          9.8                               3.19
       -100                                 13                                          9.8                               3.19
        -50                                 30                                        28.92                               1.07
        -50                                 18                                        28.92                            -10.92
        -50                                 25                                        28.92                             -3.92
                                               '>" Data continued on next page *'
C-32

WELD METAL UNIRRADIATED Page 2 Material: WELD LINDE 1092            Heat Number 27204 FLUX LOT 3714        Orientation:
Capsule: UNIRR      Total Fluence Charpy V-Notch Data (Continued)
Temperature               Input Percent Shear                   Computed Percent Shear                Differential
   -20                             40                                    47.32                           -7.32
   -20                             61                                    4732                              13.67
   -20                             44                                    4732                             -32 10                             56                                    66.47                           -10.47 10                             59                                    66.47                           -7.47 10                             75                                    66.47                              852 40                             90                                     81.4                              859 40                             95                                     81.4                             13.59 40                             75                                     81.4                             -6.4 110                            96                                    9652                              -52 110                            100                                   96.2                               3.47 110                            100                                   96.52                              3.47 It of RESIDUALS = 45.15 I
i z
q t
I I
I I
I I
I iq  i C-33

WELD METAL CAPSULE S CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 12:44.50 on 08-19-2002 Page I Coefficients of Curve 2 A = 50                    B = 50                     C = 109.59                 TO = 110.74 Equation is Shear/. = A + B     I tanh((T - TO)/C)
Temperature at 50z. Shear 110.7 Material: WELD LINDE 1092             Heat Number 27204 FLUX LOT 3714            Orientation:
Capsule: S      Total Fluence 284E+18 0
U)
CD 0
a-)
00
            -300         -200       -100             0      - 100          200           300     - 400          500          600 Temperature in Degrees F Data St(s) Plotted Plant: DCI      Cap S      Material: WELD LINDE 1092         Ori:        Heat : 270241 FLUX LOT 3714 Charpy V-Notch Data Temperature                  Input Percent Shear                     Computed Percent Shear                   Differential 25                                15                                       1729                             -229 60                                20                                       28.37                            -837 76                                45                                       34.66                             10.33 76                                40                                       34.66                              533 125                                50                                       56.46                            -6.46 200                                80                                        83.6                             -3.6 250                               100                                       92.69                              73 350                               100                                       98.74                              125 1 SUM of RESIDUAIS = 3.49 C-34

WELD METAL CAPSULE Y CVGRAPH 4.1 lyperbolic Tangent Curve Printed at 124450 on 08-19-2002 Page 1 Coefficients of Curve 3 l          A = 50                      B = 50                      C = 87.67                 TO = 168.75 Equation is Shearz. = A+ B I tanh((T - TO)/C) I Temperature at 50 Shear 168.7 Material: WELD LINDE 1092               Heat Number 27204 FLUX LOT 3714           Orientation:
Capsule: Y Total Fluenee 1.05E+19 C/)
0 I
II
          -300        -200         -100             0         100         200           300        400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: Y      Material: WELD LINDE 1092         Ori:        Heat #: 27204 FLUX LOT 3714 Charpy V-Notch Data Temperature                   Input Percent Shear                     Computed Percent Shear                  Differential 25                                 15                                        3.62                            11.37 100                                 15                                       1724                            -224 150                                 45                                       39.46                            5.53 185                                 50                                       59.16                           -9.16 215                                 70                                       74.17                           -4.17 250                                100                                       86.45                            1354 350                                100                                       98.42                             1.57 100                                100                                       99.49                              5 SUM of RSIDUAIS = 16.95 C-35

WELD METAL CAPSULE V CVGRAP}I 4.1 hlyperbolic Tangent Curve Printed at 12:44.50 on 08-19-2002 Page I Coefficients of Curve 4 l          A = 50                        B                             C 66.4                    TO    20156 Equation is: Shear = A + B          I tanh((T - T0)/C) I Temperature at 50/ Shear. 201.5 Material: WELD LINDE 1092                 Beat Number. 27204 FLUX LOT 3714            Orientation:
Capsule: V       Total Fluence 137E+19 CZ UL) 4a) 0)
C~)
0_
             -300         -200         -100                0         100          200          300         400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: V       laterial: WELD LINDE 1092            Ori:       Heat : 2"'204 FLUX LOT 3714 Charpy V-Notch Data Temperature                    Input Percent Shear                         Computed Percent Shear                  Differential 25                                   5                                           .48                               451 100                                   15                                          4.48                              10.51 150                                   25                                         17.46                              7.53 200                                   30                                         48.82                            -1882 225                                   80                                         66.94                              13.05 300                                  100                                         95.09                               4.9 325                                  100                                         97.62                              2.37 "t'   Data continued on next page 'l C-36

WELD METAL CAPSULE V                                                               I Page 2 Material: WELD LINDE 1092            Heat Number 27204 FLUX LOT 3714       Orientation:
Capsule: V      Total Fluence 137E+19 Charpy V-Notch Data (Continued)                                                     I Temperature               Input Percent Shear                   Computed Percent Shear              Differential 350                            100                                    98.86                          1.13 SUM of RESlDUAIS = 25.19 I
s C-37

HEAT AFFECTED ZONE UNIRRADIATED CVGRAPII 4.1 hlyperbolic Tangent Curve Printed at 13:33:29 on 08-19-2002 Page I Coefficients of Curve A = 69.09                     B = 66.9                     C = 137.93                    TO = -7125 Equation is: CVN = A + B
* I tanh((T - T0)/C) I Upper Shelf Energy: 136 Fixed       Temp. at 30 f-lbs -163.5          Temp. at 50 ft-lbs -111.7          Lower Shelf Energy: 219 Fixed Material: HEAT AFFD ZONE                 Heat Number.            Orientation:
Capsule: UNIRR       Total Fluence: 284E+18 U) la
            -300        -200         -100               0         100          200           300           400        500         600 Temperature in Degrees F Data Set(s) Plotted PlanL DCI       Cap: UNIRR         Material: EAT AFF'D ZONE              Ori:         Heat :
Charpy V-Notch Data Temperature                    Input CVN Energy                           Computed CVN Energy                      Differential
       -200                                 22                                          20.11                                1.88
       -200                                 21                                          20.11                                .88
       -200                                 2                                           2011                              -18.11
       -150                                 35                                          3457                                 .42
       -150                                35.5                                         34.57                                .92
       -150                                365                                          34.57                                192
       -100                                445                                          5535                              -10.85
       -100                                525                                          55.35                              -2.85
       -100                                 88                                          5535                                32.64
                                              ... Data continued on next page ....
C-38

HEAT AFFECTED ZONE UNIRRADIATED Page 2 Material: HEAT AFFD ZONE             Heat Number          Orientation:
Capsule UNIRR     Total Fluence Charpy V-Notch Data (Continued)
Temperature        Input CVN Energy                     Computed CVN Energy                    Differential
   -50                     88                                   79.32                               8.67
   -50                    825                                   79.32                                3.17
   -50                    565                                   79.32                             -22.82 10 10 115 120 104.5                              10.49   I; 104.5                              15.49 10                    87                                    104.5                             -175 40                    105.5                                 113.76                             -826 40                     100                                  113.76                            -13.76 40                    1085                                  113.76                             -526 110                    130                                  126.9a                               3.01 110                   1355                                  126.99                               8.51 110                   142.5                                 126.93                              15.51 LM of RESIDUALS = 4.09 C-39

HEAT AFFECTED ZONE CAPSULE S CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 13.53:38 on 09-03-2002 Page I Coefficients of Curve I A= 63.59                         B = 61.4                     C = 9237                      TO = -3448 Equation is: CVN =A          B I tanh((T - T0)/C) I Upper Shelf Energy: 125 Fixed. Temp. at 30 ft-lbs -912                Temp. at 50 ft-lbs -552            Lower Shelf Energy: 2.19 Fixed Mlaterial: IIEAT AFFD ZONE                   Beat Number.            Orientation:
Capsule S         Total Fluence 2.84E+18 300 cn     250_
 ;       150 100
              -300      -200          -100                  0        100           200           300           400        500         600 Temperature in Degrees F Data Setts) Plotted Plant DCI          Cap: S        Material: IEAT AFF'D ZONE               Ori:       Heat #:
Charpy V-Notch Data Temperaiture                    Input CVN Energy                              Computed CVN Energy                      Differential
_IRr I                              . IIIq                                         II I 1i                                 1.49
        -100                                   Il
        -100                                   21                                          26.13                               -5.13
        -10                                   25                                          26.13                                -1.13
        -75                                   43                                          3827                                   4.2 0                                   85                                           85.51                                -51 76                                  115                                         114.71                                  28 200                                  118                                         12423                               -623 350                                  132                                         124.97                                 7.02 SUM of RESIDUALS = 51 C-40

HEAT AFFECTED ZONE CAPSULE Y CVGRAPII 4.1 yperbolic Tangent Curve Printed at 133329 on 0-19-2002 Page I Coefficients of Curve 3 A= 5559                      B = 53.4                    C = 114.66                     T0 = -23.9 Equation is CN = A + B I tanh((T - TO)/C) I Upper Shelf Energy: 109 Fixed       Temp. at 30 ft-lbs -83.7           Temp. at 50 ft-lbs -35.9            Lower Shelf Energy: 2.19 Fixed Material: HEAT AFFD ZONE                  Heat Number           Orientation:
Capsule: Y        Total Fluence 1.05E+19 30Y 7-                                                                   _  _   __      _   _   _
U)    25CFf
 ,.0
 ~z-4    20(
bl CD a) 1507 zw-r-10(
1-u 4           4              4                        1
()
               -300     -200          -100              0          100         200           300           400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI        Cap: Y       Material: EAT AFFD ZONE               Or:         Beat #:
i I
I Charpy V-Notch Data Temperature                   Input CVN Energy                          Computed CVN Energy                        Differential
         -150                                 5                                          1285                               -785
         -100                                23                                          2458                                -1.58
          -50                                42                                          43.65                               -1.65
         -25                                 72                                          55.08                                16.91 25                                63                                          77.08                              -14.08 75                                90                                          9284                                -2.84 150                               114                                        104.09                                  9.9 225                               104                                        107.62                               -3.62 SUM of RESIDUALS = -4.83 C-41

HEAT AFFECTED ZONE CAPSULE V CVGRAPII 4.1 lyperbo]ic Tangent Curve Printed at 13:3329 on 08-19-2002 Page I Coefficients of Curve 4 A    59.09                   B = 56.9                      C=125.62                     TOz=12S Equation i CVN        A+ B      I tanh((T - TO)/C)   I Upper Shelf Energy: 116 Fixed       Temp. at 30 fL-]bs -526            Temp. at 50 ft-]bs:      -1.9      Lower Shelf Energy: 2.19 Fixed Material: HEAT AFFD ZONE                 Ileat Number.          Orientation:
Capsule: V       Total Fluence: 1.37E+19 300-U) la 200-150-a) 100                                                                 1A 50G-0
              -300       -200         -100              0          100          200         300            400        500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DC1      Cap: V        Material: HEAT AFFD ZONE              Ori:       Heat #':
Charpy V-Notch Data Temperature                     Input CVN Energy                           Computed CVN Energy                      Differential
        -125                                 19                                         12.75                                 624
        -50                                  36                                         30.89                                  51 0                                 47                                         50.87                               -3.87 72                                 66                                         8204                               -16.04 10                                 88                                         9164                                -3.64 125                               128                                          94                                  29.59 175                                95                                         10732                              -1232 I'll Data continued on next page I'l C-42

HEAT AFFECTED ZONE CAPSULE V Page 2 Material: HEAT AFFD ZONE           Ileat Number          Orientation-Capsule V     Total Fluence 137E+19 Charpy V-Notch         Data (Continued)
Temperature      Input CVN Energy                    Computed CN Energy                   Differential 225                   124                                 111.91                          12.08 SUM of RIDUALS = 17.12 II I I I  I I  I C43

HEAT AFFECTED ZONE UNIRRADIATED CVGRAPI 4.1 lyperbolic Tangent Curve Printed at 1427:03 on 08-19-2002 Page I Coefficients of Curve I A = 44.65                      B = 43.65                      C= 127.88                     TO = -78.75 Equation is: LE = A + B tI lanh((T - TO)/C)
Upper Shelf LE- 88.3                Temperature at LE 35: -1075             Lower Shelf LE I Fixed Material: HEAT AFFD ZONE                    leat Number.           Orientation:
Capsule: UNIRR         Total Fluence:
F 20a--t                                                                                   Y                         F
. P-     150-S
              --I          4             4             4              +           4              +             +           4 10                                                                                         *q.                       I
: 0)                                                     0 I/
2                                        I 5        1 1         t~0 0U             1             I      I             I                                               i
             -300       -200          -100                 0         100         200           300            400         500           600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR           Material: HEAT AFFD ZONE               Ori:        leat #:
Charpy V-Notch Data Temperature                 Input Lateral Expansion                             Computed LE                             Differential
        -200                                  15                                          12.39                                    2.6
        -200                                  17                                           12.39                                  4.6
        -200                                   3                                          IZ.39                                 -939
        -150                                  23                                          ZZ57                                    A
        -150                                  23                                          22.57                                   .42
        -150                                  24                                          2257                                    1.42
        -100                                  29                                          37.46                                 -8.46
        -100                                  33                                          37.46                                 -4.46
        -100                                  53                                          37.46                                  1553
                                                 'll Data continued on next page I'''
C-44

HEAT AFFECTED ZONE UNIRRADIATED Page 2 Material: HEAT AFFD ONE             Heat Number.        Orientation:
Capsule: UNIRR     Total Fluence Charpy V-Notch Data (Continued)
Temperature
   -50
   -50 Input ateral Expansion 60 52 Computed LE 54.3 54.3 Differential 5.69
                                                                                               -23 I
   -50                     40                                  543                            -14.3 10                    7                                   70.87                            7.12 10                    80                                  70.87                            9.12 10                    64                                  70.87                          -6.87 40                     76                                  76.51                           -.51 40                     78                                  76.51                            1.48 40                     75                                  76S5                            -1.51 110                    82                                  83.97                          -1.97 110                    84                                  83.97                             .02 110                    83                                  83.97                           -.97 SUM of RESDUAIS =-Z32 r-A,

HEAT AFFECTED ZONE CAPSULE S CVGRAPH 41 Hyperbolic Tangent Curve Printed at 1427:03 on 08-19-2002 Page 1 Coefficients of Curve 2 l        A = 4137                   B = 40.37                    C = 9453                    TO = -4921 Equation is: LE = A + B
* I tanh((T - TO)/C) I Upper Shelf LE: 81.74           Temperature at LE 35 -642              Lower Shelf LE I Fixed Material:  EAT AFFD ZONE                Heat Number          Orientalion:
Capsule S         Total luence   84E+18 U)
P-
. r-4a)
CZ
             -300      -200          -100            0          100        200          300           400        500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: S      Mlaterial: HEAT AFFD ZONE           Ori:        leat :
Charpy V-Notch Data Temperature               Input Lateral Expansion                        Compuled LE                         Differential
        -150                               15                                       9.55                               544
        -100                              205                                      2155                               -1.05
        -100                              16.5                                     21.55                             -5.05
        -75                                32                                      30.62                                1.37 0                               63                                      60.67                                2.32 76                               74                                      76.41                              -Z41 200                              80.5                                     81.33                               -.83 350                               84                                      81 .72                               2Z1 SUM of RESIDUALS = 2.05

HEAT AFFECTED ZONE CAPSULE Y CVGRAPIl 4.1 Hyperbolic Tangent Curve Printed at 14-27D03 on 08-19-2002 Page I Coefficients of Curve 3 A = 41.72                  B = 40.72                   C = 134.42                    TO = -14.06 Equation is LE = A + B
* I tanh((T - T)/C) I Upper Shelf LE 245               Temperature at LE 35: -36.4            Lower Shelf LE I ixed Material: HEAT AFED ZONE               Heat Number            Orientation:
Capsule Y        Total Fluence 1.05E+19 20UW U)
"-4 150 5ff-U
             -300      -200         -100             0         100         200           300           400         500         600 Temperature in Degrees F Data Set(s) Plotted Planl DCI       Cap: Y       Material: HEAT AFFD ZONE             Ori-        Heat #:
Charpy V-Notch Data Temperature               Input Lateral Expansion                         Computed LE                           Differential
       -150                                3                                        1051                                -751
       -100                               18                                        18.74                               -.74
        -50.                              30                                        31.09                               -1.09
        -25                               52                                        38.42                                13.57 25                               46                                        5323                               -723 75                               60                                        65.34                              -5.34 150                              8o                                        75.92                                4.07 225                              80                                        80.19                                -.19 SUlM of RIIDUALS = -4.47 C-47

HEAT AFFECTED   i ZONE CAPSULE V CVGRAPH 4.1 Hyperbolic Tangent Curve Printed at 1427:03 on 08-19-2002 Page I Coefficients of Curve 4 A=41.84                    B =40.B4                      C=143.96                     TO   4312 Equation is: LE A + B tlanh((T - TO)/C)
Upper Shelf LE 82.69             Temperature at LE 35: 18.7             Lower Shelf LE I Fixed Material: HEAT AFFD ZONE                Heat Number            Orientation:
Capsule: V       Total Fluence: 137E+19 Y                         p                         Y                          .Y*
20( i U) 1507
.r1-100 0,
50 u
             -300      -200         -100              0         100         200          300            400       500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: V        Material: HEAT AFFD ZONE            Ori:        Heat #:
Charpy V-Notch Data Temperature              Input Lateral Expansion                          Computed LE                         Differential
        -125                               4                                          82                               -42
         -50                              22                                         18.58                              3.41 0                              31                                        29.96                               1.03 (2                             45                                        49.93                              -4.93 100                             56                                        5719                               -IJ9 125                              71                                       62.85                               8.14 175                             65                                         71.41                             4.41
                                             *'*' Data continued on next page ''
C48

I HEAT AFFECTED ZONE CAPSULE V Page 2 Material: HEAT AFFD ZONE           Heat Number:          Orientation:
Capsule V     Total Fluence 1.37E+19 Charpy V-Notch Data (Continued)
Temperature   Input Lateral Expansion                     Computed LE                       Differential 225                   79                                   76.64                            2.35 SUM of RESIDUALS = -1.8 C49

HEAT AFFECTED ZONE UNIRRADIATED CVGRAPH 4.1 lyperbolic Tangent Curve Printed at 14:0124 on 09-03-2002 Page I Coefficients of Curve I I        A = 50                      B   50                     C = 109.44                     TO = -7294 Equation is Shear,. = A + B I tanh((T - TO)/C) I Temperature at 50 Shear. -729 Material: IEAT AFFD ZONE                 Heat Number            Orientation:
Capsule. UNIRR        Total Fluence:
0 C)
            -300     -200         -100              0          100        200             300          400        500         600 Temperature in Degrees F Data Set(s) Plotted Plant: CI       Cap: UNIRR         laterial: HEAT AFF'D ZONE             Ori:       Hea #:
Charpy V-Notch Data Temper, iture              Input Percent Shear                       Computed Percent Sheear                    Differential
      -200                                18                                         8.93                               9.06
      -200                                18                                         8.93                               9.06
      -200                                5                                          8.93                              -3.93
_150                               23                                         19.65                               3.34
      -150                               21                                         19.65                               1.34
      -150                               23                                         19.65                               3.34
      -100                               29                                         378                                -s.sa
      -100                               34                                         37.                                -3.88
      -100                               52                                         37M8                                1411
                                            ""  Data continued on next page       '>
C-50

HEAT AFFECTED ZONE UNIRRADIATED Page 2 Material: EAT AFFD ZONE             Heat Number         Orientation:
Capsule. UNIRR     Total Fluence Charpy V-Notch Data (Continued)
Temperature     Inpul Percent Shear                  Computed Percent Shear                Differential
   -50                   59                                   60.32                           -122
   -50                    51                                  60.32                           -9.32
   -50                   43                                   60.32                           -1722 10                   95                                  81.99                              13 10                  100                                  81.99                              18 10                  59                                   81.99                          99 40                    90                                  88.73                             126 40                   100                                  88.73                             1126 40                   100                                  88.73                             1126 110                  100                                  96.58                             3.41 110                  100                                  96.58                             3.41 110                  100                                  96.58                             3.41 SUM of REI1DUAIS = 37.67 C-51

HEAT AFFECTED ZONE CAPSULE S CV'GRAPII 4.1 lyperbolic Tangent Curve Printed at 14D1:24 on 09-03-2002 Page I Coefficients of Curve 2 A 50                      B = 50                     C = 101.74                    TO -15.46 Equation i Shear = A B             tanh((T - T)/C) 1 Temperature at       . Shear. -15.4 Material: HEAT AFFD ZONE                 Heat Number           Orientation:
Capsule S       Total Fluence 2.84E+18 CZ Q) 0 0)
C-)
0)
           -300   -200          -100             0         100         200            300          400       500         600 Temperature in Degrees F Data Sel(s) Plotted Plant: DCI       Cap: S      Material: HEAT AFFD ZONE              Ori:       Heat #:
Charpy V-Notch Data Temperature              Input Percent Shear                      Computed Percent Shear                   Differential
      -150                             5                                         6.63                            -1.63
      -100                             10                                       15.95                            -5.95
      -100                             10                                       15.95                            -5.95
       -75                            40                                        23.68                              1631 0                            50                                        57.54                            -7.54 76                            90                                       85.79                               42 200                           100                                       98.57                              1A2 350                           100                                       99.92                               .07 SUM of RESIDUALS = .94
                                                              -52

HEAT AFFECTED ZONE CAPSULE Y CYGRAPH 4.1 }yperbolic Tangent Curve Printed at 14.D124 on 09-03-2002 Page I Coefficients of Cujrve 3 A = 50                      B = 50                       C = 113.01                     1' = -3627 Equation is Shear>'. = A      B     tanh((T - T0)/C) ]                                            I Temperature at 50. Shear. -362                                                           I Material: 13EAT AFFD ZONE                Heat Number              Orientation:
Capsu]e: Y        Total Fluence: 1.05E+19 I
0-0Z 0D 0jc I  i
            -300     -200          -100             0         100          200             300           400        500         600 Temperature in Decrees F Data Set(s) Plotted Plant: DCI       Cap: Y      Material: IIEAT AFFD ZONE                Or:        1eat #:
Charpy V-Notch Data Temperature                Input Percent Shear                        Computed Percenl Shear                      Differential
      -150                                5                                           11.79                             -6.79
      -100                               25                                          24.45                                .54
       -50                               40                                          43.95                              -3.95
       -25                               70                                          54.97                               15.02 25                               65                                          74.73                              -9.73 75                               84                                          87.75                              -3.75 150                              100                                         96.43                                356 225                              100                                         99.02                                .97 SUM of RESIDUAIS = -4.12 C-53

HEAT AFFECTED ZONE CAPSULE V CVGRAPII 4.1 Hyperbolic Tangent Curve Printed at 14:0124 on 09-03-2002 Page I Coefficients of Curve 4 l        A = 50                      B = 50                      C = 116.82                     TO = -15.93 Equation is: Shear/ = A + B I tanh((T - TO)/C) I
                                 -       Temperature at 50:. Shear -15.9 Material: HEAT AFFD ZONE                 Heat Number             Ori entation:
Capsule: V       Total Fluence: 1.37E+19
        -300     -200        -100               0         100         200            300            400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI      Cap: V        Material: IEAT AFD ZONE               Ori:         Heat #:
Charpy V-Notch Data Temperature               Input Percent Shear                       Computed Percent Shear                       Differential
   -125                              10                                         13.38                               -3.38
   -50                              45                                          35.82                                 9.17 0                             50                                          56.77                                -6.77 72                             75                                          81.83                                -683 100                             90                                          87.91                                 a08 125                            100                                          91.77                                 822 175                             100                                         96.33                                 3.66
                                        *'  Data continued on next page ...

HEAT AFFECTED ZONE CAPSULE V Page 2 Material: HEAT AFFD ZONE           Heat Number        Orientation:
Capsule V     Total Fluene 137E+19 Charpy V-Notch Data (Continued)
Temperature     Input Percent Shear                 Computed Percent Shear               Differential 225                   100                                98.4                             159 SUM of RESIDUALS = 7.73 C-55

STANDARD REFERENCE MATERIAL UNIRRATIATED CVGRAPH 4.1 hlyperbolic Tangent Curve Printed at I:05:06 on 09-06-2002 Page I Coefficients of Curve I A= 659                         B = 60.4                        C =81 25                      TO = 95.5 Equation is CVN = A+ B
* I tanh((T - TO)/C) I Upper Shelf Energy: 23 Fixed        Temp. at 30 fl-lbs         46.4          Temp. at 50 ft-]bs 78.3            Lower Shelf Energy: 2.19 Fixed Material: SRM SA533BI                       Heat Number             Orientation: LT Capsule: UNIRR           Total Fluence 30(T U)    25-200 10
  ~I z-    15(
U4 1 1) 0
           =,                                                           .
0A) e0
                                           ,                      _I     II 0' 1                       I
               -300     -200          -100                 0           100          200              300        400         500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR            Material: SRM SA533BI              Ori: LT Heat #:
Charpy V-Notch Data Temperature                    Input CVN Energy                               Computed CVN Energy                        Differential
        -50                                     3                                               5.47                              -247
        -50                                     5                                               5.47                               -.47
        -50                                     5                                               5.47                               -.47
        -20                                     6                                               8.84                              -Z84
        -20                                    6.5                                              8.84                              -2.34
        -20                                     9                                                   48.I                             i5 10                                   135                                              15.32                             -1.82 10                                    12                                              15.32                             -3.32 10                                   14.5                                             15.32                              -B2
                                                  *'* Data continued on next page          '"
C-56

STANDARD REFERENCE MATERIAL UNIRRATIATED Page 2 Material: SRM SA533BI                Heat Number           Orientation: LT Capsule: UNIRR       Total Fluence:
Charpy V-Notch Data (Continued)
Temperature            Input CVN Energy                         Computed CVN Energy                  Differential 40                         22-                                      26.74                           -4.74 40                         36                                       26.74                             925 40                          35                                       26.74                             825 85                         52                                       54.83                           -2.83 85                        58.5                                      54.83                             3.66 85                        415                                       54.3                           -1333 110                        63.5                                      7325                            -9.75 110                        82.5                                      7325                              924 110                        85.5                                      7325                              1224 160                         109                                      10249                              6.5 160                       108.5                                      102.49                              6 160                          1                                       10249                          -21.49 210                         121                                      116.19                             4.8 210                         117                                      116.19                              .8 210                         115                                      116.19                           -1.19 300                        117.5                                     12221                           -4.71 300                         125                                      12221                             2.78 300                         127                                      12221                             4.78 SUM of RSIDUA: S = -4.17 C-57

STANDARD REFERENCE MATERIAL CAPSULE S CVGRAPII 4.1 Hyperbolic 'Tangent Curve Printed at 11.)5:06 on 09-06-2002 Page I Coefficienls of Curve 2 l         A = 61.09                    B = 58.9                    C = 79.04                   T0 = 158.49 Equation is CVN = A + B
* I tanh((T - TO)/C)
Upper Shelf Energy: 120 Fixed       Temp. at 30 ft-lbs       1112      Temp. at 50 f-lbs      143.4     Lower Shelf Energy: 219 Fixed Material: SRM SA533BI                 Heat Number          Orientation: LT Capsule: S       Total Fuence: 84E+18 I)
In
  .1 4-,
0) z D
               -300      -200          -100             0          100         200           300        400          500         600 Temperature in Degrees F Data Set(s) Plotted Planl: DCI      Cap S        Material: SRM SA533BI         Or: LT        Heat :
Charpy V-Notch Data Temperature                    Input CVN Energy                         Compuled CVN Energy                     Differential 25                                6                                         6.08                              -.08 76                                19                                        15.19                               3.8 125                               47                                        37.53                               9.46 125                                 31                                       37.53                             -6.53 150                               52                                        54.79                             -2.79 200                                 81                                       89.46                             4.46 250                                125                                       109.41                              15.58 400                                115                                       119.73                            -4.73
:   SiJA of RESIDUAIS = 623 C-58

STANDARD REFERENCE MATERIAL CAPSULE Y CVGRAPII .1Hyperbolic Tangent Curve Printed at 1l)5:06 on 09-06-2002 Page I Coefficients of Curve 3 l        A = 57.09                     B = 54.9                     C = 64.9                     TO = 197.34 Equation i CVN = A + B I tanh((T - TO)/C) I Upper Shelf Energy: 112 Fixed       Temp. at 30 ft-lbs 162.2          Temp. a 50 ft-]bs: 188.9           Lower Shelf Energy: 2.19 Fixed Material: SRM SA533BI                 lleat Number           Orientation: LT Capsule: Y        Total Fluence: 1.05E+19 300-250 a)     20(7--
1 150-
  -)
1007-5(7 U
             -300       -200          -100             0          100         200            300          400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI        Cap: Y        laterial: SM SA533BI          Or: LT         Ileat #:
Charpy V-Notch Data Temperature                   Inpul CVN Energy                          Computed CVN Energy                       Differential 50                                  10                                          335                                 6.64 100                                 14                                          7.41                                6.58 150                                 25                                         22.91                                2.08 175                                 38                                         38.91                               -.91 200                                 54                                         5934                              -5:34 250                                100                                         93.89                                 6.1 295                                104                                        106183                              -2.83 325                                119                                        109.89                                 9 Si3Mof REIDUAIS = 21.42 C-59

STANDARD REFERENCE-MATERIAL CAPSULE V CVGRAPII 4.1 lyperlolic Tangent Curve Printed at 11.05:06 on 09-06-2002 Page I Coefficients of Curve 4 A    59.59                    B = 57.4                      C= 8557                    TO   211.87 Equation is CVN = A + B           tanh((T - TO)/C) I Upper Shelf Energy: 117 Fixed      Temp. at 30 f-lbs         163       Temp. at 50 ft-lbs 197.4         Lower Shelf Energy: 2.19 Fixed Material: SRM SA533BI                   ieat Number         Orientation: LT Capsule: V        Total Fluence: 137E+19 300-250-200/
15f 10f F                   +~          ~~~
I            I           I
             -300       -200          -100              0          100          200         300         400          500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap: V        Material: SRM SA533BI         Ori: LT       leat #:
Charpy V-Notch Data Temperature                    Input CVN Energy                           Computed CN Energy                      Differential 25                                 4                                          3.63                                .36 50                                 8                                          4.75                               324 100                                 10                                         10.03                             -.03 150                                33                                         24.08                               8.91 200                                47                                          51.68                            -4.68 250                                 74                                         83.6                              -9.6 300                                114                                        104.01                              9.98
* Data continued on next page ....
C-60

STANDARD REFERENCE MATERIAL CAPSULE V Page 2 Maler ial: SRM SA533131             Heal Number.         Orientation: LT Capsule: V     Total Fluence: 1.37E+19 Charpy V-Notch Data (Continued)
Temperature            Input CVN Energy                       Computed CVN Energy                    Differential 325                        120                                     10928                             10.61 SUMI of RESIDUALS = 18.8 C-61

STANDARD REFERENCE MATERIAL UNIRRADIATED CVGRAPH 4.1 Hyperbolic Tangenl Curve Printed at 11D9.33 on 09-06-2002 Page I Coefficients of Curve I A = 43.65                   B = 42.65                      C 84.0S                     TO = 76X7 Equation is LE = A + B            tanh((T - TO)/C)    I Upper Shelf LE: 8631              Temperaturi ^ at LE 35:         58.9      Lower Shelf LE I Fixed Material: SRM SA533BI                   leat Number.          Orientation: LT Capsule: UNIRR         Total Fluence:
20fF 15 r-4 I00 4-,
a)                                                                        0~
DU 0
e1~~                                     4.                           I             I          I          I U
           -300        -200          -100              0          100          200           300         400        500          600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR          laterial: SRM SA533 3I         Ori: LT      Heal #:
Charpy V-Notch Da ta Temperature                Input Lateral Expansion                              Computed LE                       Differential
       -50                                  4                                           5.03                             -1.03
       -50                                  3                                           5.03                             -2.03
       -50                                  5                                           5.03                              -.03
       -20                                  9                                           8.84                                .15
       -20                                  6                                           8.a4                             -2.&4
       -20                                  10                                          8.84                                115 10                                  14                                          15.61                             -1.61 10                                 15                                          15.61                              -.61 10                                 14                                          15.61                             -1.61 I'll Data continued      n next page I'll C(62

STANDARD REFERENCE MATERIAL UNIRRADIATED Page 2 Material: SRM SA533BI              }1eat Nmber         Orientation: LT Capsule: UNIRR      Total Fluence:
Charpy V-Notch Data (Continued)
Temperature        Input Lateral Expansion                       Compuled LE.                      Differential 40                        23                                     26.31                           -3.31 40                        32                                     26.31                              5.68 40                        32                                     26.31                              5.68 85                        45                                     48.06                           -3.06 85                        51                                     48.06                              2.93 85                        42                                     48.06                           -6.06 110                       54                                      59.9                            -5.9 110                       60                                      59.9                               .09 110                       71                                      59.9                             11.09 160                        79                                     76.07                              2.92 160                        72                                      76.07                          -4.07 160                        69                                     76.07                            -7.07 210                        87                                      8291                              4.08 210                        84                                     82.91                              1.08 210                        88                                     82.91                              5.08 300                        83                                      85.9                             -2.9 300                        87                                      85.9                              1.09 300                        84                                      85.9                             -1.9 SUM of RESIDUAIS = -3.03 C-63

STANDARD REFERENCE MATERIAL CAPSULE S CVGRAPH 4.1 lyperbolic Tangent Curve Printed at 11.1933 on 09-06-2002 Page I Coefficients of Curve 2 A = 43.48                    B = 4248                     C = 100.49                  TO = 144.84 Equation is LE = A + B        I tanh((T  - TO)/C)    I Upper Shelf LE. 85.97             Temperature at LE 35: 124.4              Lower Shelf LE I Fixed NMaterial: SM SA533B I                 Heat Number:          Orientation: LT Capsule S         Total Fluence: 284E+18 200-150 10f 0
0
                                                -.-er I            ._
I-
        -300      -200           -100             0         100          200            300        400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: S       laterial: SRII SA533BI         Ori: LT       Heat #:
Charpy V-Notch Data Temperature                Input Lateral Expansion                           Computed LE                        Differential 25                                  7                                          8.16                            -1.16 76                                 20                                         1821                              1.78 125                                4Z5                                         352                               729 125                                29.5                                        352                              -5.7 150                                44.5                                       45.66                             -116 200                                59.5                                       64.71                            -521 250                                 84                                        76.64                              735 400                                82.5                                       85.44                            -294 SUM of RIDUALS = 24 C-64

STANDARD REFERENCE MATERIAL CAPSULE Y CVGRAPI 4.1 Hyperbolic Tangent Curve Printed a 1%O9.33 on 09-06-2002 Page I Coefficients of Curve 3 l        A = 51.69                   B = 50.69                   C 106.44                     TO = 214.43 Equation i LE = A B I tanh((T - T0)/C) I Upper Shelf LE. 102.39           Temperature at LE 35:         178         Lower Shelf LE I Fixed Material: SRM SA533BI                 Heat Number.          Orientation: LT Capsule Y         Total Fluence: 1.05E+19 Cl) a)
CZ
            -300       -200         -100             0          100        200             300        400         500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI       Cap: Y       Material: SRM SA533B1         Ori: LT        Beat #:
Charpy V-Notch Data Temperature               Input Lateral Expansion                          Computed LE                         Differential 50                               10                                         5.41                                4.58 100                               14                                         1157                                2.42 150                               23                                         2427                              -127 175                               32                                         33.73                             -1.73 200                               42                                         4486                              -2.B6 250                               73                                         68.03                               4.96 295                               83                                          84.1                              -1.1 325                               90                                          91.1                              -11 SUM of RESIDUALS = 3.88 C-65

STANDARD REFERENCE MATERIAL CAPSULE V CVGRAPH 4.1 lyperbblic Tangent Curve Printed at 11.09:33 on 09-06-2002 Page I Coefficients of Curve 4 A= 597                     B = 5127                     C = 117                    TO = 254.48 Equation is: LE = A B
* I tanh((T - TO)/C) I Upper Shelf LE: 103.54            Temperature at LE 35: 213.4            Lower Shelf LE I Fixed Material: SRM SA533BI                Heat Number.          Orientation: LT Capsule V        Total Fluence: 137E+19 iuu
'-4i 1507
.- 4 100 0
50
                                      -~~~~~~~~~~~~~~~
u
              -300     -200          -100            0          100         200           300        400          500         600 Temperature in Degrees F Data Set(s) Plotted Plant DCI        Cap V       Material: SRM SA533B1         Ori: LT       Heat #:
Charpy V-Notch Data Temperature               Input Lateral Expansion                         Computed LE                         Differential 25                                0                                        2.99                             -2.99 50                                3                                        4.01                              -1.01 100                               4                                       78Z                               -3.82 150                              20                                       15.72                               427 200                               31                                       2998                                 1.01 250                               48                                        50.3                              -2.3 300                               72                                       71Z7                                 .72
                                              -* Data continued on next page **>'
C-66

STANDARD REFERENCE MATERIAL CAPSULE V Page 2 Material: SRM SA533BI            Ileat Number.       Orientation: LT Capsule V     Total Fluene I.37E+9 Charpy V-Notch Data (Continued)
Temperature       Input Lateral Expansion                      Computed LE                     Differential 325                       80                                   79.9                             .09 SUM of RESIDUALS =-4.03 C-67

STANDARD REFERENCE MATERIAL UNIRRADIATED CVGRAPH 4 Hyperbolic Tangent Curve Printed at 11:15:09 on 09-06-2002 Page I Coefficients of Curve I A= 50                        B=50                       C= 100.89                TO = 85.54 Equation is.Shear/. = A + B         tanh((T - TO)/C) I Temperature at 5. Shear 85.5 Material: SRM SA533BI                  Heat Number.        Orientation: LT Capsule: UNIRR       Total Fluence:
CZ a)
          -300      -200          -100               0         100         200         300        400        500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI       Cap: UNIRR         Material: SRM SA533BI        Ori: LT     Heat #:
Charpy V-Notch Data Temperature                 Inpul Percent Shear                       Computed Percent Shear               Differential
      -50                                 9                                        6.37                            2.62
      -50                                 9                                        6.37                            Z62
      -50                                 9                                        6.37                            2.62
      -20                                13                                        10.98                            201
      -20                                 9                                        10.98                          -1.98
      -20                                13                                        10.93                            201 10                               23                                        1827                            4.72 10                               23                                        1827                            4.72 10                               23                                        1827                            4.72 I'> Data continued on next page >>>>
C-68

STANDARD REFERENCE MATERIAL UNIRRADIATED Page 2 Material: SRM SA533BI              leat Number.       Orientation: LT Capsule UNIRR       Total Fluence Charpy V-Notch Data (Continued)
Temperature          Input Percent Shear                    Computed Percent Shear                Differential 40                         33                                    28B4                              4.15 40                         29                                    28.84                              .15 40                         29                                    28.84                              .15 85                        42                                    49.72                           -7.72 85                        43                                    49.72                           -6.72 85                        41                                    49.72                           -8.72 110                        55                                    61.88                           -68 110                        58                                    61.88                           -3B8 110                        67                                    61.88                             5.11 160                         87                                   81.39                              5.6 160                        84                                    8139                               2.6 160                         85                                   81.39                              3.6 210                        100                                   9217                              7.82 210                         98                                   92.17                             5.82 210                         98                                   92.17                             5.82 300                        100                                   98.59                              1.4 300                        100                                   98.59                              1.4 300                        100                                   9859                               1.4 1 of RESIDUALS = 35.18 C-69

STANDARD REFERENCE MATERIAL CAPSULE S CVGRAPII 4.1 lyperbbli6 Tangent Curve Printed at 11:1509 on 09-6-2002 Page I Coefficients of Curve 2 l        A = 50                      B = 50                       C = 90.18                   T0 157.61 Equation is: Shear/. = A + B      I tanh((T - TO)/C)    I Temperature at 50>'. Shear. 157.6 Material: SRM SA533B]                 Ileat Number.          Orientation: LT Capsule S        Total Fluence: 2.84E+18 U)
C) 0
           -300     -200          -100             0          100         200             300       400        500          600 Temperature in Decrees F Data Set(s) Plotted Plant DCI       Cap S       Material: SRM SA5331            Ori LT        3eat Charpy V-Notch Data Temperature                Input Percent Shear                       Computed Percent Shear                   Differential 25                               I                                           5.01                           -4.01 76                               I0                                         14.06                           -4.06 125                              45                                         32.66                              1233 125                              30                                         3266                             -2.66 150                              45                                         45.78                             -.78 200                              60                                           71.9                            -11.9 250                              100                                         88.58                             11.41 400                              100                                         99.53                              .46 SUM of RIDUAIS = .77 C-70

STANDARD REFERENCE MATERIAL CAPSULE y CYGRAPII 4.1 Hyperbolic Tangent Curve Printed at 11:15:09 on 09-06-2002 Page I Coefficients of Curve 3 A = 50                     B = 50                       C = 67.9                    TO = 188.37 Equation is Shear/ = A + B I tanh((T - T0)/C) I Temperature at 507. Shear. 188.3 Material: SRM SA533B1                 Heat Number            Orientation: LT Capsule Y         Total Fluence: 1.05E+19 0)
C) 0)
SH4
           -300     -200         -100             0         100          200            300         400         500         600 Temperature in Decrees F Data Set(s) Plotted Plant: DCI     Cap: Y       MIaterial: SRM SA533B1          Ori: LT        Heat #I:
Charpy V-Notch Data Temperature                Input Percent Shear                      Computed Percent Shear                    Differential 50                              10                                         1.66                               8.33 100                              15                                         6.89                                8.1 150                              25                                        24.41                                .58 175                              40                                        4027                               -27 200                              50                                        58.47                             -8.47 250                              96                                        85.99                                 10 295                             100                                        95135                               4.14 325                             100                                        9824                                1.75 SUM of RESIDUALS = 24.18 C-71

STANDARD REFERENCE MATERIAL CAPSULE V CVGRAPII 4.1 yperbolic Tangent Curve Printed at 11:15:09 on 09-06-2002 Page I Coefficients of Curve 4 A= 50                        B = 50                      C= 901                       TO = 20343 Equation i Shear = A + B I tanh((T - TO)/C) I Temperature at 507 Shear. 203.4 Material: S1 SA533BI                    Heat Number-           Orientation: LT Capsule V        Total Fluence. 1.37E+19
;4)
C-)
0-m
            -300    -200          -100               0          100        200             300         400        500         600 Temperature in Degrees F Data Set(s) Plotted Plant: DCI      Cap V           Material: SRM SA533BI          Ori: LT        leat #:
Charpy V-Notch Data Temperature               Inpul Percent Shear                        Computed Percent Shear                    Differential 25                              5                                            255                               2.44 50                             10                                            4.18                               581 100                             15                                             10.8                             4.19 150                             30                                            25.15                             4.84 200                             40                                           4824                             -824 250                             65                                            7211                             -711 300                            100                                           87.76                              1223 I,,   Data continued on next page        'I C-72

STANDARD REFERENCE MATERIAL CAPSULE V Page 2 Material: SRM SA533BI            Ieat Number         Orientation: LT Capsule V     Total Fluence 137E+19 Charpy V-Notch Data (Continued)
Temperature          Input Percent Shear                 Computed Percent Shear                Differential 325                       100                                  9227                             7.72 SUM of RESIDUALS = 21.89 C-73

D-O APPENDIX D DIABLO CANYON UNIT 1 SURVEILLANCE PROGRAM CREDIBILITY ANALYSIS Appendix D

D-1 INTRODUCTION:
Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.
To date there have been three surveillance capsules removed from the Diablo Canyon Unit I reactor vessel. To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.
The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Diablo Canyon Unit I reactor vessel surveillance data and determine if the Diablo Canyon Unit I surveillance data is credible.
EVALUATION:
Criterion 1:   Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements", as follows:
                 "the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."
Appendix D

D-2 The Diablo Canyon Unit I reactor vessel consists of the following beltline region materials:
* Intermediate  Shell Plate B4106-1 (Heat Number C2884-1)
* Intermediate  Shell Plate B4106-2 (Heat Number C2854-2)
* Intermediate  Shell Plate B4106-3 (Heat Number C2793-1)
* Lower Shell   Plate B4107-1 (Heat C3121-1)
* Lower Shell   Plate B4107-2 (Heat Number C3131-2)
* Lower Shell   Plate B4107-3 (Heat Number C3131-1)
* Intermediate  Shell Plate Longitudinal Weld Seams 2-442 A, B, C (Heat # 27204, Linde 1092)
* Lower Shell   Plate Longitudinal Weld Seams 3-442 A, B, C (Heat # 27204, Linde 1092)
* Intermediate  to Lower Shell Plate Circumferential Weld Seam 9-442 (Heat # 21935, Linde 1092)
Per WCAP-8465, the Diablo Canyon Unit I surveillance program was based on ASTM El 85, "Recommended Practice for Surveillance Tests on Nuclear Reactor Vessels". Per Section 3.1 of ASTM El 85-70, "Sample shall represent one heat of the base metal and one butt weld if a weld occurs in the irradiated region."
At the time the Diablo Canyon Unit I surveillance capsule program was developed, intermediate shell plates were judged to be most limiting based on the lowest initial upper shelf energy values and higher initial copper values. Hence, all the intermediate shell plates were therefore utilized in the surveillance program.
The weld material in the Diablo Canyon Unit I surveillance program was made of the same wire heat as the reactor vessel upper to intermediate and lower shell longitudinal weld seams (Wire Heat No. 27204, Flux Type Linde 1092). This represents six of the seven welds in the beitline area. The seventh weld, the intermediate to lower shell girth welds, was made from heat 21935. This weld had a higher initial USE and lower copper content than heat 27204. Thus, heat 27204 was chosen as the surveillance weld.
ASTM El 85-70 only requires that the surveillance material represent a weld in the irradiated region.
Since the surveillance weld heat # 27204 is the same as the intermediate and lower shell longitudinal welds, then this criterion is true.
Hence, Criterion I is met for the Diablo Canyon Unit I reactor vessel.
Criterion 2:   Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
Appendix D

D-3 Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in Appendix C. Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy of the Diablo Canyon Unit I surveillance materials unambiguously. Hence, the Diablo Canyon Unit I surveillance program meets this criterion.
Criterion 3:    When there are two or more sets of surveillance data from one reactor, the scatter of ARTNDT   values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28&deg;F for welds and 17&deg;F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values.
Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM El 85-82.
The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 28&deg;F for welds and less than 17&deg;F for the plate.
Following is the calculation of the best fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. In addition, the recommended NRC methods for determining credibility will be followed. The NRC methods were presented to industry at a meeting held by the NRC on February 12 and 13, 1998. At this meeting the NRC presented five cases. Of the five cases Case I ("Surveillance data available from plant but no other source") most closely represents the situation listed above for Diablo Canyon Unit I surveillance weld metal. Note, for the plate materials, the straight forward method of Regulatory Guide 1.99, Revision 2 will be followed.
Appendix D

D-4 TABLE D-1 Diablo Canyon Unit I Surveillance Capsule Data MIaterial               Capsule          F('     l   FF(2    l ARTNDT(3 )   FF x ARTNDT          FF 2 Intermediate Shell              S            0.284        0.656         o(4)            0            0.430 Plate B4106-3                Y             1.05        1.014        48.66          49.34           1.028 (Longitudinal)                V             1.37        1.087        34.32          37.31           1.182 SUM        86.65           2.64 CFpalre      (FF X ARTNDT)
* X( FF ) = 86.65 . 2.64 = 32.8&deg;F 2
Weld Metal                  S      J     0.284        0.656       110.79          72.68          0.430 (Heat # 27204)                Y             1.05        1.014       232.59         235.85           1.028 V             1.37        1.087       201.07         218.56           1.182 SUM       527.09           2.64 CFm,!d = X (FF X ARTNDT)         2
                                                                           ) = 527.09 2(         . 2.64 = 199.7 0 F Notes:
: 1. F = Calculated fluence from Section 6 of this report, [x 1019 nlcm 2, E > 1.0 MeV].
: 2. FF = fluence factor = F028 - log F)
: 3. ARTNDT values are the measured 30 ft-lb shift values, [IF].
: 4. Actual value for Capsule S is -1.78. However, a negative shift in RTNDT should not physically occur.
Thus, a value of zero is conservatively assumed.
The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.
Appendix D

D-5 TABLE D-2 Best Fit Evaluation for Diablo Canyon Unit I Surveillance Materials Material          Capsule       CF (OF)       FF      Measured       Best Fit     Scatter      < 17&deg;F (Base ARTNDT       ARTNDT           of          Metals)
(30 ft-lb)      (OF)       ARTNDT       < 28&deg;F (Weld
(&deg;F)                      (&deg;F)          Mletal)
Inter. Shell           S           32.8      0.656         -1.78       21.52         -23.3           No Plate B4106-3            Y           32.8       1.014       48.66        33.26          15.4           Yes (Longitudinal)           V           32.8       1.087       34.32        35.65         -1.33           Yes Weld Metal              S          199.7      0.656        110.79       131.00       -20.21           Yes (Heat # 27204)            Y          199.7       1.014      232.59        202.50        30.09           No V          199.7       1.087       201.07       217.07          160           Yes Table D-2 indicates that one of the plate data points and one of the weld data points has a scatter value that is greater than a I a of 17&deg;F and 28&deg;F, respectively. Therefore, neither the plate nor the weld meets the criterion for credibility.
Criterion 4:    The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +/- 25&deg;F.
The capsule specimens are located in the reactor between the thermal shield and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the thermal shield.
The location of the specimens with respect to the reactor vessel beitline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25&deg;F. Hence, this criterion is met.
Criterion 5:    The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.
The Diablo Canyon Unit I surveillance program does contain correlation monitor material. NUREG/CR-6413, ORNLITM-13133 contains a plot of residual vs. Fast fluence for the correlation monitor material (Figure 9 in the report). The data used for this plot is contained in Table 14. However, the data within this report only contains the two capsules and not Capsule V. In addition, it used the old fluence values.
Thus, Table D-3 contains an updated calculation of Residual vs. Fast fluence.
Appendix D

D-6 TABLE D-3 Calculation of Residual vs. Fast Fluence Capsule                 Fluence           Fluence        Measured       RG 1.99 Shift         Residual (x 109 n/cm 2 )        Factor           Shift        (CF*FF)a)        (Nleas.- RG Shift)
_ __ _ _ _ __ __ _   _ _ _ _ _ _    (F F )     _ _  _  _  _    _  _   _ _  _  _ _   _   _    _  _ _  _
S                     0.284             0.656          65.62            73.01                 -7.39 Y                      1.05             1.014          115.79            112.9                 2.89 V                      1.37             1.087          116.61           121.0                 -4.39 Notes:
(a)PerNUREG/CR-6413, ORNL/TM-13133, the Cu and Ni values for the Correlation Monitor Material are 0.15 Cu and 0.65 Ni. This equates to a Chemistry Factor of II1.3&deg;F from Reg. Guide 1.99 Rev. 2.
Table D-3 shows a 2a uncertainty of less than 50&deg;F, which is the allowable scatter in NUREG/CR-6413, ORNL/TM-13133. Hence, this criterion is met.
CONCLUSION:
Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10 CFR 50.61, the Diablo Canyon Unit I surveillance data is not credible. This is based on not satisfying the third criterion for credibility. It is recommended that PG&E review all current reactor vessel Integrity Evaluations (PTS and PT Curves) to assess the impact, if any, of non-credible data for the plate B41 06-3 and weld heat #27204.
Appendix D

E-O APPENDIX E VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY I MEASUREMENTS Appendix E

E-1 E.l Neutron Dosimetry Comparisons of measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at Diablo Canyon Unit 1 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."IE 'I 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.
E.]. I Sensor Reaction Rate Determinations In this section, the results of the evaluations of the three neutron sensor sets withdrawn to date as a part of the Diablo Canyon Unit I 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:
Azimuthal               Withdrawal               Irradiation Capsule ID                Location                  Time               Time [EFPYI S                       400              End of Cycle 1                 1.25 Y                       400              End of Cycle 5                 5.87 V                  4&deg; - 40&deg;              End of Cycle 11               14.27
* Capsule  V was irradiated at a 40 location during Cycles 1 through 5 followed by irradiation at a 40&deg; location during Cycles 6 through II when it was subsequently removed from service.
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 E

E-2 The passive neutron sensors included in the evaluations of Surveillance Capsules S, Y, and V are summarized as follows:
Reaction Sensor Material                Of Interest        Capsule S      Capsule Y     Capsule V Copper                 6 3 Cu(n,a)6oCo           X               X             X 54 Iron                    Fe(n,p)4 Mn            X               X             X Nickel                5 8Ni(n,p)"Co             X               X             X Uranium-238                2 38 U(n,f)' 3 7Cs        X               X             X Neptunium-237                 7Np(n,f) 37CS           X               X             X Cobalt-Aluminum*              5 9 Co(n,y)6OCo           X               X             X
* The cobalt-aluminum measurements for this plant include both bare wire and cadmium-covered sensors.
The copper, iron, nickel, and cobalt-aluminum monitors, in wire form, were placed in holes drilled in spacers at several radial locations within the test specimen array. As a result, gradient corrections were applied to these measured reaction rates in order to index all of the sensor measurements to the radial center of the respective surveillance capsules. Since the cadmium-shielded uranium and neptunium fission monitors were accommodated within the dosimeter block centered at the radial, azimuthal, and axial center of the material test specimen array, gradient corrections were not required for the fission monitor reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table E-l.
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 response of each monitor, and
* the neutron energy spectrum at the monitor location.
Appendix E

E-3 The radiometric counting of the neutron sensors from Capsules S and Y was carried out at the Westinghouse Analytical Services Laboratory at the Waltz Mill Site. 1 E-2 ] The radiometric counting of the sensors from Capsule V was completed at the Pace Analytical Laboratory, also located at the 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 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 and neptunium 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 S, Y, and V was based on the reported monthly power generation of Diablo Canyon Unit I from initial reactor startup 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. The irradiation history applicable to Capsules S, Y, and V is given in Table E-2.
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:
A R =                        A NoFY     X'         Cj I-         e Pre where:
R    =     Reaction rate averaged over the irradiation period and referenced to operation at a core power level of Pref (rps/nucleus).
A     =     Measured specific activity (dps/gm).
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.
Pj    =     Average core power level during irradiation period j (MW).
Pref =      Maximum or reference power level of the reactor (MW).
Cj    =     Calculated ratio of O(E > 1.0 MeV) during irradiation period j to the time weighted average O(E > 1.0 MeV) over the entire irradiation period.
         =     Decay constant of the product isotope (I/sec).
tj    =     Length of irradiation period j (sec).
td    =     Decay time following irradiation period j (sec).
Appendix E

E-4 and the summation is carried out over the total number of monthly intervals comprising the irradiation period.
In the equation describing the reaction rate calculation, the ratio Pj]/[Pf] 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 Cj, 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, Cj is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional Cj 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 along with the computed values for Cj are listed in Table E-3.
These flux 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, additional corrections were made to the 23SU 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 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 Diablo Canyon Unit I fission sensor reaction rates are summarized as follows:
Correction               Capsule S        Capsule Y      Capsule V 235 U ImpuritylPu Build-in          0.873            0.844           0.831 23 8 U(y,f)               0.958            0.958           0.958 238 Net U Correction               0.836            0.809           0.796 237 Np(y,f)                 0.985            0.985           0.985 These factors were applied in a multiplicative fashion to the decay corrected uranium and neptunium fission sensor reaction rates.
Results of the sensor reaction rate determinations for Capsules S, Y, and V are given in Table E-4. In Table E-4, the measured specific activities, decay corrected saturated specific activities, and computed reaction rates for each sensor indexed to the radial center of the capsule are listed. The fission sensor reaction rates are listed both with and without the applied corrections for 23sU impurities, plutonium build-in, and gamma ray induced fission effects.
Appendix E

E-5 E. 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 &#xa2;(E > 1.0 MeV) or dpats 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; + R =    E,   (5qig      , +/-ci'3,9N g
relates a set of measured reaction rates, R,, to a single neutron spectrum, 4g, through the multigroup dosimeter reaction cross-section, q.g, each with an uncertainty o. 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 Diablo Canyon Unit 1 surveillance capsule dosimetry, the FERRET code'E~6' 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 three in-vessel capsules tested to date (a total of five capsules have been removed to date; two of the five are in storage).
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 Diablo Canyon Unit I 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 E. 1.1. The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library[E-7]. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations byASTM Standard E1018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (IIB)".
Appendix E

E-6 The uncertainties associated with tlie 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 in ASTM 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 Diablo Canyon Unit I 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:
Reaction                     Uncertainty Cu(n,a)'Co                           5%
                                     -Fe(n,p)-Mn                            5%
                                     -Ni(n,p)sCo                            5%
2-U(n,f) 37Cs                        10%
237 Np(n,f) 137Cs                       10%
9
                                     ' Co(n,y)6Co                          5%
These uncertainties are given at the Ia 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.
For sensors included in the Diablo Canyon Unit I surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.
Appendix E

E-7 These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.
Calculated Neutron Spectrum 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:
M      = R 2 + R
* R
* P.
where Rn 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:
Pg, = [I-6J6g, +           e where 2
H     (g - g) 2y2 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 (O specifies the strength of the latter term). The value of 5 is 1.0 when g = g', and is 0.0 otherwise.
Appendix E

E-8 The set of parameters defining the input covariance matrix for the Diablo Canyon Unit I calculated spectra was as follows:
Flux Normalization Uncertainty (Rn)                                15%
Flux Group Uncertainties (Rg, R..)
(E > 0.0055 MeV)                                            15%
(0.68 eV < E < 0.0055 MeV)                                 29%
(E < 0.68 eV)                                              52%
Short Range Correlation (0)
(E > 0.0055 MeV)                                           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 < 0.68 eV)                                              2 E. 1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Diablo Canyon Unit I surveillance capsules withdrawn to date are provided in Tables E-5 and E-6. In Table E-5, 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. In Table E-6, 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.
The data comparisons provided in Tables E-5 and E-6 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 Appendix E

E-9 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 a level. From Table E-6, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 6% for neutron flux (E > 1.0 MeV) and 7% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the Icr level.
Further comparisons of the measurement results with calculations are given in Tables E-7 and E-8.
These comparisons are given on two levels. In Table E-7, 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 E-8, calculations of fast neutron exposure rates in terms of 4(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 M/C comparisons for fast neutron reactions range from 0.78-1.12 for the 15 samples included in the data set.
The overall average M/C ratio for the entire set of Diablo Canyon Unit I data is 0.94 with an associated standard deviation of 8.3%. This value is used to determine the Best Estimate fluence (E >1.0 MeV) and iron atom displacement values on a cycle wise basis. Table E-9 lists the Best Estimate values on a cycle by cycle basis for the fluence at the capsule center as shown.
In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.86-1.00 for neutron flux (E > 1.0 MeV) and from 0.88 to 1.02 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 0.91 with a standard deviation of 8.3% and 0.93 with a standard deviation of 8.3%, 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 Diablo Canyon Unit I reactor pressure vessel.
Appendix E

E-10 Table E-1 Nuclear Parameters Used In the Evaluation of Neutron Sensors Target       90% Response                   Fission Monitor            Reaction of        Atom             Range          Product      Yield Material              Interest      Fraction                          Half-life     (7)
(MeV)
Copper             63               0.6917          4.9 - 11.8       5.271 y Cu (n,a)
Iron             54               0.0585           2.1 -8.3        312.3 d Fe (n,p)
Nickel             58Ni   (n,p)     0.6808           1.5-8.1         70.82 d Uranium-238            23 8            0.9996           1.2 - 6.7 U (n,f)                                      30.07 y      6.02 Neptunium-237         237                1.0000-         0.4 - 3.5 Np (n,f)                                      30.07 y      6.17 Cobalt-Aluminum         59Co    (n,y)    0.0015        non-threshold      5.271 y Notes: The 90% response range is defined such that, in the neutron spectrum characteristic of the Diablo Canyon Unit I 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 E

E-11 Table E-2 Monthly Thermal Generation During the First Eleven Fuel Cycles Of The Diablo Canyon Unit I Reactor (Reactor Power of 3338 MWt through October 6, 2000, and 3411 MWt thereafter)
Thermal                          Thermal                         Thermal Generation                        Generation                      Generation Year      Month     (MWt-hr)      Year      Month    (MWt-hr)       Year       Month (MWt-hr) 1984        11        167071      1988         1      2035485       1991        3         0 1984        12        781228      1988         2      1710575       1991        4     1610788 1985         1         84750      1988         3       274544       1991        5     2161086 1985         2        497207      1988         4          0         1991        6     2392176 1985         3       1854601      1988         5          0         1991        7     2481053 1985         4           0        1988         6          0         1991         8    2482327 1985         5       1632108      1988         7       927368       1991        9     2350718 1985         6       2286901      1988         8      2358057       1991        10    2481357 1985         7       2435846      1988         9      2068428       1991        11    2197143 1985         8       2218873      1988        10      2427826       1991        12    2480444 1985         9       2374552      1988        11      2368095       1992         1    2480772 1985        10       2163216      1988        12      2404073       1992        2     2322063 1985        11       1523963      1989         1      2398489       1992        3     2138149 1985        12       1929994      1989         2      2207286       1992        4     2224782 1986         1       2424269      1989         3      2449786       1992        5     2410682 1986         2       2102251      1989         4      2162399       1992        6     2400268 1986         3       2406348      1989         5      2441421       1992        7     2418213 1986         4       2132185      1989         6      2363360       1992        8     2381626 1986         5       2490682      1989         7      2468579       1992        9      835392 1986         6       2163689      1989         8      2384230       1992        10       0 1986         7       1842336      1989         9      2400292       1992        11    1352555 1986         8       1366070      1989        10       439623       1992        12    2428355 1986         9           0        1989        11          0         1993         1    2483047 1986        10           0        1989        12       818953       1993        2     2065992 1986        11           0        1990         1      2433618       1993        3     2338926 1986        12        48788       1990         2      2037409       1993        4     2402015 1987         1       1140482      1990         3      2491017       1993        5     2481334 1987         2       2028965      1990         4      2377992       1993        6     2256675 1987         3       2277945      1990         5      2516299       1993        7     2482118 1987         4       2394500      1990         6      1585625       1993        8     2480942 1987         5       2118322      1990         7      2340515       1993        9     2400588 1987         6       2141394      1990         8      2473468       1993        10    2432353 1987         7       2381703      1990         9      2370556       1993        11    2401678 1987         8       2090122      1990        10      2443130       1993        12    1867363 1987         9       2375321      1990        11      2346761       1994         1    2437616 1987        10       2308588      1990        12      1793532       1994        2     2242952 1987        11       2347282      1991         1      2391971       1994        3      872868 1987        12       1817741      1991         2        27364       1994        4        0 Appendix E

E-12 Table E-2 cont'd Monthly Thermal Generation During The First Eighteen Fuel Cycles Of The Diablo Canyon Unit I Reactor (Reactor Power of 3338 through October 6 2000 and 3411 MWt thereafter)
Thermal                            Thermal                      Thermal Generation                         Generation                    Generation Year     Month     (MWt-hr)      Year      Month      (MWt-hr)     Year      Month (MWt-hr) 1994       5        546539      1997         7        2480639     2000         9   2391812 1994       6       2383038      1997         8        2466623     2000        10    400560 1994       7       2493803      1997         9        2394045     2000        11    695918 1994       8       2490277      1997         10       2361899     2000        12   2449052 1994       9       2407121      1997         11       2389197    2001          1   2385664 1994       10       2482344      1997        12        2468651    2001          2   2291938 1994      11       2398894      1998          1       2404594    2001          3   2537268 1994      12       2059217      1998         2        2188679    2001          4   2450959 1995        1       2425927      1998         3        2414420    2001          5   2537285 1995        2       2242278      1998         4        2336535    2001          6   2381547 1995        3       2449140      1998         5        2469944    2001          7   2533658 1995        4       2298107      1998         6        2360812    2001          8   2536196 1995        5       2485576      1998         7        2414420    2001          9   2455470 1995        6       2387434      1998         8        2414420    2001         10   2534575 1995        7       2479699      1998         9        2336535    2001         11   2177067 1995        8       2478524      1998        10        2414420    2001         12   2506152 1995        9       2070677      1998        11        2336535    2002          1   2537285 1995       10           0        1998        12        1572621    2002          2   2260854 1995       11         60824      1999          1       2474763    2002          3   2530637 1995       12       1650488      1999         2         500553    2002         4    2217016 1996        1       2482638      1999         3        1098455 1996        2       2271956      1999         4        2396984 1996       3        2045407      1999         5        2480081 1996       4        2397718      1999         6        2396014 1996       5        2480874      1999         7        2473999 1996       6        2198496      1999         8        2474498 1996       7        2329842      1999         9        2136320 1996        8       1911123      1999        10        2214363 1996       9        2398306      1999        11        2224383 1996       10       2481168      1999        12        2464655 1996       11       1686924     2000           1       2377796 1996       12       2425633     2000          2        2298401 1997        1       2470296     2000          3        2469797 1997       2        2215833     2000          4        2352203 1997       3        2479111     2000          5        1311575 1997       4        1429228     2000          6        2400627 1997       5            0       2000          7        2481168 1997       6        2072263     2000          8        2479288 Appendix E

E-13 Table E-3 Calculated C. Factors at the Surveillance Capsule Center Core Midplane Elevation Fuel               O(E> 1.0 MeV) [n/c m2 -s]                             C Cycle       Capsule S      Capsule Y Capsule V*             S            Y          V*
I        7.23E+10       7.23E+10        2.24E+I 0      1.000        1.267       0.761 2                        6.03E+ 10       1.94E+I 0                  1.057        0.657 3                        6.28E+10        1.60E+10                   1.101        0.542 4                        4.85E+ 10       1.63E+ 0                   0.850        0.554 5                        4.14E+ 10       1.54E+ 10                  0.726        0.522 6                                        4.16E+10                                1.411 7                                        4.1 IE+10                               1.394 8                                        3.69E+10                                1.252 9                                        3.87E+ 10                               1.314 10                                       3.80E+ 10                               1.289 11                                       3.84E+ 10                               1.305 Average      7.23E+10       5.70E+ I0       2.95E+ 10      1.000       1.000        1.000
       *Note: Cj factors based on the ratio of the cycle specific fast (E > 1.0 MeV) neutron flux divided by the average flux over the total irradiation period were deemed unsuitable for Capsule V since reaction rates did not vary by constant values as a function of azimuthal position for this capsule. To a large extent, this was due to moving Capsule V from a 4&deg; to 40&deg; location following the fifth fuel cycle. As a result of this observation, the Cj terms that were utilized in the final Capsule V analysis were based on the individual reaction rates determined from the synthesized transport calculations. The final Cj terms for Capsule V, which are based on individual reaction rates, are reported on the next page of this table.
Appendix E

E-14 Table E-3 cont'd Calculated Ci Factors at the Surveillance Capsule Center Core Midplane Elevation (Capsule V only)
Fuel                                     Capsule V Reaction Rates [rps/atom]
Cycle 6
3Cu  (n,oa)    54 Fe (n,p)    238 U (n,f)   237 Np (n,f) 59 Co  (n,y) 59Co  (n,y) 59 Co (n,'Y) Cd I   2.22E-17          1.99E- 15      2.67E- 15      8.37E-15    5.66E-14     7.12E- 13     3.69E- 13 2      1.96E-17        1.74E-15      2.33E-15       7.25E-15   4.88E-14      6.09E-13      3.16E-13 3      1.66E- 17      1.45E-15        1.94E- 15     5.99E- 15  4.02E- 14    5.01E-13       2.60E- 13 4       1.71E-17        1.49E-15       1.99E-15      6.14E-15   4.10E-14     5.08E-13       2.63E-13 5      1.62E-17        1.40E-15       1.88E-15      5.79E-15    3.87E-14    4.79E- 13      2.49E-13 6     2.78E-17        2.98E-15       4.10E-15       1.45E-14    1.12E-13     1.69E-12      8.94E-13 7     2.77E-17        2.96E-15       4.06E-15       1.44E-14    1. IOE-13    1.66E- 12     8.81E-13 8     2.50E- 17       2.66E- 15      3.65E- 15      1.29E- 14  9.89E-14      1.49E- 12     7.90E- 13 9     2.64E- 17       2.80E- 15      3.84E-15       1.36E-14    1.04E-13     1.56E- 12     8.27E- 13 10     2.60E-17        2.75E-15       3.77E- 5       1.33E- 14   1.02E-13     1.53E-12      8.1OE-13 11     2.64E- 17       2.79E- 15      3.83E- 15      1.35E- 14   1.03E- 13    1.55E- 12     8.20E- 13 Average    2.28E- 17       2.27E-15       3.09E-15       1.05E-14   7.77E-14      1.12E-12      5.89E-13 Fuel                                                     Capsule V   Cj Cycle Cu (n,a)      -4Fe (n,p)     238w  (n,f)        Np (n,f)  59Co (n,y)      Co (n,yn,yd 1         0.97           0.88           0.86            0.80          0.73         0.64            0.63 2          0.86           0.76           0.75            0.69          0.63         0.55            0.54 3          0.73           0.64           0.63            0.57          0.52         0.45            0.44 4          0.75           0.65           0.64            0.58          0.53         0.45            0.45 5          0.71           0.62           0.61            0.55          0.50         0.43            0.42 6          1.22            1.31           1.32           1.38          1.44         1.51             1.52 7          1.21            1.30           1.31           1.37          1.42         1.49             1.50 8          1.09            1.17           1.18            1.23         1.27         1.34             1.34 9          1.16            1.23           1.24           1.29          1.34         1.40             1.40 10         1.14            1.21           1.22           1.26          1.31         1.37             1.37 11         1.16            1.23           1.24           1.28          1.33         1.39             1.39 Average       1.00            1.00       I 1.00              1.00         1.00         1.00             1.00 Appendix E

E-15 Table E-4 Measured Sensor Activities And Reaction Rates Surveillance Capsule S Radially          Radially Adjusted           Adjusted Measured              Saturated           Saturated          Reaction Activity              Activity            Activity             Rate Reaction                     Location                 (dps/g)              (dps/g)              (dps/g)         (rps/atom) 61Cu   (n,a) 60Co                    Top                4.470E+04            3.146E+05            3.269E+05          4.987E- 17 Bottom               4.290E+04            3.019E+05            3.137E+05          4.786E- 17 Average                                                                            4.887E-17 54Fe   (n,p) 5 4Mn             W-3 Charpy               1I.130E+06            2.716E+06           2.830E+06          4.486E- 15 W-4 Charpy               1I.130E+06            2.716E+06           2.830E+06          4.486E-15 W-8 Charpy               I .150E+06           2.764E+06            2.880E+06          4.565E- 15 E-41 Charpy               1.330E+06            3.196E+06           2.739E+06          4.342E- 15 R-47 Charpy              1.350E+06             3.244E+06           2.780E+06          4.408E- 15 Average                                                                           4.457E-15 5 8Ni  (n,p)    58Co               Middle               8.200E+06            4.785E+07            4.986E+07          7.137E-15 Average                                                                            7.137E-15 238U   (n f 137CS (Cd)                Middle               1.310E+05            4.634E+06            4.634E+06         3.043E- 14 238U (n,f) 137 Cs (Cd)                                   Including   235 U, 2 39 pU, and y,fission corrections:        2.545E-14 237Np    (n,f)  137 Cs  (Cd) 237Np (n,f)      37 Middle               9.970E+05             3.527E+07           3.527E+07         2.250E- 13 1 Cs    (Cd)                                                    Including y,ission correction:          2.215E-13 59                                   Top                7.560E+06             5.321 E+07          5.098E+07         3.326E- 12 Co (n,y) 6 Co Middle               7.350E+06            5.173E+07            4.956E+07         3.233E- 12 Bottom               7.870E+06             5.539E+07           5.307E+07         3.462E- 12 Average                                                                          3.340E-12 59 Co   (n,y) 60 Co   (Cd)              Top                4.030E+06             2.836E+07           2.454E+07          1.601 E-12 Middle               3.980E+06             2.801E+07           2.423E+07          1.581E-12 Bottom               4.050E+06             2.851 E+07          2.466E+07          1.609E- 12 Average                                                                           1.597E-12 Notes:    I) Measured specific activities are indexed to a counting date of February 2, 1987.
2)The average 23 8U (n.f) reaction rate of 2.545E-14 includes a correction factor of 0.873 to account for plutonium build-in and an additional factor of 0.958 to account for photo-fission effects in the sensor.
: 3) The average 237Np (n,f) reaction rate of 2.215E-13 includes a correction factor of 0.985 to account for photo-fission effects in the sensor.
Appendix E

E-16 Table E-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule Y Radially             Radially Adjusted            Adjusted Measured           Saturated            Saturated            Reaction Activity            Activity            Activity               Rate Reaction                      Location                  (dps/g)              (dps/g)             (dps/g)           (rps/atom) 63Cu   (n,ax) 6OCo                   Top                   1.23E+05            1.52E+05            1.45E+05             2.21 E-17 Bottom                  1.28E+05            1.58E+05            1.51 E+05            2.30E-17 Average                                                                              2.26E-17 54 Fe (n,p) 5Mn                W-09 Charpy                 1.02E+06            1.15E+06            1.IOE+06             1.74E- 15 W-16 Charpy                 1.05E+06            1.19E+06            1.13E+06             1.80E-15 E-49 Charpy                8.87E+05            I.OOE+06            1I.15E+06            1.83E-15 E-56 Charpy                9.03E+05            1.02E+06            1.1 7E+06            1.86E-15 Average                                                                             1.81E-15 58Ni (n,p)   5 8Co Middle                  9.58E+06           2.09E+07             1.99E+07             2.85E- 15 Average                                                                               2.85E-15 238U (n,f) 137Cs    (Cd)              Middle                 4.68E+05             1.69E+06            1.69E+06             1.11 E-14 238U (n,f)   137Cs (Cd)                                   Including 235U,239 Pu, and y,fission corrections:              8.84E-15 237Np (n,f) 137Cs (Cd)                 Middle                  3.44E+06           1.24E+07             1.24E+07             7.94E-14 237Np (n,f) '"Cs (Cd)
Including y,fission correction:             7.82E-14 59Co   (n,y) 6Co                      Top                  1.38E+07           1.70E+07              1.62E+07             1.06E-12 Middle                 1.46E+07           1.80E+07              1.71 E+07           1.12E-12 Bottom                  1.39E+07           1.71 E+07             1.63E+07            1.06E- 12 Average                                                                              1.08E-12 59                                       Top Co (n,y)   6OCo (Cd)                                      6.53E+06            8.05E+06             7.65E+06             4.99E-1 3 Middle                 7.42E+06            9.15E+06              8.69E+06            5.67E- 13 Bottom                 6.37E+06            7.85E+06             7.46E+06             4.87E-1 3 Average                                                                              5.18E-13 Notes: I) Measured specific activities are indexed to a counting date of August 1, 2002.
2
: 2) The average    38U (n.f) reaction rate of 8.84E-15 includes a correction factor of 0.831 to account for plutonium build-in and an additional factor of 0.958 to account for photo-fission effects in the sensor.
237
: 3) The average      Np (n.f) reaction rate of 7.82E-14 includes a correction factor of 0.985 to account for photo-fission effects in the sensor.
Appendix E

E-17 Table E-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule V Radially             Radially Adjusted            Adjusted Measured             Saturated           Saturated            Reaction Activity            Activity             Activity               Rate Reaction                        Location                  (dps/g)             (dps/g)              (dps/g)           (rps/atom) 63 Cu  (n,cx) 6OCo                      Top                  3.80E+04            7.80E+04             8.12E+04              1.24E-17 Bottom                  3.81 E+04           7.82E+04             8.14E+04              1.24E-17 Average                                                                               1.24E-17 54              54 Fe (n,p)        Mn             R-48 Charpy                1.58E+06            2.55E+06             2.66E+06             4.22E- 15 R-42 Charpy                1.62E+06            2.62E+06             2.73E+06             4.33E- 15 H-2 Charpy                1.47E+06            2.37E+06             2.48E+06             3.93E-15 S-58 Charpy                1.90E+06            3.07E+06             2.65E+06             4.19E-15 S-52 Charpy                1.87E+06            3.02E+06             2.60E+06             4.13E- 15 W-2 Charpy                 1.75E+06            2.83E+06             2.44E+06             3.86E-15 Average                                                                               4.11E-15 238 U   (n,f)  137 Cs   (Cd)             Middle                  2.52E+05             1.64E+06             1.64E+06             1.08E- 14 23 5 U (n,f)    13 7 Cs  (Cd)                              Including 235U, 239Pu, and yfission corrections:                    8.64E-15 237' Np   (n,f)   37 1 Cs     (Cd)             Middle                 1.23E+05            7.99E+05             7.99E+05             5.1OE-15 23 7Np    (n,f)  137 Cs (Cd)                                                      Including y,fission correction:             5.02E-15 59Co  (n,y) Co                         Top                  3.1 IE+06           6.38E+06              6.1I E+06           5.98E- 16 Middle                  2.82E+06            5.79E+06             f5.54E+06            5.42E-16 Bottom                  3.01 E+06           6.18E+06              5.91 E+06           5.79E-16 Average                                                                              5.73E-16
  "'Co (ri,y) 'Co (Cd)                       Top                  1.53E+06            3.14E+06             22.77E+06            2.71E-16 Middle                  3.17E+04            6.51 E+04            55.74E+04           5.62E-18 Bottom                  1.52E+06            3.12E+06            22.75E+06            2.69E-16 Average                                                                               1.82E-16 Notes: I) Measured specific activities are indexed to a counting date of March 30, 1985.
238
: 2) The average      U (n.f) reaction rate of 8.64E- 15 includes a correction factor of 0.837 to account for plutonium build-in and an additional factor of 0.960 to account for pholo-fission effects in the sensor.
237
: 3) The average     Np (n.f) reaction rate of 5.02E- 15 includes a correction factor of 0.984 to account for photo-fission effects in the sensor.
Appendix E

E-18 Table E-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule S Reaction Rate [rps/atom]
Best Reaction               Measured      Calculated     Estimate       M/C  M/BE 63Cu(n,a) 60Co              4.89E-17     4.46E- 17      4.69E- 17      1.10  1.04 54Fe(n,p) 54Mn              4.46E-15      5.01E-15      4.87E- 15      0.89  0.92 18Ni(n,p) Co                7.14E- 15     6.91E-15      6.96E- 15      1.03  1.03 23 8U(n,f 37Cs (Cd) 2.54E-14     2.50E-14       2.49E-14       1.02  1.02 2 37 Np(n,f)1 37Cs (Cd)        2.21E-13      1.97E-13      2.10E-13       1.13  1.05 59 Co(n,y)6oCo             3.34E- 12    2.93E- 12      3.32E- 12      1.14  1.00 5 9Co(n,y)6Co (Cd)              1.60E- 12                   1.60E- 12 1.53E-12       1.04  1.00 Capsule Y Reaction Rate [rps/atom]
Best Reaction               Measured      Calculated     Estimate       M/C  M/BE 6 3 Cu(n,a)60Co 3.67E- 17     3.69E- 17     3.58E-17       0.99  1.02 54Fe(n,p)5    Mn            3.44E- 15    4.02E- 15      3.63E-15       0.86  0.94 58Ni(n,p) 5 8 Co            5.23E- 15    5.54E- 15      5.1 OE- 15     0.94  1.02 23 8U(n,f)137 Cs (Cd)         1.82E-14      1.98E-14      1.77E-14       0.92  1.03 2 37 Np(n f)137 Cs (Cd)          1.24E-13      1.54E-13      1.30E-13       0.81  0.95 59 Co(n,y)6Co               2.35E- 12    2.26E- 12      2.35E-12       1.04  1.00 5 9Co(n,y)6oCo (Cd)             1.15E-12      1.18E-12      1.15E-12       0.97  1.00 Capsule V Reaction Rate [rps/  tom]
Best Reaction               Measured     Calculated      Estimate       M/C  M/BE 6 3 Cu(n,a)6OCo 2.26E-17     2.32E- 17      2.16E-17       0.97  1.04 5 Fe(n,p)5    Mn            1.81E-15     2.32E-15       1.97E-15       0.78  0.92 58Ni(n,p)"Co 2.85E-15     3.16E-15       2.77E-15       0.90  1.03 2 38U(n,f)13 7Cs (Cd)         8.84E-15      1.08E-14      9.24E-15       0.82  0.96 2 37 Np(n,f)' 3 7 Cs (Cd)        7.81E-14     8.06E-14       7.39E-14       0.97  1.05 59 Co(n,y)6oCo              1.08E-12      1.13E-12      1.08E- 12      0.95  1.00 59 Co(n,y)6oCo (Cd)             5.18E-13     5.87E-13       5.20E-13       0.88  1.00 Appendix E

E-19 Table E-6 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center 4(E > 1.0 MeV) [n/cm2 -s]                           I Best          Uncertainty Capsule ID           Calculated           Estimate              (I )               BE/C S               7.23E+10             7.26E+lO               6%                 1.00 Y                5.68E+10             5.05E+10               6%                 0.89 V                3.04E+I 1            2.61 E+    1           6%                 0.86 Notes: ) Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.
Iron Atom Displacement Rate [dpa/s]
Best          Uncertainty Capsule ID           Calculated           Estimate              (I )               BE/C S                I.22E-10             1.23E-10              7%                 1.01 Y                9.56E- 1             8.44E-1 1              7%                 0.88 V                5.05E- I             4.39E-1 1              7%                 0.87 Notes: I) Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.
Appendix E

E-20 Table E-7a Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions M/C Ratio Reaction                     Capsule S             Capsule Y          Capsule V 63Cu(n,(x) Co                       1.10                0.99                0.97 54Fe(n,p)5 4Mn 0.89                  0.86               0.78 s Ni(n,p)"Co                        1.03                 0.94               0.90 2 38U(n,p)' 37Cs (Cd)                   1.02                 0.92               0.82 2 37 Np(n,f)' 3 7 Cs (Cd)                1.12                 0.81               0.97 Average                          1.03                0.90                0.89
               % Standard Deviation                       8.7                  8.2                9.8 Note: 1) The overall average M/C ratio for the set of 15 sensor measurements is 0.94 with an associated standard deviation of 8.3%.
Table E-7b Comparison of Measured/Calculated Individual Sensor Reactions without Recourse to the Least Squares Adjustment Encompassing all In-Vessel and Ex-Vessel Dosimetry In-Vessel -                 Ex-Vessel               Combined Average          Unc.        Average         Unc. Average       Unc.
Reaction                    M/C           (I )           M/C           (I )     M/C          (I )
6 3Cu(n,a)'Co                  1.02           7.0           0.87           8.0     0.95          10.6 54 Fe(n,p)54Mn                 0.84           5.7           0.84          11.1     0.84          0.0 5RNi(n,p) 5SCo                 0.96           6.7           0.89          10.6     0.93          4.9 23 8U(n  p)' 3 7 Cs (Cd)           0.92          10.0           0.96          11.4     0.94          2.8 23 7 Np(n, f)' 3 7Cs  (Cd)          0.97          16.0           0.98          13.1     0.91          0.7 Linear Average                   0.94           6.7           0.91           6.0     0.91          43 Table E-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID               (E> 1.0 MeV)          dpa/s S                      1.00                1.02 Y                      0.89               0.89 V                      0.86               0.88 Average                    0.92               0.93
                           % Standard Deviation                  8.0                 8.4 Appendix E

E-21 Table E-9 Best Estimate Fluence and Iron Atom Displacement Values on a Cycle-By-Cycle Basis Cumulative                                 Best Estimate Values Operating                 &#xa2;(E > 1.0 MeV)                        Iron Displacements Cycle           Time                       I n/cm2)                                  Idpa)
{EFPY)           40            400        Capsule         40           400        Capsule V*                                      V*
1            1.25       8.03E+ 17     2.59E+18      8.03E+ 17   1.34E-03      4.51 E-03      1.34E-03 2            2.27       1.37E+ 18     4.36E+ 18     1.37E+ 18   2.28E-03      7.59E-03      2.28E-03 3            3.45       1.91 E+ 18    6.48E+18      1.91E+18    3.18E-03      1.13E-02      3.18E-03 4             4.51       2.41 E+ 18    7.96E+ 18     2.41 E+18   4.01 E-03     1.38E-02      4.01E-03 5             5.87       3.01 E+ 18    9.58E+18      3.01 E+ 18  5.01 E-03     1.67E-02      5.01E-03 6            7.14       3.60E+ 18     1.I1 E+ 19    4.53E+ 18   5.99E-03      1.93E-02      7.64E-03 7            8.47       4.19E+ 18     1.27E+19      6.09E+ 18   6.98E-03      2.20E-02       1.04E-02 8            9.75       4.69E+ 18     1.40E+ 19     7.44E+ 18   7.81 E-03     2.44E-02       1.27E-02 9           11.38       5.40E+ 18     1.58E+19      9.25E+ 18   8.98E-03      2.75E-02       1.58E-02 10           12.87       5.98E+ 18     1.75E+ 19     1.09E+ 19   9.96E-03      3.03E-02       1.87E-02 I1           14.27       6.60E+ 18     1.91 E+19     1.25E+ 19   l. lOE-02     3.3 E-02      2.14E-02 Projections       16.00       7.34E+ 18     2.1OE+19                  1.22E-02      3.64E-02 Projections       24.00       1.08E+ 19     3.02E+ 19                 1.80E-02      5.25E-02 Projections       32.00       1.43E+ 19     3.94E+ 19                 2.38E-02      6.85E-02 Projections       40.00       1.78E+19      4.87E+19                  2.97E-02      8.45E-02 Projections       48.00       2.13E+19      5.79E+19                  3.55E-02      I.OOE-01 Projections       54.00       2.39E+19                                3.98E-02      1.12E-0 1 Notes: 1)
* Capsule V was irradiated at a 4 capsule position for cycles 1-5 at which point it was moved to be irradiated in a 40&deg; location until it was removed at the end of cycle 11.
Appendix E

E-22 Table E-10                i Best Estimate Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative     Cumulative               Neutron Flux (E > 1.0 MeV)
Cycle      Irradiation    Irradiation                       [n/cm 2-s]_
Length          Time          Time Cycle      [EFPS]        [EFPS]         [EFPY]           O0         150            30&deg;       450 I     3.94E+07      3.94E+07           1.25      6.14E+09    9.73E+09       1.23E+I 0 1.90E+ l0 2     3.23E+07      7.16E+07           2.27      5.40E+09    7.69E+09       1.06E+ 10 1.59E+10 3      3.72E+07       1.09E+08          3.45. 4.39E+09    7.16E+09       1.08E+I 0 1.66E+10 4      3.34E+07       1.42E+08          4.51      4.49E+09    6.89E+09       8.68E+09  1.30E+10 5     4.31 E+07      1.85E+08          5.87      4.25E+09    6.42E+09       8.01E+09  1.09E+10 6     4.01 E+07     2.25E+08           7.14      4.44E+09    6.96E+09       8.07E+09  1.1OE+10 7     4.18E+07      2.67 E+08          8.47      4.28E+09    6.88E+09       8.18E+09  1.08E+ lO 8     4.04E+07      3.08 E+08          9.75      3.81 E+09   6.24E+09       7.50E+09  9.84E+09 9     5.13E+07      3.59 E+08         11.38      4.17E+09    6.36E+09       7.64E+09  1.02E+I 10     4.72E+07      4.06 E+08         12.87      3.71 E+09   6.61 E+09      7.95E+09  9.98E+09 11     4.58E+07      4.52 E+08         14.27      4.02E+09    7.46E+09       8.63E+09  I .OOE+ I0 Projection 5.29E+07      5.05 E+08         16.00      4.18E+09    6.84E+09       8.16E+09  1.06E+10 Projection 2.53E+08      7.57 E+08         24.00      4.18E+09    6.84E+09       8.16E+09  1.06E+ 10 Projection 2.53E+08       1.0 IE+09        32.00      4.18E+09    6.84E+09       8.16E+09  1.06E+10 Projection 2.53E+08       1.26E+09         40.00      4.18E+09    6.84E+09       8.16E+09  1.06E+10 Projection 2.53E+08       1.5 lE+09        48.00      4.18E+09    6.84E+09       8.16E+09  1.06E+10 Projection 1.89E+08       1.70E+09         54.00      4.18E+09    6.84E+09       8.16E+09  1.06E+10 Appendix E

             -                                                                                         l~~~~~~~~~~
E-23 Table E-10 cont'd Best Estimate Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative     Cumulative            Neutron Fluence (E > 1.0 MeV)
Cycle      Irradiation    Irradiation                     [n/cm 2 ]
Length          Time          Time Cycle      [EFPS]        [EFPS]         [EFPY]         00         150           300        450 I     3.94E+07      3.94E+07           1.25     2.42E+17    3.83E+ 17    4.85E+ 17  7.46E+17 2      3.23E+07      7.16E+07           2.27     4.16E+ 17   6.31E+17     8.26E+ 17  1.26E+ 18 3      3.72E+07       1.09E+08          3.45     5.79E+17    8.97E+17     1.23E+18   1.88E+18 4      3.34E+07       1.42E+08          4.51     7.29E+ 17   1.13E+18     1.52E+ 18  2.31E+18 5      4.31 E+07      1.85E+08          5.87     9.12E+17    1.40E+ 18    1.86E+18   2.78E+18 6      4.0 E+07      2.25E+08           7.14     1.09E+18    1.68E+ 18    2.19E+18   3.22E+18 7      4.18E+07      2.67 E+08          8.47     1.27E+18    1.97E+ 18    2.53E+ 18  3.67E+ 18 8     4.04E+07      3.08 E+08          9.75     1.42E+ 18   2.22E+ 18    2.83E+ 18  4.07E+ 18 9      5.13E+07      3.59 E+08         11.38     1.64E+ 18   2.55E+ 18    3.22E+ 18  4.59E+ 18 10     4.72E+07      4.06 E+08         12.87     1.81E+18    2.86E+ 18    3.60E+18   5.06E+ 18 11     4.58E+07      4.52 E+08         14.27     1.99E+ 18   3.20E+ 18    3.99E+ 18  5.52E+ 18 Projection 5.29E+07      5.05 E+08         16.00     2.22E+18    3.56E+ 18    4.42E+18   6.08E+ 18 Projection 2.53E+08      7.57 E+08         24.00     3.27E+ 18   5.29E+ 18    6.48E+ 18  8.75E+ 18 Projection 2.53E+08       1.0 IE+09        32.00     4.33E+18    7.02E+ 18    8.54E+ 18  1.14E+ 19 Projection 2.53E+08       1.26E+09         40.00     5.38E+18    8.74E+ 18    1.06E+ 19  1.41E+19 Projection 2.53E+08       1.51 E+09        48.00     6.43E+ 18   1.05E+ 19    1.27E+ 19  1.68E+ 19 Projection 1.89E+08       1.70E+09         54.00     7.22E+18    1.18E+19     1.42E+19     .88E+19 Appendix E

E-24 Table E-10 cont'd Best Estimate Azimuthal Variation of Fast Neutron Exposure Rates And Iron Atom Displacement Rates At the Reactor Vessel Clad/Base Metal Interface Cumulative    Cumulative              Iron Atom Displacement Rate Cycle     Irradiation   Irradiation                          [dpa/s]
Length        Time          Time Cycle      [EFPS]       [EFPS]        [EFPY]          00            15&deg;           300       450 3.94E+07      3.94E+07          1.25      9.96E-12     1.56E-1 1      1.99E-11  3.06E-1 I 2     3.23E+07      7.16E+07         2.27       8.74E-12     1.23E-11       1.70E-11  2.57E-Il 3     3.72E+07      1.09E+08         3.45       7.13E-12     1.15E-II       1.74E-I1  2.68E-I1 4      3.34E+07      1.42E+08         4.51      7.28E-12      I.IOE-11       1.40E-11  2.10OE-1 5      4.311E+07     1.85E+08         5.87      6.88E-12      1.03E-I1       1.29E-11  1.76E-Il 6     4.011E+07     2.25E+08         7.14      7.20E-12      1.IE-1I        1.30E-11  1.77E-I1 7     4.18E+07     2.67E+08          8.47      6.94E-12      LIOE-11        1.32E-1I  1.75E-Il 8     4.04E+07     3.081E+08         9.75      6.18E-12      9.99E-12       1.211-Il  1.59E-I1 9     5.13E+07     3.591E+08         11.38     6.76E-12      1.02E-1I       1.23E-11  1.65E-II 10     4.72E+07     4.06E+08          12.87     6.04E-12      1.06E-I1       1.28E-11  1.61E-ll 11     4.58E+07     4.52 E+08         14.27     6.55E-12      I.I9E-11       1.39E-11  1.62E-II Projection 5.29E+07     5.051E+08         16.00     6.78E-12      1.09E-11       1.31E-11  1.71E-1I Projection 2.53E+08     7.571E+08        24.00      6.78E-12      1.09E-11       1.31E-11  1.7113-II Projection 2.53E+08      I.OE+09         32.00      6.78E-12      1.09E-11       1.31E-11  1.71E-ll Projection 2.53E+08      1.26E+09        40.00      6.78E-12      1.0913-11      1.3113-11 1.71E-1l Projection 2.53E+08      1.511E+09       48.00      6.78E-12      1.09E-11       1.3113-11 1.71E-1I Projection 1.89E+08      1.70E+09        54.00      6.78E-12      1.09E-1        1.31E-11  1.71-I Appendix E

I E-25 Table E-10 cont'd Best Estimate Azimuthal Variation of Maximum Exposure Rates And Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface Cumulative    Cumulative               Iron Atom Displacements Cycle      Irradiation    Irradiation                        [d a]
Length        Time           Time Cycle     [EFPS]        [EFPS]         [EFPY]          00          150          300       450
_     3.94E+07      3.94E+07          1.25      3.92E-04    6.13E-04     7.83E-04   I.21 E-03 2      3.23E+07      7.16E+07          2.27      6.74E-04    1.01 E-03     1.33E-03  2.04E-03 3      3.72E+07      1.09E+08          3.45      9.39E-04    1.44E-03      1.98E-03  3.03E-03 4      3.34E+07      1.42E+08          4.51      1.1 8E-03   1.81 E-03    2.44E-03   3.73E-03 5      4.31 E+07     1.85E+08          5.87      1.48E-03    2.25E-03     3.OOE-03   4.49E-03 6      4.01 E+07     2.25E+08          7.14      1.77E-03    2.70E-03     3.52E-03   5.20E-03 7      4.18E+07     2.67 E+08          8.47      2.06E-03    3.16E-03     4.07E-03   5.93E-03 8      4.04E+07     3.08 E+08          9.75      2.31 E-03   3.56E-03     4.55E-03   6.57E-03 9      5.13E+07     3.59 E+08         11.38      2.65E-03    4.08E-03     5.19E-03   7.42E-03 10     4.72E+07     4.06 E+08         12.87      2.94E-03    4.58E-03     5.79E-03   8.18E-03 11     4.58E+07     4.52 E+08         14.27      3.24E-03    5.12E-03     6.43E-03   8.92E-03 Projection 5.29E+07     5.05 E+08         16.00      3.59E-03    5.70E-03     7.12E-03   9.82E-03 Projection 2.53E+08     7.57 E+08         24.00      5.31 E-03   8.47E-03     1.04E-02   1.41 E-02 Projection 2.53E+08      1.0 I E+09       32.00      7.02E-03    1.1 2E-02     1.38E-02  1.84E-02 Projection 2.53E+08      1.26E+09         40.00      8.73E-03    1.40E-02      1.71 E-02 2.28E-02 Projection 2.53E+08      1.51 E+09        48.00      1.04E-02    1.68E-02     2.04E-02   2.71 E-02 Projection 1.89E+08      1.70E+09         54.00      1.1 7E-02   1.88E-02     2.29E-02   3.03E-02 Appendix E

I E-26 To document the ex-vessel dosimetry program the following tables have been extracted from Reference E-8.
Capsule Identifications for Ex-Vessel Irradiations Azimuth              Capsule Identification - Cycle 1 Irradiation
[degrees]          Core Top         Core Midplane          Core Bottom 0.0                                    F 13.5                                    E 33.8                                    D 45.0                C                   B                    A Azimuth              Capsule Identification - Cycle 2 Irradiation
[degrees]          Core Top          Core Midplane         Core Bottom 0.0                                    A 10.9                                    B 35.1                                    C 42.0 (48.0)             D                   E                    F Azimuth             Capsule Identification - Cycles 3-4 Irradiation
[degrees]          Core Top          Core Midplane         Core Bottom 0.0                                    A 10.9                                    B 35.1                                    C 42.0 (48.0)             D                   E                    F Azimuth             Capsule Identirication - Cycles 5-6 Irradiation
[degrees]          Core Top          Core Midplane         Core Bottom 0.0                                    G 10.9                                    H 35.1                                    1 42.0 (48.0)             3                   K                    L Appendix E

E-27 Azimuth     Capsule Identification - Cycles 7-10 Irradiation
[degrees]    Core Top       Core Midplane      Core Bottom 0.0                           M 10.9                           N 35.1                           0 42.0 (48.0)     P                 Q                  R Appendix E

E-28 Contents of Multiple Foil Sensor Sets Cycle I Irradiation Capsule ID        Bare or                  Radiometric Monitor ID and           Cadmium                                              U    U Position        Covered  Fe      Ni      Cu          Ti        Co   Nat. Dep. SSTR A-1              Bare   A                                     9              DC-19 A-2            Cd Cov. 3     DU                CN/CU         3 A-3            Cd Cov.                                           UN-05 U8-05 DC-23 B-1             Bare  B/7                                    7              DC-01 B-2           Cd Cov.         SI               CL/CK         I B-3           Cd Cov.                                           UN-06 U8-06 DC-09 C-1             Bare   C                                     8              DC-17 C-2           Cd Cov. 2     SH                  CM         2 C-3           Cd Cov.                                           UN-07 U8-07 DC-21 D-1              Bare   D                                    10              DC-02 D-2            Cd Cov. 4     DK                CP/CR        4 D-3            Cd Cov.                                           UN-08 U8-08 DC-10 E-1              Bare   E                                    11              DC-03 E-2            Cd Cov. 5     DL                CT/CS        5 E-3            Cd Cov.                                           UN-09 U8-09 DC-Il F-I             Bare   F                                    12              DC-04 F-2           Cd Cov. 6     DM                AU/CU        6 F-3           Cd Cov.                                           UN-10 U8-10 DC-12 Appendix E

E-29 Cycle 2 Irradiation Capsule ID  Bare or    Radiometric Monitor ID and   Cadmium Position Covered  Fe  Cu      Nb      Co    U-238 SSTR A-1     Bare   G                   AS          W2-7 A-2    Cd Cov. H   AK        S      A A-3    Cd Cov.                             G   W2-8 B-1     Bare   N                   AR          W2-5 B-2    Cd Cov. I  AL        T      B B-3    Cd Cov.                             H   W2-6 C-1     Bare   0                   AP          W2-3 C-2    Cd Cov. J  AM       N       C C-3    Cd Cov.                             I   W2-4 D-1     Bare   p                   AN          W2-9 D-2    Cd Cov. K   AN       0       D D-3    Cd Cov.                                 W2-10 E-1     Bare   R                   AO          W2-1 E-2    Cd Cov. L   AO        p      E E-3    Cd Cov.                             K   W2-2 F-1     Bare   S                   AM          W2-11 F-2    Cd Cov. M   AP        R      F F-3    Cd Cov.                            M    W2-12 Appendix E

E-30 Cycles 3-4 Irradiation Capsule ID       Bare or        Radiometric Monitor ID and         Cadmium             I                    U Position       Covered  Fe Ni Cu     Ti      Co       De Nb SSTR A-1             Bare  AA                   G              W8-07 A-2           Cd Cov. AB K  AR     AA      H           G A-3           Cd Cov.                                     W8-08 B-1             Bare  AC                    I             W8-05 B-2           Cd Cov. AD L  AS     AB       J          H B-3           Cd Cov.                                     W8-06 C-i             Bare  AE                   K              W8-03 C-2           Cd Coy. AF M  AT     AC       L           I C-3           Cd Coy.                                     W8-04 D-1             Bare  AG                   M              W8-09 D-2           Cd Coy. AH N  BG     AD      N            J D-3           Cd Cov.                                     W8-10 E-1            Bare  Al                   0              W8-01 E-2          Cd Cov. AJ 0  BH     AE       P          K E-3          Cd Cov.                                     W8-02 F-1            Bare   T                   R              W8-11 F-2          Cd Coy. U  P  BJ     AF       S          L F-3          Cd Cov.                                     W8-12 Appendix E

E-31 Cycles 5-6 Irradiation Capsule ID       Bare or       Radiometric Monitor ID and         Cadmium                                 U Position       Covered  Fe Ni Cu     Ti     Co       Dep. Nb SSTR G-1             Bare  BA                  AA               W23-7 G-2           Cd Cov. CA    G             CA G-3           Cd Cov.                                      W23-8 H-1             Bare  BB                  AB               W23-5 H-2           Cd Cov. CB    H             CB H-3           Cd Cov.                                      W23-6 I-1            Bare  BC                  AC               W23-3 1-2          Cd Cov. CC     I            CC 1-3          Cd Cov.                                      W23-4 J-1            Bare  BD                  AD               W23-9 J-2          Cd Cov. CD                  CD J-3          Cd Cov.                                      W23-10 K-1             Bare  BE                  AE               W23-1 K-2           Cd Cov. CE    K             CE K-3           Cd Cov.                                      W23-2 L-1             Bare  BF                  AF               W23-11 L-2           Cd Cov. CF     L            CF L-3           Cd Cov.                                      W23-12 Appendix E

E-32 Cycles 7-10 Iadiation Capsule ID      Bare or          Radiometric Monitor ID and        Cadmium                          .
Position      Covered  Fe Ni Cu   Ti      Co       Nb  U-238 Np-237 M-1           Bare   BA                 BA M-2         Cd Cov. AA    A    A       AA        A M-3         Cd Cov.                                    14     8 N-1           Bare   BB                 BB AB N-2         Cd Cov.        B    B       AB        B N-3         Cd Cov.                                   15     9 BC 0-1           Bare                      BC AC 0-2         Cd Cov.        C    C       AC        C 0-3         Cd Cov.                                   16     10 BD P-1           Bare                      BD AD P-2         Cd Cov.        D    D       AD       D P-3         Cd Cov.                                   17     12 BE Q-1           Bare                      BE AE Q-2         Cd Cov.        E    E       AE        E Q-3         Cd Cov.                                   18     13 BF R-1           Bare                      BF AF R-2         Cd Cov.        F    F       AF        F R-3         Cd Cov.                                   19    14 Appendix E

E-33 The results of the dosimetry evaluations performed for the Diablo Canyon Unit I Ex-Vessel capsules withdrawn to date from locations opposite the core axial midplane are provided below. The data tabulations for each capsule evaluation include the following information:
I - The Measured, Calculated, and Best Estimate reaction rates for each sensor.
2 - The Measurement to Calculation Ratio (M/C) and the Measurement to Best Estimate Ratio (MIBE) for each sensor.
3 - The Calculated and Best Estimate values of neutron flux (E > 1.0 MeV) and Iron atom displacement rate with associated uncertainties.
4 - The Best Estimate to Calculation Ratio (BE/C) for both neutron flux (E > 1.0 MeV) and Iron atom displacement rate.
The M/C and M/BE ratios for the individual sensors establish a comparison between measurement and calculation before and after the least squares evaluation. The reduction in these reaction rate ratios for the best estimate case is an indication of the improvement in the neutron spectrum and corresponding reduction in uncertainty brought about by the application of the least squares procedure. The comparisons of calculated and best estimate values of neutron flux (E > 1.0 MeV) and Iron atom displacement rate with associated uncertainties also provided an indication of the improved results obtained with the least squares procedure.
Appendix E

E-34 Capsule IDF Azimuthal LocationO.0&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycle I Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.97E-1 9  2.24E-19   1.92E-1 9  0.88   1.03 Fe-54(n,p)Mn-54                        1.37E-1 7  1.68E-17   1.41 E-17  0.82  0.97 Ni-58(n,p)Co-58                       1.98E-1 7   2.41 E-17 2.03E-1 7   0.82  0.98 U-238(n,f)Cs-1 37 Cd                  8.61 E-17   9.52E-17  8.33E-1 7   0.90   1.03 Np-237(n,f)Cs-137 Cd                   1.88E-15   1.68E-1 5  1.72E-15   1.12   1.09 Co-59(n,g)Co-60                       4.22E-1 4   6.93E-1 4 4.27E-14    0.61  0.99 Co-59(n,g)CO-60      Cd               1.94E-14    2.59E-1 4  1.94E-14   0.75   1.00 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     3.37E+08        14    3.03E+08      6   0.90 dpa/s                                 1.33E-12        14     1.26E-12     9   0.95 Capsule IDE Azimuthal Location 13.5&deg; Ex-Vessel Axial Location Core Midplane Irradiation PeriodCycle I Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                       2.28E-1 9   2.97E-19  2.23E-1 9   0.77  1.02 Fe-54(n,p)Mn-54                       1.65E-17    2.36E-1 7 1.71 E-17   0.70  0.96 Ni-58(n,p)Co-58                       2.41 E-17   3.39E-1 7 2.47E-1 7   0.71  0.98 U-238(n ,f)Cs-137   Cd                1.08E-1 6   1.37E-16  1.02E-16    0.79  1.06 Np-237(n,f)Cs-137 Cd                  2.12E-15    2.43E-1 5 2.02E-1 5   0.87  1.05 Co-59(n,g)Co-60                       4.98E-1 4   9.30E-1 4 5.1OE-14    0.54  0.98 Co-59(n,g)CO-60     Cd                2.96E-1 4   3.95E-14  2.93E-1 4   0.75  1.01 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     4.89E+08        14    3.74E+08      6   0.76 dpa/s                                 1.93E-1 2       14    1.57E-12     10   0.81 Appendix E

E-35 Capsule IDD Azimuthal Location33.8' Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycle I Measured Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                       3.11E-19   3.91 E-1 9 3.10E-19    0.80   1.00 Fe-54(n,p)Mn-54                       2.57 E-17  3.30E-1 7  2.59E-1 7   0.78  0.99 Ni-58(n,p)Co-58                       3.72E-1 7 4.81 E-17   3.77E-1 7   0.77  0.99 U-238(n,f)Cs-137 Cd                    1.67E-16  2.03E-16   1.61 E-16   0.82   1.04 Np-237(n,f)Cs-137 Cd                  3.06E-15   3.78E-1 5  3.07E-1 5   0.81   1.00 Co-59(n,g)Co-60                       8.58E-14   1.35E-13   8.69E-14    0.64  0.99 Co-59(n,g)CO-60      Cd               4.56E-14   5.78E-14   4.54E-14    0.79   1.00 Calculated   % Una. Best Est.  % Unc. BEJC Flux(E > 1.0 MeV)                     7.44E+08       14     5.96E+08      6   0.80 dpa/s                                  3.OOE-1 2      14     2.46E-12      9   0.82 Capsule IDB Azimuthal Location45.00 Ex-Vessel Axial Location Core Midplane Irradiation PeriodCycle I Measured  Calculated  Best Est. WC    MBE Cu-63(n,a)Co-60                       3.73E-1 9  4.26E-1 9  3.68E-1 9   0.88   1.01 Fe-54(n,p)Mn-54                       2.93E-17   3.63E-17   3.11 E-1 7  0.81  0.94 Ni-58(n,p)Co-58                       4.72E-1 7  5.30E-1 7  4.67E-1 7   0.89  1.01 U-238(n,f)Cs-137 Cd                   2.32E-16   2.26E-16   2.03E-1 6   1.03   1.14 Np-237(n,f)Cs-137 Cd                  3.73E-15   4.11E-15   3.76E-1 5   0.91  0.99 Co-59(n,g)Co-60                        6.60E-14   1.32E-13   6.81 E-14   0.50  0.97 Co-59(n,g)CO-60      Cd               4.06E-14   5.02E-14   4.OOE-1 4   0.81  1.02 Calculated   % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     8.34E+08      14      7.60E+08      6   0.91 dpals                                  3.15E-12      14      2.88E-12      9   0.91 Appendix E

E-36 Capsule IDA Azimuthal LocationO.0&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycle 2 Measured    Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.88E-1 9    1.98E-19     1.86E-19    0.95   1.01 Fe-54(n,p)Mn-54                        1.33E-17     1.46E-17     1.35E-17    0.91
* 0.99 Ni-58(n,p)Co-58 U-238(n,f)Cs-1 37    Cd                7.87E-1 7    8.20E-17     7.62E-17    0.96   1.03 Np-237(n,f)Cs-137    Cd Co-59(n,g)Co-60                        4.24E-14     5.81 E-14    4.26E-14    0.73   1.00 Co-59(n,g)CO-60      Cd                1.72E-14     2.17E-14     1.73E-14    0.79   0.99 Calculated     % Unc. Best Est.  % Unc. BE/C Fldx(E > 1.0 MeV)                      2.89E+08         14      2.68E+08       8    0.93 dpa/s                                  1.12E-12         14       1.04E-12      11   0.93 Capsule IDB Azimuthal Location 10.9&deg; Ex-Vessel Axial Location Core Midplane Irradiation PeriodCycle 2 Measured    Calculated   Best Est. M/C    M/BE Cu-63(n,a)Co-60                       2.OOE-19     2.36E-19     1.99E-19    0.85   1.01 Fe-54(n,p)Mn-54                       1.47E-17     1.82E-17     1.51E-17    0.81   0.97 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                   9.41 E-17    1.04E-16    8.84E-17     0.90   1.06 Np-237(n,f)Cs-137 Cd Co-59(n,g)Co-60                        4.94E-14     7.28E-14    4.98E-1 4    0.68   0.99 Co-59(n,g)CO-60      Cd                2.36E-1 4    3.05E-14    2.36E-1 4    0.77   1.00 Calculated     % Unc. Best Est.   % Une. BE/C Flux(E > 1.0 MeV)                      3.68E+08         14      3.17E+08       8    0.86 dpa/s                                  1.46E-12         14      1.28E-12      12    0.88 Appendix E

E-37 Capsule IDC Azimuthal Location35. 1&deg; Ex-Vessel Axial Location Core Midplane Irradiation PeriodCycle 2 Measured Calculated    Best Est. M/C   M/BE Cu-63(n,a)Co-60                        3.11E-19   3.54E-1 9  3.08E-1 9   0.88   1.01 Fe-54(n,p)Mn-54                       2.45E-1 7 2.95E-17    2.53E-1 7   0.83  0.97 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                    1.71 E-16  1.80E-1 6   1.59E-16   0.95   1.08 Np-237(n,f)Cs-137 Cd                   3.03E-1 5  3.31 E-1 5 3.02E-1 5   0.92   1.00 Co-59(n,g)Co-60                        8.55E-14   1.16E-13   8.62E-14    0.74  0.99 Co-59(n,g)CO-60      Cd                4.29E-1 4  4.96E-14   4.28E-14    0.86   1.00 Calculated   % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     6.57E+08        14     5.88E+08      7   0.90 dpa/s                                  2.62E-1 2       14    2.39E-12     10   0.91 Capsule IDE Azimuthal Location42.0 0 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycle 2 Measured Calculated    Best Est. M/C   MIBE Cu-63(n,a)Co-60                        3.21 E-19  3.68E-19   3.14E-19    0.87  1.02 Fe-54(n,p)Mn-54                        2.44E-17   3.11E-17   2.56E-17    0.78  0.95 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                    1.77E-16   1.93E-16   1.62E-16    0.92  1.09 Np-237(n,f)Cs-137 Cd                   2.95E-15   3.56E-1 5  2.99E-15    0.83  0.99 Co-59(n,g)Co-60                        7.65E-1 4  1.1 6E-13  7.71 E-1 4  0.66  0.99 Co-59(n,g)CO-60      Cd                3.51 E-14  4.66E-1 4  3.52E-1 4   0.75  1.00 Calculated    %Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     7.13E+08        14     5.99E+08      7   0.84 dpals                                  2.76E-112      14     2.37E- 12     9   0.86 Appendix E

E-38 Capsule IDA Azimuthal Location O.00 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 3-4 Measured    Calculated    Best Est. M/C   MIBE Cu-63(n,a)Co-60                        1.55E-1 9    1.72E-1 9   1.55E-1 9    0.90   1.00 Fe-54(n,p)Mn-54                        1.12E-17     1.25E-17    1.13E-17     0.90   0.99 Ni-58(n,p)Co-58                        1.61 E-17    1.79E-17    1.61E-17     0.90   1.00 U-238(n,f)Cs-137    Cd                 6.46E-17     6.98E-17    6.34E-17     0.93   1.02 Np-237(n,f)Cs-137 Cd Co-59(n,g)Co-60                        3.58E-14     5.05E-14    3.62E-14     0.71   0.99 Co-59(n,g)CO-60     Cd                 1.70E-14     1.88E-14    1.69E-14     0.90   1.01 Calculated I% Unc.        Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.45E+08          14      2.24E+08       7    0.91 dpa/s                                  9.60E-1 3        14      8.80E-1 3     11    0.92 Capsule IDB Azimuthal Location 10.90 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 3-4 Measured    Calculated   Best Est. M/C    M/BE Cu-63(n,a)Co-60                       1.82E-19     2.14E-19    1.81 E-19    0.85   1.01 Fe-54(n,p)Mn-54                       1.34E-17     1.63E-17    1.37E-17     0.82   0.98 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                   8.26E-17     9.24E-17    8.07E-17     0.89   1.02 Np-237(n,f)Cs-137 Cd                  1.61 E-15    1.62E-15    1.54E-15     0.99   1.05 Co-59(n,g)Co-60                       4.45E-14     6.43E-14    4.49E-14     0.69   0.99 Co-59(n,g)CO-60     Cd                2.16E-14     2.69E-1 4   2.16E-14     0.80   1.00 Calculated     % Unc. Best Est.   % Unc. BE/C Flux(E > 1.0 MeV)                     3.27E+08         i4      2.92E+08       7    0.89 dpa/s                                 1.30E-12         14      1.1 9E-12     10    0.92 Appendix E

E-39 Capsule IDC Azimuthal Location35.1&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 3-4 Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                         2.94E-1 9  3.34E-1 9 2.89E-1 9  0.88   1.02 Fe-54(n,p)Mn-54                        2.23E-1 7  2.75E-17  2.31 E-17  0.81   0.97 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                    1.52E-16   1.66E-16   1.43E-16  0.92   1.06 Np-237(n,f)Cs-137 Cd Co-59(n,g)Co-60                         7.50E-14   1.06E-13  7.56E-14   0.71   0.99 Co-59(n,g)CO-60      Cd                 3.68E-14   4.50E-14  3.68E-14   0.82   1.00 Calculated   % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                     6.06E+08        14    5.24E+08     8    0.86 dpals                                   2.40E-12       14    2.13E-12    12    0.88 Capsule IDE Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 3-4 Measured   Calculated Best Est. MIC   M/BE Cu-63(n,a)Co-60                         2.78E-1 9  3.50E-1 9 2.78E-19   0.79   1.00 Fe-54(n,p)Mn-54                         2.29E-17   2.92E-1 7 2.34E-17   0.78  0.98 Ni-58(n,p)Co-58                         3.46E-1 7  4.25E-1 7 3.46E-1 7  0.81   1.00 U-238(n,f)Cs-1 37    Cd                 1.60E-1 6  1.80E-16  1.50E-16   0.89   1.07 Np-237(n,f)Cs-137 Cd Co-59(n,g)Co-60                         6.52E-14   1.05E-13  6.60E-14   0.62  0.99 Co-59(n,g)CO-60      Cd                 3.28E-14   4.23E-14  3.27E-14   0.78   1.00 Calculated    % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                      6.60E+08        14    5.58E+08     7   0.84 dpals                                   2.54E-1 2      14    2.19E-12    11   0.86 Appendix E

E-40 Capsule IDG Azimuthal LocationO.0&deg; Ex-Vessel Axial Location Core Midplane Irradiation PeriodCycles 5-6 Measured:   Calculated   Best Est. M/C    MIBE Cu-63(n,a)Co-60                         1.58E-19    1.67E-19     1.56E-1 9    0.95    1.01 Fe-54(n,p)Mn-54                        1.1OE-17    1.22E-17     1.14E-17     0.90    0.96 Ni-58(n,p)Co-58                        1.63E-17    1.73E-17     1.64E-1 7    0.94    0.99 U-238(n,f)Cs-137 Cd                   7.41E-17     6.76E-17    6.62E-1 7     1.10    1.12 Np-237(n,f)Cs-137 Cd                    1.24E-15    1.17E-15     1.21 E-15    1.06    1.02 Co-59(n,g)Co-60                        3.43E-14     4.71 E-14   3.46E-14      0.73    0.99 Co-59(n,g)CO-60      Cd                 1.48E-1 4   1.76E-1 4    1.48E-14     0.84    1.00 Calculated     % Unc. Best Est.   % Unc. BE/C Flux(E > 1.0 MeV)                      2.37E+08        14       2.37E+08        6     1.00 dpa/s                                  9.19E-13        14       9.28E-1 3       9     1.01 Capsule IDH Azimuthal Location 10.90 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 5-6 Measured Calculated      Best Est. M/C    M/BE Cu-63(n,a)Co-60                        1.80E-1 9 2.05E-1 9     1.78E-19      0.88    1.01 Fe-54(n,p)Mn-54                       1.28E-17     1.56E-17     1.32E-17     0.82   0.97 Ni-58(n,p)Co-58                       1.89E-1 7 2.23E-17        1.90E-17     0.85   0.99 U-238(n,f)Cs-137 Cd                   8.20E-1 7 8.79E-1 7      7.61 E-17     0.93   1.08 Np-237(n,f)Cs-1 37 Cd Co-59(n,g)Co-60                       4.06E-14     5.87E-14    4.1 OE-14     0.69   0.99 Co-59(n,g)CO-60     Cd                2.05E-14     2.47E-14    2.05E-14      0.83   1.00 Calculated     % Unc. Best Est.    % Unc. BE/C Flux(E > 1.0 MeV)                     3.11 E+08        14      2.72E+08        7    0.87 dpa/s                                 1.22E-12         14      1.09E-12       11    0.89 Appendix E

E-41 Capsule IDI Azimuthal Location35.1&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 5-6 Measured Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        2.39E-1 9 2.66E-1 9 2.35E-19     0.90   1.02 Fe-54(n,p)Mn-54                        1.79E-17   2.17E-17   1.87E-1 7  0.82  0.96 Ni-58(n,p)Co-58                        2.78E-1 7 3.14E-17   2.76E-1 7   0.89   1.01 U-238(n,f)Cs-137 Cd                    1.21 E-16  1.30E-1 6  1.15E-16   0.93   1.05 Np-237(n,f)Cs-137 Cd                   2.21 E-15  2.38E-15  2.19E-15    0.93   1.01 Co-59(n,g)Co-60                        6.45E-14   8.43E-14  6.49E-1 4   0.77  0.99 Co-59(n,g)CO-60     Cd                 3.12E-14   3.58E-14  3.12E-14    0.87   1.00 Calculated   % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     4.74E+08        14    4.23E+08      6   0.89 dpa/s                                  1.89E-12       14     1.73E-12     9   0.92 Capsule IDK Azimuthal Location42.0 0 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 5-6 Measured Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                        2.23E-1 9 2.67E-1 9  2.19E-19    0.84   1.02 Fe-54(n,p)Mn-54                        1.65E-17   2.21 E-17  1.75E-17   0.75  0.94 Ni-58(n,p)Co-58                        2.63E-17   3.22E-17  2.60E-17    0.82  1.01 U-238(n,f)Cs-137 Cd                    1.22E-16   1.36E-16   1.1OE-16   0.90  1.11 Np-237(n,f)Cs-137 Cd                   1.92E-15   2.48E-1 5  1.99E-15   0.77  0.96 Co-59(n,g)Co-60                        5.44E-1 4 8.23E-14   5.49E-1 4   0.66  0.99 Co-59(n,g)CO-60     Cd                 2.64E-14   3.29E-14  2.63E-14    0.80  1.00 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     4.98E+08        14    4.05E+08      6   0.81 dpa/s                                  1.93E-12       14     1.60E-12     9   0.83 Appendix E

E-42 Capsule IDM Azimuthal LocationO.0&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 7-10 Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.46E-19   1.56E-1 9  1.44E-19   0.94   1.01 Fe-54(n,p)Mn-54                        1.03E-17   1.1 3E-17  1.04E-17   0.91   0.99 Ni-58(n,p)Co-58                        1.43E-17   1.62E-17   1.48E-17   0.88   0.97 U-238(n,f)Cs-1 37 Cd                   6.29E-17   6.32E-1 7 5.98E-17    1.00   1.05 Np-237(n,f)Cs-137 Cd                   1.24E-1 5  1.10E-15   1.16E-15   1.13   1.07 Co-59(n,g)Co-60                        3.1 8E-14  4.53E-1 4 3.21 E-1 4  0.70   0.99 Co-59(n,g)CO-60      Cd                1.38E-14   1.69E-1 4  1.38E-14   0.82   1.00 Calculated   % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.22E+08        14    2.14E+08      6    0.97 dpa/s                                   8.67E-1 3      14    8.65E-1 3     9    1.00 Capsule IDN Azimuthal Location 10.90 Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 7-10 Measured Calculated   Best Est. MIC   M/BE Cu-63(n,a)Co-60                         1.70E-19   1.96E-1 9 1.67E-1 9   0.87   1.02 Fe-54(n,p)Mn-54                         1.22E-17   1.49E-17  1.26E-17    0.82  0.97 Ni-58(n,p)Co-58                         1.79E-17   2.13E-17  1.82E-17    0.84  0.98 U-238(n,f)Cs-1 37    Cd                 7.87E-1 7  8.41 E-17 7.50E-17    0.94   1.05 Np-237(n,f)Cs-137    Cd                 1.64E-1 5  1.47E-15  1.52E-15    1.12   1.08 Co-59(n,g)Co-60                         3.89E-1 4  5.69E-1 4 3.93E-14    0.68  0.99 Co-59(n,g)CO-60      Cd                 1.96E-1 4  2.39E-1 4 1.96E-14    0.82   1.00 Calculated    % Unc. Best Est.  % Unc. BEIC Flux(E  > 1.0 MeV)                     2.98E+08        14    2.73E+08      6   0.92 dpa/s                                   1.17E-12       14    1.14E-12      9   0.97 Appendix E

E43 Capsule IDO Azimuthal Location35.1&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 7-10 Measured Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                        2.25E-1 9 2.54E-19   2.22E-1 9   0.89   1.01 Fe-54(n,p)Mn-54                        1.74E-1 7 2.07E-17    1.79E-1 7  0.84  0.97 Ni-58(n,p)Co-58                        2.59E-1 7 3.OOE-17   2.63E-17    0.86  0.98 U-238(n,f)Cs-137 Cd                    1.18E-16  1.24E-16    1.13E-16   0.95   1.04 Np-237(n,f)Cs-137 Cd                   2.53E-15  2.27E-1 5  2.35E-1 5   1.11   1.08 Co-59(n,g)Co-60                        6.OOE-1 4 8.11E-14   6.04E-1 4   0.74  0.99 Co-59(n,g)CO-60     Cd                 2.85E-1 4 3.45E-14   2.85E-1 4   0.83   1.00 Calculated  % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                      4.52E+08      14     4.22E+08      6   0.93 dpa/s                                  1.80E-1 2     14      1.76E-12     9   0.98 Capsule IDQ Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Midplane Irradiation PeriodCycles 7-10 Measured Calculated   Best Est. MIC   M/BE Cu-63(n,a)Co-60                        2.07E-1 9 2.52E-1 9  2.05 E-1 9  0.82  1.01 Fe-54(n,p)Mn-54                        1.65E-17  2.08E-17    1.71 E-17  0.79  0.96 Ni-58(n,p)Co-58                        2.53E-17  3.03E-1 7  2.54E-17    0.83  1.00 U-238(n,f)Cs-137 Cd                    1.18E-16  1.28E-1 6   1.11E-16   0.92  1.06 Np-237(n,f)Cs-137 Cd                   2.42E-1 5 2.34 E-1 5 2.29E-15    1.03  1.06 Co-59(n,g)Co-60                        5.14E-14  7.87E-14   5.19E-14    0.65  0.99 Co-59(n,g)CO-60     Cd                 2.40E-1 4 3.15E-14   2.40E-1 4   0.76  1.00 Calculated  % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     4.68E+08       14     4.19E+08      6   0.89 dpa/s                                  1.82E-12      14     1.70E-12      9   0.93 Appendix E

E-44 The results of the dosimetry evaluations performed for the Diablo Canyon Unit I Ex-Vessel capsules withdrawn to date from locations opposite the top and bottom of the active are provided following. The data tabulations for each capsule evaluation include the following information:
I - The Measured, Calculated, and Best Estimate reaction rates for each sensor.
2- The Measurement to Calculation Ratio (M/C) and the Measurement to Best Estimate Ratio (M/BE) for each sensor.
3 - The Calculated and Best Estimate values of neutron flux (E > 1.0 MeV) and Iron atom displacement rate with associated uncertainties.
4 - The Best Estimate to Calculation Ratio (BE/C) for both neutron flux (E > 1.0 MeV) and Iron atom displacement rate.
The M/C and M/BE ratios for the individual sensors establish a comparison between measurement and calculation before and after the least squares evaluation. The reduction in these reaction rate ratios for the best estimate case is an indication of the improvement in the neutron spectrum and corresponding reduction in uncertainty brought about by the application of the least squares procedure. The comparisons of calculated and best estimate values of neutron flux (E > 1.0 MeV) and Iron atom displacement rate with associated uncertainties also provided an indication of the improved results obtained with the least squares procedure.
Appendix E

E-45 Capsule IDC Azimuthal Location45.0&deg; Ex-Vessel Axial Location Core Top Irradiation PeriodCycle I Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.04E-19   1.1 9E-19  1.07E-19   0.87   0.97 Fe-54(n,p)Mn-54                       9.41 E-1 8  1.03E-17   1.01 E-17  0.91   0.93 Ni-58(n,p)Co-58                        1.67E-17   1.50E-17   1.57E-1 7  1.11   1.06 U-238(n,f)Cs-137    Cd                 8.49E-17   6.47E-17  6.99E-1 7   1.31   1.21 Np-237(n,f)Cs-1 37 Cd                  1.10E-15   1.21 E-15  1.21 E-15  0.91  0.91 Co-59(n,g)Co-60                       3.68E-14    4.09E-1 4 3.70E-14    0.90  0.99 Co-59(n,g)CO-60     Cd                 1.77E-14   1.56E-14   1.76E-14   1.13   1.01 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.40E+08        14    2.64E+08      6    1.10 dpals                                 9.36E-1 3       14    9.92E-13      9    1.06 Capsule IDA Azimuthal Location45.0&deg; Ex-Vessel Axial LocationCore Bottom Irradiation PeriodCycle 1 Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                       1.38E-19    1.29E-19   1.41 E-19  1.07  0.98 Fe-54(n,p)Mn-54                       1.31 E-17   1.11E-17  1.28E-17    1.18  1.02 Ni-58(n,p)Co-58 U-238(n,f)Cs-137    Cd                8.02E-17    7.04E-1 7 8.13E-17    1.14  0.99 Np-237(n,f)Cs-137 Cd                  1.53E-15    1.32E-15  1.52E-15    1.16  1.01 Co-59(n,g)Co-60                       4.31 E-1 4  4.41 E-14 4.35E-14    0.98  0.99 Co-59(n,g)CO-60     Cd                2.27E-1 4   1.69E-14  2.24E-1 4   1.34  1.01 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.62E+08        14    3.03E+08      7   1.16 dpa/s                                  1.02E-12        14    1.16E-12      9   1.13 Appendix E

E-46 Capsule IDD Azimuthal Location42.0&deg; Ex-Vessel Axial Location Core Top Irradiation PeriodCycle 2 Measured   Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.13E-19   1.35E-1 9  1.11E-19   0.84   1.02 Fe-54(n,p)Mn-54                        8.36E-1 8  1.15E-17   9.14E-18   0.73  0.91 Ni-58(n,p)Co-58 U-238(n,f)Cs-1 37   Cd                 7.64 E-17  7.13E-17   6.14E-17   1.07   1.24 Np-237(n,f)Cs-137 Cd                   1.12E-15   1.32E-15   1.16E-15   0.85  0.97 Co-59(n,g)Co-60                        3.58E-1 4  4.17E-14   3.60E-1 4  0.86  0.99 Co-59(n,g)CO-60      Cd                1.79E-1 4  1.70E-14   1.78E-14   1.05  1.01 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.63E+08        14    2.31 E+08     7   0.88 dpa/s                                  1.02E-12       14     9.37E-1 3   10   0.92 Capsule IDF Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Bottom Irradiation PeriodCycle 2 Measured Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                        1.39E-1 9  1.36E-19  1.39E-19    1.02  1.00 Fe-54(n,p)Mn-54                        1.1 8E-17  1.16E-17  1.19E-17    1.02  0.99 Ni-58(n,p)Co-58 U-238(n,f)Cs-137    Cd                7.67E-1 7   7.28E-1 7 7.50E-1 7   1.05  1.02 Np-237(n,f)Cs-137   Cd Co-59(n,g)Co-60                       4.14E-14    4.28E-14  4.16E-14    0.97  1.00 Co-59(n,g)CO-60     Cd                2.OOE-14    1.75E-14   1.99E-14   1.14  1.01 Calculated    % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     2.69E+08       14     2.78E+08      8   1.03 dpa/s                                 1.05E-1 2      14     1.09E-12     11   1.03 Appendix E

E-47 Capsule IDD Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Top Irradiation PeriodCycles 3-4 Measured Calculated   Best Est. M/C   M/BE Cu-63(n,a)Co-60                       9.72E-20   1.17E-19   9.62E-20   0.83   1.01 Fe-54(n,p)Mn-54                       7.58E-1 8 9.79E-18    8.07E-1 8  0.77  0.94 Ni-58(n,p)Co-58 U-238(n,f)Cs-137 Cd                   6.1OE-17   6.05E-1 7  5.43E-17   1.01  1.12 Np-237(n,f)Cs-137 Cd                  1.20E-1 5  1.12E-15    1.15E-15  1.07  1.04 Co-59(n,g)Co-60                       3.22E-14   3.59E-14   3.23E-1 4  0.90  1.00 Co-59(n,g)CO-60     Cd                1.56E-14   1.46E-1 4   1.55E-14  1.07  1.01 Calculated   % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                     2.23E+08       14     2.07E+08     7   0.93 dpa/s                                 8.69E-1 3      14     8.62E-1 3   10   0.99 Capsule IDF Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Bottom Irradiation PeriodCycles 3-4 Measured  Calculated  Best Est. M/C   M/BE Cu-63(n,a)Co-60                       9.98E-20   1.15E-19   1.01 E-19  0.87  0.99 Fe-54(n,p)Mn-54                       8.74E-1 8  9.71 E-1 8 8.72E-1 8  0.90  1.00 Ni-58(n,p)Co-58 U-238(n,f)Cs-137    Cd                5.65E-1 7  6.05 E-1 7 5.51 E-17  0.93  1.03 Np-237(n,f)Cs-137 Cd                  9.83E-16   1.13E-15   1.01 E-15  0.87  0.97 Co-59(n,g)Co-60                       3.65E-14   3.63E-1 4  3.66E-14   1.01  1.00 Co-59(n,g)CO-60     Cd                1.74E-14   1.48E-14   1.72E-1 4  1.18  1.01 Calculated   % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                     2.23E+08       14     2.04E+08     7   0.91 dpa/s                                 8.77E-13       14     8.11 E-13    9   0.92 Appendix E

E-48 Capsule IDJ Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Top Irradiation PeriodCycles 5-6 Measured Calculated  Best Est. MIC   M/BE Cu-63(n,a)Co-60                        7.70E-20  9.04E-20  7.77E-20    0.85  0.99 Fe-54(n,p)Mn-54                        6.26E-18  7.54E-1 8 6.80E-1 8   0.83  0.92 Ni-58(n,p)Co-58                        1.10E-17  1.10E-17  1.05E-17    1.00   1.05 U-238(n,f)Cs-137    Cd                 5.40E-17  4.65E-1 7 4.70E-17    1.16  1.15 Np-237(n,f)Cs-137 Cd                   9.87E-16  8.60E-1 6 9.63E-1 6   1.15   1.02 Co-59(n,g)Co-60                        2.60E-14  2.83E-1 4 2.61 E-1 4  0.92  1.00 Co-59(n,g)CO-60     Cd                 1.27E-14  1.15E-14  1.26E-14    1.10   1.01 Calculated  % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                      1.71 E+08     14    1.80E+08      6   1.06 dpals                                  6.71 E-13     14    7.30E-1 3     9   1.09 Capsule IDL Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Bottom Irradiation PeriodCycles 5-6 Measured Calculated Best Est. M/C   M/BE Cu-63(n,a)Co-60                        6.77E-20  8.66E-20  6.91 E-20   0.78  0.98 Fe-54(n,p)Mn-54                        5.68E-18  7.28E-18  5.95E-1 8   0.78  0.95 Ni-58(n,p)Co-58                        9.62E-18  1.06E-17  9.09E-1 8   0.91  1.06 U-238(n,f)Cs-137 Cd                    3.91 E-17 4.53E-17  3.88E-17    0.86  1.01 Np-237(n,f)Cs-137 Cd                   6.99E-16  8.49E-16  7.27E-1 6   0.82  0.96 Co-59(n,g)Co-60                        2.72E-14  2.84E-14  2.72E-14    0.96  1.00 Co-59(n,g)CO-60     Cd                 1.23E-1 4 1.15E-14  1.22E-14    1.07  1.01 Calculated   % Unc. Best Est.  % Unc. BE/C Flux(E > 1.0 MeV)                     1.67E+08      14     1.45E+08      6   0.87 dpals                                  6.64E-1 3     14    5.89E-1 3     9   0.89 Appendix E

E-49 Capsule IDP Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Top Irradiation PeriodCycles 7-10 Measured Calculated  Best Est. M/C   M/BE Cu-63(n,a)Co-60                       7.25E-20   9.84E-20  7.53E-20   0.74  0.96 Fe-54(n,p)Mn-54                       6.37E-18   8.14E-18  6.81 E-18  0.78  0.94 Ni-58(n,p)Co-58                       1.17E-17   1.18E-17  1.07E-17   0.99  1.09 U-238(n,f)Cs-1 37 Cd                  4.57E-17   4.98E-17  4.69E-1 7  0.92  0.97 Np-237(n,f)Cs-137 Cd                  1.05E-1 5 9.12E-16   9.93E-16   1.15  1.06 Co-59(n,g)Co-60                       2.27E-14   2.92E-1 4 2.29E-1 4  0.78  0.99 Co-59(n,g)CO-60      Cd               1.15E-14   1.19E-14  1.14E-14   0.97  1.01 Calculated   % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                     1.83E+08       14    1.81 E+08    6   0.99 dpals                                 7.08E-13       14    7.28E-13     9   1.03 Capsule IDR Azimuthal Location42.0&deg; Ex-Vessel Axial LocationCore Bottom Irradiation PeriodCycles 7-10 Measured Calculated  Best Est. M/C   M/BE Cu-63(n,a)Co-60                       7.59E-20   9.48E-20  7.99E-20   0.80  0.95 Fe-54(n,p)Mn-54                       7.39E-18   7.90E-18  7.30E-1 8  0.94  1.01 Ni-58(n,p)Co-58                       1.1 6E-17  1.15E-17  1.1OE-17   1.01  1.05 U-238(n,f)Cs-137 Cd                   4.05E-17   4.88E-17  4.69E-17   0.83  0.86 Np-237(n,f)Cs-1 37 Cd                 9.42E-1 6  9.04E-1 6 9.20E-1 6  1.04  1.02 Co-59(n,g)Co-60                       2.68E-14   2.92E-1 4 2.69E-1 4  0.92  1.00 Co-59(n,g)CO-60     Cd                1.30E-14   1.19E-14  1.29E-14   1.09  1.01 Calculated   % Unc. Best Est. % Unc. BE/C Flux(E > 1.0 MeV)                     1.80E+08       14    1.76E+08     6   0.98 dpals                                 7.04E-1 3      14    6.95E-13     9   0.99 Appendix E

E-50 Appendix E References E-l. 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.
E-2. RSAC-PGE-807, "Analysis of Neutron Dosimetry form Diablo Canyon Unit I Surveillance Capsule Y," Anderson, S. L. July 26, 1993.
E-3. E. B. Norris, "Reactor Vessel Material Surveillance Program, Capsule S - Turkey Point Unit No. 3, Capsule S - Turkey Point Unit No. 4," Final Report SwRI Project No. 02-5131 and SwRI Project No. 02-5380, Southwest Research Institute, May 1979.
E-4. P. K. Nair and E. B. Norris, "Reactor Vessel Material Surveillance Program for Turkey Point Unit No. 3: Analysis of Capsule V," Final Report SwRI Project No. 06-8575, Southwest Research Institute, August 1986.
E-5. WCAP-14044, Revision 0, "Westinghouse Surveillance Capsule Neutron Fluence Reevaluation,"
April 1994.
E-6. A. Schmittroth, FERRETDataAnalysis Core, HEDL-TME 7940, Hanford Engineering Development Laboratory, Richland, WA, September 1979.
E-7. RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.
E-8. WCAP-15780. "Fast Neutron Fluence and Neutron Dosimetry Evaluations for the Diablo Canyon Unit I Reactor Pressure Vessel." December 2001.
Appendix E}}