ML20063N725
| ML20063N725 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 05/28/1982 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Lowenberg H NRC |
| Shared Package | |
| ML20062N348 | List: |
| References | |
| FOIA-82-344 NUDOCS 8210060458 | |
| Download: ML20063N725 (14) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
R- 0 May 28, 1982 NOTE T0:
Hoiaer Lowenberg FROM:
Paul S. Check
SUBJECT:
CRBR FUEL CYCLE - REVIEW 0F DRAFT MATERIAL FOR FES UPDATE We have reviewed the material you provided with a memorandum dated May 21, 1982, and herewith return it with our suggestions indicated on individual pages.
Most of our notations are editorial.
There are two items we wish to call to your attention.
In Section 7.2, we suggest the addition of a brief discussion on uranium hexafluoride.
On page D.14, the efficiency of HEPA filters needs further attention (see attached Proceedings of Fourteenth ERDA Air Cleaning Conference.)
In general, the draft material is prepared well and it appears appropriate for our purpose.
We appreciate the good efforts that have gone into it and look forward to receiving the final version.
Pau S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation cc:
H. Denton C. Thomas P. Leech B. Morris JJ. Swift go 58 820824 WEISSB2-344 PDR j
l
=
(\\ - 20 s
.c TABLE 12.1-32 ISOTOPIC CURIE CONTENT - EQUILlBRIUM CORE-EOC CO2 72 N12 72 CU2 72 ZN2 72 GA2 72 CO2 73 2.984E+0 4.894E+02 2.607 E+03 4.207 E+03 4.245E+03 7.212E-02 N12 73 CU2 73 ZN2 73 GA2 73 GE1 73 CO2 74 2.783 E+01 9.889+02 4.940E+03 5.645E+03 5.669E+03 1.339E-1 N12 74 CU2 74 ZN2 74 GA2 74 CO2 75 N12 75 5.263E+01 1.224+03 9.817E+03 1.141 E+04 3.389E-02 1.544+01 CU2 75 ZN2 75 GA2 75 N12 76 CU2 76 ZN2 76 7.692E+02 1.212E+04 1.813E+04 4.798E+00 3.184+02 1.481 +04 GA2 76 AS2 76 N12 77 CU2 77 ZN2 77 GA2 77 3.394E+04 8.747E+02 1.529E+00 1.879E+02 1.192E+04 5.780 E+04 GE1 77 GE2 77 AS2 77 SE1 77 N12 78 CU2 78 6.581 E+04 3.483E+04 8.750+04 2.651 E+02 2.607E-01 7.504E+01 ZN2 78 GA2 78 GE2 78 AS2 78 CU2 79 ZN2 79 8.095 E+03 6.008E+04 1.467E+05 1.524E+05 1.694E+01 2.538E+03 i
\\
GA2 79 GE2 79 AS2 79 SE1 79 SE2 79 BR1 79 4.868E+04 2.489E+05 2.875E+05 2.899E+05 4.678E+00 3.245 E-01 CU2 80 ZN2 80 GA2 80 GE2 80 AS2 80 BR1 80 4.742E+00 1.962+03 3.772E+04 3.208E+05 4.433+05 1.121 E+01 12.1-63 Amend. 65 c9e_ wriq.
TABLE 12.1-32 (Continued) l h
BR2 80 CU2 81 ZN2 81 GA2 81 GE2 81 AS2 81 2.272E+01 5.134E-01 5.110E+02 2.289E+04 3.513 E+05 6.476E+05 SE1 81 SE2 81 KR1 81 KR2 81 ZN2 82 GA2 82 3.133E+04 7.175E+05 2.961E-01 2.273E-06 9.049+01 8.798E+03 GE2 82 ASI 82 AS2 82 BR1 82 BR2 82 ZN2 83 3.377 E+05 2.934E+05 6.587+05 9.033 E+03 1.781 E+04 8.255 E+00 GA2 83 GE2 83 AS2 83 SE1 83 SE2 83 BR2 83 2.565E+03 2.253E+05 1.329E+06 1.567E+06 1.175E+06 2.823 E+06 KR1 83 GA2 84 GE2 84 AS2 84 SE2 84 BR1 84 2.823 E+06 5.228E+02 1.051 E+05 1.052E+06 3.947E+06 2.532E+05 BR2 84 GA2 85 GE2 85 AS2 85 SE1 85 SE2 85 4.206E+06 1.002E-08 1.299E+04 4.030E+05 1.455+06 1.949E+06 l
BR2 85 KR1 85 KR2 85 GE2 86 AS2 86 SE2 86 4.884E+06 4.957 E+06 1.034E+05 2.875E+03 1.733E+05 3.090E+06 BR1 86 BR2 86 RB1 86 RB2 86 GE2 87 AS2 87 3.031 E+06 3.138E+06 1.700E+04 1.382 E+05 3.251E+02 4.210E+04 li SE2 87 BR2 87 KR2 87 RB2 87 SR1 87 GE2 88 1.726E+06 5.565E+06 8.056E+06 2.092E-04 8.554E+02 2.543 E+01 i
5 t
12.1 -63a Amend. 65 e
- 4 TABLE 12.1-32 (Continued)
AS2 88 SE2 88 BR2 88 KR2 88 RB2 88 AS2 89 9.865E+03 8.761 E+05 5.111+06 1.141 E+07 1.193+07 1.110E+03 SE2 89 BR2 89 KR2 89 RB2 89 Y1 89 AS2 90 2.170E+05 3.087E+06 1.244E+07 1.558E+07 3.000E+01 3.812E-08 SE2 90 BR2 90 KR2 90 21 90 22 90 SR2 90 5.248E+04 1.339E+06 1.183E+07 4.718E+06 1.308E+07 6.791 E+05 Y1 90 Y2 90 ZR1 90 SE2 91 BR2 91 KR2 91 9.232E+02 7.108+05 2.437E-01 6.532E+03 3.994E+05 8.030+06 22 91 SR2 91 Y1 91 Y2 91 SE2 92 BR2 92 l
1.799E+07 2.102E+07 1.212E+07 2.042E+07 8.293E+02 1.093E+05 KR2 92.
RB2 92 SR2 92 Y2 92 SE2 93 BR2 93 4.188E+06 1.506E+07 2.459E+07 2.492E+07 7.106E-08
- 1.%6E+04 l
KR2 93 22 93 SR2 93 Y1 93 Y2 93 ZR2 93 1.670E+06 1.152E+07 2.921 E+07 1.159E+02 3.065E+07 3.419E+01 21 93 BR2 94 KR2 94 22 94 SR2 94 Y2 94 1.856E+00 2.024E+03 3.099E+05 5.461E+06 2.864E+07 3.326E+07 21 94 22 94 BR2 95 KR2 95 RB2 95 SR2 95 7.821 E+01 8.026E-03 1.481 E+02 8.760+04 1.626E+06 2.525E+07
- SR2 89 1.60+07 12.1 -63b Amend. 65 k
l Feb. 1982
.s TABLE 12.1-32 (Continued)
Y2 95 ZR2 95 21 95 22 95 BR2 %
KR2 %
3.657 E+07 3.624E+07 4.353E+05 3.476E+07 1.018E+01 1.578E+04 RB2 %
SR2 %
Y2 %
22 %
KR2 97 RB2 97 5.848E+05 1.489E+07 3.397E+07 1.381E+05 4.564E+02 6.197E+04 SR2 97 Y2 97 ZR2 97 21 97 22 97 KR2 98 4.154E+06 2.203E+07 4.092E+07 3.542E+07 4.124E+07 1.455E+02 RB2 98 SR2 98 Y2 98 ZR2 98 21 98 E2 98 3.975E+04 2.656E+06 1.150E+07 4.145E+07 4.257 E+07 6.661E+05 RB2 99 SR2 99 Y2 99 ZR2 99 21 99 22 99 4.399E+03 3.685E+05 8.17 4E+06 3.667E+07 2.466E+06 4.327 E+07 M02 99 TC) 99 RB2 100 SR2 100 Y2 100 ZR2 100 4.664E+07 4.025E+07 5.381 E+02 2.518E+05 3.797 E+06 3.509E+07 El 100 22 100 TC2 100 RB2 101 SR2 101 Y2 101 2.368E+07 2.367 E+07 4.477 E+06 3.386E-08 2.923 E+04 1.389E+07 ZR2 101 E2 101 M02 101 TC2 101 SR2 102 Y2 102 1.988E+07 4.129E+07 5.136E+07 5.139E+07 3.200E+03 2.883E+05 g
i ZR2 102 22 102 M02 102 TC1 102 TC2 102 SR2 103 1.346E+07 3.673E+07 5.141 E+07 1.009E+05 5.151 +07 9.053 E+01
(
f l
\\
12.1-63c Amend _. 65
W
.s TABLE 12.1-32 (Continued)
Y2 103 ZR2 103 22 103 M02 103 TC2 103 RU2 103 5.192E+04 4.267EM]6 2.587E+07 5.014E+07 5.144E+07 5.260E+07 l
l RH1 103 SR2 104 Y2 104 ZR2 104 22 104 M02 104 5.260+07 3.966E+00 4.130E+03 1.115E+06 9.915E+06 4.414E+07 TC2 104 RH1 104 RH2 104 Y2 105 ZR2 105 22 105 4.892E+07 2.552E+05 3.567E+06 2.120E+02 1.030E+05 3.097E+06 M02 105 TC2 105 RU2 105 RH1 105 RH2 105 Y2 106 2.784E+07 3.712E+07 3.851 E+07 9.935E+06 3.850E+07 2.280E-08 ZR2 106 22 106 M02 106 TC2 106
~RU2 106 RH1 106 9.031 E+03 5.245E+05 1.513E+07 3.000E+07 1.957E+07 1.206E+04 RH2 106 Y2 107 ZR2 107 22 107 M02 107 TC2 107 1.958E+07 8.634E-02 2.9% E+02 5.869E+04 4.308E+06 1.572E+07 RU2 107 RH2 107 PD1 107 P02 107 ZR2 108 22 108 2.228E+07 2.238E+07 1.867E+05 3.361E+00 1.445E+02 1.576E+04 M02 108 TC2 108 RU2 108 RH1 108 RH2 108 AG2 108 9.097E+05 6.679E+06 1.489E+07 2.056E+05 1.510E+07 3.464E-01 ZR2 109 22 109 M02 109 TC2 109 RU2 109 RH1 109 1.195 E+01 3.857E+03 4.258E+05 4.718E+06 1.081 E+07 5.613E+06 12.1-63d Amend. 65 r m 9ena
TABLE 12.1-32 (Continued)
RH2 109 PD1 109 PD2 109 AG1 109 CD2 109
$2 110 1.123 E+07 5.622E+06 1.159E+07 1.159E+07 3.468E-03 1.121 E+02 M02 110 TC2 110 RU2 110 RH1 110 RH2 110 AG1 110 3.152E+04 5.001E+05 3.766E+06 3.168E+05 4.187 E+06-4.327 E+04 AG2 110 22 111 M02 111 TC2 111 RU2 111 RP2 111 6.042E+05 1.045E+01 2.782E+03 1.122E+05 1.615E+06 2.418E+06 PD1 111 PD2 111 AG1 111 AG2 111 CD1 111 22 112 6.111 E+04 2.575E+06 2.566E+06 2.609E+06 1.963E+02 9.922E-10 M02 112 TC2 112 RU2 112 RH2 112 F02 112 AG2 112 2.445 E F02 1.255E+04 3.241E+05 1.173E+06 1.360E+06 1.363E+06 M02 113 TC2 113 RU2 113 RH2 113 PD2 113 AG1 113 2.584E+01 3.356E+03 1.563E+05 5.042E+05 9.061E+05 9.309E+05 AG2 113 CD1 113 IN1 113 M02 114 TC2 114 RU2 114 8.193E+05 1.914E+03 2.350 E-04 1.543 E+00 3.877 E+02 4.533E+04 RH2 114 FD2 114 AG2 114 IN1 114 IN2 114 M02 115 2.661 E+05 6.535E+05 6.714E+05 2.007 E+01 3.226E+01 8.050E-02 TC2 115 RU2 115 RH2 115 PD2 115 AG1 115 AG2 115 6.701 E+01 8.954E+03 1.325E+05 5.015Et05 1.650E+05 3.991E+05 12.1-63e Amend. 65 pg g g
/
TABLE 12.1-32 (Continued)
CD1 115 CD2 115 IN1 115 IN2 115 TC2 116 RU2 116 3.545E+04 5.462E+05 5.461 E+05 1.107 E-09 5.069E+00 2.249E+03 RH2 116 PD2 116 AG1 116 AG2 116 INI 116 IN2 116 3.526E+04 3.315E+05 2.184E+05 2.248E+05 3.233E+04 8.907E+03 TC2 117 RU2 117 RH2 117 PD2 117 AG1 117 AG2 117 2.474E-01 2.264E+02 1.406E+04 2.239E+05 2.027 E+05 2.084E+05 CD1 117 CD2 117 IN1 117 IN2 117 SN1 117 TC2 118 6.490E+04 3.991 E+05 3.712E+05 2.674E+05 2.463E+02 1.992E-11 RU2 118 RH2 118 P02 118 AG1 118 AG2 118 CD2 118 1.708E+03 1.184E+04 1.257 E+05 1.713E+05 2.019E+05 4.458E+05 IN1 118 IN2 118 RU2 119 RH2 119 PD2 119 AG2 119 5.170E+02 4.464E+05 6.936E-07
' 6.082E+03 1.927E+05 4.020E+05 l
CD1 119 CD2 119 INI 119 IN2 119 '
SNI 119 RU2 120 2.206E+05 2.206E+05 2.207 E+05 2.317 E+0 5 9.973E+03 3.864E-01 f
RH2 120 FD2 120 AG2 120 CO2 120 IN1 120 IN2 120
['
1.472E+02 1.923E+04 1.277E+05 4.162E+05 2.193E+05 2.206E+05 i
RH2 121 PD2 121 AG2 121 CD2 121 INI 121 IN2 121 2.759E+01 4.928E+03 7.9%E+05 3.984E+05 1.055E+05 3.656E+05 12.1-63f Amend. 65
~
TABLE 12.1-32 (Continued)
SN1 1 21 SN2 121 RH2 122 PD2 122 AG2 122 CD2 122 1.941 E+01 4.747E+05 4.007 E+00 1.870E+03 2.311 E+04 3.339E+05 INI 122 IN2 122 SB1 122 SB2 122 RH2 123 PD2 123 5.355E+04 4.179E+05 4.222E+02 4.110E+04 5.249E-01 3.835E+02 AG2 123 CD2 123 IN1 123 IN2 123 SN1 123 SN2 123 1.662E+04 3.118E+05 1.959E+05 3.646E+05 2.041 E+05
'3.615E+05 l
TE1 123 TE2 123 PD2 124 AG2 124 CD2 124 IN2 124 1.695E+02 2.219E-11 1.214E+02 5.920E+03 2.604E+05 6.125E+05 SB2 124 PD2 125 AG2 125 CD2 125 IN1 125 IN2 125 2.498E+04 4.483E-08 2.903E+03 1.816E+05 3.917E+05 4.415E+05 SN1 125 SN2 125 SB2 125 TE1 125 PD2 126 AG2 126 5.836E+05 7.583E+05 3.%4E+05 7.878E+04 3.681 E+00 8.480E+02 l
CD2 126 IN2 126 SN2 126 SB2 126 AG2 127 CD2 127 1.093E+05 7.273E+05 1.947 E+00 6.887+04 8.151 E-08 4.680E+04 INI 127 lN2 127 SN1 127 SN2 127 SB2 127 TE1 127 4.104E+05 3.841 E+05 1.266E+06 2.165E+06 3.762E+06 5.399E+05 TE2 127 AG2 128 CD2 128 lN2 128 SN2 128 SB1 128 3.690E+06 1.225E+02 4.099E+04 6.840E+05 4.626E+06 5.225E+06 9
12.1-63g Amend. 65 gg m
r TABLE 12.1-32 (Continued)
SB2 128 12 128 CD2 129 IN2 129 SN1 129 SN2 129 6.054E+05 2.573E+05 9.224E+03 4.333E+05 3.347 E+06 3.352E+06 SB2 129 TE1 129 TE2 129 12 129 XE1 129 CD2 130 1.029E+07 2.651E+06 9.706E+06 6.730E-01 2.071E+03 2.092E+04 IN2 130 SN2 130 SB1 130 SB2 130 11 130 12 130 5.655 E+05 1.003E+07 1.226E+07 4.224E+06 3.288E+05 6.079E+05 CD2 131 IN2 131 SN2 131 SB2 131 T 1 131 TE2 131 3.291 E+03 2.360E+05 9.170E+06 2.447 E+07 4.454E+36 2.633E+07 12 131 XE1 131 CD2 132 IN2 132 SN2 132 SB1 132 3.004E+07 2.121 E+05.
3.220E+02 6.328E+04 4.786E+06 8.503 E+06 SB2 132 TE2 132 12 132 IN2 133 SN2 133 SB2 133 1.332E+07 3.998E+07 4.080E+07 9.661 E+03 1.435E+06 1.361 E+07 TE1 133 TE2 133 11 133 12 133 XE1 133 XE2 133 l
1.683 E+07 3.204E+07 2.349E+06 5.150E+07 1.62E+06 5.226E+07 IN2 134 SN2 134 SB1 134 SB2 134 TE2 134 11 134
/
6.657 E+02 2.828E+05 2.691 E+06 2.343E+06 4.032E+07 7.157E+06 5,
^
SN2 135 SB2 135 12 134 XE1 134 CSI 134 CS2 134 5.465E+07 2.889E+05 2.652E+05 6.603 E+05 2.819E+04 1.515E+06 12.1-63h Amend. 65 l
cym, m j
~
TABLE 12.1-32 (Continued)
TE2 135 12 135 XE1 135 XE2 135 CSI 135 CD2 135 2.459E+07 5.039E+07 1.109E+07 5.648E+07 2.758E+04 2.549E+01 BA1 135 SN2 136 SB2 136 TE2 136 11 136 12 136 2.318E+02 3.145E+03 2.441 E+05 1.073E+07 1.254E+07 2.349E+07 CS2 136 BA1 136 SB2 137 TE2 137 12 137 XE2 137 2.654E+06 4.247E+05 5.553E+04 3.948E+06 2.134E+07 4.569E+07
{
)
CS2 137 BA1 137 SB2 138 TE2 138 12 138 XE2 138 1.702E+06 1.617 E+06 7.528E+03 1.060E+06 1.075E+07 3.643E+07 CSI 138 CS2 138 XE2 138 LA2 138 SB2 139 TE2 139 2.542+06 4.649E+07 3.643E+07 6.734E-10 6.001 E+02 2.014E+05 l
12 139 XE2 139 CS2 139 BA2 139 TE2 140 12 140 4.354E+06 3.334E+07 4.444E+07 4.529E+07 3.452E+04 1.181 E+06 XE2 140 CS2 140 DA2 140 LA2 140 TE2 141 12 141 1.955E+07 3.823E+07 4.190E+07 4.218E+07 1.312E+03 2.028E+05 XE2 141 CS2 141 BA2 141 LA2 141 CE2 14' TE2 142 7.600E+06 1.495E+07 4.265E+07 4.290E+07 4.287E+07 1.954E+02 12 142 XE2 142 CS2 142 BA2 142 LA2 142 CE2 142 4.102E+04 2.711 E+06 1.495E+07 3.655E+07 3.770E+07 3.806E-04 6
12.1-631 Amend gm
~
d TABLE 12.1-32 (Continued)
PR1 142 PR2 142 12 143 XE2 143 CS2 143 BA2 143 2.570E+05 5.130E+05 3.377 E+03 3.726E+05 6.734E+06 3.046E+07 LA2 143 CE2 143 PR2 143 12 144 XF.2 144 CS2 144 3.455E+07 3.481 E+07 3.478E+07 2.823E+02 1.192E+05 2.448E+06 BA2 144 LA2 144 CE2 144 PRI 144 PR2 144 ND2 144 2.120E+07 2.894E+07 2.016E+07 2.552E+05 2.019E+07 7.649E-09 12 145 XE2 145 CS2 145 BA2 145 LA2 145 CE2 145 1.427E-08 1.710E+04 5.590 E+05 1.148E+07 2.237 E+07 2.501 E+07 PR2 145 XE2 146 CS2 146 BA2 146 LA2 146 CE2 146 2.503E+07 1.143E+03 8.232E+04 4.536E+06 1.495E+07 2.060E+07 PR2 146 XE2 147 CS2 147 BA2 147 LA2 147 CE2 147 2.070E+07 8.668E+01 2.758E+04 1 ~.376E+06 7.677E+06 1.620E+07 PR2 147 NO2 147 PM2 147 SM2 147 CS2 148 BA2 148 1.676E+07 1.703E+07 5.021E+06 3.044E-05 1.597E+03 3.829E+05 LA2 148 CE2 148 PR2 148 PM1 148 PM2 148 SM2 148 2.797 E+06 1.218E+07 1.372E+07 7.387E+05 7.891 E+05 1.157E-10 CS2 149 BA2 149 LA2 149 CE2 149 PR2 149 ND2 149 3.283E-07 4.344E+04 9.875E+05 5.986E+05 1.051 E+07 1.110E+07 1
I 12.1-63J Amend. 65
_ rgs ggp2
j l TABLE 12.1-32 (Continued)
PM2 149 SM2 149 CS2 150 BA2 150 LA2 150 CE2 150 1.110E+07 1.065E-09 1.593E+00 4.159E+03 1.722E+05 2.879E+06 PR2 150 PM2 150 BA2 151 LA2 151 CE2 151 PR2 151 7.327 E+06 1.026E+04 1.152E-05 3.065E+04 1.043 E+06 4.280E+06 ND2 151 PM2 151 SM2 151 BA2 152 LA2 152 CE2 152 6.637 E+06 6.673E+06 6.838E+04 1.075E+01 3.215E+03 3.853E+05 PR2 152 ND2 152 PM2 152 Eul 152 EU2 152 GD2 152 2.259E+06 4.874E+06 4.949E+06 4.909E+03 3.072E+02 1.844E-11 LA2 153 CE2 153 PR2 153 ND2 153 PM2 153 SM2 153 4.127 E+02 7.587 E+04 8.321 E+05 2.856E+06 3.178E+06 3.464E+06 GD2 153 LA2 154 CE2 154 PR2 154 ND2 154 PM1 154 5.706E+01 1.709E+01 1.181 E+04 2.213E+05 1.830E+06 2.415E+05 PM2 154 EU2 154 LA2 155 CE2 155 PR2 155 ND2 155 2.095 E+06 3.147 E+04 5.061 E-09 1.156E+03 6.465E+04 9.661E+05 PM2 155 SM2 155 EU2 155 CE2 156 PR2 156 ND2 156 1.518E+06 1.657 E+06 2.834E+05 1.272E+02 1.022E+04 4.255E+05 PM2 156 SM2 156 EU2 156 CE2 157 PR2 157 ND2 157 8.852E+05 1.022E+06 1.339E+06 6.965E+00 1.555E+03 1.148E+05 12.1-63k g,g
~.
TABLE 12.1-32 (Continued)
PM2 157 SM2 157 EU2 157 PR2 158 ND2 158 PM2 158 5.038E+05 7.415E+05 7.531E+05 9.092E+01 1.896 E+04 1.679E+05 SM2 158 EU2 158 PR2 159 ND2 159 PM2 159 SM2 159 4.487 E+05 4.682E+05 3.674E+00 1.621 E+03 4.116E+04 2.302E+05 e
EU2 159 GD2 159 ND2 160 PM2 160 SM2 160 EU2 160 2.671 E+05 2.954E+05 1.395E+02 6.625E+03 1.120E+05 1.624E+05 TB2 160 ND2 161 PM2 161 SM2 161 EU2 161 GD2 161 3.984E+04 7.062E+00 6.466E+02 2.282E+04 6.093 E+04 9.125E+04 TB2 161 PM2 162 SM2 162 EU2 162 GD2 162 1B1 162 9.183E+04 8.563E+00 1.974E+03 1.799E+04 4.037E+04 1.592E+03 TB2 162 SM2 163 EU2 163 GD2 163 TB2 163 SM2 164 4.036E+04 1.318E+02 3.358E+03 1.587E+04 1.786E+04 1.052E+01 EU2 164 GD2 164 TB2 164 SM2 165 EU2 165 GD2 165 6.291 E+02 8.073E+03 1.102E+04 3.951 E-01 8.256 E+01 2.744E+03 1B2 165 DY1 165 DY2 165 DY2 166 H01 166 H02 156 5.591 E+03 4.335E+03 7.815E+03 1.131E+03 2.607 E-01 1.731 E+03 ER1 167 1.894E+00 12.1-63L Amend. 65
7
.(;'
)Qd '
p DISTRIBUTION TEN 1RAL FILE AEB R/F MThadnai MAYn,wb i--
WPasedag Plant File R / RP RF RE!Y)DA"DU'i FOR: Paul S. Check, Director Clinch River Dreeder Reactor Program Office, NRC FR0":
R. W. Houston, Assistant Director for Radiation Protection Division of Systems Integration SUOJECT:
EVALUATION OF CLASS 9 ACCIDD!TS FOR T!!E CR3R EINIRDIC'lTAL REVIEU In response to your request to L'. G. Hulr.an, dated 3/31/82, the Accident Evaluction Branch (AED) has re evaluated the risks resulting from a Class 9 accident at CRCR site.
Per your recuest, AED has utilized as a basis the Class 9 accident scenario in the existing FCS. The event chosen in the FES results in release into the outer containment of 100% of the noble cases,10% of the volatiles includinu hstogenc, and 1% of the solid fission products and fuel (including plutoniun). Radionuclides are assuned to be released to etr.osphere as a result of the failure of the containnent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after their release from the core. The accidetit probability of one enance in one hundred thousand per year provided in your request was used in the present analysis. Since our evatustion is based on the methodologies of the Reactor Safety Study and the related follow-on work on calculation of Licht water reactor (LWR) consequences, our cethods at present do not account for the Lerge quantities of sodium present in the CRGRP in place of the large cuantities of water f, resent in tiie LURs.
The results of the AEP analysis indicate that the calculated risks for the selected CRER accider.t release are substantially below the risks that the staff has presented in the environmental stater.ents of Light water reactors which have been Licensed since the issuance of the Comission's June,19P0 Statement of policy. Dased on this analysis the AE9 has revised its 12/18/81 transmittal to you by including the findings of the present analysis. The revised input is enclosed.
This evaluation was performed, and the attached input prepared by Mohan Thadani X2P.941. The addendur.t on the Liquid pathway was prepared by R. CodeLL (HGED), and reported tr m
o you dated 12/19/62. Original signed by.
i' R. W2yne Housten gg
_4 J --
R. Wayne Houston, Assistant Director a
e
!,(,@ - -
f~
for Radiation Protection i
J L
Division of systems Intecration y
e: As stated cc: H. Denton W. Pasedag G. Lear E. Case M. Thadani R. Mattson R. CodeLL P. Leech
- See Previous concurrence Sheet J. Zw;i DSI:AEB
- DSI:AEB*
E 1@f crncr>
(.... '.
.E....;.J... W:i..i..
".ik"..'sisE.."."..".
..... i a " ~~"
.............g...........g m,
ac ronu sia no-somacu eno OFFICIAL RECORD COPY usce mi--sam
.33y
..y q.
g.. q ; 3, ; ; y ;.; ;.
(,
qy
- ..zm
i ACCIDENT EVALUATION BRANCH INPUT TO THE FINAL ENVIRONMENTAL STATEMENT UPDATE FOR CLINCH RIV4R BREEDER REACTOR PLANT Addendum to Section 7.1 7.1 PLANT ACCIDENTS INVOLVING RADIOACTIVE MATERIALS The staf f has examined the Clinch River Breeder Rea t c or Plant (CRBRP) Final Environmental Statement 7
(FES) with a view to updating the FES reflecting any plant-site features or regulatory framework changes that have occurred since the.FES issued in February 1977.
was The staff finds that since the issuance of the FES no plant-site changes have occurred that would materially change the environmental impacts or risks of accidents as reported in the FES.
Since the issuance of the FES, however, the Commission has issued a Statement of Interim Policy (June 13,1980) that provides guidance on the considerations to be given to nuclear power plant accidents under NEPA.
Among other things the Commission's statement indicated that "this change in policy is not to be construed as any lack of confidence in conclusions regarding the environmental risks of accidents expressed in any previously issued (Environmental Impact) statements, nor, absent a showing of ---
special circumstances, as a basis for opening, reopening,
(
or expanding any previous or ongoing proceeding."
1 I
i l
l t
- 9%~
The staff in its environmental review of the CRBRP application concluded that the CRBRP did constitute a special circumstance that warranted consideration of Class 9 accidents in the Environmental Statement.
Since the CRBRP reactor was very different from the conventional light water reactor plants for which the safety experience base is much broader, the staff included in the CRBRP FES a discussion of the potential impacts and risks of such accidents.
As noted in the Statement of Interim Policy, the fact that the staff had identified this case as a special circumstance was one of the conside.'ations that led to the promulgation of the June 13, 1980 Statement.
In examining the CRBRP FES, as issued in 1977, the staff has considered the guidance of the Interim Policy Statement which was provided for " Future NEPA Reviews." We have concluded that the discussion of accidents as presented in the FES generally meets that guidance except for consideration of the risks due to liquid pathways.
A discussion of the liquid pathway risks is included below.
O
The staff has also performed some new calculations to provide an additional perspective on the risk associated with the atmospheric release pathway for a hypothetical Class 9 accident at the CRBR, as discussed below:
A probabilistic risk analysis such as the Reactor Safety Study, WASH-1400, attempts to portray the complete spectrum of possible Class 9 event sequence.
Such a probabilistic risk analysis has not been performed for the CRBR as l
currently designed. Therefore, for the purpose of estimating the risks of Class 9 events at the CRBR site comparable to the risks presented in environmental statements for LMRs, the staff has selected, as representative of ~the Class 9 event category, a specific release of radioactivity from the CRBR core with an associated estimate of a probability of its occurrence.
The event analyzed is that described in the FES (Table 7.2, f.n.11).
Specifically, an accident is postulated which results in a core release of 100% of the noble gases and volatiles,10% of the solid fission product inventory and 10% of the plutonium inventory.* In this scenario, the volatiles, including halogens, are reduced to 10% of the core inventory eid the solid fission products and fuel are reduced to 1% of the core inventory during passage c.ut of the reactor vessel and into the outer containment building. Containment Leakage is taken as proportional'to the square roo't of the pressure for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at which time containn nt integrity is assumed to be Lost and aLL airborne m'aterial released to the environment.
- In addition to these elements, activation products of the primary coolant (i.e.
radioactive isotopes of sodium) would be released to the containment in accidents involving the loss of primary coolant. Although it is recognized that these isotopes could be substantial contributors to the accident source term, the present analytical models used by the staff are not readily amenable to an explicit inclusion of these isotopes in the quantitative analysis described herein.
b
The probability of this representative event has been estimated to be not greater than one in one hundred thousand per reactor year.
j This probability was selected for the new calculations discussed here in consideration of the nature of the representative sequence, in comparison with the results of other probabilistic risk ansyses, and in consideration of the staff's objective that there be no greater than one chance in a million per year for potential consequences greater than 10 CFR Part 100 guidelines for an individual plant.
ATMOSPHERIC PATHWAYS The potential atmospheric pathway radiological consequences of this release have been calculated by the consequence model used in the RSS (NUREG-0340) adapted and modified to the specific CRBRP site. The model used one year site meteorology data, projected population for the year 2010 extending throughout regions of 80-km (50-mi) radius and 56-km (350-mi) radius from the site, and habitable land fractions within the 563-km (350-mi) radius.
The results of the calculations are summarized in table 7-1A as expectation values, or averages of environmental risk per year of reactor operation. These averages are instructive as an aid to the comparison of radiological risks associated with CRBR accident releases and those associated with risks calculated for recently evaluated LWRs. The table shows the average risk associated with population " dose, early fatstities, latent fatalities, and cost of evacuation and protective actions.
TABLE 7.1A Average Values of Environmental Risks due to Selected CRBR Accident Envi ronmental Risk (Per Reactor Year)
Average Value Population exposure Person-rems within 80 km 8
12 Total person-rems Early Fatalities 0.0000004 Latent cancer, fatalities AlL organs excluding thyroid 0.0007 Thyroid only 0.00005 Cost of protective actions and decontamination
$ 15 6*
- 1980 dollars 1
It should be noted that these results do not fully account for the effects of the sodium coolant on the radioactive source term.
For example, inclusion of the effects of sodium is expected to reduce the quantity of iodine available for leakage. The large mass of sodium aerosol also contributes to the agglomeration and settling of aerosols in the primary containment. On the other hand, the sodium activation products would be released together with the primary coolant, thereby adding to the amount of radioactive material released to the containment. On balance, it is expected that these effects would not be so large as to
-invalidate the conclusiens of these calculations.
Further consideration of this subject wiLL be included in the staff's review of the Probabilistic Risk Assessment for this plant, and in the staff's Safety Evaluation Report.
The assessment of environmental risks of atmospheric pathways, assuming reasonable protective action, shows that they are 3
i significantly Lower than similarly calculated values for light water reactors currently being Licensed for operation.
See, for example, FEC for Callowey (NUREG-0813), DES for Seabrook Station (NUREG-0895),
FES for Susquehanna Station (NUREG-0564), and DES for Skagit (NUREG-0894) for the environmental risks of Li,'ht water reactors.
l l
1 l
i
~..
l LIQUID PATHWAYS Surf ace water hydrologic properties at CRBRP should be similar to those used for the Liquid Pathways Generic Study (LPGS) small river site which was based on the Clinch - Tennessee - Ohio - Mississippi rivers system, although the river uses and populations in the LPGS were based upon national averages and have not been directLy compared to the CRBRP. The groundwater characteristics at Clinch River do not indicate any unusual adverse transport characteristics.
Additionally, the CRBRP is a considerably smaller plant than LPGS case (CRBRP is 1121 MWt vs. 3425 MWt assumed for LPGS), and contrary to the Light Water Reactors characteristics, CRBRP does not contain any large storage of water which could serve as a potential " prompt source" to to the environmental liquid pathways. Therefore, only the radioactive material Leached f rom the core debris by the local groundwater is likely to be transported to the Clinch River. This source was found in the LPGS to be considerably smaller than the "pronpt source". Therefore, based on the preliminary appraisal of the Liquid pathways, the staff concludes that the liquid pathways impacts of CRBRP would be probably smaller than those for the LWRs analyzed in the LPGS "Small River" site case.
dl
CONCLUSION i
The foregoing sections have evaluated the environmental impacts of a severe accident including potential radiation exposure to the population as a whole, the risk of near - and long-term adverse health effects that such exposures could entait, and the potential economic and societal consequences of accidental contamination of the environment. The overall assessment of environmental risk of accidents, assuming reasonable protective action, shows that it is significantly lower than the risk from Light water reactors currently being licensed for operation, and the conclusions reached in the FES remain unchanged by this evaluation.
_ - - _ _ _ _ _ _ _ _ _ _. - - - - -