ML20206F669
| ML20206F669 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/31/1998 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20206F649 | List: |
| References | |
| NUDOCS 9905060204 | |
| Download: ML20206F669 (29) | |
Text
, . . .
Attachment 1 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 Summary of Radioactive Liquid and Gaseous Emuents and Solid Waste Released from the SNEC Facility Site during 1998
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Attachment 2 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 Solid Waste Shipped Offsite from the SNEC Facility Site during 1998 f
4
l NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0 Waste Stroom : Resins, Filters, and Evap Bottoms Waste Volume Curles % Error Class Ft^3 M*3 Shipped (Cl)
A 0.00E+00 0.00E+00 - 0.00E+00 +/- 25%
B 0.00E+00 0.00E+00 0.00E+00 +/- 25%
C 0.00E+00 0.00E+00 0.00E+00 +/- 25%
All 0.00E+00 0.00E+00 0.00E+00 +/- 25%
Waste Stream : Dry Active Waste Main Coolant 98 Pressure Relief 98 Red Avg B-25 Red Avg Sealand Blue Piping Sealand S/L R.Y & B Piping L Dia Main Coolant Area 6-Rx Cavity DAW-Area 1 & 2 Waste Volume Curles % Error Class Ft*3 M*3 Shipped (Cl)
A ' 1.20E+04 3.40E+02 5.35E+00 +/-25%
B 0.00E+00 0.00E+00 0.00E+00 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 1.20E+04 3.40E+02 5.35E+00 +/-25%
Waste Stream : Irradiated Components Reactor Support Can SNEC RX Vessel W
_ aste Volume Curles % Error Class Ft*3 M^3 Shipped (Cl)
A 9.60E+01 2.72E+00 7.32E-01 +/-25%
B- 1.10E+03 3.13E+01 1.26E+03 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 1.20E+03 3.40E+01 1.26E+03 +/-25%
l NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0 Weste Stream : Other Weste Combined Packages Shield Block Shield Key Composite: Area 1& 2 SNEC PZR SNEC S/G" Wants Volume Curles % Error Claes Ft*3 M^3 Shipped (Cl)
A 4.39E+03 1.24E+02 4.03E+00 +/-25%
B 0.00E+00 0.00E+00 0.00E+00 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-25%
All 4.39E+03 1.24E+02 4.03E+0^ +/-25%
Waste Stream : Sum of All4 Categories Combined Packages Shield Block Shield Key Main Coolant 98 Pressure Relief 98 Red Avg B-25 Red Avg Sealand Blue Pipit.g Sealand S/L R.Y & B Piping L Dia Main Coolant Area 6-Rx Cavity DAW-Area 1 & 2 Weste Volume Curles % Error Class Ft^3 M^3 Shipped (Cl)
A 1.65E+04 4.67E+02 1.01E+01 +/-25%
B 1.10E+03 ' 3.13E+01 1.26E+03 +/-25%
C 0.00E+00 0.00E+00 0.00E+00 +/-259'-
All 1.76E+04 4.98E+02 1.27E+03 +/-25%
-Combined Waste Type Shipment. Major Volume Waste Type Shown l
NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0 Dry Active Weste Waste Class A Nuclide Name ,
Percent Abundance Curies C-14 0.000 % 3.80E-06 Fe-55 0.537 % 2.87E-02 Co-60 2.016 % 1.08E-01 Ni-59 1.266 % 6.77E-02 Ni-63 80.990 % 4.33E+00 Sr-90 0.518 % 2.77E-02 Nb-94 0.070 % 3.76E-03 Tc-99 0.000 % 6.81 E-06 Cs-134 0.004 % 2.32E-04 Cs-137 6.186 % 3.31 E-01 Co-144 0.030 % 1.58E-03 Eu-152 0.045 % 2.40E-03 Eu-154 0.023 % 1.23E-03 Eu-156 0.005 % 2.76E-04 U-234 0.000 % 2.99E-06 U-238 '
0.000 % 2.01 E-06 Pu-238 O.195 % 1.04E-02 Pu-239 0.370 % 1.98E-02 Pu-240 0.074 % 3.95E-03 Pu-241 7.249 % 3.88E-01 Pu-242 0.000 % 4.60E-08 Am-241 0.421 % 2.26E-02 Cm-242 0.000 % 1.95E-06 Cm-243 0.000 % 5.92E-06 Cm-244 0.000 % 1.36E-06 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curles C-14 0.000 % 3.80E-06 Fe-55 0.537 % 2.87E-02 Co-60 2.016 % 1.08E-01 Ni-59 1.266 % 6.77E-02 Ni-63 80.990 % 4.33E+00 Sr-90 0.518 % 2.77E-02 Nb-94 0.070 % 3.76E-03 To-99 0.000 % ~
6.81 E-06 Cs-134 0.004 % 2.32E-04 Cs-137 6.186 % 3.31 E-01 Co-144 0.030 % 1.58E-03 Eu-152 0.045 % 2.40E-03
c
, 1 NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0 Eu-154 0.023 % 1.23E-03 Eu-155 0.005 % 2.76E-04 U-234 0.000 % 2.99E-06 U-238 0.000 % 2.01 E-06 Pu-238 0.195 % 1.04E-02 Pu-239 0.370 % 1.98E-02 j Pu-240 0.074 % 3.95E-03 '
Pu-241 7.249% 3.88E-01 Pu-242 0.000 % 4.80E-08 Am-241 0.421 % 2.26E-02 Cm-242 0.000 % 1.95E-06 Cm-243 0.000 % 5.92E-06 Cm-244 0.000 % 1.36E-06 trradiated Components Waste Class A Nudide Name Percent Abundance Curies H-3 0.118% 8.64E-04 C-14 0.076 % 5.58E-04 Ar-39 0.000% 0.00E+00 Ca-41 0.000 % 0.00E+00 Ca-45 0.000 % 0.00E+00 Mn-54 0.000 % 0.00E+00 Fe-55 1.222 % 8.94E-03 Co-60 47.094% 3.45E-01 Ni-59 0.415 % 3.03E-03 Ni-63 51.070 % 3.74E-01 Zn-65 0.000 % 0.00E+00 Sr-90 0.000 % 9.35E-06 Nb-94 0.000% 9.70E-08 Tc-99 0.000 % 3.41ii-06 Ru-106 0.000% 0.00E+00 Sb-125 0.000% 0.00E+00 1-129 0.000 % 3.88E-11 Cs-134 0.000 % 0.00E+00 Cs-137 0.004 % 3.14E-05 Co-144 0.000% 0.00E+00 Eu-152 0.000 % 0 00E+00 I U-234 0.000 % 0.00E+00 l U-235 0.000 % 0.00E+00 U-238 0.000 % 0.00E+00 Np-237 0.000 % 0.00E+00 Pu-238 0.000 % 0.00E+00 Pu-239 0.000% 0.00E+00 Pu-240 0.000 % 0.00E+00
7 NRC Regulatory Guide 1.21 Reports Page 3
' Report Date : 4/28/1999 Solid Weste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0
)
1 Pu-241 - 0.000 % 4.56E-06 Pu-242 0.000 % 0.00E+00 Am-241 0.000 % 0.00E+00 Cm-242 0.000 % 6.55E-13 Cm-244 0.000 % 0.00E+00 Irradiated Components Waste Class B Nuclide Name Percent Abundance Curies H-3 0.115 % 1.45E+00 C-14 0.093 % - 1.16E+00 Fe 55 1.523 % 1.91E+01 Co-60 33.727 % 4.24E+02 Ni-59 0.523 % 6.57E+00 Ni-63 63.813 % 8.02E+02 Sr-90 0.006 % 7.66E-02 Nb-94 0.001 % 1.31E-02 To 99 0.000 % 2.23E-03 Co-137 0.000 % 8.10E-02 Co 144 0.100 % 1.37E+00 Eu-154 0.000 % 2.50E-03 Eu-155 0.000 % 5.49E-04 U-234 0.000 % 2.29E-05 Pu-238 0.002 % 3.02E-02 Pu-239 0.000 % 6.92E-02 Pu-241 0.064 % 8.00E-01 Pu-242 0.000 % 3.00E-09 Am-241 0.011 % 1.44E-01 Cm-242 0.000 % 2.73E-06 Cm-243 0.000 % 1.25E-03 Irradiated Components Waste Class All Nuclide Name Percent Abundance Curies H3 0.115 % 1.45E+00 C-14 0.093 % 1.16E+00 Ar-39 0.000 % 0.00E+00 Co-41 0.000 % 0.00E+00 Co-45 0.000 % 0.00E+00 Mn-54 0.000 % 0.00E+00 Fe-56 1.523 % 1.91 E+01 Co-60 33.734 % 4.24E+02 Ni-59 0.523 % 6.57E+00 N643 63.806 % 8.02E+02 Zn-65 0.000 % 0.00E+00
I l
NRC Regulatory Guide 1.21 Reports Page 4 Report Date : 4/28/1999 - l Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: O Sr-90 0.006 % 7.66E-02 Nb-94 0.001 % 1.31E-02 To-99 0.000 % 2.23E-03 Ru-106 0.000 % 0.00E+00
. Sb-125 0.000 % 0.00E+00 1-129 0.000 % 3.88E-11 Cs-134 - 0.000 % 0.00E+00 Cs-137 0.006 % 8.10E-02 Co-144 0.100 % 1.37E+00 Eu-152 0.000 % - 0.00E+00 Eu 154 0.000 % 2.50E-03 Eu-155 0.000 % 5.49E-04 U-234 0.000 % 2.29E-05 U-235 0.000 % 0.00E+00 U-238 0.000 % 0.00E+00 Np.237- 0.000 % 0.00E+00 Pu-238 0 002% 3.02E-02 Pu-239 0.006 % 6.92E-02 Pu-240 0.000% 0.00E+00 Pu-241 0.064 % 8.00E-01 Pu-242 0.000 % 3.00E-09 Am-241 0.011 % 1.44E-01 Cm-242 0.000 % 2.73E-06 Cm-243 0.000 % 1.25E-03 Cm-244 0.000 % 0.00E+00 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.060% 3.22E-03 C-14 0.042 % 1.68E-03 Ar-39 0.000 % 0.00E+00 Ca-41 0.000 % 0.00E+00 Co-45 0.000 % 0.00E+00 Mn-54 0.000 % 0.00E+00 Fe-56 1.000 % 4.06E-02 Co40 28.922 % 1.17E+00 Ni-50 0.524 % - 2.11E-02 Ni 50.266 % 2.03E+00
- Zn-66 0.000 % 0.00E+00 Sr-90 0.233 % 9.38E-03 Nb-94 0.000 % 3.79E-04 To-99 0.000 % 1.28E-05 Ru-106 0.000 % 0.00E+00 Sb-125 0.000 % 0.00E+00
s NRC Regulatory Guide 1.21 Reports Page 5 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998_ to 12/31/1998 Percent Cutoff:~ 0 1-129- 0.000 % - 1.84E-06 Co-134 - 0.001 % 4.21E-05 Cs-137 14.775 % 5.95E-01 Co 144 0.088 % 3.55E-03 Eu-152 0.005 % 1.98E-04 )
Eu-154 0.005 % 2.02E-04 Eu-155 0.001 % 2.16E-05 U-234 0.000 % 1.05E-07 U-235 0.000 % 0.00E+00 U-238 0.000 % 6.93E-08 -l Np-237 0.000 % 0.00E+00 Pu-238 0.072 % 2.91E-03 l Pu 239 0.500 % 2.26E-02 Pu-240 0.004 % 1.52E-04 Pu-241 3.144 % 1.27E-01 Pu-242 0.000 % 3.19E-08 l Am-241 0.258 % 1.04E-02 Cm-242 0.000 % - 3.00E-06 Cm-243 0.003 % 1.14E-04 Cm-244 0.000 % 2.55E-06 Other Waste Weste Class All Nuclide Name Percent Awndance Curies H-3 0.080 % 3.22E-03 C 0.042 % 1.68E-03 Ar-39 0.000% 0.00E+00 Cs-41 0.000 % 0.00E+00 Co-45 0.000 % 0.00E+00 Mn-54 0.000 % 0.00E+00 Fe-55 1.009 % 4.06E-02 Co40 28.922 % 1.17E+00 Ni-50 0.524 % 2.11E-02 Ni-63 50.206 % 2.03E+00 Zn-65 0.000 % 0.00E+00 Sr-90 0.233 % 9.38E-03 Nb-94 0.000 % 3.79E44 !
I
__ To-99 0.000 % 1.28E-05 Ru-106 0.000 % 0.00E+00 Sb-125 0.000 % 0.00E+00 1-129 0.000% 1.84E-06 ,
l Cs-134 0.001 % 4.21E-05 Cs-137 14.775 % 5.95E-01 j Co-144 0.088 % 3.55E-03 '
Eu-152 0.005 % 1.98E-04 )
H
I i
NRC Regulatory Guide 1.21 Reports Page 6 Report Date : '4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From . 01/01/1998- - to 12/31/1998 - Percent Cutoff: 0
~
Eu-154 0.005 % 2.02E-04 Eu 156 0.001 % 2.16E-06 U-234 0.000 % 1.06E-07 U-236 0.000 % ' O.00E+00 U-238 0.000 % 6.93E-08 Np-237 0.000 % 0.00E+00 Pu-238 0.072 % 2.91E-03 Pu-230 0.560 % 2.20E-02 Pu-240 0.004 % 1.52E-04 i Pu-241 3.144 % 1.27E-01 Pu-242 0.000 % 3.19E Am-241 0.258 % 1.04E-02 Cm-242 0.000 % 3.00E-06 l
Cm-243 - 0.003 % 1.14E-04 Cm-244 0.000 % 2.56E-08 Sum of All 4 Categones Weste Class A Nuclide Name Percent Abundance Curtes H-3 0.040 % 4.08E-03 C-14 0.022 % 2.24E-03 Ar 39 0.000 % 0.00E+00 Ca-41 0.000 % 0.00E+00 Cs-45 0.000 % 0.00E+00 Mn-54 0.000 % 0.00E+00 Fe-56 0.775 % 7.83E-02 Co-60 15.998 % 1.62E+00 Ni-59 0.909 % 9.19E-02 Ni-63 66.583 % 6.73E+00 2n-66 0.000 % 0.00E+00 Sr-90 0.367 % 3.71E-02 Nb-94 0.041 % 4.14E-03
-To-99 0.000 % 2.30E-05 Ru-106 0.000 % 0.00E+00 -
Sb-125 0.000 % 0.00E+00 1-129 0.000 % 1.84E-06 Co.134 0.003 % 2.74E-04 Co-137 9.161 % 9.26E 01 Co-144 0.061 % 5.14E-03 Eu-152 0.026 % 2.60E-03 Eu-154 0.014 % 1.43E-03 Eu-155 0.003 % 2.97E-04 U-234 0.000 % 3.10E-08 U-235 0.000 % 0.00E+00 U-238 0.000 % 2.08E-06
NRC Regulatory Guide 1.21 Reports Page 7 i
Report Date : 4/28/1999
' Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Percent Cutoff: 0 Np-237 0.000 % 0.00E+00 Pu 238 0.132 % 1.33E-02 Pu-239 0.419 % - 4.24E-02 Pu-240 0.041 % 4.10E-03 Pu-241 5.069 % . 5.15E-01 Pu-242 0.000 % - 7.79E-06 Am-241 0.326 % 3.29E-02 Cm-242 0.000 % 4.95E-06 Cm-243 0.001 % 1.20E-04 Cm-244 0.000 % - 1.39E-06 Sum of All 4 Categories Weste Class B Nuclide Name - Percent Abundance Curies
- H-3 0.115 % 1.45E+00 C-14 0.003 % 1.16E+00 Fe-55 1.523 % 1.91E+01 Co-60 33.727 % 4.24E+02 Ni-59 0.523 % 6.57E+00 Ni-63 63.813% 8.02E+02 Sr-90 0.006% 7.66E-02 Nb-94 0.001 % 1.31E-02 To-99 0.000 % 2.23E-03 Co-137 0.006 % 8.10E-02 Co 144 0.100% 1.37E+00 Eu-154 0.000 % 2.50E-03 Eu-155 0.000 % 5.49E-04 U-234 0.000 % 2.29E-05
~
id-238 0.002 % 3.02E-02 Pu-239 0.006 % 6.92E-02 Pu-241 0.064 % 8.00E-01 Pu-242 0.000 % 3.00E-09 i Am-241 0.011 % 1.44E-01 Cm-242 0.000 % 2.73E-06 Cm-243 0.000 % 1.25E-03 Sum of All 4 Categories Weste Class AR Nuclide Nome Percent Abundance Curies H-3 0.115% 1.45E+00 C-14 0.092 % 1.18E+00 Ar-39 0.000 % - 0.00E+00 Co-41 0.000 % 0.00E+00 Co-40 0.000 % 0.00E+00 h 54 0.000 % 0.00E+00
F 1 i
NRC Regulatory Guide 1.21 Reports Page 8 Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 ' to 12/31/1998 Percent Cutoff: 0 l Fe-55 1.517 % 1.92E+01 Co-60 33.585 % 4.25E+02 Ni-59 0.526 % 6.66E+00 j Ni-63 63.835 % 8.08E+02 !
Zn-85 0.000 % 0.00E+00 l Sr-90 0.000% 1.14E-01 1 Nb-94 0.001 % 1.72E-02 To-99 0.000 % 2.25E 03 Ru-106 0.000 % 0.00E+00 l Sb-125 0.000 % 0.00E+00 I l-129 0.000 % 1.84E-06 Cs-134 0.000 % 2.74E-04 ;
Cs-137 0.080 % 1.01E+00 1 Ce-144 0.109 % 1.37E+00 Eu-152 0.000 % 2.60E-03 Eu-154 0.000 % 3.93E-03 Eu-155 0.000 % 8.47E-04 U-234 0.000 % 2.60E-05 U-235 0.000 % 0.00E+00 U-238 0.000 % 2.08E-06 Np-237 0.000 % 0.00E+00 Pu-238 0.003 % 4.35E-02 Pu-239 0.009 % 1.12E-01 Pu-240 0.000 % 4.10E-03 Pu-241 0.104 % 1.31 E+00 Pu-242 0.000 % 8.10E-08 Am-241 0.014 % 1.77E-01 Cm-242 0.000 % 7.68E-06 Cm-243 0.000 % 1.37E-03 .
Cm-244 0.000 % 1.39E-06
r 1 i
NRC Regulatory Guide 1.21 Reports Page 1 l Report Date : 4/28/1999 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/1998 to 12/31/1998 Number of Shipments Mode of Transportation Destination 2 T A G Transport Inc. ATG Richland Corp.
1 Kindrick Trucking Company Bamwell Waste Management Facility 1 FW Hake / Conrail Barnwell Waste Management Facility 3 Kindrick Trucking Company Fred W Hake Associates 1 Tri State Motor Transit Co. Fred W Hake Associates 5 Kindrick Trucking Company Manufacturing Sciences Corp l
I
s, Attachment 3 -
t.
1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 Summary of Unplanned Releases from the SNEC Facility Site During 1998 There were no unplanned releases to unrestricted areas from the SNEC Facility Site during 1998.
p E
t Attachment 4
- 1998 Annual Radioactive Effluent Releases Report for SNEC
! 1920-99-20231 l
Changes to the Process Control Program and the Offsite Dose Calculation Manual during 1998, And a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census
- 1. . Changes to the Process Control Program In 1998, the Process Control Program (PCP) Procedure was initially issued. There have been no revisions to this procedure.
- 2. Changes to the Offsite Dose Calculation Manual during 1998 In 1998, the Offsite Dose Calculation Manual (ODCM) was approved by the NRC and was issued. During 1998, there have been no revisions to the ODCM.
- 3. A listing of new locations for dose calculations and/or environmental monitoring identified by the land use census Per the SNEC ODCM Section 2.3.2 broad leaf vegetation was collected and Tnalyzed for l gamma-emitting radionuclides in lieu of performing a land use census. Therefore, no new environmental monitoring locations were identified.
L
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' Attachment 5 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 Instrumentation not returned to Operable status within 30 days during 1998 There was no instmmentation not retumed to operable status within 30 days per the SNEC ODCM Pan 1, Control 2.1.1.b. during 1998.
l
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Attachment 6 -
' 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released from the SNEC Facility Site during 1998 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 1998 SNEC Facility Site (SNEC) releases of gaseous and liquid effluents. Provided below is a brief explanation of the table.
A. Liauid Gndividual)
SNEC released no liquid effluents in 1998.
B. Gaseous Ondividual) i There were four major pathways considered in the dose calculations for SNEC gaseous effluents. These were: (1) individual inhalation of airborne nuclides (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subse-quent exposure of man. In lieu of real time meteorology, the highest average gaseous dispersion factor was used in all dose calculations for gaseous effluents.
Since there were no noble gases released from SNEC during 1998, the gamma and beta air doses were zero.
The maximum hypothetical dose to any orgt.n for any age group due to the release of particulates and tritium from SNEC in 1998 was 5.15E-3 to a hypothetical individual residing 200 meters from the site in the N sector.
C. Liauid and Gaseous (Boulation) '
SNEC released no liquid effluents in 1998. The estimated person-rem doses resulting from 1998 SNEC gaseous effluents are shown in the attached table. These doses were summed over all pathways and the affected populations. The person-rem doses from gaseous effluents were based upon the population estimate and age distribution assumed in the analysis provided in GPUN letter to the Commission 6L20-98-20105 (Docket No.
50-146). Consistent with this analysis, dose calculations were not performed beyond 10 l-miles as specific population data is not easily available and releases form the site are i considered to be at ground level. As a result, releases of particulates beyond 10 miles will !
be insignificant since it is assumed diffusion and wet and dry deposition mechanisms will i deplete the plume before it reaches 10 miles. W i
4 Attachment .6 1998 Annual Radioactive Efiluent Releases Report for SNEC l 1920-99-20231 I l
(
Additionally, since the plant has been shut down for so long and all spent fuel has been removed from the site, iodines and noble gases no longer exist. j SNEC gaseous effluents resulted in a whole body population dose of 1.52E-4 person-rem. This is a small fraction of the dose estimated in the previously referenced analysis.
For 1998, SNEC liquid and gaseous effluents resulted in maximum hypothetical doses that were a small fraction of the quarterly and yearly 10 CFR.50 Appendix I dose limits.
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1 Attachment 7
~ 1998 Annual Radioactive Effluent Releases Report for.SNEC 1920-99-20231 Assessment of Radiation Doses from Liquid and Gaseous Ef11uents Releases to Members of the Public within the SNEC Facility Site Boundaries during 1998 The Offsite Dose Calculation Manual requires an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of public due to their activities inside the site boundary during the reporting period. The public did not have unrestricted access to the SNEC Facility Site during 1998. Therefore no assessment of this dose is applicable.
l l
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' Attachment 8 7l 1998 Annual Radioactive Effluent Releases Report for SNEC r
1920-99-20231 l
i Assessment of Radiation Dose to Most Likely Exposed Real Individual per 40 CFR 190 -l l
Dose calculations were also performed to demonstrate compliance with 40 CFR 190 (ODCM Part IV Section 2.10).- Gaseous and liquid effluents released from SNEC in 1998 would have resulted in -
)
maximum individual doses (regardless of age group) of 5.15E-3 mrem to any organ including the l whole body. The direct radiation component was determined using the highest 1998 fenceline i exposure rate as. measured by a TLD and subtracting from it the lowest TLD exposure rate. This method more accurately' determines the exposure from SNEC by subtracting out the exposure rate from other sources 'of radiation in the environment. '. Based on the maximum exposure rate of' l.25E+1 mrem / standard month, a person residing at the fenceline fo'r 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (shoreline exposure
' from Reg. Guide 1.109) would have received an exposere of 1.146E+0 mrem. Based on the lowest exposure rate of 4.50E+0 mrem / standard month and converting it by the same method gives a background exposure of 4.13E-ImR. Therefore, the net exposure from direct radiation from SNEC is 7.34E-1 mrem. Combining the direct radiation exposure (assumed to be equal to dose) with the maximum organ doses from liquid and gaseous releases, the maximum potential (total) dose would have been 7.39E-Irnrem to any organ. Both doses are well below the limits specified in 40 CFR
'190.
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Attachment 9 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 !
(
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1 l
Deviation from the ODCM Sampling and Analysis Regime during 1998 l
There were two sampling and analysis regime deviations during 1998. Both occurred with the j tritium sample desiccant columns being prematurely exhausted. Laboratory deviation reports !
were written and appropriate actions were taken to prevent reoccurrence. For off-site dose {
calculations, the average tritium concentration for 1998 was used for the deviation time periods. I No other deviations occurred during 1998.
I 1
l i
g Enclosure 1 1998 Annual Radioactive Effluent Releases Report for SNEC 1920-99-20231 i,
SNEC Facility Offsite Dose Calculation Manual, Revision 0 l 6575-PLN 4542.08 1
(Revision 0 was issued on April 23,1998)- -
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