ML020720361

Part 2 of 2, Nine Mile Point, Unit 2, January-December 2001 Radioactive Effluent Release Report

ML020720361
Person / Time
Site:	Nine Mile Point
Issue date:	02/28/2002
From:	Montgomery B Constellation Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP2L 2051, RG-1.021, Rev 1
Download: ML020720361 (91)

Text

TABLE D 3-6 DOSE AND DOSE RATE Ri VALUES - INHALATION - TEEN mrem/yr 3

uCi/m NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 1.27E3 C 14* 2.60E4 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 4.87E3 Cr 51 1.35E2 7.50E1 3.07E1 2.1 0E4 3.00E3 Mn 54 5.1 1E4 8.40E3 1.27E4 1.98E6 6.68E4 Fe 55 3.34E4 2.38E4 5.54E3 1.24E5 6.39E3 Fe 59 1.59E4 3.70E4 1.43E4 1.53E6 1.78E5 Co 58 2.07E3 2.78E3 1.34E6 9.52E4 Co 60 1.51E4 1.98E4 8.72E6 2.59E5 Zn 65 3.86E4 1.34E5 6.24E4 8.64E4 1.24E6 4.66E4 Sr 89 4.34E5 1.25E4 2.42E6 3.71E5 Sr 90 1.08E8 6.68E6 1.65E7 7.65E5 Zr 95 1.46E5 4.58E4 3.15E4 6.74E4 2.69E6 1.49E5 Nb 95 1.86E4 1.03E4 5.66E3 1.00E4 7.51 E5 9.68E4 Mo 99 1.69E2 3.22E1 4.1 1E2 1.54E5 2.69E5 1131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 6.49E3 1133 1.22E4 2.05E4 6.22E3 2,92E6 3.59E4 1.03E4 5.02E5 1.13E6 5.49E5 3.75E5 1.46E5 9.76E3 Cs 134 6.70E5 8.48E5 3.1 1E5 3.04E5 1.21E5 8.48E3 Cs 137 Ba 140 5.47E4 6.70E1 3.52E3 2.28E1 2.03E6 2.29E5 La 140 4.79E2 2.36E2 6.26E1 2.14E5 4.87E5 Ce 141 2.84E4 1.90E4 2.17E3 8.88E3 6.14E5 1,.26E5 Ce 144 4.89E6 2.02E6 2.62E5 1.21E6 1.34E7 8.64E5 Nd 147 7.86E3 8.56E3 5.13E2 5.02E3 3.72E5 1.82E5 Ag 110m 1.38E4 1.31E4 7.99E3 2.50E4 6.75E6 2.73E5

• mrem/yr per ýCi/m3 Unit 2 Revision 22 II 42 December 2001

TABLE D 3-7 DOSE AND DOSE RATE Ri VALUES - INHALATION - ADULT mrem/yr uCi/m 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 1.26E3 1.26E3 1.26E3 1.26E3 H3* 3.41 E3 3.41E3 3.41E3 3.41E3 3.41E3 3.41E3 C 14* 1.82E4 1.00E2 5.95E1 2.28E1 1.44E4 3.32E3 Cr 51 7.74E4 3.96E4 6.30E3 9.84E3 1.40E6 Mn 54 6.03E3 1.70E4 3.94E3 7.21E4 Fe 55 2.46E4 1.06E4 1.02E6 1.88E5 Fe 59 1. 18E4 2.78E4 2.07E3 9.28E5 1.06E5 Co 58 1.58E3 1.48E4 5.97E6 2.85E5 Co 60 1. 15E4 4.66E4 6.90E4 8.64E5 5.34E4 Zn 65 3.24E4 1.03E5 8.72E3 1.40E6 3.50E5 Sr 89 3.04E5 6.1 0E6 9.60E6 7.22E5 Sr 90 9.92E7 2.33E4 5.42E4 1.77E6 1.50E5 Zr 95 1.07E5 3.44E4 4.2 1E3 7.74E3 5.05E5 1.04E5 Nb 95 1.41E4 7.82E3 2.30E1 2.91 E2 9.12E4 2.48E5 Mo 99 1.21E2 2.05E4 1. 19E7 6.13E4 6.28E3 1 131 2.52E4 3.58E4 4.52E3 2.15E6 2.58E4 8.88E3 1 133 8.64E3 1.48E4 7.28E5 2.87E5 9.76E4 1.04E4 Cs 134 3.73E5 8.48E5 4.28E5 2.22E5 7.52E4 8.40E3 Cs 137 4.78E5 6.21E5 2.57E3 1.67E1 1.27E6 2.18E5 Ba 140 3.90E4 4.90E1 4.58E1 1.36E5 4.58E5 La 140 3.44E2 1.74E2 1.53E3 6.26E3 3.62E5 1.20E5 Ce 141 1.99E4 1.35E4 1.84E5 8.48E5 7.78E6 8.16E5 Ce 144 3.43E6 1.43E6 3.65E2 3.56E3 2.21E5 1.73E5 Nd 147 5.27E3 6.1 0E3 5.94E3 1.97E4 4.63E6 3.02E5 Ag 110m 1.08E4 1.00E4

• mrem/yr per ýtCi/m 3 Unit 2 Revision 22 1143 December 2001

TABLE D 3-8 DOSE AND DOSE RATE Rl VALUES - GROUND PLANE ALL AGE GROUPS M2 -mrelyý/r uCilsec NUCLIDE TOTAL BODY SKIN H13 C 14 Cr 51 4.65E6 5.50E6 Mn 54 1.40E9 1.64E9 Fe 55 Fe 59 2.73E8 3.20E8 Co 58 3.80E8 4.45E8 Co 60 2.15E10 2.53E10 Zn 65 7.46E8 8.57E8 Sr 89 2.16E4 2.51 E4 Sr 90 Zr 95 2.45E8 2.85E8 Nb 95 1.36E8 1.61E8 Mo 99 3.99E6 4.63E6 1131 1.72E7 2.09E7 1 133 2.39E6 2.9 1E6 Cs 134 6.83E9 7.97E9 Cs 137 1.03El0 1.20E10 Ba 140 2.05E7 2.35E7 La 140 1.92E7 2.18E7 Ce 141 1.37E7 1.54E7 Ce 144 6.96E7 8.07E7 Nd 147 8.46E6 1.01E7 Ag 110m 3.44E9 4.01E9 Unit 2 Revision 22 II 44 December 2001

TABLE D 3-9 DOSE AND DOSE RATE Ri VALUES - COW MILK - INFANT n 2-mrem/yr uCi/sec BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 2.38E3 H3* 6.89E5 6.89E5 3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 C 14* 1.06E5 2.43E6 8.35E4 5.45E4 1.19E4 Cr 51 9.21E6 2.5 1E7 5.68E6 5.56E6 Mn 54 2.66E7 6.91E6 Fe 55 8.43E7 5.44E7 1.45E7 8.38E7 6.29E7 1.02E8 Fe 59 1.22E8 2.13E8 3.46E7 3.46E7 Co 58 1.39E7 1.39E8 1.40E8 Co 60 5.90E7 5.58E9 5.87E9 1.02E10 Zn 65 3.53E9 1.21E10 1.99E8 1.42E8 Sr 89 6.93E9 1.02E9 Sr 90 8.19E10 2.09E10 6.66E2 1.01E3 4.68E5 Zr 95 3.85E3 9.39E2

1. 17E5 1.54E5 3.03E8 Nb 95 4.2lE5 1.64E5 2.03E7 1.55E8 3.43E7 Mo 99 1.04E8 3.53E8 2.64E 11 9.37E8 2.86E7 1 131 6.81E8 8.02E8 3.63E6 2.26E9 1.46E7 2.10E6 1133 8.52E6 1.24E7 4.54E9 1.16E10 4.74E9 1.22E8 Cs 134 2.41E10 4.49E10 2.88E9 1.09E10 4.41E9 1.27E8 Cs 137 3.47E10 4.06E10 6.22E6 2.87E4 7.42E4 2.97E7 Ba 140 1.21E8 1.21E5 9.39E4 La 140 2.03E1 7.99 2.06 1.64E3 4.28E3 7.18E6 Ce 141 2.28E4 1.39E4 8.34E4 2.46E5 8.54E7 Ce 144 1.49E6 6.10E5 2.79E1 1.76E2 2.89E5 Nd 147 4.43E2 4.55E2 1.19E8 2.56E8 9.29E9 Ag 110r 2.46E8 1.79E8

• mrem/yr per ýtCi/m 3 .

Unit 2 Revision 22 December 2001 1145

TABLE D 3-10 DOSE AND DOSE RATE Ri VALUES - COW MILK - CHILD m=-mrem/yr uCi/sec BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 1.57E3 H 3* 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 C 14* 1.65E6 5.27E4 2.93E4 7.99E3 5.34E4 2.80E6 Cr 51 1.13E7 1.35E7 3.59E6 3.78E6 Mn 54 6.85E6 3.07E7 1. 15E7 2.09E7 Fe 55 6.97E7 1.06E8 5.26E7 3.06E7 1. 10E8 Fe 59 6.52E7 6.94E6 2.13E7 4.05E7 Co 58 1.60E8 Co 60 2.89E7 8.52E7 7.00E9 4.35E9 4.41E9 1.23E9 Zn 65 2.63E9 1.04E8 1.41E8 Sr 89 3.64E9 1.91E10 1.01E9 Sr 90 7.53E10 4.77E2 4.25E2 6.83E2 4.98E5 Zr 95 2.17E3 1.03E4 5.69E4 1.00E5 4.42E8 Nb 95 1.86E5 4.07E7 1.01E7 8.69E7 3.37E7 Mo 99 2.92E7 3.26E8 3.28E8 1.86E8 1.08E1I 5.39E8 1 131 4.99E6 1.89E6 9.27E8 8.32E6 2.01E6 1133 4.04E6 2.45E10 5.18E9 7.61E9 2.73E9 1.32E8 Cs 134 1.50El0 2.08E10 3.07E9 6.78E9 2.44E9 1.30E8 Cs 137 2.17E10 3.43E6 1.67E4 3.07E4 2.97E7 Ba 140 5.87E7 5.14E4 1.14 9.45E4 La 140 9.70 3.39 5.73E3 8.51 E2 2.51 E3 7.15E6 Ce 141 1. 15E4 3.26E5 5.55E4 1.80E5 8.49E7 Ce 144 1.04E6 1.81E2 1.40El 9.94E1 2.87E5 Nd 147 2.24E2 8.97E7 7.17E7 1.67E8 1.07E10 Ag 110m 1.33E8

.mrem/yr per 4+/-Ci/m 3.

Unit 2 Revision 22 II 46 December 2001

TABLE D 3-11 DOSE AND DOSE RATE R1 VALUES - COW MILK - TEEN m -mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 9.94E2 C 14" 1.34E5 6.70E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr 51 2.58E4 1.44E4 5.66E3 3.69E4 4.34E6 Mn 54 9.01E6 1.79E6 2.69E6 1.85E7 Fe 55 2.78E7 1.97E7 4.59E6 1.25E7 8.52E6 Fe 59 2.81 E7 6.57E7 2.54E7 2.07E7 1.55E8 Co 58 4.55E6 1.05E7 6.27E7 Co 60 1.86E7 4.19E7 2.42E8 Zn 65 1.34E9 4.65E9 2.17E9 2.97E9 1.97E9 Sr 89 1.47E9 4.21 E7 1.75E8 Sr 90 4.45E10 1.10E10 1.25E9 Zr 95 9.34E2 2.95E2 2.03E2 4.33E2 6.80E5 Nb 95 1.86E5 1.03E5 5.69E4 1.00E5 4.42E8 Mo 99 2.24E7 4.27E6 5.12E7 4.01E7 1 131 1.34E8 1.88E8 1.01E8 5.49E10 3.24E8 3.72E7 1133 1.66E6 2.82E6 8.59E5 3.93E8 4.94E6 2.13E6 Cs 134 6.49E9 1.53E10 7.08E9 4.85E9 1.85E9 1.90E8 Cs 137 9.02E9 1.20E10 4.18E9 4.08E9 1.59E9 1.71E8 Ba 140 2.43E7 2.98E4 1.57E6 1.01E4 2.00E4 3.75E7 La 140 4.05 1.99 5.30E-1 1. 14E5 Ce 141 4.67E3 3.12E3 3.58E2 1.47E3 8.91E6 Ce 144 4.22E5 1.74E5 2.27E4 1.04E5 1.06E8 Nd 147 9.12E1 9.91E1 5.94E0 5.82E1 3.58E5 Ag 110m 6.13E7 5.80E7 3.53E7 1.11E8 1.63E10

• mrem/yr per ýLCi/m 3.

Unit 2 Revision 22 II 47 December 2001

TABLE D 3-12 DOSE AND DOSE RATE Ri VALUES - COW MILK - ADULT me-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2 7.63E2

• C 14 3.63E5 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.48E4 8.85E3 3.26E3 1.96E4 3.72E6 Mn 54 5.41 E6 1.03E6 1.61E6 1.66E7 Fe 55 1.57E7 1.08E7 2.52E6 6.04E6 6.21E6 Fe 59 1.61E7 3.79E7 1.45E7 1.06E7 1.26E8 Co 58 2.70E6 6.05E6 5.47E7 Co 60 1. 10E7 2.42E7 2.06E8 Zn 65 8.71E8 2.77E9 1.25E9 1.85E9 1.75E9 Sr 89 7.99E8 2.29E7 1.28E8 Sr 90 3.15E10 7.74E9 9.1 1E8 Zr 95 5.34E2 1.71E2 1. 16E2 2.69E2 5.43E5 Nb 95 1.09E5 6.07E4 3.27E4 6.00E4 3.69E8 Mo 99 1.24E7 2.36E6 2.8 1E7 2.87E7 1131 7.41E7 1.06E8 6.08E7 3.47E10 1.82E8 2.80E7 1133 9.09E5 1.58E6 4.82E5 2.32E8 2.76E6 1.42E6 Cs 134 3.74E9 8.89E9 7.27E9 2.88E9 9.55E8 1.56E8 Cs 137 4.97E9 6.80E9 4.46E9 2.3 1E9 7.68E8 1.32E8 Ba 140 1.35E7 1.69E4 8.83E5 5.75E3 9.69E3 2.77E7 La 140 2.26 1.14 3.01E-I 8.35E4 Ce 141 2.54E3 1.72E3 1.95E2 7.99E2 6.58E6 Ce 144 2.29E5 9.58E4 1.23E4 5.68E4 7.74E7 Nd 147 4.74E1 5.48E1 3.28E0 3.20E1 2.63E5 Ag 110m 3.71E7 3.43E7 2.04E7 6.74E7 1.40E10 "nmrem/yr per 4Ci/m 3 .

Unit 2 Revision 22 II 48 December 2001

TABLE D 3-13 DOSE AND DOSE RATE Ri VALUES - GOAT MILK - INFANT m 2 -mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 C 14* 3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 6.89E5 Cr 51 1.00E4 6.56E3 1.43E3 1.28E4 2.93E5 Mn 54 3.01E6 6.82E5 6.67E5 1.11E6 Fe 55 1. 10E6 7.08E5 1.89E5 3.46E5 8.98E4 Fe 59 1.59E6 2.78E6 1.09E6 8.2 1E5 1.33E6 Co 58 1.67E6 4.16E6 4.16E6 Co 60 7.08E6 1.67E7 1.68E7 Zn 65 4.24E8 1.45E9 6.70E8 7.04E8 1.23E9 Sr 89 1.48E10 4.24E8 3.04E8 Sr 90 1.72E11 4.38E10 2.15E9 Zr 95 4.66E2 1.13E2 8.04E1 1.22E2 5.65E4 Nb 95 9.42E4 3.88E4 2.24E4 2.78E4 3.27E7 Mo 99 1.27E7 2.47E6 1.89E7 4.17E6 1131 8.17E8 9.63E8 4.23E8 3.16E1l 1. 12E9 3.44E7 1 133 1.02E7 1.49E7 4.36E6 2.71 E9 1.75E7 2.52E6 Cs 134 7.23E10 1.35Eli 1.36E10 3.47E10 1.42E10 3.66E8 Cs 137 1.04El1 1.22E11 8.63E9 3.27E10 1.32E10 3.81E8 Ba 140 1.45E7 1.45E4 7.48E5 3.44E3 8.91E3 3.56E6 La 140 2.430 9.59E-1 2.47E-1 1.13E4 Ce 141 2.74E3 1.67E3 1.96E2 5.14E2 8.62E5 Ce 144 1.79E5 7.32E4 1.00E4 2.96E4 1.03E7 Nd 147 5.32E1 5.47E1 3.35E0 2.1 lEl 3.46E4 Ag 110m 2.95E7 2.15E7 1.43E7 3.07E7 1.11E9 "mrem/yr per 4Ci/m 3 .

Unit 2 Revision 22 II 49 December 2001

TABLE D 3-14 DOSE AND DOSE RATE Ri VALUES - GOAT MILK - CHILD m 2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 H3*

1.65E6 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 3.29E5 C 14" Cr 51 6.34E3 3.52E3 9.62E2 6.43E3 3.36E5 1.62E6 4.31 E5 4.54E5 1.36E6 Mn 54 9.06E5 4.81E5 1.49E5 2.72E5 8.91E4 Fe 55 Fe 59 8.52E5 1.38E6 6.86E5 3.99E5 1.43E6 Co 58 8.35E5 2.56E6 4.87E6 3.47E6 1.02E7 1.92E7 Co 60 3.15E8 8.40E8 5.23E8 5.29E8 1.48E8 Zn 65 Sr 89 7.77E9 2.22E8 3.01E8 1.58Ell 4.01E10 2.13E9 Sr 90 Zr 95 2.62E2 5.76E1 5.13E1 8.25E1 6.01E4 Nb 95 5.05E4 1.96E4 1.40E4 1.85E4 3.63E7 4.95E6 1.22E6 1.06E7 4.09E6 Mo 99 1 131 3.91E8 3.94E8 2.24E8 1.30E1I 6.46E8 3.50E7 1133 4.84E6 5.99E6 2.27E6 1.11E9 9.98E6 2.41E6 4.49E10 7.37E10 1.55E10 2.28E10 8.19E9 3.97E8 Cs 134 6.52E10 6.24E10 9.21E9 2.03E10 7.32E9 3.91E8 Cs 137 7.05E6 6.18E3 4.12E5 2.01E3 3.68E3 3.57E6 Ba 140 1.16 4.07E-1 1.37E-1 1.13E4 La 140 1.38E3 6.88E2 1.02E2 3.02E2 8.59E5 Ce 141 1.25E5 3.91E4 6.66E3 2.16E4 1.02E7 Ce 144 2.68E1 2.17E1 1.68E0 1.19E 1 3.44E4 Nd 147 1.60E7 1.08E7 8.60E6 2.00E7 1.28E9 Ag 110r

• mrem/yr per 1 ,Ci/m3.

Unit 2 Revision 22 II 50 December 2001

TABLE D 3-15 DOSE AND DOSE RATE R, VALUES - GOAT MILK - TEEN e:=-mre/y-r uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI

-TEEN RATE MILK DOSE AND

-GOAT TABLE uCi/sec DOSE VALUES Rl H3* 2.64E3 2.64E3 2.64E3 m2-mrem/yr 2.64E3 2.64E3 2.64E3 C 14* 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr 51 3.11E3 1.73E3 6.82E2 4.44E3 5.23E5 Mn 54 1.08E6 2.15E5 3.23E5 2.22E6 Fe 55 3.61E5 2.56E5 5.97E4 1.62E5 1.1 1E5 Fe 59 3.67E5 8.57E5 3.31 E5 2.70E5 2.03E6 Co 58 5.46E5 1.26E6 7.53E6 Co 60 2.23E6 5.03E6 2.91E7 Zn 65 1.61E8 5.58E8 2.60E8 3.57E8 2.36E8 Sr 89 3.14E9 8.99E7 3.74E8 Sr 90 9.36E10 2.31E1 0 2.63E9 Zr 95 1. 13E2 3.56E1 2.45E1 5.23E1 8.22E4 Nb 95 2.23E4 1.24E4 6.82E3 1.20E4 5.30E7 Mo 99 2.72E6 5.19E5 6.23E6 4.87E6 1 131 1.61E8 2.26E8 1.21E8 6.59E10 3.89E8 4.47E7 1 133 1.99E6 3.38E6 S1.03E6 4.72E8 5.93E6 2.56E6 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70E8 Cs 137 2.71E10 3.60E10 1.25E10 1.23E10 4.76E9 5.12E8 Ba 140 2.92E6 3.58E3 1.88E5 1.21E3 2.41E3 4.50E6 La 140 4.86E-1 2.39E-1 6.36E-2 1.37E4 Ce 141 5.60E2 3.74E2 4.30E1 1.76E2 1.07E6 Ce 144 5.06E4 2.09E4 2.72E3 1.25E4 1.27E7 Nd 147 1.09E1 1. 19E1 7.13E-1 6.99E0 4.29E4 Ag 110m 7.36E6 6.96E6 4.24E6 1.33E7 1.96E9 "mrem/yr per ýtCi/m 3.

Unit 2 Revision 22 II 51 December 2001

TABLE D 3-16 DOSE AND DOSE RATE Ri VALUES - GOAT MILK - ADULT m 2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3" 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 2.03E3 C 14* 3.63E5 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.78E3 1.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50E5 1.24E5 1.93E5 1.99E6 Fe 55 2.04E5 1.41E5 3.28E4 7.85E4 8.07E4 Fe 59 2.10E5 4.95E5 1.90E5 1.38E5 1.65E6 Co 58 3.25E5 7.27E5 6.58E6 Co 60 1.32E6 2.91E6 2.48E7 Zn 65 1.05E8 3.33E8 1.51E8 2.23E8 2.10E8 Sr 89 1.70E9 4.89E7 2.73E8 Sr 90 6.62E10 1.63E10 1.91E9 Zr 95 6.45E1 2.07E1 1.40E1 3.25E1 6.56E4 Nb 95 1.31E4 7.29E3 3.92E3 7.2 1E3 4.42E7 Mo 99 1.51E6 2.87E5 3.41E6 3.49E6 1 131 8.89E7 1.27E8 7.29E7 4.17E10 2.18E8 3.36E7 1 133 1.09E6 1.90E6 5.79E5 2.79E8 3.31 E6 1.71E6 Cs 134 1.12E10 2.67E10 2.18E10 8.63E9 2.86E9 4.67E8 Cs 137 1.49E10 2.04E10 1.34E10 6.93E9 2.30E9 3.95E8 Ba 140 1.62E6 2.03E3 1.06E5 6.9 1E2 1. 16E3 3.33E6 La 140 2.71E-1 1.36E-1 3.61E-2 1.00E4 Ce 141 3.06E2 2.07E2 2.34E1 9.60E1 7.90E5 Ce 144 2.75E4 1. 15E4 1.48E3 6.82E3 9.30E6 Nd 147 5.69E0 6.57E0 3.93E-1 3.84E0 3.15E4 Ag 110m 4.45E6 4.12E6 2.45E6 8.09E6 1.68E9

• mrem/yr per JLCi/m 3.

Unit 2 Revision 22 II 52 December 2001

TABLE D 3-17 DOSE AND DOSE RATE R, VALUES - COW MEAT - CHILD m 2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 2.34E2 5.29E5 1.06E5 1.06E5 1.06E5 1.06E5 1.06E5 1.06E5 C 14*

4.55E3 2.52E3 6.90E2 4.61E3 2.41E5 Cr 51 Mn 54 5.15E6 1.37E6 1.44E6 4.32E6 2.89E8 1.53E8 4.74E7 8.66E7 2.84E7 Fe 55 2.04E8 3.30E8 1.65E8 9.58E7 3.44E8 Fe 59 9.41E6 2.88E7 5.49E7 Co 58 4.64E7 1.37E8 2.57E8 Co 60 2.38E8 6.35E8 3.95E8 4.00E8 1. 12E8 Zn 65 2.65E8 7.57E6 1.03E7 Sr 89 7.01E9 1.78E9 9.44E7 Sr 90 1.51E6 3.32E5 2.95E5 4.75E5 3.46E8 Zr 95

4. 10E6 1.59E6 1.14E6 1.50E6 2.95E9 Nb 95 5.42E4 1.34E4 1.16E5 4.48E4 Mo 99 4.15E6 4.18E6 2.37E6 1.38E9 6.86E6 3.72E5 1 131 9.38E-2 1.16E-1 4.39E-2 2.15E1 1.93E-1 4.67E-2 1133 6.09E8 1.00E9 2.11E8 3. 1OE8 1.1 1E8 5.39E6 Cs 134 8.99E8 8.60E8 1.27E8 2.80E8 1.01E8 5.39E6 Cs 137 2.20E7 1.93E4 1.28E6 6.27E3 1.15E4 1.1 1E7 Ba 140 2.80E-2 9.78E-3 3.30E-3 2.73E2 La 140

1. 17E4 5.82E3 8.64E2 2.55E3 7.26E6 Ce 141 1.48E6 4.65E5 7.91E4 2.57E5 1.21E8 Ce 144 5.93E3 4.80E3 3.72E2 2.64E3 7.61E6 Nd 147 5.62E6 3.79E6 3.03E6 7.05E6 4.52E8 Ag 110m

• mrem/yr per ý Ci/m 3.

Unit 2 Revision 22 II 53 December 2001

TABLE D 3-18 DOSE AND DOSE RATE Rj VALUES - 2COW MEAT - TEEN m -mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 1.94E2 C 14" 2.8 1E5 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 5.62E4 Cr 51 2.93E3 1.62E3 6.39E2 4.16E3 4.90E5 Mn 54 4.50E6 8.93E5 1.34E6 9.24E6 Fe 55 1.50E8 1.07E8 2.49E7 6.77E7 4.62E7 Fe 59 1. 15E8 2.69E8 1.04E8 8.47E7 6.36E8 Co 58 8.05E6 1.86E7 1.11E8 Co 60 3.90E7 8.80E7 5.09E8 Zn 65 1.59E8 5.52E8 2.57E8 3.53E8 2.34E8 Sr 89 1.40E8 4.01E6 1.67E7 Sr 90 5.42E9 1.34E9 1.52E8 Zr 95 8.50E5 2.68E5 1.84E5 3.94E5 6.19E8 Nb 95 2.37E6 1.32E6 7.24E5 1.28E6 5.63E9 Mo 99 3.90E4 7.43E3 8.92E4 6.98E4 1131 2.24E6 3.13E6 1.68E6 9.15E8 5.40E6 6.20E5 1133 5.05E-2 8.57E-2 2.6 1E-2 1.20E1 1.50E-1 6.48E-2 Cs 134 3.46E8 8.13E8 3.77E8 2.58E8 9.87E7 1.01E7 Cs 137 4.88E8 6.49E8 2.26E8 2.21E8 8.58E7 9.24E6 Ba 140 1. 19E7 1.46E4 7.68E5 4.95E3 9.8 1E3 1.84E7 La 140 1.53E-2 7.51E-3 2.OOE-3 4.31 E2 Ce 141 6.19E3 4.14E3 4.75E2 1.95E3 1.18E7 Ce 144 7.87E5 3.26E5 4.23E4 1.94E5 1.98E8 Nd 147 3.16E3 3.44E3 2.06E2 2.02E3 1.24E7 Ag 110m 3.39E6 3.20E6 1.95E7 6.13E6 9.01E8

.mrem/yr per ý,Ci/m 3.

Unit 2 Revision 22 II 54 December 2001

TABLE D 3-19 DOSE AND DOSE RATE Ri VALUES - COW MEAT - ADULT m2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 3.25E2 3.25E2 3.25E2 3.25E2 3.25E2 3.25E2 C 14" 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr 51 3.65E3 2.18E3 8.03E2 4.84E3 9.17E5 Mn 54 5.90E6 1. 13E6 1.76E6 1.81E7 Fe 55 1.85E8 1.28E8 2.98E7 7.14E7 7.34E7 Fe 59 1.44E8 3.39E8 1.30E8 9.46E7 1.13E9 Co 58 1.04E7 2.34E7 2.12E8 Co 60 5.03E7 1.11E8 9.45E8 Zn 65 2.26E8 7.19E8 3.25E8 4.81E8 4.53E8 Sr 89 1.66E8 4.76E6 2.66E7 Sr 90 8.38E9 2.06E9 2.42E8 Zr 95 1.06E6 3.40E5 2.30E5 5.34E5 1.08E9 Nb 95 3.04E6 1.69E6 9.08E5 1.67E6 1.03E10 Mo 99 4.71 E4 8.97E3 1.07E5 1.09E5 1131 2.69E6 3.85E6 2.21E6 1.26E9 6.61E6 1.02E6 I 133 6.04E-2 1.05E-1 3.20E-2 1.54E1 1.83E-1 9.44E-2 Cs 134 4.35E8 1.03E9 8.45E8 3.35E8 1.11E8 1.81E7 Cs 137 5.88E8 8.04E8 5.26E8 2.73E8 9.07E7 1.56E7 Ba 140 1.44E7 1.81E4 9.44E5 6.15E3 1.04E4 2.97E7 La 140 1.86E-2 9.37E-3 2.48E-3 6.88E2 Ce 141 7.38E3 4.99E3 5.66E2 2.32E3 1.91E7 Ce 144 9.33E5 3.90E5 5.011E4 2.3 1E5 3.16E8 Nd 147 3.59E3 4.15E3 2.48E2 2.42E3 1.99E7 Ag 110m 4.48E6 4.14E6 2.46E6 8.13E6 1.69E9

.mrem/yr per ýLCi/m 3 .

Unit 2 Revision 22 1155 December 2001

TABLE D 3-20 DOSE AND DOSE RATE Ri VALUES - VEGETATION - CHILD m2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3* 4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 4.01E3 3.50E6 7.01E5 7.01E5 7.01E5 7.01E5 7.01E5 7.01E5 C 14" 1.17E5 6.49E4 1.77E4 1.18E5 6.20E6 Cr 51 6.65E8 1.77E8 1.86E8 5.58E8 Mn 54 7.63E8 4.05E8 1.25E8 2.29E8 7.50E7 Fe 55 3.97E8 6.42E8 3.20E8 1.86E8 6.69E8 Fe 59 6.45E7 1.97E8 3.76E8 Co 58 3.78E8 1. 12E9 2.10E9 Co 60 8.12E8 2.16E9 1.35E9 1.36E9 3.80E8 Zn 65 3.59E10 1.03E9 1.39E9 Sr 89 1.24E12 3.15Ell 1.67E10 Sr 90 3.86E6 8.50E5 7.56E5 1.22E6 8.86E8 Zr 95 1.02E6 3.99E5 2.85E5 3.75E5 7.37E8 Nb 95 7.70E6 1.91E6 1.65E7 6.37E6 Mo 99 7.16E7 7.20E7 4.09E7 2.38E10 1.18E8 6.41E6 1131 1.69E6 2.09E6 7.92E5 3.89E8 3.49E6 8.44E5 1 133 1.60E10 2.63E10 5.55E9 8.15E9 2.93E9 1.42E8 Cs 134 2.39E10 2.29E10 3.38E9 7.46E9 2.68E9 1.43E8 Cs 137 2.77E8 2.43E5 1.62E7 7.90E4 1.45E5 1.40E8 Ba 140 3.25E3 1. 13E3 3.83E2 3.16E7 La 140 6.56E5 3.27E5 4.85E4 1.43E5 4.08E8 Ce 141 1.27E8 3.98E7 6.78E6 2.21E7 1.04E10 Ce 144 7.23E4 5.86E4 4.54E3 3.22E4 9.28E7 Nd 147 3.21 E7 2.17E7 1.73E7 4.04E7 2.58E9 Ag 110m

• mrem/yr per ýLCi/m 3.

Unit 2 Revision 22 II 56 December 2001

TABLE D 3-21 DOSE AND DOSE RATE Ri VALUES - VEGETATION - TEEN m2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 2.59E3 2.59E3 2.59E3 2.59E3 LZ.YVIJ 2.9 1E5 2.91E5 2.91E5 2.91E5 2.9 1E5 2.9 1E5 C 14" 1.45E6 6.16E4 3.42E4 1.35E4 8.79E4 1.03E7 Cr 51 9.32E8 4.54E8 9.01E7 1.36E8 Mn 54 9.53E7 3.1 0E8 2.20E8 5.13E7 1.40E8 Fe 55 9.89E8 4.18E8 1.61E8 1.32E8 Fe 59 1.79E8 4.37E7 1.01E8 6.02E8 Co 58 3.24E9 Co 60 2.49E8 5.60E8 1.47E9 6.86E8 9.41E8 6.23E8

• Zn 65 4.24E8 4.33E8 1.80E9 Sr 89 1.51El0 1.85E11 2.11E1O Sr 90 7.51E11 5.44E5 3.74E5 7.99E5 1.26E9 Zr 95 1.72E6 2.66E5 1.46E5 2.58E5 1.14E9 Nb 95 4.80E5 5.64E6 1.08E6 1.29E7 1.01E7 Mo 99 1.07E7 3.85E7 5.39E7 2.89E7 1.57E10 9.28E7 1 131 1.19E6 9.29E5 1.58E6 4.80E5 2.20E8 2.76E6 1133 2.08E8 1.67E10 7.75E9 5.3 1E9 2.03E9 Cs 134 7. 10E9 1.35E10 4.69E9 4.59E9 1.78E9 1.92E8 Cs 137 1.01E10 1.69E5 8.91E6 5.74E4 1. 14E5 2.13E8 Ba 140 1.38E8 2.36E2 5.10E7 La 140 1.81E3 8.88E2 2.17E4 8.89E4 5.40E8 Ce 141 2.83E5 1.89E5 2.18E7 2.83E6 1.30E7 1.33E10 Ce 144 5.27E7 2.3863 2.34E4 1.44E8 Nd 147 3.66E4 3.98E4 8.72E6 2.74E7 4.03E9 Ag 110m 1.51E7 1.43E7

• mrem/yr per .tCi/m3 Unit 2 Revision 22 II 57 December 2001

TABLE D 3-22 DOSE AND DOSE RATE R1 VALUES - VEGETATION - ADULT m 2-mrem/yr uCi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3* 2.26E3 2.26E3 2.26E3 2.26E3 2.26E3 2.26E3 C 14' 8.97E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E5 1.79E5 Cr 51 4.64E4 2.77E4 1.02E4 6.15E4 1. 17E7 Mn 54 3.13E8 5.97E7 9.3 1E7 9.58E8 Fe 55 2.00E8 1.38E8 3.22E7 7.69E7 7.9 1E7 Fe 59 1.26E8 2.96E8 1.13E8 8.27E7 1.02E9 Co 58 3.08E7 6.90E7 6.24E8 Co 60 1.67E8 3.69E8 3.14E9 Zn 65 3.17E8 1.01E9, 4.56E8 6.75E8 6.36E8 Sr 89 9.96E9 2.86E8 1.60E9 Sr 90 6.05E11 1.48E1l 1.75E10 Zr 95 1.18E6 3.77E5 2.55E5 5.92E5 1.20E9 Nb 95 3.55E5 1.98E5 1.06E5 1.95E5 1.20E9 Mo 99 6.14E6 1.17E6 1.39E7 1.42E7 1131 4.04E7 5.78E7 3.31 E7 1.90E10 9.91E7 1.53E7 1 133 1.00E6 1.74E6 5.30E5 2.56E8 3.03E6 1.56E6 Cs 134 4.67E9 1.11El0 9.08E9 3.59E9 1. 19E9 1.94E8 Cs 137 6.36E9 8.70E9 5.70E9 2.95E9 9.8 1E8 1.68E8 Ba 140 1.29E8 1.61E5 8.42E6 5.49E4 9.25E4 2.65E8 La 140 1.98E3 9.97E2 2.63E2 7.32E7 Ce 141 1.97E5 1.33E5 1.51E4 6.19E4 5.09E8 Ce 144 3.29E7 1.38E7 1.77E6 8.16E6 1.11E10 Nd 147 3.36E4 3.88E4 2.32E3 2.27E4 1.86E8 Ag 110m 1.05E7 9.75E6 5.79E6 1.92E7 3.98E9

• mrem/yr per ptCi/m 3 Unit 2 Revision 22 II 58 December 2001

TABLE D 3-23 1

DISPERSION PARAMETERS AT CONTROLLING LOCATIONS X/Q,W, and W, VALUES DIRECTION DISTANCE (m) X/Q (sec/m 3)

VENT Site 2.00 E-6 1,600 2.1 OE-9 Boundary2 E Inhalation 1.42E-7 2.90E-9 1,800 and Ground E (1040)

Plane 4.1lE-8 4.73E-10 ESE (1300) 4,300 Cow Milk 3.56E-08 5.32E-10 3 SE (1400) 4,800 Goat Milk 1.17E-7 1.86E-9 E (1140) 2,600 Meat Animal 1.04E-7 1.50E-9 E (960) 2,900 Vegetation STACK Site 1,600 4.50E-8 2 E 6.OOE-9 Boundary Inhalation 1.34E-9 1,700 8.48E-9 and Ground E (109°)

Plane 4,200 1.05E-8 3.64E-10 Cow Milk ESE (1350) 3 4,800 2.90E-08 5.71E-10 Goat Milk SE (1400) 2,500 1.13E-8 1.15E-9 Meat Animal E (114°)

2,800 1.38E-8 9.42E-10 Vegetation E (96°)

season only.

NOTE: Inhalation and Ground Plane are annual average values. Others are grazing X/Q and D/Q values from NMP-2 ER-OLS.

2 X/Q and D/Q from NMP-2 FES, NUREG-1085, May 1985, Table D-2.

3 X/Q and DIQ from C.T. Main Data Report dated November 1985.

Unit222 Revision December 2001 II 59

TABLE D 3-24 MEMBERS PARAMETERS FOR THE EVALUATION OF DOSES TO REAL OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS Value Reference Pathway Parameter 21 Reg. Guide 1.109 Fish U (kg/yr) - adult Table E-5 Reg. Guide 1.109 Daipi (mrem/pCi) Each Radionuclide Table E-1 1 Fish Shoreline U (hr/yr)

- adult 67 Reg. Guide 1.109 67 Assumed to be Same as Adult

- teen Each Radionuclide Reg.Table GuideE-6 1.109 Shoreline Dalpi (mrem/hr per pCi/mý)

Reg. Guide 1.109 Inhalation DFAija Each Radionuclide Table E-7 Unit22 2

Revision December 2001 1160

TABLE D 5.1 NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site Location Location (Env. Program No.)

Type of Sample 1.8 mi@ 88'E Radio iodine and I Nine Mile Point Road North (R-1)

Particulates (air) 1.1 mi @ 104' ESE Radioiodine and 2 County Route 29 & Lake Road Particulates (air) (R-2) 1.5 mi @ 132" SE Radioiodine and 3 County Route 29 Particulates (air) (R-3) 1.8 mi @ 143' SE Radioiodine and 4 Village of Lycoming, NY (R-4)

Particulates (air) 16.4 mi @ 42" NE Radioiodine and 5 Montario Point Road (R-5)

Particulates (air) 0.1 mi@ 5' N 6 North Shoreline Area Direct Radiation (TLD)

(75) 0.1 mi @ 25* NNE Direct Radiation (TLD) 7 North Shoreline Area (76) 0.2 mi @ 45' NE 8 North Shoreline Area Direct Radiation (TLD)

(77) 0.8 mi @ 70" ENE Direct Radiation (TLD) 9 North Shoreline Area (23) 1.0 mi @ 90' E Direct Radiation (TLD) 10 JAF East Boundary (78) 1.1 mi@ 115" SE Direct Radiation (TLD) 11 Route 29 (79) 1.4 mi @ 133" SE 12 Route 29 Direct Radiation (TLD)

(80) 1.6 mi @ 159" SSE 13 Miner Road Direct Radiation (TLD)

(81) 1.6 mi@ 181'S 14 Miner Road Direct Radiation (TLD)

(82) 1.2 mi @ 200' SSW Direct Radiation (TLD) 15 Lakeview Road (83) 1.1 mi @ 225" SW 16 Lakeview Road Direct Radiation (TLD)

(84) 0.7 mi @ 250' WSW 17 Site Meteorological Tower Direct Radiation (TLD)

(7) 0.4 mi @ 265" W 18 Energy Information Center Direct Radiation (TLD)

(18) 0.2 mi @ 294' WNW 19 North Shoreline Direct Radiation (TLD)

(85)

• Map = See Fig ures D 5.1-1 and D 5.1-2.

Unit 2 Revision 22 1161 December 2001

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site (Env. Program No.) Location Type of Sample Location 20 North Shoreline 0.1 mi @ 315' NW Direct Radiation (TLD)

(86) 21 North Shoreline 0.1 mi @ 341" NNW Direct Radiation (TLD)

(87) 22 Hickory Grove 4.5 mi @ 97" E Direct Radiation (TLD)

(88) 23 Leavitt Road 4.1 mi@ 111 ESE Direct Radiation (TLD)

(89)

Route 104 4.2 mi @ 135" SE Direct Radiation (TLD) 24 (90) 25 Route 51A 4.8 mi @ 156" SSE Direct Radiation (TLD)

(91)

Maiden Lane Road 4.4 mi @ 183' S Direct Radiation (TLD) 26 (92) 27 County Route 53 4.4 mi @ 205 SSW Direct Radiation (TLD)

(93) 28 County Route I 4.7 mi @ 223 SW Direct Radiation (TLD)

(94)

Lake Shoreline 4.1 mi @ 237" WSW Direct Radiation (TLD) 29 (95)

Phoenix, NY Control 19.8 mi @ 163" S Direct Radiation (TLD) 30 (49) 12.6 mi @ 226" SW Direct Radiation (TLD) 31 S. W. Oswego, Control (14) 32 Scriba, NY 3.6 mi @ 199" SSW Direct Radiation (TLD)

(96) 3.1 mi @ 220" SW Direct Radiation (TLD) 33 Alcan Aluminum, Route 1A (58) 1.8 mi @ 143" SE Direct Radiation (TLD) 34 Lycoming, NY (97) 5.3 mi @ 123" ESE Direct Radiation (TLD) 35 New Haven, NY (56)

W. Boundary, Bible Camp 0.9 mi @ 237 WSW Direct Radiation (TLD) 36 (15)

Lake Road 1.2 mi @ 101" E Direct Radiation (TLD) 37 (98)

• Map = See Figures D 5.1-1 and D 5.1-2.

Unit 2 Revision 22 II 62 December 2001

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site Location Type of Sample Location (Env. Program No.)

7.6 mi @ 235 SW Surface Water 38 OSS Inlet Canal (NA) 0.5 mi @ 70" ENE Surface Water 39 JAFNPP Inlet Canal (NA) 1.5 mi @ 80" E Shoreline Sediment 40 Sunset Bay Shoreline (NA) 0.3 mi @ 315" NW Fish 41 NMP Site Discharge Area (NA)

(and/or) 0.6 mi @ 55 NE Fish 42 NMP Site Discharge Area (NA) 6.2 mi @ 235 SW Fish 43 Oswego Harbor Area (NA) 8.2 mi @ 93" E Milk 44 Milk Location #50 9.0 mi @ 95" E I Milk 64 Milk Location #55 9.5 mi @ 90 E Milk 65 Milk Location #60 7.8 mi @ 113 ESE Milk 66 Milk Location #4 13.9 mi @ 191' SSW Milk (CR) 77 Milk Location (Summerville) 1.9 mi @ 141' SE Food Product 48 Produce Location #6**

(Bergenstock) (NA) 1.7 mi @ 96" E Food Product 49 Produce Location #I**

(Culeton) (NA) 1.9mi@ 101 E Food Product 50 Produce Location #2**

(Vitullo) (NA) 1.5 mi@ 114 ESE Food Product 51 Produce Location #5"*

(C.S. Parkhurst) (NA) 1.6 mi @ 84" E Food Product 52 Produce Location #3**

(C. Narewski) (NA)

• Map See Figures D 5.1-1 and D 5.1-2.

highest calculated Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the site average D/Q.

(NA) Not applicable.

CR Control Result (location).

Unit 2 Revision 22 II 63 December 2001

TABLE D 5.1 (Cont'd)

NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS

• Map Collection Site Type of Sample Location (Env. Program No.) Location Food Product 53 Produce Location #4** 2.1 mi@ 1100 ESE (P. Parkhurst) (NA)

Food Product (CR) 54 Produce Location #7** 15.0 mi @ 2230 SW (Mc Millen) (NA)

Food Product (CR) 55 Produce Location #8** 12.6 mi @ 2250 SW (Denman) (NA)

Food Product 56 Produce Location #9** 1.6 mi @ 1710 S (O'Connor) (NA)

Food Product 57 Produce Location #10"* 2.2 mi @ 1230 ESE (C. Lawton) (NA) 58 Produce Location # 11* 2.0 mi @ 1120 ESE Food Product (C. R. Parkhurst) (NA)

Food Product 59 Produce Location # 12* 1.9 mi @ 1150 ESE (Barton) (NA)

Food Product (CR) 60 Produce Location #13** 15.6 mi @ 2250 W (Flack) (NA) 61 Produce Location #14** 1.9 mi @ 950 E Food Product (Koeneke) (NA)

Food Product 62 Produce Location #15** 1.7 mi @ 1360 SE (Whaley) (NA)

Food Product 63 Produce Location #16** 1.2 mi @ 2070 SSW:

(Murray) (NA) 67 Produce Location #17** 1.76 mi @ 970 E Food Product (Battles) (NA)

• Map = See Figures D 5.1-1 and D 5.1-2.

• • = Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.

(NA) = Not applicable.

CR = Control Result (location).

Unit 2 Revision 22 II 64 December 2001

APPENDIX A LIQUID DOSE FACTOR DERIVATION Unit 2 Revision 22 1165 December 2001

Appendix A Liquid Effluent Dose Factor Derivation, Aiat Aiat (mrem/hr per uCi/ml) which embodies the dose conversion factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water and the sediment. The total body and organ dose conversion factors for each radionuclide will be used from Table E- 11 of Regulatory Guide 1.109. To expedite time, the dose is calculated for a maximum individual instead of each age group. The maximum individual dose factor is a composite of the highest dose factor Aiat of each nuclide i age group a, and organ t, hence Aiat. It should be noted that the fish ingestion pathway is the most significant pathway for dose from liquid effluents. The water consumption pathway is included for consistency with NUREG 0133.

The equation for calculating dose contributions given in section 1.3 requires the use of the composite dose factor Al, for each nuclide, i. The dose factor equation for a fresh water site is:

- 69.3U W e-'*'*

A K, UW e-e " +U BFi e-'* DFL,,,-+ U3D 1-e-' )DFSi Where:

Ajat Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per uCi/ml)

K. Is the unit conversion factor, 1. 14E5 = 1E6pCi/uCi x 1E3 ml/liter 8760 hr/yr U= Water consumption (liters/yr); from Table E-5 of Reg. Guide 1.109 U= Fish consumption (kg/yr); from Table E-5 of Reg. Guide 1.109 U, Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg. Guide 1.109 BFi Bioaccumulation factor for nuclide, i, in fish, (pCi/kg per pCi/liter),

from Table A-I of Reg. Guide 1.109 DFLiat Dose conversion factor for age, nuclide, i, group a, total body or organ t, (mrem/pCi); from Table E- 11 of Reg. Guide 1.109 DFSj = Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mrem/hr per pCi/m2 ); from Table E-6 of Reg.

Guide 1.109 Unit 2 Revision 22 1I 66 December 2001

Appendix A (Cont'd)

D, Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitan Water Board, Onondaga County intake structure located west of the City of Oswego.

(Unitless)

D= Dilution factor from the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles; unitless) 2 69.3 = conversion factor .693 x 100, 100 = K, (liters/kg-hr)*40 kg/m *24 hr/day/.693 in liters/m 2 -d, and K, = transfer coefficient from water to sediment in liters/kg per hour.

tpw, tpf, Average transit time required for each nuclide to reach the tp., point of exposure for internal dose, it is the total time elapsed from release of the nuclides to either ingestion for water (w) and fish (f) or shoreline deposit (s), (hr) tb = Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life),

(hrs).

i decay constant for nuclide i (hrl1)

W = Shore width factor (unitless) from Table A-2 of Reg. Guide 1.109 Example Calculation For 1-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release:

(DFS)i = 2.80E-9 mrem/hr per pCi/m2 (DFL)iat = 1.95E-3 mrem/pCi tw = 40 hrs. (w = water)

BFj = 15 pCi/kg per pCi/liter tf = 24 hrs. (f = fish)

Uf = 21 kg/yr tb = 1.314E5 hr (5.48E3 days)

Dw = 62 unitless U, = 730 liters/yr DS = 17.8 unitless Ko = 1.14E5 (pCi/uCi)(ml/kg)

Us = 12 hr/yr (hr/yr)

W = 0.3 Xi = 3.61E-3hr' tpS = 7.3 hrs (s =Shoreline Sediment)

These values will yield an Aia, Factor of 6.65E4 mrem-ml per uCi-hr as listed in Table D 2-2. It should be noted that only a limited number of nuclides are listed on Tables D 2-2 to D 2-5. These are the most common nuclides encountered in effluents. If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.

In addition, not all dose factors are used for the dose calculations. A maximum individual is used, which is a composite of the maximum dose factor of each age group for each organ as reflected in the applicable chemistry procedures.

Unit 2 Revision 22 II 67 December 2001

APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION Unit 2 Revision 22 II 68 December 2001

Appendix B For elevated releases the plume shine dose factors for gamma air (Bi) and whole body (Vi), are calculated using the finite plume model with an elevation above ground equal to the stack height. To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is adjusted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air. The equations are as follows:

Gamma Air Bi = ýsaE Is Where: K1 conversion factor (see S RO V* below for actual value).

- mass absorption coefficient (cm 2 /g; air for B,, tissue for Vi)

E Energy of gamma ray per disintegration (Mev)

VS average wind speed for each stability class (s), rns R = downwind distance (site boundary, m)

E = sector width (radians) s = subscript for stability class I = I function = I, + k12 for each stability class. (unitless, see Regulatory Guide 1.109) k = Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)

Whole Body

- ltatg Vi = 1.1ISFBie Where: td = tissue depth (g/cm2 )

SF = shielding factor from structures (unitless) 1.11 Ratio of mass absorption coefficients between tissue and air.

Where all other parameters are defined above.

Unit 2 Revision 22 II 69 December 2001

Appendix B (Cont'd)

'K = conversion factor 3.7 El0 dis 1.6 E-6 erg Ci-sec Mev = .46 1293 g 100 erg m3 g-rad iLa Where: IL mass attenuation coefficient (cm 2/g; air for Bi, tissue for V1 )

i = defined above There are seven stability classes, A thru F. The percentage of the year that each stability class is taken from the U-2 FSAR. From this data, a plume shine dose factor is calculated for each stability class and each nuclide, multiplied by its respective fraction and then summed.

The wind speeds corresponding to each stability class are, also, taken from the Unit 2 FSAR.

To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values. The average wind speed of the actual data is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.

The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide. These energies were taken from the handbook "Radioactive Decay Data Tables", David C. Kocher.

The mass absorption (11a) and attenuation (pi) coefficients were calculated by multiplying the mass absorption (a!/p) and mass attenuation (1/0p) coefficients given in the Radiation Health Handbook by the air density equal to 1.293 E-3 g/cc or the tissue density of 1 g/cc where 2

applicable. The tissue depth is 5g/cm for the whole body.

The downwind distance is the site boundary.

SAMPLE CALCULATION Ex. Kr-89 F STABILITY CLASS ONLY - Gamma Air

-DATA E = 2.2 2MeV k = .871 K = .46 VF = 5.55 m/sec

[La - 2.943 E-3m-1 [la 1 R 1600m

[= 5.5064E-3m- =

e = .39

= 19m vertical plume spread taken from "Introduction to Nuclear Engineering", John R. LaMarsh Unit 2 Revision 22 II 70 December 2001

Appendix B (Cont'd)

-I Function Uaz .11 I1 .3 I2 .4 1

11 + k12 = .3 + (.871) (.4) = .65 dis.

0.46 [Ci-sec) (Mev/ergs] (2. 943E-3m-1 ) (2.22Mev) (. 65) 3 (R/2 [ (g/m ) (ergs) (5.55 m/s) (.39) (1600m)

(g-rad)

= 3.18(-7) rad/s (3600 s/hr) (24 h/d) (365 d/y) (iE3mrad/rad)

Ci/s (lE6uCi)

Ci 1.00(-2) mrad/yr uCi sec 2

-(.0253 cm2 /g) (5g/cm )

Vi 1.1i (.7) (1E-2) mrad/yr [e pCi/sec]

6.85(-3) mrad/yr PCi/sec Note: The above calculation is for the F stability class only. For Table D 3-2 and procedure values, a weighted fraction of each stability class was used to determine the Bi and Vi values.,

Unit 2 Revision 22 1171 December 2001

APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM Unit 2 Revision 22 II 72 December 2001

Appendix C DOSE PARAMETERS FOR IODINE - 131 AND - 133, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the organ dose factors for 1-131, 1-133, particulates, and tritium. The dose factor, R-, was calculated using the methodology outlined in NUREG-0133. The radioiodine and particulate DLCO 3.2.1 is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor. Washout was calculated and determined to be negligible. R, values have been calculated for the adult, teen, child and infant age groups for all pathways. However, for dose compliance calculations, a maximum individual is assumed that is a composite of highest dose factor of each age group for each organ and pathway. The methodology used to calculate these values follows:

C. 1 Inhalation Pathway Ri(I) = K'(BR)a(DFA)ija where:

R,(I) dose factor for each identified radionuclide i of the organ of interest (units = mrem/yr per uCi/m 3 );

K' - a constant of unit conversion, 1E6 pCi/ýtCi (BR)a = Breathing rate of the receptor of age group a, (units = m3/yr);

(DFA)ija The inhalation dose factor for nuclide i, organ j and age group a, and organ t (units = mrem/pCi).

The breathing rates (BR), for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.

Age Group (a) Breathing Rate (m 3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFA)ija for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.

Unit 2 Revision 22 II 73 December 2001

Appendix C (Cont'd)

C.2 Ground Plane Pathway

-Lit Ri(G)= K'K (SF) (DFG)i (1-e Where:

Rj(G) = Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units = m2-mrem/yr per uCi/sec)

K' = A constant of unit conversion, 1E6 pCi/uCi K" = A constant of unit conversion, 8760 hr/year S= The radiological decay constant for radionuclide i, (units = sec-)

t - The exposure time, sec, 4.73E8 sec (15 years)

(DFG)i = The ground plane dose conversion factor for radionuclide i; (units =

mrem/hr per pCi/mr)

SF = The shielding factor (dimensionless)

A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision

1. A tabulation of DFGj values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.

Unit 2 Revision 22 II 74 December 2001

Appendix C (Cont'd)

C. 3 Grass-(Cow or Goat)-Milk Pathway

-Aith -Xitf Ri(C) K'Qf(Uap) F. (r) (DFL)iat [fPf s + (1-fpf.) (e ) ]e (Xi + X.) YP [ Y. J Where:

Rj(C) Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, (units = m2-mrem/yr per uCi/sec)

K' = A constant of unit conversion, 1E6 pCi/ýtCi Q= The cow's or goat's feed consumption rate, (units = kg/day-wet weight)

Uap The receptor's milk consumption rate for age group a, (units = liters/yr) y= The agricultural productivity by unit area of pasture feed grass, (units = kg/m2)

Y= The agricultural productivity by unit area of stored feed, (units = kg/m2)

Fm = The stable element transfer coefficients, (units = pCi/liter per pCi/day) r = Fraction of deposited activity retained on cow's feed grass (DFL)iat = The ingestion dose factor for nuclide i, age group a, and total body or organ t (units = mrem/pCi)

The radiological decay constant for radionuclide i, (units=sec -1)

- The decay constant for removal of activity on leaf and plant surfaces by weathering, equal to 5.73E-7 sec -1 (corresponding to a 14 day half-life) tf= The transport time from pasture to cow or goat, to milk, to receptor, (units = sec) th = The transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units = sec) fP= Fraction of the year that the cow or goat is on pasture (dimensionless) f= Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless)

Unit 2 Revision 22 II 75 December 2001

Appendix C (Cont'd)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of

f. is considered unity in lieu of site specific information. The value of fp is 0.5 based on 6 month grazing period. This value for fP was obtained from the environmental group.

Table C-1 contains the appropriate values and their source in Regulatory Guide 1.109 Revision 1.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RT(C) is based on X/Q:

RT(C) = K'K'" FmQfUap(DFL)iac 0.75(0.5/H)

Where:

RT(C) - Dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units = mrem/yr per ýtCi/m 3 )

K" = A constant of unit conversion, 1E3 g/kg 3

H = Absolute humidity of the atmosphere, (units = g/m )

0.75 = The fraction of total feed that is water 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water 3

Other values are given previously. A site specific value of H equal to 6.14 g/m is used.

This value was obtained from the environmental group using actual site data.

Unit 2 Revision 22 II 76 December 2001

Appendix C (Cont'd)

C.4 Grass-Cow-Meat Pathway I(C) = KQfU.PFf(r)DFLa, f[f, +(1- fpf,)e-] e_&tf (R+A.w) YEY Ri(M) Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units = m'-mrem/yr per ýtCi/sec)

Ff = The stable element transfer coefficients, (units = pCi/kg per pCi/day)

Uap = The receptor's meat consumption rate for age group a, (units = kg/year) th = The transport time from harvest, to cow, to receptor, (units = sec) tf The transport time from pasture, to cow, to receptor, (units = sec)

All other terms remain the same as defined for the milk pathway. Table C-2 contains the values which were used in calculating Ri(M).

The concentration of tritium in meat is based on airborne concentration rather than deposition.

Therefore, the RT(M) is based on X/Q.

RT(M) = K'K' "FfQfUap(DFL)Qat [0.75(0.5/H)]

Where:

RT(M) = Dose factor for the meat ingestion pathway for tritium for any organ of interest, (units = mrem/yr per *Ci/m 3)

All other terms are defined above.

C.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed for milk. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:

-litL -- Xith Ri(V) = K' r (DFL)iat[ ULaFLe + USaFge Y, (Xi + X.)

Unit 2 Revision 22 1177 December 2001

Appendix C (Cont'd)

Where:

Rj(V) Dose factor for vegetable pathway for radionuclide i for the organ of interest, (units = m2-mrem/yr per 1aCi/sec)

K' = A constant of unit conversion, 1E6 pCi/lCi ULa = The consumption rate of fresh leafy vegetation by the receptor in age group a, (units = kg/yr)

Usa The consumption rate of stored vegetation by the receptor in age group a (units = kg/yr)

FL = The fraction of the annual intake of fresh leafy vegetation grown locally Fg = The fraction of the annual intake of stored vegetation grown locally tL = The average time between harvest of leafy vegetation and its consumption, (units = sec) th = The average time between harvest of stored vegetation and its consumption, (units = sec)

Y= The vegetation areal P density, (units = kg/m 2)

All other factors have been defined previously.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.

In lieu of site-specific data, values for FL and Fg of, 1.0 and 0.76, respectively, were used in the calculation. These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the RT(V) is based on X/Q:

RT(V) = K'K" [ULa fL + USa fg](DFL)iat 0.75(0.5/H)

Where:

RT(V) dose factor for the vegetable pathway for tritium for any organ of interest, (units = mrem/yr per gCi/m3).

All other terms are defined in preceeding sections.

Unit 2 Revision 22 1178 December 2001

TABLE C-1 Parameters for Grass - (Cow or Goat) - Milk Pathways Reference Parameter Value (Reg. Guide 1.109 Rev. 1)

Qf (kg/day) 50 (cow) Table E-3 6 (goat) Table E-3 r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL)ija (mrem/ pCi) Each radionuclide Tables E-11 to E-14 Fm (pCi/liter pe r pCi/day) Each stable element Table E-1 (cow)

Table E-2 (goat)

Y, (kg/M 2) 2.0 Table E-15 Yp (kg/m2) 0.7 Table E- 15 th (seconds) 7.78 x 106 (90 days) Table E-15 tf (seconds) 1.73 x 10' (2 days) Table E-15 Uap (liters/yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 Unit 2 Revision 22 I 79 December 2001

TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Reference Value (Reg. Guide 1.109 Rev. 1)

Parameter 1.0 (radioiodines) Table E-15 r Table E-15 0.2 (particulates)

Each stable element Table E-1 Ff (pCi/kg per pCi/day) 0 infant Table E-5 Uap (kg/yr) Table E-5 41 child 65 teen Table E-5 110 adult Table E-5 Each radionuclide Tables E-11 to E-14 (DFL)ija (mrem/pCi) 0.7 Table E-15 Yp (kg/m 2 )

2.0 Table E-15 Y, (kg/m 2) 7.78E6 (90 days) Table E-15 th (seconds) 1.73E6 (20 days) Table E-15 tf (seconds) 50 Table E-3 Qf (kg/day)

Unit 2 Revision 22 December 2001 1180

TABLE C-3 Parameters for the Vegetable Pathway Reference Parameter Value (Reg. Guide 1.109 Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-I 0.2 (particulates) Table E-1 (DFL)ija (mrem/pCi) Each radionuclide Tables E-11 to E-14 UL)a (kg/yr) - infant 0 Table E-5

- child 26 Table E-5

- teen 42 Table E-5

- adult 64 Table E-5 US)a (kg/yr) - infant 0 Table E-5

- child 520 Table E-5

- teen 630 Table E-5

- adult 520 Table E-5 tL (seconds) 8.6E4 (1 day) Table E-15 th (seconds) 5.18E6 (60 days) Table E-15 yv (kg/m 2) 2.0 Table E-15 Unit 2 Revision 22 II 81 December 2001

APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMS AND MONITORING SYSTEMS Unit 2 Revision 22 December 2001 II 82

Liquid Radwaste Treatment System Diagrams Unit 2 Revision 22 1I 83 December 2001

SPENT FUEL POOL COOLING THERMEX SYSTEM RADWASTE DEMINERALIZER REACTOR WATER CLEANUP SYSTEM REGENERANT EVAPORATOR'"

CONDENSATE DEMINERALIZERS REACTOR BUILDING EQUIPMENT DRAINS PHASE SEPARATOR RECOVERY, SAMPLE TANKS' TURBINE BLDGC EQUIPMENT DRAINS RESIDUAL HEAT, REMOVAL SYSTEM' RECOVERY SAMPLE SYSTEM

. RADWASTE FILTERS FLOOR DRAIIN FILTER RADWASTE FILTERS WASTE COLLECTION 1184

AIR SPENT RESIN TK 16 AIR TYPICAL OF 2 RECVR A .1 TAW rA&6" TO/FROM CONIDES FLOOR DRAIN DEMIRS COLLECTOR TKS TO OTHER 4 WASTE OISCli DEMIN SAMPLE TKS WASTE COLL SUR6E TAWK I AOV51 FVY7 WASTE CCOL I PumpsP FLOOR DmX COLL PUMPS K2 S Tp DEMI WASTE COLLECTOR TOOTHER SURK P"r DEMIH TYPICAL OF 2 CONDENSATE "TRANSFER SPENT RESIN L TAWK TK REGEHERANT WASTE TANKS SLULOE TANK DEMIN WASTE COLLECTOR TREATMENT SYSTEM II 85

REGENCOOLER DIST EVAP TYPICAL OF2 I- --L:-- - - - - -

OTHER PS RICIRC LINE LAOV279_ EVAP REGEN RECOVERY SAMPLE SYSTEM and WASTE DISCHARGE SAMPLE SYSTEM II 86

FLOOR DRAIN COLLECTION SYSTEM II 87

• FFV 122 WASTE COLLECTOR SURGE TANK AFE30 INSTRUMENT FLOOR DRAIN AIR COLLECTOR COND. MAKEUP SURGE TANK AND DRAW OFF FLOOR DRAIN COLLECTOR TANKS REGEN. WASTE TANKS WASTE COLLECTOR SLUDGE TANK TANKS AOV214 REGEN. WASTE TANK AOV 127 WASTE DISCH.

SAMPLE TANK AOV123 FLOOR DRAIN COLLECTOR'TANK 1 AOV126 CLT STANK COLLECTO R:

WASTE FLOOR DRAIN FILTER SYSTEM 1188

THERMEX TYPICAL OF 2 SYSTEM COND DEMIN' I

I I .

AO V3 K II^ Il BACK TX 3 T3A0V69 = $I REGENERANT TANK OTHER I WASTE SREGEN EVAP 4 "

.wTHERMEX SYSTEM AOV93 i

-- - - -- - - -- - - -- - - - J REGENERANT WASTE SYSTEM 1189

TANKS FLOOR DRAIN AV 187 COLL. TANKS

- WASTE DISCH AOV14 7 SAMPLE TANKS REGENERANT EVAPORATOR SY!STEM 1190

Gaseous Treatment System Diagrams Unit 2 Revision 22 1191 December 2001

TO OFFGAS.

soy iI I SYSTEM 1192

TODAYEIIS FROM AUXLIAnY PVT7 8 STEAM SYSTEM 1193

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4 FROM OFFOAS DRYERS To Main Stack

Title:

OFFGAS SYSTEM 1195 CHARCOAL ABSORBERS

OUTSDE'AIR

Title:

STANDBY GAS 1196 TREATMENT SYSTEM

Liquid Radiation Monitoring Diagrams Unit 2 Revision 22 1197 December 2001

FROM MWSSYSTEM OARSERVICE RATER(A)

RIR SERVICERATER(8) -

FROMARR HEATEX. EIA.

FROMCC? BEATEX.EIA,IO.IC FROMOAI HEATEX,EID.

FROMCCSHEATEX.EIA.IM.IC.

FROMSJAE PRECOOLERS E2A,28.

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a

( GLOBE VALVE. ALL OTHER MANUALLY OPERATED VALVES ARE BALL VALVES CALIBRATION/DRAIN OFFLINE LIOUID MONITOR CONNECTION 2CCP-CABII5 2CCS-CABI52 LEGEND 2CWS-CAS157 O PRESSURE INDICATOR FLOW INOICATING SW.

SOLENOID OPERATED SW.

pr4 NORMALLY CLOSED VALVE NORMALLY OPEN VALVE OFF-LINE LIQUID MONITOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT L___ __v 1D-1-UT- 3 OCTOBER 199r 0Q

• a*=*.,, v . -

TT Go

I E4----FLOW PURGE/TEEST SAMPLE INLET CONNECT ION P LOW FLOW DATA ACQUISITION UNIT (OAU)

DETECTOR-J I CHECK SOURCE I I I PURGE CONTROL GRAB SAMPLER PUMP CONTROL KA KI r- KA & A I I CALIBRATION/DRAIN OFFLINE LIQUID MONITOR CONNECTION CALIBRATION TEST/

VENT CONNECTION 2LWS-CAB206 NOTES LEGEND (II GLOBE VALVE, ALL OTHER MANUALLY OPERATED VALVES ARE BALL VALVES O PRESSURE INDICATOR Q FLOW INDICATING SW.

S] SOLENOID OPERATED SW.

NORMALLY CLOSED VALVE N NORMALLY OPEN VALVE OFF-LINE LIQUID MONITOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 UPDATED SAFETY ANALYSIS REPORT

-- ADOTI i

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USARDT XLIQIN ~f.,

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I LOW FLOW/NORIMAL FLOW I112 FLOW FS SAMPLE SAMPLE I OUTLET

-i INLET t DATA ACOUISITION UNIT (DALU)

I I I I I I. I I GRIAB Iu SAMPLE tPURGE PUMP CONTROL rIi =

NOTES a GLOBE VALVE. ALL OTHER MANUALLY OPERATED VALVES CALIBRATION TEST/ ARE BALL VALVES VENT CONNECTION CALIBRATION/DRAIN OFFLINE LIOUID MONITOR CONNECTION 2SWPoCABZ3A 2SWPCAS238 LEGEND 2SWP*CAB146A 2SWP*CAB1468 S-i: PRESSURE INDICATOR O FLOW SW.

MS SOLENOID OPERATED SW.

NORMALLY CLOSED VALVE N NORMALLY OPEN VALVE OFF-LINE LIQUID MONITOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 TI fl IjPATFFI- qAFFTY ANAl Yr1S RFPf'RT

Gaseous Effluent Monitoring System Diagrams Unit 2 Revision 22 December 2001 11102

LINER FILLING*_BO HEPA FILTER HOOD EXH.

CFM CAM tatBO CFNI R ARADWAWASTE AUX.

RADWASTEBUILDING 2965 CFMPUEPA ECONI. FLTER l RVICF BLOG GENERAL AREA NTLAIO " AREA A IAREAENT XH."

.EE EXH.

CAM I OOr RABWASTE ,OAOFM

• CA 11t EOUIPE EX RADWASTE BUILDING 286.35 CFT I,, J CEN. AREA VENTILATION t HEPA FILTER I2 ARE¢*

& PARTICULATE- GAS. CAM SGAS ACF (VENTILATION IRE REACTOR BUILDING ABOVE REFUELING FLOOR '

I'A ISOLATION) F :4 T

l (RE ........... _ i_

70000 CFMJ REACTOR BUILDING BELOW REFUELING FLOOR --... -----.-.. ---... --.----- --.-- ----

. . .----. . - I.. OA CAT 11 OA CAT 1

• A "

E *66S00-69000 CFM iooo-3S00 CFm '

RECIRCULATION MODE -* .------------ 7 I- ---. SCTS p3SOO CFM CONTAINMENT PURGE CAM CAT II CAM CA CAT IIl--OA CAT I OA CAT I AT II--ý-OA GAS I PARTICULATE SOTS. .

T - SAMPLE TAP 500 CF OFFGAS SYSTEM MECHANICAL VACUUM PUMP DISCHARGE INTAKE IEAST)

OUTSIDE AIR sO00 CFI INTAKE FOR 2250 C.M CONTROL ROOM ENVELOPE CONTROL ROOM RECIRC 750 CFMP INTAKE ACF (BYPASS

'GAS ACTIVATION$ ACTIVATION1

,WEST)

ACt' AUTOMATIC CONTROL FUNCTION PAM: POST ACCIDENT MONITOR

.  : PARTICULATE & IODINE SAMPLING CAPABILITY CAM' CONTINUOUS AIRBORNE MONITOR I

• SAFETY-RELATED MONITOR NOTES CONCURRENT I. MOOIFICATION 95-011 HAS BEEN INSTALLED TO ALLOW ARE RUNNING OPERATION OF ALL 3 EXHAUST FANS. WHEN ALL 3 FANS EXHAUST OF z 17.S00 CFM.

THERE WILL BE AN ADDITIONAL I c I c I

DUAL DISK DRIVE BLOCK DIAGRAM TYPICAL GASEOUS EFFLUENT MONITORING SYSTEM NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 2 II 104 UPDATED SAFETY ANALYSIS REPORT

APPENDIX E NINE MILE POINT ON-SITE AND OFF-SITE MAPS Unit 2 Revision 22 December 2001 11105

7 76 6 VanrM Pddy NOM volnoy We 42 1 31 c: w Im G 0 21 HN Saylo's Cwcýmrs 5 .14 vo 4 C11:1.19.111."

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ATTACHMENT 15 Radwaste Process Control Program (RPCP)

HalG 1 TP~- LI flE NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2 RADWASTE PROCESS CONTROL PROGRAM REVISION 05 TECHNICAL SPECIFICATION REQUIRED Approved By: Date M. F. Peckham P a-n ager-

-a Unit 2 THIS IS A FULL REVISION Effective Date: 2 /1312003

LIST OF EFFECTIVE PAGES Page No. Change No. Page No. Change No. Page No. Change No.

Coversheet i . . . .

ii . . . .

8 . . . .

6..

10 . . . .

11 . .

12 . . . .

13 . . . .

14 . . . .

15 . . . .

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18 . . .

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Page i Rev 05

TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ..... ....... ... .................... .............. 1 2.0 RESPONSIBILITIES ...... ..... .............................. 1 3.0 PROGRAM . .. . . . ...

• 3.1 System Description ...... ... ........................ I 3.2 Radioactive Waste Dewatering System (RDS 1000) .... ....... 4 3.3 Disposition of other Radioactive Material ..... ......... 8 3.4 Sampling ...... ..... ..... .......................... 9 3.5 Waste Classification ........ .................... ... 10 3.6 Administrative Controls ......... .................. ... 11 4.0 DEFINITIONS ..... ....... ... ............................ ... 14

5.0 REFERENCES

...... ......... ............................. ... 15 ATTACHMENT 1: UNIT 2 RADWASTE PROCESS CONTROL PROGRAM REFERENCE AND IMPLEMENTING PROCEDURES ...... ........... 17 ATTACHMENT 2: SOLID WASTE SOURCES ........ .................... ... 18 Page ii Rev 05

1.0 PURPOSE 1.0.1 To describe the methods for processing, packaging and transportation of low-level radioactive waste and provide assurance of complete stabilization of various radioactive "wet wastes" in accordance with applicable NRC regulations and guidelines.

1.0.2 To satisfy the Nuclear Regulatory Commission's Low-Level Waste and Uranium Recovery Projects Branch (WMLU) requirement and establish process parameters within which the Chem-Nuclear Rapid Dewatering System (RDS-1000) must be operated to meet current disposal criteria at low-level waste disposal facilities.

NOTE: Conformance with WMLU requirements provides assurance that the requirements identified in IOCFR61, Sub Part D, Technical Requirements for L-and Disposal Facilities and Final Waste Classification are satisfied.

2.0 RESPONSIBILITIES 2.1 The Plant Manager is responsible for:

2.1.1 Ensuring the Unit 2 Radwaste Process Control Program provides for the health and safety of the general public as it applies to Radwaste Management.

2.1.2 Reviewing and approving changes to the Unit 2 Radwaste Process Control Program in accordance with the Quality Assurance program.

2.2 The Manager Radiation Protection is responsible for the content and maintenance of this procedure.

2.3 The General Supervisor Radwaste is responsible for overall implementation of the Radwaste Process Control Program.

3.0 PROGRAM

3.1 System Description

3.1.1 General

a. The Solid Waste Management System (SWMS), implemented by the procedures identified in the Unit 2 Radwaste Process Control Program Implementing Procedures (Attachment 1) collects, reduces the volume, dewaters or solidifies and packages wet and dry types of radioactive waste in preparation for shipment off-site for further processing or disposal at a licensed burial site. The processing and storage methods used for interim storage are consistent with the present waste form stability requirements.

Page I Rev 05

3.1.1 (Cont)

b. Types of solid waste sources are identified in Solid Waste Sources (Attachment 2).

c. The Solid Waste Management System accepts dry solid trash which is then compacted with a trash compactor (when physically possible) or sent off site for separation and processing.

NOTE: When required, Unit 2 will use the services of a vendor to solidify, dewater, separate, recover, or incinerate waste.

d. Bead resins, powdered resins and charcoal are dewatered using RDS-1000 in:

1. Vendor Certified Polyethylene containers, or

2. Carbon steel liners, or

3. High Integrity Container (HIC)

e. Bead resins, powdered resins and charcoal are solidified by cement solidification using an approved vendor.

f. Concentrated wastes are processed offsite to dryness by an approved vendor.

3.1.2 Evaporator Bottoms Tank

a. The evaporator bottoms tank and lines are electrically heat traced to prevent crystallization of waste salts.

b. Contents of the tank are transferred to a liner in the Radwaste Truckbay, via the concentrated waste transfer pump/for offsite processing.

3.1.3 Waste Sludge Tank

a. The waste sludge tank is supplied with waste from the following sources:

1. Radwaste filters,

2. The Thermex System, and

3. The spent resin tank

b. The waste sludge tank has the ability for decantation. A decant pump takes a suction off the sludge tank and discharges to the spent resin tank.

Page 2 Rev 05

3.1.3 (Cont)

c. Contents of the waste sludge tank are fed by one of two redundant waste sludge pumps, to the Radwaste Truckbay for dewatering by the RDS 1000 or cement solidification by an approved vendor.

3.1.4 Ventilation System The Radwaste Building Ventilation System (HVW) provides filtered, conditioned outside air to various areas of the Radwaste Building and exhaust the air to the atmosphere through the Reactor Building Vent. The HVW system maintains the building at a pressure below atmospheric to help prevent any unmonitored air leakage to the environment.

3.1.5 Liners

a. The RDS-1000 system is compatible with Chem-Nuclear System Incorporated (CNSI) dewatering waste containers.

b. These containers and their dewatering internals are designed to ensure uniform dewatering of waste slurries. They are fabricated and inspected in accordance with CNSI Quality Assurance Program.

c. Waste classification requirements will enter into selection of liner type.

d. Liners used to transport concentrated waste are fabricated and inspected in accordance with CNSI Quality Assurance Program and are compatible with Liquid Waste.

3.1.6 Crane

a. All liners movements are completed using a radio controlled/operated crane.

b. Liners are moved if required by crane to the Radwaste Building storage area using a ceiling grid coordinated system for placement of the liner.

c. When liners stored in the Radwaste Building storage area are to be shipped, the liners scheduled for shipment are moved, capped just before shipment, and then loaded for transportation to the burial location.

Page 3 Rev 05

3.2 Radioactive Waste Dewatering System (RDS 1000) 3.2.1 Rapid Dewaterinq System (RDS-1000)

a. The rapid dewatering system is a self-contained, free standing portable system for dewatering radioactive spent resins and filter sludges in a variety of liners to meet current disposal criteria at low-level waste disposal facilities. The system is comprised of:

1. A dewatering skid

2. A plant connection skid

3. A control console

4. A container fillhead

5. A waste container complete with interconnecting hoses and cables

b. The radioactive waste slurry is transferred by waste transfer pumps to the RDS 1000, which includes a waste inlet automatic control valve.

c. The water removed from the radioactive waste is pumped from the waste liner by a dewatering pump through a media specific filtering device and returned to the plant through a floor drain.

d. Fill operation is controlled remotely and viewed with a video monitor on the control panel. A remote level-control system detects and monitors waste level in the liner.

Overfill protection is provided through this system and an independent level control in the fillhead, either of which will automatically close the waste inlet valve.

e. Upon completion of dewatering, warm air between 160-180 deg. F is recirculated through the liner and moisture separator until water content of the waste is within the low-level burial site Acceptance Criteria.

NOTE: The limiting factor on air temperature recirculated through the liner is based on maximum allowable temperature of a HIC. The maximum measured acceptable temperature is 200 deg. F.

f. The type of media which can be dewatered by the RDS-1000 is divided into two categories:

1. Granular media which includes bead resin, charcoal, and zeolites

2. Filter precoat media which includes ecodex, powdex, ecosorb, ecocoat, and diatomateous earth.

Page 4 Rev 05

3.2.1 (Cont)

g. All discharge air is passed through HEPA filtration units contained within the RDS-1000 Skid before passing to permanent plant vent.

3.2.2 Acceptance Criteria Acceptance Criteria for process completion is established by a minimum dewatering time and a maximum water collection rate. The resultant waste form meets the requirements of 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste" and NRC Branch Technical Position on Waste Form (May, 1983 Rev 0).

a. Bead Resin

1. The dewatering pump has run for one hour after the final waste transfer.

2. The RDS-1000 has been run for a minimum of four hours.

3. The moisture separator sight glass does not increase more than 1/2 inch during a thirty minute period.

b. Precoat Media

1. The dewatering pump has run, after the final waste transfer for a minimum of one hour and dewatering pump suction is equal to or less than 16" of mercury with all lateral suction valves opened.

2. The RDS-1000 has been run for a minimum of eleven hours.

3. The moisture separator sight glass does not increase more than 1 inch during a thirty minute period.

3.2.3 Plant Connection Stand The plant connection stand, consists of the following:

a. A remotely operated waste inlet valve to control influent to the processing liner. This valve is interlocked to close on High Level, High High Level (mechanical float inside fillhead), and decreasing air pressure or loss of electrical power.

b. A diaphragm pump with connections to the fillhead for gross initial dewatering.

c. Manifold for air and water supplies to control elements and flush components.

Page 5 Rev 05

3.2.4 Filihead

a. Camera and light provides remote visual observation of the container level during the resin transfer and dewatering.

b. Connections on the underside of the fillhead can connect to break away fittings in order to facilitate remote removal from the container for ALARA.

c. The external connections on the fillhead are camlock except the waste inlet.

d. A float switch inside the fillhead is a high high level backup to the level detection system (FAVA) installed inside the liner for automatic closure of the waste isolation valve.

3.2.5 RDS Dewatering Skid The RDS Skid consists of a vacuum pump, moisture separator, air conditioning unit, and piping interface to the plant connection stand. Pressures and temperatures are monitored at various points on this component to safeguard mechanical operations. A HEPA filter is installed downstream of the safety relief valve and manual valve bypass.

3.2.6 Control Panel A control panel containing electrical and pneumatic controls to allow remote operation of all components and monitoring of individual parameters. A video monitor of the liner is provided as well as temperature and pressure indications of primary components. Audible and visual alarms to indicate off-normal conditions are also found on the control panel.

3.2.7 Level Detection System (FAVA)

The term FAVA is the manufacturers designation for a level detection system which is installed in the liner with a remote readout display on the control console. There are four probes inserted to different levels in the liner. The level detection system works on the conduction principle. It is used in the process to indicate the level of the liquid in the container.

3.2.8 Radwaste Operators Radwaste Operators shall ensure proper equipment is available before beginning radwaste processing. Radwaste Operators may process wastes when the following equipment is operable:

a. Closed circuit television system stations

b. Radwaste Building Ventilation Page 6 Rev 05

3.2.8 (Cont)

c. Radwaste Building Floor Drain System

d. Radwaste Building CNS System

e. Service Air System 3.2.9 Vendor Operators All operations of RDS-1000 shall be performed by technicians training that have successfully completed the CNSI technicians Initial indoctrination training includes approximately program.

30 days of general knowledge examinations, health physics instructions, and equipment operation. The operator shall have practical experience, certification on the RDS-1000 system and two years. Each phase of is subjected to recertification every cards, on the training is monitored by the use of qualification tests and certificates of the job training reports, written completion.

3.2.10 Quality Assurance Procedure, Chem-Nuclear's Quality Assurance Program, CNSI shall be employed to control the design, fabrication, QA-AD-QOO, the and record keeping for inspection, testing, operation, RDS-1000.

3.2.11 Records and testing of CNSI maintains records of the design, fabrication of the system is each RDS-1000 system. The setup and operation FO-OP-032, Setup maintained in accordance with CNSI Procedures, Setup and Operating Procedure for RDS-1000 unit and FO-OP-035, Media in a 21-300 and Operating Procedure for Dewatering Precoat Liner Using the RDS-1000.

3.2.12 Waste Containers The General Supervisor Radwaste shall ensure:

the

a. Waste Containers are used for dewatering to satisfy stability requirements.

1. Polyethylene container may be used as the disposal package for NRC Class "A" waste.

2. Polyethylene container may also be used for NRC CLASS is "B" and "C" waste, but enhanced structural stability required for burial at the Barnwell site.

Page 7 Rev 05

3.2.12 (Cont)

NOTE: This structural stability to meet requirements of IOCFR61.56 and the State of South Carolina is accomplished by the use of DHEC approved concrete overpack structures at the Barnwell burial site.

b. Each Waste Container is accompanied by a certificate of compliance.

c. Dewatering procedures based on an NRC approved vendor process control program or "Topical Report" are part of FO-OP-032, RDS-1O00 Dewatering Procedure.

d. Documentation of adherence to procedures are maintained as records.

e. No polyethylene container is stored in direct sunlight for a period greater than one year.

f. Waste containers used to transport concentrated waste are compatible with this type of waste.

3.3 Disposition of other Radioactive Material 3.3.1 Contaminated Oils The General Supervisor Radwaste shall ensure:

a. Contaminated oils are stored in containers at designated areas within the plant.

b. A vendor with an approved process control program acceptable at the selected burial site is used to solidify the oil.

c. A vendor may also be used to incinerate the oils.

3.3.2 Temporary Radwaste Processing The General Supervisor Radwaste shall ensure:

a. The vendor is NRC approved and has demonstrated a commitment to 10CFR61, Sub Part D, Technical Requirements for Land Disposal Facilities and Final Waste Classification and Waste Form Technical Position Papers stability requirements.

b. The vendor has completed Class B and C waste testing or has provided a schedule of completion.

c. The vendor has an approved procedure to process Class A waste (Dewatering, Evaporation, Solidification).

Page 8 Rev 05

3.3.2 (Cont)

d. Vendor procedures are acceptable as follows:

1. Vendor procedures are reviewed and approved in accordance with NIP-PRO-03, Preparation and Review of Technical Procedures.

is

2. A production sample level process control procedure implemented.

The vendor provides samples in accordance with N2-WHP-4,

3. 6 , Dewatered Waste Transfer Procedure, for N2-CSP-WSS-@40 Waste Sludge surveillance at Unit 2.

3.3.3 Dry Active Waste (DAW)

The General Supervisor Radwaste shall ensure:

and

a. The proper and safe steps are performed to collect accordance with prepare low specific activity (LSA) DAW in N2-WHP-12, Solid Dry Waste Collection and Compaction.

compromise

b. DAW is examined for liquids or items that would the burial site the integrity of the package or violate items are license and/or criteria before compacting. These removed or separated.

c. DAW is shipped in containers meeting the transport for Low requirements of 49CFR173.427, Transport Requirements Specific Activity (LSA) Radioactive Materials.

due to

d. Waste precluded from disposal in LSA boxes or drums with radiation limits is disposed of in liners in accordance N2-WHP-4, Waste Transfer Procedure.

e. DAW shipped off-site for vendor processing meets any and 49CFR173.427, Transport Requirements for LSA, additional vendor requirements, if specified.

3.4 Sampling ensure:

Radwaste Operators or the Chemistry Branch shall Tank (TK8), or

a. The Evaporator Bottoms Tank (TK1O), the Waste Sludge input when further the Spent Resin Tank (TK7) are isolated from is assigned.

preparing to process waste and a batch number to ensure a

b. The Evaporator Bottoms Tank (TK1O) is recirculated homogeneous mixture.

Spent Resin Tank

c. The Waste Sludge Tank (TK8) is agitated and the mixture.

(TK7) is recirculated to ensure a homogeneous Page 9 Rev 05

3.4 (Cont)

d. A sample is obtained from the tank(s) to be processed in accordance with N2-WHP-4, Waste Transfer Procedure, for N2-CSP-WSS-@406, Dewatered Waste Surveillance at Unit 2.

e. The sample from the tank(s) to be processed is analyzed and the sample data sheet form in N2-CSP-WSS-@406, Dewatered Waste Surveillance at Unit 2, is completed.

of

f. The Chemistry Branch shall determine the radionuclide content each sample.

3.5 Waste Classification that

a. The Unit 2 Radwaste Process Control Program, procedure assures disposal are properly wastes determined acceptable for near surface classified.

b. Waste classification is performed consistent with the guidance provided in the Branch Technical Position pertaining to Waste Classification and is based upon the concentration of certain radionuclides in the waste form as given in 10CFR61.55, Waste Classification, and IOCFR61.56, Waste Characteristics.

NOTE: The methods used and the frequency for determining the radionuclide concentration of the final waste form are conducted in accordance with N2-CSP-WSS-@406, Dewatered Waste Surveillance at Unit 2.

c. The General Supervisor Radwaste shall ensure:

1. The minimum waste characteristic requirements identified in 10CFR61.56, Waste Characteristics, are satisfied by implementation of applicable S-RPIPs for the packaging and transportation of radioactive material.

2. The radionuclide concentration determination methods and frequency are conducted in accordance with N2-CSP-WSS-@406, Dewatered Waste Surveillance at Unit 2 and N2-CSP-WSS-@403.

of

d. The Manager Radiation Protection shall ensure classification S-WHP-03, Classification and waste is performed in accordance with the RADMAN computer code or Shipment of Radioactive Material, using of Radioactive Material, using S-WHP-04, Classification and Shipment the RAMSHP computer program.

Page 10 Rev 05

3.6 Administrative Controls to stop NOTE: The Manager, Nuclear QA, Operations has the authorityexist and work when significant conditions adverse to quality require corrective action.

3.6.1 Quality Assurance (QA) procedures and the Nuclear QA Program require:

a. Ongoing review, monitoring, and audit functions.

SRAB, of

b. Performance of audits, under the cognizance of the for procedures the Process Control Program and implementing once at least processing and packaging of radioactive waste every 24 months.

c. Compliance with the waste classification and characterization requirements of 10CFR61.55, Waste Classification and 10CFR61.56, Waste Characteristics.

inspections

d. Quality Assurance Inspectors performing radwaste and have documented training in Department of Transportation NRC radwaste regulatory requirements.

ensure

e. Quality Assurance review of vendor programs to of compliance with 10CFR71, Packaging and Transportation Radioactive Materials, Quality Assurance requirements.

3.6.2 Training Procedures and Training Programs require:

of the

a. Radwaste Operator qualification by completion Unit 2 Plant Training Program with:

Radwaste Operations

1. An average grade of 80 percent or above.

2. On-the-job training in conjunction with classroom instruction to ensure each radwaste operator maintains an acceptable level of skill and familiarity associated with radwaste controls and operational procedures.

3. Training in accordance with approved training procedures.

NOT be

b. Training of Radwaste Operators to include, but radwaste limited to, familiarity with the following components or related systems:

waste

1. Liquid-drains, collection tanks with subsystems, and regeneration evaporators, and seal water

2. Solid Waste and associated support systems

3. LWS-Computer operation and interfaces Page 11 Rev 05

3.6.2.b (Cont) shipping of

4. Waste handling procedures for packaging and radioactive materials

5. Condensate demineralizer system

6. Spent fuel and phase separators subsystem

7. Steam supplies

8. The Thermex System

9. Rapid Dewatering System (RDS-1000)

Technician

c. Chemistry Technician and Radiation Protection with approved training procedures.

training in accordance schedule based

d. A formal classroom Radwaste Training Program on the needs of Radwaste Operations personnel.

cycle NOTE: This training may be covered in a continuous or as part of the normal rotating shift schedule.

personnel on a

e. Continuing Training of Radwaste Operator individual cyclic basis (i.e. every 4 yrs.) to identify needs for retraining.

in a

1. Personnel demonstrating a significant deficiency in a proficiency are placed given area of knowledge and General as directed by the remedial training program Supervisor Radwaste.

training

2. Successful completion of the accelerated written and/or oral program is evaluated by a examination as directed by the General Supervisor Radwaste.

a NOTE: The Requalification Training Program covers fundamental review of system modifications, or revisions or changes to procedures, and changes experiences in the nuclear industry.

f. Training records to:

1. Be maintained for audit and inspection purposes.

2. Be considered permanent records.

Page 12 Rev 05

3.6.2.f (Cont) of QATR-1, Quality

3. Meet the applicable requirements for Nine Mile Point Assurance Program Topical Report 17.0, Quality Nuclear Station Operations, Section and Qualification Assurance Records, NIP-TQS-O1, Identification, Certification, and NIP-RMG-O1, of Nuclear Division Maintenance, Storage and Transfer Records Retention 3.6.3 Documentation Control and Record QA program audits of waste

a. Station management shall evaluate the requirements of classification records to satisfy and Manifests.

10CFR20.2006.d, Transfer for Disposal affecting operating

b. Personnel shall forward changes the for review in parallel with procedures to Nuclear-QAas required.

NMPC Operations review maintain waste management

c. Site Records Management shall the appropriate administrative records in accordance with procedures.

the Unit 2 Radwaste Process 3.6.4 Licensee-initiated changes to Control Program:

in the Radioactive Effluent

a. Are submitted to the Commission which the change(s) was in Release Report for the period required by USAR Section made, and contain the information 11.4.7, Process Control Program.

and acceptance by the SORC.

b. Become effective upon review shall ensure:

3.6.5 The General Supervisor Radwaste and tracked to satisfy the

a. Shipping manifests are completed Transfer for Disposal and requirements of 10CFR20.2006.d.

Waste Handling Procedures.

Manifests, in accordance with the status of the manifests in

b. Radwaste Management monitors Departure.

accordance with N2-WHP-7, Cask/Van/Flatbed/Seavan material awaiting

c. Temporary storage of solid radioactive a designated area is done in shipment in an area other than of Material Storage accordance with GAP-INV-02, Control Areas.

Rev 05 Page 13

3.6.6 Solid Radioactive Wastes Specification 3.11.1

a. Technical Requirements Manual (TRM) Specification of contains requirements for solidification and dewatering radioactive wastes.

3.11.1

b. Although the specification is housed in the TRM, TRM to Control Program and is subject is a part of the Process the controls and change processes of this document.

4.0 DEFINITIONS 4.1 Class "A" Waste at the disposal site.

Waste usually segregated from other waste classes the minimum The physical form and characteristics shall meet requirements of 10CFR61.56, Waste Characteristics.

4.2 Class "B" Waste to ensure stability Waste meeting more rigorous waste form requirements and after disposal. Class B waste form shall meet both the minimum stability requirements of 10CFR61.56, Waste Characteristics.

4.3 Class "C" Waste measures at the Waste meeting Class B standards and requiring additional disposal facility to prevent inadvertent intrusion.

4.4 Homogeneous Most waste streams are Of the same kind or nature; essentially alike.

considered homogeneous for purposes of waste classification.

4.5 Batch having essentially An isolated quantity of feed waste to be processed constant physical and chemical characteristics.

4.6 Dewatered Waste other than Refers to waste that has been processed by means or absorption to meet the free standing solidification, encapsulation, liquid requirements of 10 CFR 61.56 (a)(3) and (b)(2).

4.7 Concentrated Waste particulate solid Liquid waste that has a high level of dissolved and/or content.

4.8 Dried Waste to dryness.

Solid waste that has been processed by evaporation Page 14 Rev 05

5.0 REFERENCES

5.1 Licensee Documentation Nine Mile 5.1.1 QATR-1, Quality Assurance Program Topical Report for Point Nuclear Station Operations, Section 17.0, Quality Assurance Records 5.1.2 Unit 2 Technical Specifications Section 5.6.3, Radioactive Effluent Release Report 5.1.3 Nuclear Quality Assurance Program Process 5.1.4 Unit 2 Updated Safety Analysis Report Section 11.4.7, Control Program 3.11.1, Solid 5.1.5 Unit 2 Technical Requirements Manual Specification Radioactive Wastes 5.2 Standards, Regulations. and Codes for Solid 5.2.1 ANSI/ANS 55.1, 1979, American National Standard for Light Water Cooled Radioactive Waste Processing System Reactor Plants 5.2.2 IOCFR20.2006.d, Transfer for Disposal and Manifest Low Level 5.2.3 10CFR20 App G, Requirements for Transfers of for Disposal at Licensed Land Radioactive Waste intended Disposal Facilities and Manifests Land Disposal 5.2.4 10CFR61, Sub Part D, Technical Requirements for Waste Form Facilities and Final Waste Classification and Technical Position Papers 5.2.5 IOCFR61.55, Waste Classification 5.2.6 10CFR61.56, Waste Characteristics 5.2.7 10CFR71, Packaging and Transportation of Radioactive Material 5.2.8 49CFR173.1.b, Transportation Activity 5.2.9 49CFR173.427, Transport Requirements for Low Specific (LSA) Radioactive Materials 5.2.10 NUREG-0123, Standard Radiological Effluent Technical Specifications for Boiling Water Reactors Page 15 Rev 05

5.2.11 NUREG-0800,

a. Section 11.2, Standard Review Plan for Liquid Waste Management Systems Waste

b. Section 11.4, Standard Review Plan for Solid Management Systems of 1976 (Ref.

5.2.12 Resource Conservation and Recovery Act (RCRA)

Spill Reporting)

Corporate Guide to Hazardous Waste Disposal and for Radioactive 5.2.13 Regulatory Guide 1.143, Rev. 0, Design Guidance Installed Waste Management Systems, Structures, and Components in Light Water Cooled Nuclear Power Plants 5.3 Supplemental References Control, 5.3.1 South Carolina Department of Health and Environmental Radioactive Material License 097, as amended No. WN-1019-2, 5.3.2 State of Washington Radioactive Material License as amended 12-13536-02, as 5.3.3 NRC Special Nuclear Material License No.

amended, for Barnwell, SC 16-19204-01, as 5.3.4 NRC Special Nuclear Material License No.

amended, for Richland, WA Position on Waste 5.3.5 Nuclear Regulatory Commission Branch Technical Classification and Waste Form, May 1983 5.3.6 CNSI Proprietary Topical Report No. RDS-25506-01-NP-A, Rev. 1- March 1988.

Appendix A,B,C,D and Material Safety Data Sheets Radioactive 5.3.7 SE 92-049, Interim On-Site Storage of Low Level and Storage Building Waste (LLRW) in the Radwaste Solidification (RSSB) at Unit 1.

Elevation Storage, at Unit 2.

5.3.8 SE 92-061, Upgrade Radwaste 245' 5.3.9 N2-WHP-25, Thermex Operating Procedure 5.3.10 Safety Evaluation 94-074, Installation of the Thermex System Page 16 Rev 05

ATTACHMENT 1: UNIT 2 RADWASTE PROCESS CONTROL PROGRAM REFERENCE AND IMPLEMENTING PROCEDURES Waste Handling Procedures (WHPs)

Radiation Protection Procedures (S-RPIPs)

Chemistry Procedures (CSPs)

Quality Assurance Procedures (QAPs)

Operating Procedures (OPs)

Generation Administrative Procedures (GAP/APs)

Nuclear Division Interfacing Procedures (NIPs)

Page 17 Rev 05

ATTACHMENT 2: SOLID WASTE SOURCES (Sheet 1 of 3) 1.0 RADWASTE FILTERS crud (backwash material) 1.1 Mechanical radwaste filters filter resin and from the waste collector sub-system.

pressure, the filter 1.2 When a filter reaches a pre-determined differential tank, which is then pumped to backwashes the material into the backwash the spent resin tank.

2.0 RADWASTE DEMINERALIZERS an ionic exchange media for 2.1 The radwaste demineralizers are used as collector tanks.

processing high quality water from the waste used, the depleted resin is 2.2 When determined the resin can NO longer be pumped to the spent resin tank.

3.0 CONDENSATE DEMINERALIZER and insoluble impurities 3.1 The condensate demineralizers remove soluble feedwater purity.

from the condensate water to maintain reactor NO longer be used, the depleted 3.2 After it is determined these resins can or spent resin tank.

resins are pumped to the Radwaste Demineralizer 4.0 THERMEX SYSTEM waste tank for further 4.1 Concentrated waste will be pumped to the regen a liner and eventually concentration by an evaporator or stored in Truckbay for offsite pumped to a transport liner in the Radwaste processing.

to the filter sludge tank.

4.2 Exhausted resin and charcoal are sluiced tank mixed to a homogenous This waste is transferred to the Spent Resin truckbay for dewatering.

in the mixture and then transferred to a liner be processed as DAW.

4.3 Exhausted reverse osmosis membranes will 5.0 SPENT FUEL PHASE SEPARATOR filter media (resins) from These tanks receive the exhausted powdered pumped to the spent the fuel pool cleanup system which is subsequently Truckbay for Radwaste resin tank or directly to a liner in the processing.

Rev 05 Page 18

ATTACHMENT 2: SOLID WASTE SOURCES (Cont)

(Sheet 2 of 3) 6.0 RWCU PHASE SEPARATOR filter media (resins)

These separator tanks receive exhausted powdered pumped to the spent from the water cleanup system which is subsequently Truckbay for resin tank or directly to a liner in the Radwaste processing.

7.0 CONTAMINATED OIL contaminated is either stored Oil from sources within Unit 2 that become with an approved procedure) in containers (to be solidified by a vendor or shipped off-site for incineration.

8.0 COMPACTIBLE SOLIDS and compacted in a 8.1 Compactible low level trash is either processed off-site for vendor shipped hydraulically operated box compactor, or separation and processing.

the chemistry lab, and 8.2 Shoe covers, trash, contaminated paper from category.

similar materials are included in this 9.0 FILTERS AND MISCELLANEOUS ITEMS on a case-by-case basis, Solid items with high dose rates are handled to the burial site or shipped being disposed of by methods acceptable off-site for vendor recovery or disposal.

10.0 WASTE EVAPORATOR waste from the floor drain 10.1 The waste evaporator processes low quality and, as an option, waste from collector system, Regeneration Waste Tanks the Waste Discharge Tanks.

waste to a 25% solid 10.2 The waste evaporator is designed to concentratethe evaporator bottoms to concentration which may then be discharged the Radwaste Truckbay for vendor processing.

tank for transfer to Page 19 Rev 05

ATTACHMENT 2: SOLID WASTE SOURCES (Cont)

(Sheet 3 of 3) 11.0 REGENERANT EVAPORATOR waste from the 11.1 The Regenerant Waste Evaporator may receive concentrated from the Condensate Demineralizer Thermex System, regeneration solutions Resin Regeneration System, and the System, the Radwaste Demineralizer radwaste regeneration sump. It can also process waste from the Floor Tanks.

Drain Collector System and the Waste Discharge concentrate to a 25% by 11.2 The Regenerant Waste Evaporator is designed to weight solid concentration of sodium sulfate.

Bottoms Tank for 11.3 The concentrates are then discharged to the Evaporator processing.

transfer to the Radwaste Truckbay for vendor 12.0 SPENT RESIN STORAGE TANK the Radwaste 12.1 Exhausted resin from the condensate demineralizer, Fuel Pool Phase Demineralizer, RWCU phase separator, the Spent sluiced to the are Separator, and the Radwaste Filter Backwash Tanks Spent Resin Storage Tank.

is pumped to the Waste 12.2 The waste from the Spent Resin Storage Tank in the Radwaste Truckbay.

Sludge Tank for processing by the RDS 1000 Rev 05 Page 20