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9 to Updated Final Safety Analysis Report, Appendix 12A - Tables
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Catawba Nuclear Station UFSAR Appendix 12A. Tables Appendix 12A. Tables

Catawba Nuclear Station UFSAR Table 12-1 (Page 1 of 2)

(22 OCT 2001)

Table 12-1. Design Basis Source Strengths for Fluids Gamma Groups Source Designation 1

2 3

4 5

6 A.

Reactor coolant, high temperature, fission and corrosion products SS 3.44 E + 6 4.76 E + 5 4.79 E + 5 1.33 E + 5 1.14 E + 5 1.26 E + 4 E

.10

.476

.898 1.33 2.12 2.71 B.

Reactor coolant, nitrogen-16 term (per microcurie/cc)

SS 3.70 E + 2 2.55 E + 4 1.85 E + 3 E

2.75 6.13 7.12 C.

Reactor coolant, pressure SS 1.33 E + 6 1.77 E+5 2.63 E + 5 3.33 E + 4 7.49 E + 2 6.76 E + 1 E

.167

.471

.890 1.26 1.83 2.55 D.

Reactor coolant, ambient temperature SS 4.86 E + 6 6.73 E + 5 6.77 E + 5 1.89 E + 5 1.61 E + 5 1.78 E + 4 E

.100

.476

.898 1.33 2.12 2.71 E.

Reactor coolant, downstream mixed - bed demineralizer SS 4.58 E + 6 2.96 E + 5 2.89 E + 5 5.18 E + 4 1.27 E + 5 1.19 E + 4 E

.0958

.448

.902 1.33 2.19 2.68 F.

Reactor coolant, downstream mixed -bed and cation-bed demineralizer SS 4.57 E+6 2.86 E+5 2.67 E+4 4.84 E+5 1.25 E+5 1.1 E + 4 E

.0956

.446

.902 1.33 2.2 2.67 G.

Reactor coolant, demineralized, gas-stripped (volume control tank)

SS 3.41 E+6 2.14 E+5 2.52 E+5 4.67 E+4 7.38 E+4 7.24 E+3 E

.094

.449

.902 1.33 2.19 2.72 H.

Reactor coolant, fully degassed SS 3.70 E+5 5.14 E+5 6.45 E+5 1.85 E+5 5.69 E+4 1.09 E+4 E

.171

.493

.897 1.33 1.88 2.79 I.

Reactor coolant, degassed, diluted with other leakage (factor = 1/50)

SS 7.40 E+3 1.02 E+3 1.29 E+4 3.70 E+3 1.13 E+3 2.18 E+2 E

.171

.493

.897 1.33 1.88 2.79 J.

Reactor coolant, degassed, evaporated (DF=1000)

SS 3.7 E+2 5.14 E+2 6.45 E+2 1.85 E+2 5.69 E+1 1.09 E+1 E

.171

.493

.897 1.33 1.88 2.79

Catawba Nuclear Station UFSAR Table 12-1 (Page 2 of 2)

(22 OCT 2001)

Gamma Groups Source Designation 1

2 3

4 5

6 K.

Reactor coolant, residual heat removal mode SS 4.35 E+6 4.50 E+5 4.73 E+5 1.07 E+5 3.94 E+4 1.15 E+3 E

.096

.462

.869 1.29 2.21 2.52 L.

Evaporator concentrates (non-recyclable)

SS 1.81 E+6 1.56 E+6 1.95 E+6 2.78 E+5 3.22 E+3 1.68 E+2 E

.159

.493

.889 1.26 1.84 2.42 M. Demineralizer resins (combined no sluice water)

SS 6.76 E+8 5.82 E+9 5.54 E+9 3.04 E+8 1.5 E+6 1.28 E+5 E

.167

.573

.830 1.30 1.82 2.54 N.

Demineralizer resins (combined, 6 mo. Decay, no sluice water)

SS 6.37 E+7 2.04 E+9 1.05 E+9 3.67 E+7 1.56 E+3 6.69 E-1 E

0.33

.621

.807 1.36 2.19 2.55 O.

Waste gas tank (maximum)

SS 5.45 E+7 1.55 E+6 1.79 E+4 1.54 +3 5.95 E+4 1.31 E+3 E

.084

.434

.896 1.50 2.29 2.59 Notes:

1. SS = Source Strength in gammas/cc-sec

2. E = Average energy in MeV

3. 1.10 E+6 means 1.10 x 106

Catawba Nuclear Station UFSAR Table 12-2 (Page 1 of 1)

(22 OCT 2001)

Table 12-2. Design Basis Source Strengths for Demineralizers Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/gamma)

Demineralizer (In Place)

.2-.4

.4-.9

.9-1.35 1.35-1.8 1.8-2.2 2.2-2.6 2.6-3.0 3.0-4.0 Mixed Bed 1.8E8 7.7E8 7.7E7 2.6E7 1.4E6 8.4E5 1.9E5 5.7E4 Cation Bed 7.5E6 6.5E8 4.3E7 1.5E7 5.5E5 1.9E5 1.9E5 4.4E4 Recycle Evaporator Feed 8.9E6 3.8E8 4.2E7 8.9E6 2.8E4 2.1E4 Boron Thermal Regeneration 2.7E6 1.8E6 4.4E5 2.4E5 2.1E4 1.4E4 Spent Fuel Pool 1.0E4 6.5E5 3.0E5 5.9E3 Recycle Evaporator Condensate 3.4E4 2.2E4 4.2E3 2.0E3 1.8E2 1.2E2 Waste Evaporator Condensate 3.2E5 6.1E5 1.8E5 2.6E4 1.7E3 1.1E3 Waste Monitor Tank 2.5E6 1.5E7 6.6E6 9.1E5 7.9E4 4.0E4 S.G. Blowdown Recycle 1.3E6 1.3E8 8.0E6 3.1E6 8.5E3 2.3E3

Catawba Nuclear Station UFSAR Table 12-3 (Page 1 of 1)

(22 OCT 2001)

Table 12-3. Design Basis Source Strengths for Filters Estimated Source Strengths (MeV/cc-sec) & Energies (MeV/gamma)

Filter

.2-.4

.4-.9

.9-1.35 1.35-1.8 1.8-2.2 2.2-2.6 Recycle Evaporator Condensate 3.4E4 2.2E4 4.2E3 2.0E3 1.8E2 1.2E2 Recycle Evaporator Concentrate 1.6E5 8.4E5 3.7E5 4.5E4 3.5E3 2.0E3 Waste Evaporator Condensate 3.2E5 6.1E5 1.8E5 2.6E4 1.7E3 1.1E3 Boric Acid 1.6E5 8.4E5 3.7E5 4.5E4 3.5E3 2.0E3 Reactor Coolant 5.7E7 1.5E7 Seal Water Injection 4.8E7 1.2E7 Spent Fuel Pool (Pre & Post) 1.1E7 3.0E6 Seal Water Return 1.1E7 3.0E6 Recycle Evaporator Feed 1.1E7 3.0E6 Spent Resin Sluice 1.1E7 3.0E6 Spent Fuel Pool Skimmer 1.1E7 3.0E6 Waste Monitor Tank Waste Evaporator Feed Floor Drain Tank Laundry & Hot Shower Tank (primary & secondary carbon) 3.4E7 8.9E6

Catawba Nuclear Station UFSAR Table 12-4 (Page 1 of 1)

(22 OCT 2001)

Table 12-4. Reactor Coolant System Nitrogen-16 Activity Component N-16

µCi/gm Reactor Vessel, Core 95 Reactor Vessel, Upper Region 125 Reactor Vessel Outlet 113 Steam Generator 92 Reactor Coolant Pump 69 Reactor Vessel Inlet 65

Catawba Nuclear Station UFSAR Table 12-5 (Page 1 of 1)

(22 OCT 2001)

Table 12-5. Fluxes on Inside Surface of Primary Concrete Energy Group Neutron Flux (cm sec-1)

E J 1 MeV 7.6 E+8 5.53 keV < E 1.0 MeV 1.2 E+10 0.625eV E 5.53 keV 7.1 E+9 E < 0.625ev 1.8 E+9 Energy (MeV)

Gamma Flux (cm sec -1) 7.5 4.9 E+8 4.0 8.2 E+8 2.5 6.8 E+8 0.8 1.2 E+8

Catawba Nuclear Station UFSAR Table 12-6 (Page 1 of 1)

(22 OCT 2001)

Table 12-6. Design Source Strengths for Outside Storage Tanks Steam Generator Drain Tank:

SS 2.03 E + 5 2.82 E+5 3.54 E+5 1.01 E+5 3.12 E+4 5.99 E+3 E

.171

.493

.897 1.33 2.19 2.72 Refueling Water Storage Tank:

SS 3.06 E+1 9.59 E+1 1.29 E+1 1.09 E+1 E

.151

.553

.884 1.25 Reactor Makeup Water Storage Tank SS 4.34 E+1 3.74 E+1 4.68 E+1 6.67 E+0 E

.159

.493

.889 1.26 Notes:

1.

1.1E+6 = 1.10 x 106

2.

SS= Source Strength in gammas/cc-sec

3.

E= Average energy in MeV

Catawba Nuclear Station UFSAR Table 12-7 (Page 1 of 1)

(22 OCT 2001)

Table 12-7. Spent Fuel Source Term - (MeV/cc - sec). Time After Shutdown Energy (MeV) 4 Hours 12 Hours 1 Day 1 Week 1 Month 3 Months 0.4 3.1 E+11 2.3 E+11 1.9 E+11 9.2 E+10 3.8 E+10 1.3 E+10 0.8 1.3 E+12 9.8 E+11 8.0 E+11 4.0 E+11 2.3 E+11 1.2 E+11 1.3 3.9 E+11 2.9 E+11 2.5 E+11 1.6 E+11 1.2 E+11 5.8 E+10 1.7 5.1 E+11 3.8 E+11 3.3 E+11 2.3 E+11 6.2 E+10 2.9 E+9 2.2 7.2 E+10 2.6 E+10 1.5 E+10 8.5 E+9 6.7 E+9 5.0 E+9 2.5 8.9 E+10 4.7 E+10 3.7 E+10 2.5 E+10 7.9 E+9 3.5 E+8 3.5 8.2 E+9 2.0 E+9 1.3 E+9 9.6 E+8 2.0 E+8 1.5 E+7 Note:

1. 1.10E+6 = 1.10 x 106

Catawba Nuclear Station UFSAR Table 12-8 (Page 1 of 1)

(22 OCT 2001)

Table 12-8. Source Terms for Calculating Airborne Radioactivity in Auxiliary Building Cubicles Area Source Term (%)1 543' level Seal Water HX Room 1

Mechanical Penetration Room 2

Recycle Evaporator Feed Pump Room 5

Recycle Evaporator Package Room 10 Centrifugal Charging Pump Rooms 5

Reciprocal Charging Pump Room 30 Waste Gas Compressor Rooms 5

560' level Seal Water Injection Filter Rooms 2

Seal Water Return Filter Room 1

Reactor Coolant Filter Rooms 1

Recycle Evaporator Feed Filter Rooms 1

Cation Bed Demineralizer Room 1

Mixed Bed Demineralizer Rooms 1

Recycle Evaporator Feed Demineralizer Rooms 1

577' level Letdown Reheat HX Room 5

Letdown Chiller HX Room 2

Moderating HX Room 2

Letdown HX Room 4

Mechanical Penetration Room 5

Note:

1. Source terms are expressed as a percent Table 11-14 Auxiliary Building releases.

Catawba Nuclear Station UFSAR Table 12-9 (Page 1 of 5)

(22 OCT 2001)

Table 12-9. Concentration Estimates of Airborne Radioactivity in Auxiliary Building Cubicles (µCi/ml)

Isotope Seal Water HX (1 Unit)

Mechanical Penetration (El. 543') (1 Unit)

Recycle Evap. Feed Pump (2 Units)

Recycle Evap. Package (2 Units)

Kr-85m 3.0E-9 5.9E-10 1.0E-7 2.4E-8 Kr-87 1.8E-9 3.5E-10 6.0E-8 1.4E-8 Kr-88 5.6E-9 1.1E-9 1.9E-7 4.4E-8 Xe-133m 2.7E-9 5.3E-10 9.0E-8 2.0E-8 Xe-133 1.3E-7 2.6E-8 4.4E-6 1.0E-6 Xe-135 8.4E-9 1.6E-9 2.7E-7 6.4E-8 Xe-138 1.3E-9 2.6E-10 4.4E-8 1.0E-8 I-131 5.0E-12 1.0E-12 1.7E-10 3.9E-11 I-133 7.6E-12 1.5E-12 2.6E-10 5.8E-11 Mn-54 2.2E-13 4.4E-14 7.5E-12 1.7E-12 Fe-59 6.7E-14 1.3E-14 2.2E-12 5.2E-13 Co-58 4.5E-13 8.8E-14 1.5E-11 3.4E-12 Co-60 3.4E-13 6.6E-14 1.1E-11 2.6E-12 Sr-89 1.5E-14 2.9E-15 4.8E-13 1.1E-13 Sr-90 2.7E-15 5.3E-16 9.0E-14 2.1E-14 Cs-134 2.0E-13 3.95E-14 6.8E-12 1.6E-12 Cs-137 3.4E-13 6.6E-14 1.1E-11 2.6E-12 Fraction of 10CFR20 Restricted Area DAC

.006

.0035

.207

.048

Catawba Nuclear Station UFSAR Table 12-9 (Page 2 of 5)

(22 OCT 2001)

Isotope Centri. Charging Pump Reciprocal Charging Pump Seal Water Inject. Filter Seal Water Return Filter Kr-85m 2.6E-8 2.6E-7 7.2E-8 6.0E-8 Kr-87 1.5E-8 1.5E-7 4.3E-8 3.6E-8 Kr-88 4.8E-8 4.8E-7 1.3E-7 1.1E-7 Xe-133m 2.3E-8 2.3E-7 6.4E-8 5.4E-8 Xe-133 1.2E-6 1.2E-5 3.2E-6 2.7E-6 Xe-135 7.2E-8 7.2E-7 2.0E-7 1.7E-7 Xe-138 1.2E-8 1.2E-7 3.2E-8 2.7E-8 I-131 4.3E-11 4.3E-10 1.2E-10 1.0E-10 I-133 6.5E-11 6.5E-10 1.8E-10 1.5E-10 Mn-54 1.9E-12 1.9E-11 5.4E-12 4.5E-12 Fe-59 5.8E-13 5.8E-12 1.6E-12 1.3E-12 Co-58 3.8E-12 3.8E-11 1.1E-11 8.9E-12 Co-60 2.9E-12 2.9E-11 8.1E-12 6.7E-12 Sr-89 1.2E-13 1.2E-12 3.5E-13 2.9E-13 Sr-90 2.3E-14 2.3E-13 6.4E-14 5.4E-14 Cs-134 1.7E-12 1.7E-11 4.8E-12 4.0E-12 Cs-137 2.9E-12 2.9E-11 8.1E-12 6.7E-12 Fraction of 10CFR20 Restricted Area DAC

.054

.807

.146

.123

Catawba Nuclear Station UFSAR Table 12-9 (Page 3 of 5)

(22 OCT 2001)

Isotope Reactor Coolant Filter Recycle Evap. Feed Filter Cation Bed Demin.

Mixed Bed Demin.

1A

/

1B Kr-85m 7.2E-8 9.0E-8 4.5E-8 6.0E-8 4.0E-8 Kr-87 4.3E-8 5.4E-8 2.7E-8 3.6E-8 2.4E-8 Kr-88 1.3E-7 1.7E-7 8.4E-8 1.1E-7 7.5E-8 Xe-133m 6.4E-8 8.1E-8 4.0E-8 5.4E-8 3.6E-8 Xe-133 3.2E-6 4.0E-6 2.0E-6 2.7E-6 1.8E-6 Xe-135 2.0E-7 2.5E-7 1.3E-7 1.7E-7 1.1E-7 Xe-138 3.2E-8 4.0E-8 2.0E-8 2.7E-8 1.8E-8 I-131 1.2E-10 1.5E-10 7.6E-11 1.0E-10 6.7E-11 I-133 1.8E-10 2.3E-10 1.1E-10 1.5E-10 1.0E-10 Mn-54 5.4E-12 6.7E-12 3.4E-12 4.5E-12 3.0E-12 Fe-59 1.6E-12 2.0E-12 1.0E-12 1.4E-12 9.0E-13 Co-58 1.1E-11 1.3E-11 6.7E-12 9.0E-12 6.0E-12 Co-60 8.1E-12 1.0E-11 5.0E-12 6.8E-12 4.5E-12 Sr-89 3.5E-13 4.4E-13 2.2E-13 2.9E-13 1.9E-13 Sr-90 6.4E-14 8.1E-14 4.0E-14 5.4E-14 3.6E-14 Cs-134 4.8E-12 6.0E-12 3.0E-12 4.1E-12 2.7E-12 Cs-137 8.1E-12 1.0E-11 5.0E-12 6.8E-12 4.5E-12 Fraction of 10CFR20 Restricted Area DAC

.141

.186

.093.

.123

.083

Catawba Nuclear Station UFSAR Table 12-9 (Page 4 of 5)

(22 OCT 2001)

Isotope Recycle Evap. Feed Demin.

Letdown Reheat HX Letdown Chiller HX Waste Gas Comp.

1A

/

1B Kr-85m 5.2E-8 3.7E-8 9.1E-8 3.6E-8 1.4E-8 Kr-87 3.1E-8 2.2E-8 5.4E-8 2.1E-8 8.2E-9 Kr-88 9.6E-8 6.9E-8 1.7E-7 6.7E-8 2.6E-8 Xe-133m 4.6E-8 3.3E-8 8.1E-8 3.2E-8 1.24E-8 Xe-133 2.3E-6 1.6E-6 4.0E-6 1.6E-6 6.2E-7 Xe-135 1.4E-7 1.0E-7 2.5E-7 1.0E-7 3.9E-8 Xe-138 2.3E-8 1.6E-8 4.0E-8 1.6E-8 6.2E-9 I-131 8.6E-11 6.1E-11 1.5E-10 6.0E-11 2.3E-11 I-133 1.3E-10 9.3E-11 2.3E-10 9.1E-11 3.5E-11 Mn-54 3.4E-12 2.4E-12 6.4E-12 2.7E-12 1.0E-12 Fe-59 1.2E-12 8.6E-13 2.0E-12 8.1E-13 3.1E-13 Co-58 7.7E-12 5.5E-12 1.3E-11 5.4E-12 2.1E-12 Co-60 5.8E-12 4.1E-12 1.0E-11 4.0E-12 1.5E-12 Sr-89 2.5E-13 1.8E-13 4.4E-13 1.7E-13 6.7E-14 Sr-90 4.6E-14 3.3E-14 8.1E-14 3.2E-14 1.2E-15 Cs-134 3.5E-12 2.5E-12 6.0E-12 2.4E-12 9.3E-13 Cs-137 5.8E-12 4.1E-12 1.0E-11 4.0E-12 1.5E-12 Fraction of 10CFR20 Restricted Area DAC

.106

.075

.187

.074

.029

Catawba Nuclear Station UFSAR Table 12-9 (Page 5 of 5)

(22 OCT 2001)

Isotope Moderating HX Letdown HX Mechanical Penetration Other Areas (El. 577')

Kr-85m 3.6E-8 9.5E-9 4.3E-9 4.2E-10 Kr-87 2.1E-8 5.7E-9 2.5E-9 2.5E-10 Kr-88 6.7E-8 1.8E-8 8.0E-9 7.8E-10 Xe-133m 3.2E-8 8.5E-9 3.8E-9 3.8E-10 Xe-133 1.6E-6 4.2E-7 1.9E-7 1.9E-8 Xe-135 1.0E-7 2.6E-8 1.2E-8 1.2E-9 Xe-138 1.6E-8 4.2E-9 1.9E-9 1.9E-10 I-131 6.0E-11 1.6E-11 7.1E-12 7.1E-13 I-133 9.1E-11 2.4E-11 1.1E-11 1.1E-12 Mn-54 2.7E-12 7.1E-13 3.2E-13 3.1E-14 Fe-59 8.1E-13 2.1E-13 9.5E-14 9.4E-15 Co-58 5.4E-12 1.4E-12 6.4E-13 6.3E-14 Co-60 4.0E-12 1.1E-12 4.8E-13 4.7E-14 Sr-89 1.7E-13 4.6E-14 2.1E-14 2.0E-15 Sr-90 3.2E-14 8.5E-15 3.8E-15 3.8E-16 Cs-134 2.4E-12 6.4E-13 2.9E-13 2.8E-14 Cs-137 4.0E-12 1.1E-12 4.8E-13 4.7E-14 Fraction of 10CFR20 Restricted Area DAC

.074

.019

.009

.001

Catawba Nuclear Station UFSAR Table 12-10 (Page 1 of 1)

(22 OCT 2001)

Table 12-10. Concentration Estimates of Airborne Radioactivity in Turbine Building Isotope Concentration (µCi/ml)

Kr-83m 8.2E-14 Kr-85m 8.7E-13 Kr-85 4.6E-11 Kr-87 2.4E-13 Kr-88 1.5E-12 Kr-89 2.2E-14 Xe-131m 1.7E-12 Xe-133m 2.7E-12 Xe-133 2.3E-10 Xe-135m 5.5E-14 Xe-135 3.1E-12 Xe-137 3.8E-14 Xe-138 1.8E-13 I-131 2.8E-14 I-133 3.7E-14 H-3 1.5E-10 Fraction of 10CFR20 Unrestricted Area DAC 1.4E-5

Catawba Nuclear Station UFSAR Table 12-11 (Page 1 of 1)

(22 OCT 2001)

Table 12-11. Concentration Estimates of Airborne Radioactivity in Upper Containment During Operation Isotope Concentration (µCi/ml)

Kr-83m 5.0E-9 Kr-85m 1.3E-7 Kr-85 1.1E-5 Kr-87 6.5E-9 Kr-88 1.0E-7 Kr-89 1.1E-12 Xe-131m 1.0E-5 Xe-133m 1.0E-5 Xe-133 1.4E-3 Xe-135m 6.7E-11 Xe-135 1.5E-6 Xe-137 2.8E-12 Xe-138 1.7E-10 I-131 8.4E-9 I-133 2.0E-9 Ar-41 4.2E-5 H-3 2.3E-6 Fraction of 10CFR20 Restricted Area DAC 30 H-3 (during refueling) 1.2E-6

Catawba Nuclear Station UFSAR Table 12-12 (Page 1 of 1)

(22 OCT 2001)

Table 12-12. Concentration Estimates of Airborne Radioactivity in the Administration Building Isotope Concentration (µCi/ml)

Kr-83m 5.1E-15 Kr-85m 5.5E-14 Kr-85 3.0E-12 Kr-87 1.5E-14 Kr-88 9.2E-14 Kr-89 1.4E-15 Xe-131m 1.1E-13 Xe-133m 1.7E-13 Xe-133 1.5E-11 Xe-135m 3.4E-15 Xe-135 1.9E-13 Xe-137 2.4E-15 Xe-138 1.1E-14 I-131 1.5E-16 I-133 7.8E-16 H-3 9.4E-12 Fraction of 10CFR20 Unrestricted Area DAC 7.8E-7

Catawba Nuclear Station UFSAR Table 12-13 (Page 1 of 1)

(22 OCT 2001)

Table 12-13. Concentration Estimates of Airborne Radioactivity in the Control Room Isotope Concentration (µCi/ml)

Kr-83m 1.1E-13 Kr-85m 1.2E-12 Kr-85 6.3E-11 Kr-87 3.2E-13 Kr-88 2.0E-12 Kr-89 2.9E-14 Xe-131m 2.3E-12 Xe-133m 3.7E-12 Xe-133 3.2E-10 Xe-135m 7.3E-14 Xe-135 4.1E-12 Xe-137 5.1E-14 Xe-138 2.4E-13 I-131 3.2E-15 I-133 2.9E-15 H-3 2.0E-10 Fraction of 10CFR20 Restricted Area DAC 1.7E-5

Catawba Nuclear Station UFSAR Table 12-14 (Page 1 of 1)

(22 OCT 2001)

Table 12-14. Concentration Estimates of Airborne Radioactivity in Fuel Handling Area Isotope Concentration (µCi/ml)

Kr-83m 8.5E-14 Kr-85m 9.1E-13 Kr-85 4.9E-11 Kr-87 2.5E-13 Kr-88 1.5E-12 Kr-89 2.3E-14 Xe-131m 1.8E-12 Xe-133m 2.8E-12 Xe-133 2.5E-10 Xe-135m 5.7E-14 Xe-135 3.2E-12 Xe-137 4.0E-14 Xe-138 1.9E-13 I-131 2.5E-15 I-133 2.3E-15 H-3 1.4E-6 Fraction of 10CFR20 Restricted Area DAC

.07

Catawba Nuclear Station UFSAR Table 12-15 (Page 1 of 1)

(15 NOV 2007)

Table 12-15. Design Radiation Zones HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Zone Dose Rate Limit1 (mrem/hr)

Occupancy Examples I

2.0 Continuous

-Offsite areas II 0.5 Continuous

-Control Room

-Yard

-Service Building

-Turbine Building III 1.0 Extended

-Cable Room

-Battery Room

-Electrical Penetrations IV 2.5 Periodic

-Aux. Building Corridors

-Spent Fuel Pool Surface V

15.

Intermittent

-Incore Instrument Room

-Pipe Tunnel Cover VI

15. - 100 Infrequent

-Demineralizer Rooms

-Filter Rooms VII

>100 Infrequent

-Spent Resin Rooms

-NC Filter Rooms

-Evaporator Concentrate.

Note:

1. For anticipated operational occurrences

Catawba Nuclear Station UFSAR Table 12-16 (Page 1 of 1)

(22 OCT 2001)

Table 12-16. Present W E-Specs On Cobalt Content of Materials Weight Percent Cobalt Reactor Internals (SS) 0.12 maximum Reactor Vessel Clad (SS) 0.2 maximum RCS Piping (SS) 0.2 maximum Reactor Internal Bolting Materials (SS) 0.25 maximum RCS Pumps (SS) 0.2 maximum Auxiliary HX Surfaces Exposed to RCS (SS) 0.2 maximum Steam Generators (Inconel) 0.1 maximum(Unit 2)

Fuel (SS)2 0.12 maximum Fuel (SS) 0.08 maximum Fuel (Inconel) 0.1 maximum Fuel (Zircaloy) 0.002 maximum Notes:

1. SS = Stainless Steel

2. Refers to stainless steel outside active region on zircaloy clad fuel (e.g. top and bottom nozzles)

3. Refers to stainless steel inside active region

Catawba Nuclear Station UFSAR Table 12-17 (Page 1 of 4)

(22 OCT 2001)

Table 12-17. Catawba Radiation Zones - Reactor Building Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/Shutdown At Power Shutdown 12-1

1. Incore Tunnel VII VII No No Accessible only when thimbles are in core and prior to flux mapping process.

12-2

2. Inside Cranewall VII VII Very Limited No Radiation levels will greatly limit shutdown access.

3. Outside Cranewall -

pipe tunnel area VII VI Very Limited Yes Letdown, charging, seal water, and RHR piping in tunnel.

4. Annulus VII V

Limited Yes 12-3

5. Inside Cranewall VII Varies from VI to VII Very Limited Limited Radiation levels will remain high during shutdown due to corrosion products.

6. Accumulator Tank VII VII Very Limited Limited

7. Refueling Canal VII VII Limited Limited

8. Outside Cranewall VI VI Limited Limited

9. Regenerative and Excess Letdown Hx Rooms 116° VII VI No Limited Radiation levels will remain high due to Corrosion Products.

Catawba Nuclear Station UFSAR Table 12-17 (Page 2 of 4)

(22 OCT 2001)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/Shutdown At Power Shutdown

10. Annulus VII V

Limited Yes 12-4

11. Steam Generator Area VII VII Very Limited Limited

12. Pressurizer Area VII VII Very Limited Limited

13. Inside Cranewall VII VII Very Limited Limited

14. Refueling Canal VII VII Limited Limited

15. Reactor Vessel Area VII VII No Very Limited

16. Outside Cranewall VII VI Limited Yes

17. Annulus VII V

Limited Yes 12-5

18. Operating Level Reactor Vessel Area VI V

Limited Yes

19. Reactor Internals Stand Area VI V

Limited Yes

20. Steam Generator VII VII Very Limited Limited

Catawba Nuclear Station UFSAR Table 12-17 (Page 3 of 4)

(22 OCT 2001)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/Shutdown At Power Shutdown

21. Pressurizer Area VII VI Very Limited Limited

22. Outside Cranewall VI V

Limited Yes

23. Inside Cranewall Operating Floor VII VI Limited Limited 12-5

24. Annulus VI V

Limited Yes 12-6

25. Top of Steam Generator VII VI Limited Yes

26. Above Control Rod Drive Shield VII V

Limited Yes

27. Outside Cranewall VI V

Limited Yes

28. Annulus VI V

Limited Yes 12-7

29. Inside Containment Above Cranewall V

IV Limited Yes

30. Annulus VI V

Limited Yes 12-8

1. Inside Cranewall VII VI to VII Very Limited Limited

Catawba Nuclear Station UFSAR Table 12-17 (Page 4 of 4)

(22 OCT 2001)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/Shutdown At Power Shutdown

2. Incore Tunnel VII VII No No Access controlled by location of thimbles and incore detectors along with guide tube leakage.

3. Pipe Tunnel EL. 552+0 VII VI Very Limited Yes Letdown, charging, seal water, and RHR Piping in tunnel.

4. Incore Inst.

Rm.

V V

Limited Yes

5. Reactor Coolant Drain Tank Area EL.

552+0 VII VII Very Limited Limited 12-8

6. Equipment Compartment s Outside Cranewall Varies from V to VII (See plan views)

Limited Yes

7. Above Operating Floor VI V

Limited Yes

8. Upper Building section V

IV Limited Yes Notes:

1. Location numbering corresponds to that on drawings.

2. Reference Table 12-15 for definition.

Catawba Nuclear Station UFSAR Table 12-18 (Page 1 of 11)

(15 NOV 2007)

Table 12-18. Catawba Radiation Zones - Auxiliary Building Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power 12-9

1. Residual Heat Removal Pump Rooms 53-54 FF-HH VI VI Limited (not during refueling)

Corrosion product buildup on pump and piping is significant.

2. CS Pump Rooms 54-56 FF-HH IV IV Yes Manual controls necessary should be outside of rooms.

3. Corridors IV IV Yes CS Piping crosses corridor.

4. Covered Trench 56 FF-HH V

VI Yes Trench may be crossed to access controls in corridor. (Carries ND piping).

5. Chemical Drain Tk Room and Gas Decay Tk Pump Rooms VI VI No

6. Hot Side of Recycle Evap.

Skid 55-57 VII VII No No access while Evap. Operating.

7. Entrance to Recycle Evap.

Skid 55-57 V

V Yes Short term access while Evap. Operating, Concentrates transfer pump and heat exchanger operation may affect accessibility.

12-10 Refer to Figure 12-9 for similar area zoning 12-11 Refer to for Figure 12-12 similar area zoning.

Catawba Nuclear Station UFSAR Table 12-18 (Page 2 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power 12-12

1. Mechanical Penetration Area 51-53 GG-KK VII VI Very Limited Possible Airborne Contamination-High-maintenance equipment should not be located here.

2. Mechanical Penetration Area 52-53 GG-KK VI VI Limited RHR Lines during refueling.

3. Mechanical Penetration Area 50 KK VI V

Limited

4. Hot Skid of Waste Evap. 52 KK-MM VII VII No Process controlled.

5. Entrance to Waste Evap.

V V

Limited Concentrates transfer pump and heat exchanger operation may affect accessibility.

6. Recycle Holdup Tk Rooms 51-55 NN-QQ VII VII No No manually operated controls in room.

7. Waste Evap.

Feed Tk. Room 52-53 KK-LL VII VII No No manually operated controls in room.

8. Waste Drain Tk. Room 52-54 KK-LL VII VII No No manaully operated controls in room.

9. Pump Rooms 52-54 LL-MM VI VI Limited Located for valve bodies. Maintenance considerations are important.

Catawba Nuclear Station UFSAR Table 12-18 (Page 3 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

10. Charging Pump Rooms 53-54 JJ-JJ 54 56 HH-KK VII VII Only when drained for repair Safety Injection piping in Recip. Charging Pump Room.

11. S.I. Pump Rooms 53-54 GG-JJ IV IV Yes (Used for initial high pressure injection from RWST and for recirculation later).

12. Sample Hx Area 53 EE-FF VI VI Limited Corrosion Produts add significantly to radiation levels.

13. Accident Sample Panel Area 53-54 EE-FF VI VI Limited Normal operation dead legs located in in this area.

14. Pipe Trench 55-58 KK V

V Yes Radioactive piping in trench.

15. Recycle Evap.

Feed Pump and Valve Rooms 55-57 PP-QQ VI VI Limited Design for maintenance considerations.

16. Valve Operator Area IV IV Yes Contains controls for valve operations to reduce radiation exposures.

17. Corridor Areas IV IV Yes 12-13

1. Mechanical Penetration Area 61-64 GG-KK VII VI Very Limited Possible Airborne Contamination. High maintenance equipment should not be located here.

Catawba Nuclear Station UFSAR Table 12-18 (Page 4 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

2. Mechanical Penetration Area 61-62 EE-GG VI V

Limited Accident recirculation lines in area.

3. Mechanical Penetration Area VI V

Limited

4. Waste Gas Decay Tk.

Room 59-63 NC-QQ VII VII No No controls should be in area.

5. Waste Gas Valve Area 59-60 NN-QQ VII VII Limited Access for maintenance.

6. Gas Anal.

Rack-A Room 59-60 MM-NN V

V Processing controls radiation levels

7. Hydrogen Recombiner Room 60-61 MM-NN VI VI No Access limited due to operation of recombiner and WG piping in trench.

8. Gas Anal.

Rack-B 60-61 MM-NN VI VI Processing controls access. WG piping in trench limits access.

9. Hydrogen Recomb. Room 61-62 MM-NN VI VI No Limited access when recombiner not opening.

10. Waste Gas VII VII No Serves both Units

Catawba Nuclear Station UFSAR Table 12-18 (Page 5 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power Compressor Room 61-62 MM-NN

11. Waste Gas Compressor Room 62-63 MM-NN VII VII No Serves both Units.

12. LHST Pump Room 63 LL-MM V

V Limited

13. FDT Pump Room 63 KK-LL VI VI Limited

14. FDT & LHST Room VI VI Limited

15. Spent Resin Sluice Pump Room 61-62 LL-MM VI VI Accessible when isolated from SRST

16. SRST rooms 59-62 KK-MM VII VII No No valve or operators should be placed in rooms

17. SR Valve Room 59-60 LL-MM VII VII Limited accessibility when resins are not being handled.

18. Mixing and Settling Tank Room 59 KK-LL VI VI No Radiation levels vary dependent on material processed.

Catawba Nuclear Station UFSAR Table 12-18 (Page 6 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

19. Mixing And Settling Tank Room 59 KK-LL VI VI No Radiation levels vary dependent on material processed.

20. Charging Pump Rooms 58-61 HH-KK VII VII No Limited access when not in service.

21. Safety Injection Pump Rooms 60-61 GG-JJ IV IV Yes

22. Sample Hx Area 61 EE-FF VI VI Limited Corrosion add significantly to radiation level.

23. Accident Sample Panel 60 EE-FF VI VI Limited Normal operation dead legs located in this area.

24. Corridor Area IV IV Yes 12-14

1. Auxilliary Feedwater Pump Area 49-53, 61-65, AA-DD III III Yes 12-15 Refer to Figure 12-16 for similar zoning.

12-16

1. Mechanical Penetration Area 50-53 EE-KK VII VII Very Limited NV piping in area of VCT makes this a high radiation area.

Catawba Nuclear Station UFSAR Table 12-18 (Page 7 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

2. Entrance to MPA 53-54 EE-FF V

V Limited

3. Corridor Section in MPA & NV Valve Bodyarea 51 KK-MM + 53 KK-MM V

VI Limited RHR piping in area for shutdown cooling. Access depedent on resin sluice operations.

4. RHR & CS 11x Rooms 51-52 KK-MM VII VII No Corrosion Product buildup important.

5. Valve Body Room 51-52MM VI VI Limited

6. Recycle Holdup Tank Rooms 51-55 NN-QQ VII VII No No operators should be in area.

7. Filter and Demin. Rooms VII VII No Rooms are accessible when filter bale or resins are moved and equipment drained.

8. Seal Water Hx Room 53-54 GG VII VII No

9. Boronometer Room 53-54 FF VII VII Yes Deleted Per 2007 Update.

Catawba Nuclear Station UFSAR Table 12-18 (Page 8 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

10. Corridor Areas IV IV Yes 12-17 Refer to Figure 12-16 for similar area zoning 12-18 Refer to Figure 12-19 for similar area zoning.

12-19

1. Reactor Building Emergency Personnel Lock Area 67-69, 45-47 BB-DD IV IV Yes

2. Electrical Penetration Room 45-53, 61-69 AA-DD III III Yes 12-20 Refer to Figure 12-22 for similar area zoning 12-21 Refer to Figure 12-22 for similar area zoning.

12-22

1. Mechanical Penetration Room 61-63 GG-KK VI V

Limited NS supply piping in area.

2. Mechanical Penetration Room 62-64 JJ-MM V

V Limited NS supply piping in area.

3. Main Steam Doghouse 61-62 DD-GG IV III

4. RHR & CS Hx Rooms 62-63 KK-MM VII VII No Corrosions product buildup adds significantly to radiation level.

5. Hx Area 60-61 JJ-KK VII VII No Acessible when drained and flushed.

Catawba Nuclear Station UFSAR Table 12-18 (Page 9 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

6. Drum Storage Area 57-58 MM-QQ VII VII No Storage for Liners and drums. Accessibility controlled by activity.

7. Evap. Conc.

Holdup 59 NN-PP VII VII No Accessible when tank is drained and flushed.

8. Radwaste Batching Tank Room 59-60 NN-PP VII VII No Accessible when tank is drained and flushed.

9. Concentrates Batch 59 PP-QQ VII VII Limited Accessible when tank is drained and flushed.

10. Radwaste Feed Skid Room 59-60 PP-QQ VII VII No Accessible when flushed.

11. Fuel Pool Cooling Hx and Pump Room 61-63 NN-QQ V

V Limited

12. Fuel Pool Cooling Demin. Room 63 NN-PP VII VII No Accessible when demin. Is empty.

13. Corridor Areas IV IV Yes

14. Filter Bunker Access Hallway VI VI Limited Access limited due to concentrates transfer line and activity in concentrates batching tank.

Catawba Nuclear Station UFSAR Table 12-18 (Page 10 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

15. Filter Bunker Area Varies from IV to VII Varies from IV to VII Limited Access to this area is limited due to spent radioactive filter storage as well as periodic transfer of radioactive spent resins (piped through this area) from the Radwaste Batching Tank to the Waste Solidification facility.

12-23 Refer to Figure 12-24 for similar area zoning.

12-24

1. Electrical Penetration Room 45-53, 61-69 AA-DD III III Yes 12-25 Refer to Figure 12-26 for similar area zoning.

12-26

1. Annulus Ventilation Filter Area 50-53 GG-KK IV IV Yes

2. Doghouse 52-53 DD-GG IV IV Yes

3. RHR Hx and CS Hx Rooms 51-52 KK-MM VII VII No

4. Open Corridor Area 52-56 FF-MM IV IV Yes

5. Vent. Equipment Room 54-56 FF-HH III III Yes

6. Vent Equipment Room 54-60 EE-HH III III Yes

7. Fuel Pool Exhaust Filter Area 51-54 KK-QQ IV IV Yes

Catawba Nuclear Station UFSAR Table 12-18 (Page 11 of 11)

(15 NOV 2007)

Figure Location1 Radiation Zone2 Accessible Special Considerations Design Operation Refueling/

Shutdown At Power

8. Inst. Calibration Room 54-44 PP-QQ VII VII Accessibility determined by source position. For source in storage position, room is Zone III.

9. H.P Lab and Open Corridor Area 54-57 MM-QQ III III Yes

10. Open Corridor Area IV IV Yes 12-27 Refer to Figure 12-26 for similar area zoning 12-28

1. Control Room Area 53-60 AA-EE II II Yes

2. Vent. Equip. Area 54-60 EE III III Yes

3. Elect. Penet. Rooms 53-61 AA-DD III III Yes Notes:

1.

Location numbering corresponds to that on drawings.

2.

Reference Table 12-15 for definition.

Catawba Nuclear Station UFSAR Table 12-19 (Page 1 of 7)

(24 APR 2006)

Table 12-19. Design Shield Thickness Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Reactor Coolant System Vessel 543 FF-49 86.5 488 Note 1 6.0 Pump 560 GG-47 72 72 12-1,A/B 3.0 Steam Generator 577 FF-46 56.3 406 12-1,A/B 3.0(7)

Pressurizer 577 EE-49 40 240 12-1,C/B 3.0(7)

Pressurizer Relief Tank 594 DD-49 60 222 12-1,C 3.0 Safety Injection System Pump 543 HH-54 18 12 Note 2 2.0 Residual Heat Removal System Pump 522 GG-54 17.4 12 12-1,K 2.5(10)

Heat Exchanger 577 LL-52 21.75 377 12-1,K 2.5 Containment Spray System Pump 522 GG-55 8

12 Note 2 3.0 Heat Exchanger 577 LL-51 28 485 Note 2 2.5 Chemical & Volume Control System Regenerative Heat Exchanger 560 DD-51 5.2 174 12-1,A/G 3.0 Excess Letdown Heat Exchanger 560 DD-51 4.3 214 12-1,D 3.0(8)

Catawba Nuclear Station UFSAR Table 12-19 (Page 2 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Note:

Reciprocating Charging Pump No. 1 has been abandoned in place per NSM CN-11392/00.

Reciprocating Charging Pump No. 2 has been abandoned in place per NSM CN-21392/00.)

543 JJ-53 8

40 12-1,G 2.5 Centrifugal Charging Pump 543 JJ-55 7

40 12-1,G 2.0 Boric Acid Transfer Pump 560 PP-59 3.5 10 (note 3) 1.5 Letdown Heat Exchanger 577 KK-53 11 197 12-1,D 2.5 Seal Water Heat Exchanger 560 GG-54 10 140 12-1,G 2.0 Volume Control Tank 560 KK-50 45 110 12-1,F 3.0 Boric Acid Tank 560 PP-60 192 81 (note 3) 3.0 Mixed Bed Demineralizer 560 LL-53 15.75 43.75 12-2 4.0 (9)

Cation Bed Demineralizer 560 MM-53 12.75 36 12-2 4.0 Reactor Coolant Filter 560 KK-56 3

16.875 12-3 3.0

Catawba Nuclear Station UFSAR Table 12-19 (Page 3 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Seal Water Return Filter 560 LL-56 3

16.875 12-3 2.0 Seal Water Injection Filter 560 KK-56 1

19.5 12-3 2.5 Boric Acid Filter 560 NN-57 3

16.875 12-3 1.5 Boronometer 560 FF-54 6.65 18.7 12-1,F 2.0 Boron Recycle System Holdup Tank 543 PP-52 180 289 12-1,E 3.0 Evaporator 537 NN-56 21 119 12-1,L 3.0 Evaporator Feed Pump 543 PP-56 2

14 12-1,E 1.5 Evaporator Feed Demineralizer 560 QQ-57 15.5 43.75 12-2 4.0 Evaporator Feed Filter 560 NN-56 3

16.875 12-3 2.5 Evaporator Condensate Demineralizer 560 PP-57 12.75 36 12-2 1.5 Evaporator Condensate Filter 560 PP-57 1

9.875 12-3 1.5 Evaporator Concentrate Filter 560 PP-56 1

9.875 12-3 2.0 Boron Thermal Regeneration System Moderating Heat Exchanger 577 JJ-53 9

212 12-1,F 2.5

Catawba Nuclear Station UFSAR Table 12-19 (Page 4 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Letdown Chiller Heat Exchanger 577 JJ-54 10 206 12-1,F 2.5 Letdown Reheat Heat Exchanger 577 KK-54 281 71.1 12-1,D/F 2.5 Thermal Regeneration Demineralizer 560 LL-54 23.5 68 12-2 4.0 (9)

Liquid Radwaste System Evaporator Feed Tank 543 LL-53 54 126 12-1,H 2.5 Waste Drain Tank 543 LL-54 66 85 12-1,D 2.5 Evaporator Feed Pump 543 MM-53 2

14 12-1,H 3.0 Evaporator Feed Filter 560 KK-55 1

9.875 12-3 2.5 Waste Drain Tank Pump 543 MM-54 4

18 12-1,D 3.0 Evaporator 537 LL-52 21 119 12-1,L 3.0 Evaporator Condensate Demineralizer 560 KK-55 15.75 43.75 12-2 1.5 Evaporator Condensate Filter 560 MM-56 1

9.875 12-3 2.0 Reactor Coolant Drain Tank 543 HH-49 18 80 12-1,D 3.0 RCDT Heat Exchanger 543 GG-49 7

175 12-1,D 3.0 RCDT Pump 543 GG-48 5.5 15 12-1,D 3.0

Catawba Nuclear Station UFSAR Table 12-19 (Page 5 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Laundry & Hot Shower Tank 543 LL-63 64 178 12-1,I 1.5 LHST Pump 543 LL-63 4

8 12-1,I 1.5 LHST Primary Filter, Secondary Filter 560 LL-58 1

9.875 12-3 2.0 LHST Carbon Filter 560 KK-63 1

9.875 12-3 2.0 Waste Monitor Tank Filter 560 KK-59 1

9.875 12-3 1.0 Waste Monitor Tank Demineralizer 560 MM-62 15.75 43.75 12-2 3.0 Floor Drain Tank 543 KK-62 57 288 12-1,I 1.5 Floor Drain Tank Pump 543 KK-63 6

10 12-1,I 1.5 Floor Drain Tank Filter 560 LL-58 1

9.875 12-3 2.0 Mixing & Settling Tank 543 KK-59 30 66.5 12-1,I 1.5 Sludge Pump 543 KK-59 4

15 12-1,I 1.5 Mixing & Settling Tank Pump 543 KK-59 4

15 12-1,I 1.5 Solid Radwaste System Chemical Drain Tank 537 LL-55 21 120 12-1,H 3.0 Chemical Drain Tank Pump 537 LL-55 60 104 12-1,M 3.0 Spent Resin Storage Tank 543 LL-61 60 77 12-1,M 4.0

Catawba Nuclear Station UFSAR Table 12-19 (Page 6 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Spent Resin Sluice Filter 560 KK-59 3

16.875 12-3 3.0 Radwaste Batching Tank 577 PP-60 29.75 70.67 12-1,N 4.0(9)

Evaporator Concentrate Storage Tank 577 NN-59 42 126 12-1,L 3.0 Gaseous Radwaste System Compressor 543 NN-62 6

24.5 12-1,O 4.0 Tank 543 PP-61 60.5 92 12-1,O 4.0 Hydrogen Recombiner 543 NN-61 7

25 12-1,O 1.5 Spent Fuel Pool Cooling System SFPC Pump 577 QQ-52 11 15 Note 3 2.0 SFPC Heat Exchanger 577 PP-53 19.5 204 Note 3 2.0 SFPC Demineralizer 577 PP-51 35.75 60 12-2 2.0 SFPC Filter 560 LL-56 6

16.25 12-3 2.0 Skimmer Pump 577 QQ-52 7

4 Note 3 2.0 Skimmer Filter 560 MM-56 3

16.875 12-3 2.0 Nuclear Sampling System Heat Exchangers(4) 543 EE-53 2.4 14.4 12-1,A 2.0

Catawba Nuclear Station UFSAR Table 12-19 (Page 7 of 7)

(24 APR 2006)

Component Unit 1 Location Source el.

Column Lines Dimension5 Table/Flag Shield6 (ft)

R(in)

H(in)

Notes:

1. Source is reactor coolant activity and reactor core at full power.

2. Accident source only.

3. Minimal radioactivity expected. Shielding provided for conservatism.

4. Heat exchangers for potentially radioactive samples are located behind a shield wall in the Sample Room.

5. Dimensions are for a right circular cylinder unless otherwise noted.

6. Ordinary concrete or equivalent.

7. Biological shield provided above operating deck level for active height of component.

8. Intermittent use only. No shield on annulus side.

9. Hatch thickness of 3.0 feet have been determined to be adequate shielding.

10. Access to elevation 522 is prohibited Post-LOCA.

Catawba Nuclear Station UFSAR Table 12-20 (Page 1 of 1)

(22 OCT 2001)

Table 12-20. Primary Shield Description Region Material Thickness (in.)

Core Baffle Stainless Steel 1.125 Coolant Water 6.52 Core Barrel Stainless Steel 2.25 Coolant/Neutron pads1 Water/Stainless Steel 4.75/2.75 Pressure Vessel Carbon Steel 8.625 Gap Air, Insulation 7.00 Biological Shield Reinforced Concrete Detector Wells 72.0 Other 102.0 Note:

1. Neutron pads are affixed to the barrel and cover azimuthal regions which experience peak fast neutron exposures. There are four such panels covering the regions from 30° to 65°, 117° to 150°,

210° to 245°, and 297° to 330°.

Catawba Nuclear Station UFSAR Table 12-21 (Page 1 of 1)

(22 OCT 2001)

Table 12-21. Parameters Used for Design Basis Accident Analysis of Control Room Direct Dose Power level 3582 MWt Equivalent fraction of core melting 1.0 Fission product fractional releases Noble gases 1.0 Halogens 0.5 Remaining inventory 0.01 Minimum full power operating time 650 days Clean-up rate following accident 0.0 Containment net free volume 1.02 x 106 ft3 Post-accident water depth 15.2 ft Shielding (see Section 12.3.2.2)

Occupancy time 90 days

Catawba Nuclear Station UFSAR Table 12-22 (Page 1 of 1)

(22 OCT 2001)

Table 12-22. Design Basis Accident Containment Source Strength. (gammas/cc-sec) vs (hours after release)

Gas 0

1 24 720 2

0.2 MeV 3.9E8 0.2 2.7E8 0.2 2.4E8 0.1 1.4E8 0.1 4.2E6 0.5 6.6E8 0.5 3.9E8 0.5 3.1E8 0.5 1.1E8 0.4 6.1E6 0.9 5.3E8 0.9 3.1E8 0.9 2.0E8 0.9 1.8E7 0.8 2.9E6 1.4 1.7E8 1.4 1.6E8 1.4 1.2E8 1.3 2.9E7 1.6 4.8E5 2.0 1.7E8 2.1 9.4E7 2.1 6.7E7 1.9 1.8E6 2.2 1.7E4 3.0 2.8E7 2.7 1.2E7 2.7 7.4E6 2.5 1.8E5 2.5 1.7E4 Liquid 0

1 24 720 2

0.2 4.4E9 0.2 3.0E9 0.2 2.7E9 0.1 1.6E9 0.1 4.8E7 0.5 7.5E9 0.5 4.4E9 0.5 3.5E9 0.5 1.3E9 0.4 6.9E7 0.9 5.9E9 0.9 3.5E9 0.9 2.3E9 0.9 2.0E8 0.8 3.3E7 1.4 2.0E9 1.4 1.7E9 1.4 1.4E9 1.3 3.3E8 1.6 5.4E6 2.0 1.9E9 2.1 1.1E9 2.1 7.6E8 1.9 2.0E7 2.2 1.7E5 3.0 3.1E8 2.7 1.4E8 2.7 8.3E7 2.5 2.1E6 2.5 2.0E5

Catawba Nuclear Station UFSAR Table 12-23 (Page 1 of 7)

(24 APR 2006)

Table 12-23. Comparison of Control Room Area Ventilation System (VC) Filtration System with Regulatory Guide 1.52, Revision 2, March 1978 Paragraph Compliance Status Comments A.

In compliance This section contains general introductory information. CNS is considered in compliance with this information.

B.

See comments This section contains a general discussion that CNS is considered in compliance with. It should be noted that the VC filter units were designed in accordance with ANSI/ASME N509-76. However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-

80.

C.

See comments This section contains general information that CNS is considered in compliance with. It should be noted that the VC filter units were designed in accordance with ANSI/ASME N509-76. However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-

80.

C-1-a In compliance CNS-1211.00-11 C-1-b In compliance

a. Original post-accident shielding calculations were performed in accordance with Reg. Guides 1.4 and 1.25, as well as, requirements outlined in NUREG 0737.

b. Environmental Qualification Criteria Manual.

c. Refer to Reg. Guide section C-3-i for specific values used to meet this criteria.

C-1-c In compliance This general philosophy was followed in the design of the filter units.

C-1-d In compliance Environmental Qualification Criteria Manual C-1-e In compliance

a. Environmental Qualification Criteria Manual

b. NUREG 0588 Review

Catawba Nuclear Station UFSAR Table 12-23 (Page 2 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-2-a In compliance

a. CNS-1211.00-11 (Filter Units)

b. CNS-1211.00-05 Supplement 2 (Ductwork)

c. CNS-1211.00.06 (Fans)

C-2-b In compliance

a. Electrical Discipline Design Manual, Design Criteria 1.02 (electrical separation)

b. CNS-1108.02-00-0001 (missiles)

C-2-c In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 2 (Ductwork)

c. CNS-1211.00-06 (Fans)

C-2-d In compliance This atmospheric clean-up system is not subject to any containment pressure surges.

C-2-e In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 2 (Ductwork)

c. CNS-1211.00-06 (Fans)

C-2-f In compliance The VC filter unit design flow rate is 6,000 cfm.

C-2-g See comments Instrument gauges are provided for flow and pressure drops C-2-h See comments In compliance with IEEE Standard 279 and, to the extent applicable, IEEE Standard 334.

Compliance with Regulatory Guides 1.30, 1.32, 1.89, 1.100 and 1.118 is discussed in UFSAR Section 8.1.5.

C-2-i In compliance System operation is initiated by redundant, safety related load sequencers.

C-2-j See comments Filter units will not be removed as intact units.

Gasketless filter adsorbers will be used - the design of which permits the fluidizing of the carbon bed for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as low level radwaste.

C-2-k In compliance The location and design of the VC system intakes protects them from environmental effects.

Catawba Nuclear Station UFSAR Table 12-23 (Page 3 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-2-l See comments Startup testing was done in accordance with ANSI/ASME N509-1976 and ASME/ANSI N510-1975. Current and future testing will utilize ANSI/ASME N509-80 and ANSI/ASME N510-80.

C-3-a See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-b See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-c See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-d See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-e See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-f See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-g See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11

Catawba Nuclear Station UFSAR Table 12-23 (Page 4 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-h See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-i See comments

a. CNS complies to the requirements of ANSI/ASME N509-80.

b. Specified residence time is based on actual bed thickness and screen area.

C-3-j See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-k See comments

a. Heat generation is addressed in CNC-1227.00-00-0120

b. System does include low-flow air bleed system and water sprays but these components do not meet the single failure criteria nor do they provide the required low humidity air.

C-3-l See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 2

c. CNS-1211.00-06 C-3-m In compliance

a. Environmental Qualification Criteria Manual

b. CNS-1211.00-06 C-3-n See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria except ANSI/ASME N509-80 is followed.

b. CNS-1211.00-05 Supplement 2 C-3-o See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

Catawba Nuclear Station UFSAR Table 12-23 (Page 5 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-p See comments

a. This requirement applied to the initial design of the dampers. The dampers were designed, in general, to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 2 C-4-a See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-4-b In compliance Since all filter banks are arranged for external servicing, three linear feet of separation between filter banks is not needed. Two and one-half feet between filter banks is provided for inspection purposes.

C-4-c See comments

a. Testing is done per ANSI/ASME N510-80.

b. CNS generally uses a grain thief to obtain carbon samples although the filter units are designed to allow for the use of test canisters.

C-4-d See comments In general, CNS complies with this requirement. However, since carbon sample testing is done in accordance with ASTM D-3803, moisture is not a significant concern.

Thus, operation of the heaters for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is interpreted as an option not as a requirement.

C-4-e In compliance This requirement applied to the initial design of the plant. Filters will only be removed for future "construction" activities if those activities will significantly degrade the filters.

C-5-a See comments In compliance except ANSI/ASME N510-80 is used.

C-5-b See comments In compliance except ANSI/ASME N510-80 will be used for current and future air uniformity tests. Initial tests were in conformance with ANSI/ASME N510-75.

Catawba Nuclear Station UFSAR Table 12-23 (Page 6 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-5-c See comments

a. ANSI/ASME N510-80, section 9, "Air-Aerosol Mixing Uniformity Test" will not be performed on the downstream HEPA banks.

b. ANSI/ASME N510-80, section 10, "In-Place Leak Test, HEPA Filter Banks" will not be performed on the downstream HEPA banks.

c. ANSI/ASME N510-80 will be used for current and future in-place DOP tests.

Initial tests were in conformance with ANSI/ASME N510-75.

d. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-5-d See comments

a. The <0.01 ppm residual refrigerant will not be verified in the air system following the challenge of the carbon adsorber bed.

Instead, the system will be run with the preheaters energized for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months following the test, to drive off any excess refrigerant.

b. In compliance except ANSI/ASME N510-80 will be used for current and future in-place carbon penetration tests. Initial tests were in conformace with ANSI/ASME N510-75.

c. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-6-a See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 98.05% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 0.95%."

Catawba Nuclear Station UFSAR Table 12-23 (Page 7 of 7)

(24 APR 2006)

Paragraph Compliance Status Comments C-6-b See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 98.05% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 0.95%."

c. Footnote c of Table 2 should read "after 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months of operation" not "after 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of operation."

d. A grain thief is an acceptable method for obtaining representative carbon samples.

e. Use of grain thief shall be in accordance with MP/0/A/7450/031 and this shall be assumed to meet all requirements of this section.

f. Carbon shall meet the requirements of ANSI/ASME N509-80 and shall be tested in accordance with ASTM D-3803-89.

D.

See comments Clarifications to Regulatory Guide 1.52 are contained within this table, the CNS Technical Specifications and PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

These clarifications and differences are considered to meet the intent of Regulatory Guide 1.52.

Catawba Nuclear Station UFSAR Table 12-24 (Page 1 of 8)

(24 APR 2006)

Table 12-24. Comparison Of Auxiliary Building Ventilation System (VA) Filtration System with Regulatory Guide 1.52, Revision 2, March 1978 Paragraph Compliance Status Comments A.

In compliance This section contains general introductory information. CNS is considered in compliance with this information.

B.

See comments This section contains a general discussion that CNS is considered in compliance with. It should be noted that the VA filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C.

See comments This section contains general information that CNS is considered in compliance with. It should be noted that the VA filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C-1-a In compliance CNS-1211.00-11 C-1-b In compliance

a. Original post-accident shielding calculations were performed in accordance with Reg. Guide 1.4 and the requirements outlined in NUREG 0737.

b. Environmental Qualification Criteria Manual.

c. Refer to Reg. Guide section C-3-i for specific values used to meet this criteria.

C-1-c In compliance This general philosophy was followed in the design of the filter units.

C-1-d In compliance Environmental Qualification Criteria Manual

Catawba Nuclear Station UFSAR Table 12-24 (Page 2 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-1-e In compliance

a. Environmental Qualification Criteria Manual

b. NUREG 0588 Review C-2-a In compliance

a. CNS-1211.00-11 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-b In compliance

a. Electrical Discipline Design Manual, Design Criteria 1.02 (electrical separation)

b. CNS-1108.02-00-0001 (missiles)

C-2-c In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-d In compliance This atmospheric clean-up system is not subject to any containment pressure surges.

C-2-e In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-f In compliance

a. The VA filter unit design flow rate is 30,000 cfm. An allowance of 10%

over this flowrate is acceptable.

b. The HEPA filter arrangement is five wide and four high.

C-2-g See comments Instrument gauges are provided for flow and pressure drops C-2-h See comments In compliance with IEEE Standard 279 and, to the extent applicable, IEEE Standard 334. Applicability and compliance with Reg Guides 1.30, 1.32, 1.89, 1.100 and 1.118 are as discussed in UFSAR Section 8.1.5.

C-2-i In compliance System operation is initiated by redundant, safety related load sequencers.

Catawba Nuclear Station UFSAR Table 12-24 (Page 3 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-2-j See comments Filter units will not be removed as intact units. Gasketless filter adsorbers will be used - the design of which permits the fluidizing of the carbon bed for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as low level radwaste.

C-2-k In compliance The VA filter system does not have any outside air intakes.

C-2-l See comments Startup testing was done in accordance with ANSI/ASME N509-1976 and ASME/ANSI N510-1975. Current and future testing will utilize ANSI/ASME N509-80 and ANSI/ASME N510-80.

C-3-a See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-b See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-c See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-d See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-e See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11

Catawba Nuclear Station UFSAR Table 12-24 (Page 4 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-f See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-g See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-h See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-i See comments

a. CNS complies to the requirements of ANSI/ASME N509-80.

b. Specified residence time is based on actual bed thickness and screen area.

C-3-j See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-k See comments

a. Heat generation is addressed in CNC-1227.00-00-0120.

b. System does include low-flow air bleed system and water sprays but these components do not meet the single failure criteria nor do they provide the required low humidity air.

C-3-l See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 5

c. CNS-1211.00-13 C-3-m In compliance

a. Environmental Qualification Criteria Manual

b. CNS-1211.00-13

Catawba Nuclear Station UFSAR Table 12-24 (Page 5 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-n See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria except ANSI/ASME N509-80 is followed.

b. CNS-1211.00-05 Supplement 5 C-3-o See comments

a. This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-3-p See comments

a. This requirement applied to the initial design of the dampers. The dampers were designed, in general, to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 5 C-4-a See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-4-b In compliance Since all filter banks are arranged for external servicing, three linear feet of separation between filter banks is not needed. Two and one-half feet between filter banks is provided for inspection purposes.

C-4-c See comments

a. Testing is done per ANSI/ASME N510-80.

b. CNS generally uses a grain thief to obtain carbon samples although the filter units are designed to allow for the use of test canisters.

C-4-d See comments In general, CNS complies with this requirement. However, since carbon sample testing is done in accordance with ASTM D-3803, moisture is not a significant concern. Thus, operation of the heaters for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is interpreted as an option not as a requirement.

C-4-e In compliance This requirement applied to the initial design of the plant. Filters will only be removed for future "construction" activities if those activities will significantly degrade the filters.

Catawba Nuclear Station UFSAR Table 12-24 (Page 6 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-5-a See comments In compliance except ANSI/ASME N510-80 is used.

C-5-b See comments In compliance except ANSI/ASME N510-80 will be used for current and future air uniformity tests. Initial tests were in conformance with ANSI/ASME N510-75.

C-5-c See comments

a. ANSI/ASME N510-80, section 9, "Air-Aerosol Mixing Uniformity Test" will not be performed on the downstream HEPA banks.

b. ANSI/ASME N510-80, section 10, "In-Place Leak Test, HEPA Filter Banks" will not be performed on the downstream HEPA banks.

c. In compliance except ANSI/ASME N510-80 will be used for current and future in-place DOP tests. Initial tests were in conformance with ANSI/ASME N510-75.

d. The upstream HEPA filters will meet a DOP penetration criteria of

<1.0% in accordance with FOL Amendment 227/222.

e. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

Catawba Nuclear Station UFSAR Table 12-24 (Page 7 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-5-d See comments

a. The <0.01 ppm residual refrigerant will not be verified in the air system following the challenge of the carbon adsorber bed. Instead, the system will be run with the preheaters energized for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months following the test, to drive off any excess refrigerant.

b. In compliance except ANSI/ASME N510-80 will be used for current and future in-place carbon penetration tests. Initial tests were in conformance with ANSI/ASME N510-75.

c. The upstream HEPA filters will meet a penetration criteria of <1.0%

in accordance with FOL Amendment 227/222.

d. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-6-a See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 92% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

Catawba Nuclear Station UFSAR Table 12-24 (Page 8 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-6-b See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 92% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

c. A grain thief is an acceptable method for obtaining representative carbon samples.

d. Use of grain thief shall be in accordance with MP/0/A/7450/031 and this shall be assumed to meet all requirements of this section.

e. Carbon shall meet the requirements of ANSI/ASME N509-80 and shall be tested in accordance with ASTM D-3803-89.

D.

See comments Clarifications to Regulatory Guide 1.52 are contained within this table, the CNS Technical Specifications and PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP). These clarifications and differences are considered to meet the intent of Regulatory Guide 1.52.

Catawba Nuclear Station UFSAR Table 12-25 (Page 1 of 8)

(24 APR 2006)

Table 12-25. Comparison Of Fuel Handling Building Ventilation System (VF) Filtration System with Regulatory Guide 1.52, Revision 2, March 1978 Paragraph Compliance Status Comments A.

In compliance This section contains general introductory information. CNS is considered in compliance with this information.

B.

See comments This section contains a general discussion that CNS is considered in compliance with. It should be noted that the VF filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C.

See comments This section contains general information that CNS is considered in compliance with. It should be noted that the VF filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C-1-a In compliance CNS-1211.00-11 C-1-b In compliance

a. Original post-accident shielding calculations were performed in accordance with Reg. Guides 1.3, 1.4 and 1.25, as well as, requirements outlined in NUREG 0737.

b. Environmental Qualification Criteria Manual.

c. Refer to Reg. Guide section C-3-i for specific values used to meet this criteria.

C-1-c In compliance This general philosophy was followed in the design of the filter units.

C-1-d In compliance Environmental Qualification Crtieria Manual

Catawba Nuclear Station UFSAR Table 12-25 (Page 2 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-1-e In compliance

a. Environmental Qualification Criteria Manual

b. NUREG 0588 Review C-2-a In compliance

a. CNS-1211.00-11 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-b In compliance

a. Electrical Discipline Design Manual, Design Criteria 1.02 (electrical separation)

b. CNS-1108.02-00-0001 (missiles)

C-2-c In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-d In compliance This atmospheric clean-up system is not subject to any containment pressure surges.

C-2-e In compliance

a. CNS-1211.00-00-0011 (Filter Units)

b. CNS-1211.00-05 Supplement 5 (Ductwork)

c. CNS-1211.00-13 (Fans)

C-2-f In compliance The VF filter unit design flow rate is 16,565 cfm.

C-2-g See comments Instrument gauges are provided for flow and pressure drops C-2-h See comments In compliance with IEEE Standard 279 and, to the extent applicable, IEEE Standard 334. Applicability and compliance with Reg Guides 1.30, 1.32, 1.89, 1.100 and 1.118 are as discussed in UFSAR Section 8.1.5.

C-2-i In compliance System is in operation whenever irradiated fuel is being moved in the storage pool and during crane operation with loads over the storage pool.

Catawba Nuclear Station UFSAR Table 12-25 (Page 3 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-2-j See comments Filter units will not be removed as intact units. Gasketless filter adsorbers will be used - the design of which permits the fluidizing of the carbon bed for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as low level radwaste.

C-2-k In compliance The VF filter system does not have any outside air intakes.

C-2-l See comments Startup testing was done in accordance with ANSI/ASME N509-1976 and ASME/ANSI N510-1975. Current and future testing will utilize ANSI/ASME N509-80 and ANSI/ASME N510-80.

C-3-a See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-b See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-c See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-d See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-e See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11

Catawba Nuclear Station UFSAR Table 12-25 (Page 4 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-f See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-g See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-h See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-i See comments

a. CNS complies to the requirements of ANSI/ASME N509-80.

b. Specified residence time is based on actual bed thickness and screen areas.

C-3-j See comments

a. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

b. CNS-1211.00-11 C-3-k See comments

a. Heat generation is addressed in CNC-1211.00-00-0108

b. System does include low-flow air bleed system and water sprays but these components do not meet the single failure criteria nor do they provide the required low humidity air.

C-3-l See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 5

c. CNS-1211.00-13

Catawba Nuclear Station UFSAR Table 12-25 (Page 5 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-m In compliance

a. Environmental Qualification Criteria Manual

b. CNS-1211.00-13 C-3-n See comments

a. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria except ANSI/ASME N509-80 is followed.

b. CNS-1211.00-05 Supplement 5 C-3-o See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-3-p See comments

a. This requirement applied to the initial design of the dampers. The dampers were designed, in general, to be in compliance with this criteria.

b. CNS-1211.00-05 Supplement 5 C-4-a See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-4-b In compliance Since all filter banks are arranged for external servicing, three linear feet of separation between filter banks is not needed. Two and one-half feet between filter banks is provided for inspection purposes.

C-4-c See comments

a. Testing is done per ANSI/ASME N510-80.

b. CNS generally uses a grain thief to obtain carbon samples although the filter units are designed to allow for the use of test canisters.

C-4-d See comments In general, CNS complies with this requirement. However, since carbon sample testing is done in accordance with ASTM D-3803, moisture is not a significant concern. Thus, operation of the heaters for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is interpreted as an option not as a requirement.

Catawba Nuclear Station UFSAR Table 12-25 (Page 6 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-4-e In compliance This requirement applied to the initial design of the plant. Filters will only be removed for future "construction" activities if those activities will significantly degrade the filters.

C-5-a See comments In compliance except ANSI/ASME N510-80 is used.

C-5-b See comments In compliance except ANSI/ASME N510-80 will be used for current and future air uniformity tests. Initial tests were in conformance with ANSI/ASME N510-75.

C-5-c See comments

a. ANSI/ASME N510-80, section 9, "Air-Aerosol Mixing Uniformity Test" will not be performed on the downstream HEPA banks.

b. ANSI/ASME N510-80, section 10, "In-Place Leak Test, HEPA Filter Banks" will not be performed on the downstream HEPA banks.

c. In compliance except ANSI/ASME N510-80 will be used for current and future in-place DOP tests. Initial tests were in conformance with ANSI/ASME N510-75.

d. The upstream HEPA filters will meet a penetration criteria of <1.0%

in accordance with Generic Letter 83-13.

e. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

Catawba Nuclear Station UFSAR Table 12-25 (Page 7 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-5-d See comments

a. The <0.01 ppm residual refrigerant will not be verified in the air system following the challenge of the carbon adsorber bed. Instead, the system will be run with the preheaters energized for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months following the test, to drive off any excess refrigerant.

b. In compliance except ANSI/ASME N510-80 will be used for current and future in-place carbon penetration tests. Initial tests were in conformance with ANSI/ASME N510-75.

c. The carbon filters will meet a penetration criteria of <1.0% in accordance with Generic Letter 83-

13.

d. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-6-a See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 95% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

Catawba Nuclear Station UFSAR Table 12-25 (Page 8 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-6-b See comments

a. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

b. For decontamination efficiencies of 95% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

c. A grain thief is an acceptable method for obtaining representative carbon samples.

d. Use of grain thief shall be in accordance with MP/0/A/7450/031 and this shall be assumed to meet all requirements of this section.

e. Carbon shall meet the requirements of ANSI/ASME N509-80 and shall be tested in accordance with ASTM D-3803-89.

D.

See comments Clarifications to Regulatory Guide 1.52 are contained within this table, the CNS Technical Specifications and PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP). These clarifications and differences are considered to meet the intent of Regulatory Guide 1.52.

Catawba Nuclear Station UFSAR Table 12-26 (Page 1 of 8)

(24 APR 2006)

Table 12-26. Comparison Of Annulus Ventilation System (VE) Filtration System with Regulatory Guide 1.52 Revision 2, March 1978 Paragraph Compliance Status Comments A.

In compliance This section contains general introductory information. CNS is considered in compliance with this information.

B.

See comments This section contains a general discussion that CNS is considered in compliance with. It should be noted that the VE filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C.

See comments This section contains general information that CNS is considered in compliance with. It should be noted that the VE filter units were designed in accordance with ANSI/ASME N509-76.

However, CNS also may refer to ANSI/ASME N509-80 for some design criteria. Also, pre-startup testing was done per ANSI/ASME N510-75, but current testing is done in accordance with ANSI/ASME N510-80.

C-1-a In compliance CNS-1211.00-11 C-1-b In compliance

1. Original post-accident shielding calculations were performed in accordance with Reg. Guide 1.4 and the requirements outlined in NUREG 0737.

2. Environmental Qualification Criteria Manual.

3. Refer to Reg. Guide section C-3-i for specific values used to meet this criteria.

C-1-c In compliance This general philosophy was followed in the design of the filter units.

C-1-d In compliance Environmental Qualification Criteria Manual

Catawba Nuclear Station UFSAR Table 12-26 (Page 2 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-1-e In compliance

1. Environmental Qualification Criteria Manual

2. NUREG 0588 Review C-2-a In compliance

1. CNS-1211.00-11 (Filter Units)

2. CNS-1211.00-05 Supplement 6 (Ductwork)

3. CNS-1211.00-06 (Fans)

C-2-b In compliance

1. Electrical Discipline Design Manual, Design Criteria 1.02 (electrical separation)

2. CNS-1108.02-00-0001 (missiles)

C-2-c In compliance

1. CNS-1211.00-00-0011 (Filter Units)

2. CNS-1211.00-05 Supplement 6 (Ductwork)

3. CNS-1211.00-06 (Fans)

C-2-d In compliance This atmospheric clean-up system is not subject to any containment pressure surges.

C-2-e In compliance

1. CNS-1211.00-00-0011 (Filter Units)

2. CNS-1211.00-05 Supplement 6 (Ductwork)

3. CNS-1211.00-06 (Fans)

C-2-f In compliance The VE filter unit design flow rate is 9,000 cfm.

C-2-g See comments Instrument gauges are provided for flow and pressure drops C-2-h See comments In compliance with IEEE Standard 279 and, to the extent applicable, IEEE Standard 334. Applicability and compliance with Reg Guides 1.30, 1.32, 1.89, 1.100 and 1.118 are as discussed in UFSAR Section 8.1.5.

C-2-i In compliance

1. System operation is initiated by redundant, safety related load sequencers.

Catawba Nuclear Station UFSAR Table 12-26 (Page 3 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-2-j See comments Filter units will not be removed as intact units. Gasketless filter adsorbers will be used - the design of which permits the fluidizing of the carbon bed for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as low level radwaste.

C-2-k In compliance The VE filter system does not have any outside air intakes.

C-2-l See comments Startup testing was done in accordance with ANSI/ASME N509-1976 and ASME/ANSI N510-1975. Current and future testing will utilize ANSI/ASME N509-80 and ANSI/ASME N510-80.

C-3-a See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-b See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-c See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-d See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-e See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11

Catawba Nuclear Station UFSAR Table 12-26 (Page 4 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-f See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-g See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-h See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-i See comments

1. CNS complies to the requirements of ANSI/ASME N509-80.

2. Specified residence time is based on actual bed thickness and screen data.

C-3-j See comments

1. This requirement applied to the initial design of the filter units. The filter units were designed to be in compliance with this criteria.

2. CNS-1211.00-11 C-3-k See comments

1. Heat generation is addressed in CNC-1227.00-00-0120.

2. System does include low-flow air bleed system and water sprays but these components do not meet the single failure criteria nor do they provide the required low humidity air.

C-3-l See comments

1. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria.

2. CNS-1211.00-05 Supplement 6

3. CNS-1211.00-06 C-3-m In compliance

1. Environmental Qualification Criteria Manual

2. CNS-1211.00-06

Catawba Nuclear Station UFSAR Table 12-26 (Page 5 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-3-n See comments

1. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria except ANSI/ASME N509-80 is followed.

2. CNS-1211.00-05 Supplement 6 C-3-o See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria, however, the discharge connection to the Unit Vent is a water trap.

C-3-p See comments

1. This requirement applied to the initial design of the dampers. The dampers were designed, in general, to be in compliance with this criteria.

2. CNS-1211.00-05 Supplement 6 C-4-a See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-4-b In compliance Since all filter banks are arranged for external servicing, three linear feet of separation between filter banks is not needed. Two and one-half feet between filter banks is provided for inspection purposes.

C-4-c See comments

1. Testing is done per ANSI/ASME N510-80.

2. CNS generally uses a grain thief to obtain carbon samples although the filter units are designed to allow for the use of test canisters.

C-4-d See comments In general, CNS complies with this requirement. However, since carbon sample testing is done in accordance with ASTM D-3803, moisture is not a significant concern. Thus, operation of the heaters for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is interpreted as an option not as a requirement.

Catawba Nuclear Station UFSAR Table 12-26 (Page 6 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-4-e In compliance This requirement applied to the initial design of the plant. Filters will only be removed for future "construction" activities if those activities will significantly degrade the filters.

C-5-a See comments In compliance except ANSI/ASME N510-80 is used.

C-5-b See comments In compliance except ANSI/ASME N510-80 will be used for current and future air uniformity tests. Initial tests were in conformance with ANSI/ASME N510-75.

C-5-c See comments

1. ANSI/ASME N510-80, section 9, "Air-Aerosol Mixing Uniformity Test" will not be performed on the downstream HEPA banks.

2. ANSI/ASME N510-80, section 10, "In-Place Leak Test, HEPA Filter Banks" will not be performed on the downstream HEPA banks.

3. In compliance except ANSI/ASME N510-80 will be used for current and future in-place DOP tests. Initial tests were in conformance with ANSI/ASME N510-75.

4. The upstream HEPA filters will meet a penetration criteria of <1.0%

in accordance with FOL Amendment 227/222.

5. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

Catawba Nuclear Station UFSAR Table 12-26 (Page 7 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-5-d See comments

1. The <0.01 ppm residual refrigerant will not be verified in the air system following the challenge of the carbon adsorber bed. Instead, the system will be run with the preheaters energized for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months following the test, to drive off any excess refrigerant.

2. In compliance except ANSI/ASME N510-80 will be used for current and future in-place carbon penetration tests. Initial tests were in conformace with ANSI/ASME N510-75.

3. The upstream HEPA filters will meet a penetration criteria of <1.0%

in accordance with FOL Amendment 227/222.

4. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-6-a See comments

1. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

2. For decontamination efficiencies of 92% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

Catawba Nuclear Station UFSAR Table 12-26 (Page 8 of 8)

(24 APR 2006)

Paragraph Compliance Status Comments C-6-b See comments

1. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

2. For decontamination efficiencies of 92% given in Table 2, the Laboratory Test for Representative Sample should be "a methyl iodide penetration of less than 4%."

3. A grain thief is an acceptable method for obtaining representative carbon samples.

4. Use of grain thief shall be in accordance with MP/0/A/7450/031 and this shall be assumed to meet all requirements of this section.

5. Carbon shall meet the requirements of ANSI/ASME N509-80 and shall be tested in accordance with ASTM D-3803-89.

D.

See comments Clarifications to Regulatory Guide 1.52 are contained within this table, the CNS Technical Specifications and PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP). These clarifications and differences are considered to meet the intent of Regulatory Guide 1.52.

Catawba Nuclear Station UFSAR Table 12-27 (Page 1 of 1)

(22 OCT 2001)

Table 12-27. Filter System Design Parameters System Carbon Bed (Minimum Depth, In.)

Heater Size (KW)

Annulus Ventilation 2

45 Control Room Area Pressurizing 4

25 Fuel Handling Area Exhaust 2

80 Auxiliary Building Filtered Exhaust 2

30 Containment Purge Exhaust 2

120

Catawba Nuclear Station UFSAR Table 12-28 (Page 1 of 7)

(21 OCT 2009)

Table 12-28. Comparison of Containment Purge Ventilation System (VP) Filtration System with Regulatory Guide 1.52, Revision 2, March 1978 Paragraph Compliance Status Comments A.

See comments

1. The Containment Purge Filter System is not an engineered safety feature and, thus, Reg Guide 1.52 is not applicable to the system. However, since some credit is taken for the system in the dose analysis, this comparison is presented to indicate the level of adherence to Reg.

Guide 1.52.

2. System design is based on normal plant operation and shutdown modes.

System design does, however, ensure a safe release path from the containment in the event of a fuel handling accident inside containment with the purge system operating.

3. Reference to the Containment Purge Filter System (VP) and/or the VP filters in this comparison is meant to include the CPES filters but not the incore instrumentation filters.

B.

See comments

1. See comments for section A.

2. Guidance from ANSI N510 is used to support periodic testing including Technical Specification Requirements.

C.

See comments This section contains general information that CNS is considered in compliance with.

It should be noted that the VP filter units were designed in accordance with ANSI/ASME N509-76. However, CNS also may refer to ANSI/ASME N509-80 for some design criteria.

C-1-a See comments See comments for section A.

C-1-b See comments

1. Reg Guide 1.4 does not apply as the Containment Purge System is Technical Specification limited such that a LOCA is not postulated while the system is in operation.

2. Environmental Qualification Criteria Manual.

C-1-c See comments See comments for section C-1-b.

Catawba Nuclear Station UFSAR Table 12-28 (Page 2 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-1-d See comments

1. The Containment Purge System is Technical Specification limited such that a LOCA is not postulated while the system is in operation.

2. Environmental Qualification Criteria Manual C-1-e In compliance Environmental Qualification Criteria Manual C-2-a See comments System design provides two (2) 50%

capacity filter trains and fans. System design does not include demisters or HEPA filters downstream of the adsorbers.

Heaters can be used to control relative humidity prior to filtration but are not necessary since carbon sample testing is done in accordance with ASTM D-3803-89.

C-2-b See comments

1. See comments for section C-2-a.

2. Electrical Discipline Design Manual, Design Criteria 1.02 (electrical separation)

3. CNS-1108.02-00-0001 (missiles)

C-2-c See comments

1. CNS-1211.00-00-0012 (Filter Units)

2. CNS-1211.00-05 Supplement 6 (Ductwork)

C-2-d See comments The Containment Purge System is isolated during the pressure surge resulting from a postulated LOCA. The system is not required to operate during or after the postulated LOCA.

C-2-e In compliance

1. CNS-1211.00-00-0012 (Filter Units)

2. CNS-1211.00-05 Supplement 6 (Ductwork)

C-2-f In compliance The VP filter unit design flow rate is below 30,000 cfm.

C-2-g See comments System instrument consists of local flow and pressure drop indication. System discharge flow is totalized and indicated locally. System discharge flow is not recorded at the control room.

Catawba Nuclear Station UFSAR Table 12-28 (Page 3 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-2-h See comments

a. Not applicable - the system is not designated as Class 1E electrical except for its containment isolation functions.

C-2-i In Compliance The Containment Purge System operates continuously during fuel handling activities within the containment. No credit is taken for filtration by the Containment Purge Exhaust System during a postulated fuel handling accident involving non-recently irradiated fuel in the containment. All containment penetrations open to the outside atmosphere must be exhausting through an operable Containment Purge Exhaust System during the movement of recently irradiated fuel assemblies within the containment.

C-2-j See comments Filter units will not be removed as intact units. Gasketless filter adsorbers are used -

which permits the fluidizing of the carbon bed for external filling and removal. In this manner, CNS complies with the ALARA recommendations.

C-2-k In compliance The VP filter system does not have any outside air intakes.

C-2-l See comments The VP filters are not ESF atmospheric cleanup systems.

C-3-a See comments

1. This requirement applied to the initial design of the filter units.

2. The system does not include demisters.

3. CNS-1211.00-12 C-3-b See comments

1. This requirement applied to the initial design of the filter units.

2. Heaters are Seismic Category II.

3. CNS-1211.00-12 C-3-c See comments

1. This requirement applied to the initial design of the filter units.

2. Prefilters are tested in accordance with ASHRAE Standard 52 and carry UL Class 2 labels.

3. CNS-1211.00-12

Catawba Nuclear Station UFSAR Table 12-28 (Page 4 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-3-d See comments

1. This requirement applied to the initial design of the filter units.

2. CNS-1211.00-12 C-3-e See comments

1. This requirement applied to the initial design of the filter units.

2. CNS-1211.00-12 C-3-f See comments

1. This requirement applied to the initial design of the filter units.

2. CNS-1211.00-12 C-3-g See comments

1. This requirement applied to the initial design of the filter units.

2. CNS-1211.00-12 C-3-h See comments

1. This requirement applied to the initial design of the filter units.

2. CNS-1211.00-12 C-3-i See comments

1. The VP system is not an ESF system.

2. Specified residence time is based on actual bed thickness and screen area.

C-3-j See comments

1. This requirement applied to the initial design of the filter units

2. CNS-1211.00-12 C-3-k See comments Adsorber section design includes a manual water spray system. Single-failure criterion is not considered in its design.

C-3-l See comments

1. This requirement applied to the initial design of the system.

2. CNS-1211.00-05 Supplement 6 C-3-m In compliance Environmental Qualification Criteria Manual C-3-n See comments

1. This requirement applied to the initial design of the system. The system was designed to be in compliance with this criteria except ANSI/ASME N509-80 is followed.

2. CNS-1211.00-05 Supplement 6 C-3-o See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

Catawba Nuclear Station UFSAR Table 12-28 (Page 5 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-3-p See comments

1. This requirement applied to the initial design of the dampers. The dampers were designed, in general, to be in compliance with this criteria.

2. CNS-1211.00-05 Supplement 6 C-4-a See comments This requirement applied to the initial design of the system. The system was designed, in general, to be in compliance with this criteria.

C-4-b See comments Since all filter banks are arranged for external servicing, three linear feet of separation between filter banks is not needed. Two and one-half feet between filter banks are provided for inspection purposes.

C-4-c See comments

1. Testing is done per ANSI/ASME N510-

80.

2. CNS generally uses a grain thief to obtain carbon samples although the filter units are designed to allow for the use of test canisters.

C-4-d See comments

1. Containment purge system operation is Technical Specification limited.

2. In general, CNS complies with this requirement. However, since carbon sample testing is done in accordance with ASTM D-3803, moisture is not a significant concern. Thus, operation of the heaters for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months is interpreted as an option not as a requirement.

C-4-e In compliance This requirement applied to the initial design of the plant. Filters will only be removed for future "construction" activities if those activities will significantly degrade the filters.

C-5-a See comments In compliance except ANSI/ASME N510-80 is used.

C-5-b See comments In compliance except ANSI/ASME N510-89 will be used for current and future airflow distribution tests. Initial tests were in conformance with ANSI/ASME N510-

75.

Catawba Nuclear Station UFSAR Table 12-28 (Page 6 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-5-c See comments

1. The "Air-Aerosol Mixing Uniformity Test" acceptance criteria shall be that all concentration readings are >50% of the average reading. The HEPA and carbon upstream sample probes will be located at the lowest concentration reading.

2. In compliance except ANSI/ASME N510-80 will be used for current and future in-place DOP tests. Initial tests were in conformance with ANSI/ASME N510-75.

3. A DOP penetration criteria is <1.0%

instead of <0.05%. (reference Generic Letter 83-13)

4. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

C-5-d See comments

1. The <0.01 ppm residual refrigerant will not be verified in the air stream following the challenge of the carbon adsorber bed. Instead, the system will be run with the preheaters energized for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months following the test, to drive off any excess refrigerant.

2. In compliance except ANSI/ASME N510-80 will be used for current and future in-place carbon penetration tests.

Initial tests were in conformance with ANSI/ASME N510-75.

3. The carbon adsorber penetration criteria is <1.0% instead of <0.05%. (reference Generic Letter 83-13)

4. Painting, fire and chemical release are as defined in PT/0/A/4450/020, Ventilation Filter Testing Program (VFTP).

Catawba Nuclear Station UFSAR Table 12-28 (Page 7 of 7)

(21 OCT 2009)

Paragraph Compliance Status Comments C-6-a See comments

1. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

2. For decontamination efficiencies of 90% given in Table 2, the Laboratory Test for Representative Sample should be a "methyl iodide penetration of less than 6%."

C-6-b See comments

1. References to ANSI N509-1976 should be interpreted to be ANSI/ASME N509-80.

2. Table 2 does not apply. Instead, a 6%

methyl iodide penetration and a 1%

inplace penetration are used to correspond with a decontamination factor of 6.7.

3. A grain thief is an acceptable method for obtaining representative carbon samples.

4. Use of grain thief shall be in accordance with MP/0/A/7450/031 and this shall be assumed to meet all requirements of this section.

5. Carbon shall meet the requirements of ANSI/ASME N509-80 and shall be tested in accordance with ASTM D-3803-89.

D.

See comments The Containment Purge Filter System is not an engineered safety feature and, thus, Reg Guide 1.52 is not applicable to the system.

However, since some credit is taken for the system in the dose analysis, this comparison is presented to indicate the level of adherence to Reg Guide 1.52.

Catawba Nuclear Station UFSAR Table 12-29 (Page 1 of 4)

(21 OCT 2010)

Table 12-29. Area Radiation Monitoring System Detector Number Identification Location Sensitivity Range Accuracy 1EMF1 Auxiliary Building Corridor EL 522 FF, 57 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF2 Sample Room EL 543 EE-FF, 54 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF3 Charging Pump Area EL 543 GG, 55 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF5 Auxiliary Building Corridor EL 543 NN, 53 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF7 Auxiliary Building Corridor EL 560 NN, 55 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF9 Filter Hatch Area EL 577 LL, 55 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF12 Control Room EL 594 CC, 57 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF16 Waste Shipping Area EL 594 RR, 58 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF13 Hot Machine Shop EL 594 VV, 55 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF14 Hot Chemistry Laboratory EL 609 UU, 60 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF15 Refueling Bridge - Spent Fuel Building EL 605 + 10 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF11 Incore Instrument Room EL 570 + 3 53'6", 90° 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF17 Refueling Bridge -

Reactor Building EL 605 + 10 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF1 Sample Room EL 543 EE-FF, 60 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

Catawba Nuclear Station UFSAR Table 12-29 (Page 2 of 4)

(21 OCT 2010)

Detector Number Identification Location Sensitivity Range Accuracy 1EMF4 Charging Pump Area EL 543 GG, 59 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF6 Auxiliary Building Corridor EL 543 MM, 61-62 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF8 Auxiliary Building Corridor EL 560 NN, 59 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF10 Filter Hatch Area EL 577 LL, 58 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF4 Refueling Bridge - Spent Fuel Building EL 605 + 10 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF3 Incore Instrument Room EL 570 53'6", 90° 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF2 Refueling Bridge -

Reactor Building EL 605 + 10 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF18 Reactor Coolant Filter 1A EL 568 KK, 56 1 x 10-10 Amps R/hr 10 104 R/hr

+/-15%

1EMF19 Reactor Coolant Filter 1B EL 568 KK-LL,56 1 x 10-10 Amps R/hr 10 104 R/hr

+/-15%

2EMF5 Reactor Coolant Filter 2A EL 568 KK-LL,58 1 x 10-10 Amps R/hr 10 104 R/hr

+/-15%

2EMF6 Reactor Coolant Filter 2B EL 568 KK-LL, 58 1 x 10-10 Amps R/hr 10 104 R/hr

+/-15%

1EMF20 New Fuel Storage Area 1A EL 610 VV, 51 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF21 New Fuel Storage Area 1B EL 610 VV, 49 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

Catawba Nuclear Station UFSAR Table 12-29 (Page 3 of 4)

(21 OCT 2010)

Detector Number Identification Location Sensitivity Range Accuracy 2EMF7 New Fuel Storage Area 2A EL 611+11 VV, 65 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF8 New Fuel Storage Area 2B EL 611+11 VV, 63 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF22 Reactor Building Purge Filter-Unit 1 EL 594 KK, 53 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF9 Reactor Building Purge Filter-Unit 2 EL 594 KK, 61 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

EMF24 Technical Support Center EL 601 U, 26 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

EMF23 Waste Solidification Pad EL 594 WW, 57A 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF26 Main Steam Line Loop A EL 601 GG, 43 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF27 Main Steam Line Loop B EL 601 GG, 53 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF28 Main Steam Line Loop C EL 601 GG, 53 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

1EMF29 Main Steam Line Loop D EL 601 GG, 44 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF10 Main Steam Line Loop A EL 601 GG, 70 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF11 Main Steam Line Loop B EL 601 GG, 61 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF12 Main Steam Line Loop C EL 601 GG, 61 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

2EMF13 Main Steam Line Loop D EL 601 GG, 70 120 hr

/

mR min

/

counts 10 104 mR/hr

+/-15%

EMF80 Waste Monitor Tank Building Pipe Chase MTB EL 594 D-1a 110 hr

/

mR min

/

counts 10 104 mR/hr

+/-10%

Catawba Nuclear Station UFSAR Table 12-29 (Page 4 of 4)

(21 OCT 2010)

Detector Number Identification Location Sensitivity Range Accuracy EMF81 Waste Monitor Tank Building Sump Corridor MTB EL 594 F-2 110 hr

/

mR min

/

counts 10 104 mR/hr

+/-10%

EMF82 Waste Monitor Tank Building Truck Bay MTB EL 594 B-4 110 hr

/

mR min

/

counts 10 104 mR/hr

+/-10%

Catawba Nuclear Station UFSAR Table 12-30 (Page 1 of 2)

(22 OCT 2001)

Table 12-30. Estimated - Station Organization and Work Area Total per Work Area Total per Work Area Total per Work Area Personnel and Staff Technical Services Maintenance Office1:

90/10(2):

Manager Secretary Superintendent Clerks Nurse Security 1

1 1

32 1

214 36 214 Office1:

Superintendent Licensing & Projects Performance Engr.

Chemist Radiation Protection Clerks 1

1 1

9 14 Office:

Superintendent Engr (I&E)

Maint. Engr.

Planning Engr.

Materials Super.

Materials Personnel Clerks 1

1 1

23 11 40 50/503:

Engineering &

Supervisors Safety Assts.

9 3

12 50/50:

Engr (Licensing &

Proj)

Engr (Performance)

Asst Chemist Asst R.P.

13 12 16 17 25 33 50/50:

Engr & Supv (I&E)

Engr & Supv (Maint)

Engr (Planning) 18 19 15 18 34 Office:

OPERATIONS Superintendent Clerks 1

4 5

Field:

Tech (Performance)

Tech (Chemist)

Tech (R.P.)

10 46 46 10 92 Field:

Tech. (I&E)

Tech. (Maint.)

P.M. Personnel 60 55 5

60 60(1) 50*/504:

Operating Eng Asst Oper Eng 4

3 7

MISC Control Area:

Shift Super Asst Shift Sup Control Oper Asst Cntl Oper 7

13 15 10 45 50/50:

SSD Station Maint Sup Janitorial Quality Assurance Outside Vendors 100 150 50 39 10 250 99 Field:

Operators Enginering 43 12 55 Office:

Transmission 8

Catawba Nuclear Station UFSAR Table 12-30 (Page 2 of 2)

(22 OCT 2001)

Total per Work Area Total per Work Area Total per Work Area Notes:

1. 100% Of Time In Office

2. 90% In Office, 10% In Field

3. 50/50, 50% Office, 50% Field

4. 50*/50, 50% in Control Area, 50% Time In Field

Catawba Nuclear Station UFSAR Table 12-31 (Page 1 of 2)

(22 OCT 2001)

Table 12-31. Dose Assessment - Number of Personnel and Times of Occupancy in Radiation Areas Radiation Work Areas Personnel and Staff Man/Hrs per Week Maintenance Misc.

Operations Tech. Services 92/7.2 60(1)/12

1. Aux. Bldg. Corridors 214/4 7/2 33/3.6 60/6 99/8 3/10 55/4 10/4 18/2 250/4 9/8 25/2 34/6 92/7.2 34/1.6 250/.4

2. Sample Room and Hot Lab 9/4 7/1 33/3.6 60/1 55/2 10/2 25/1

3. Letdown Recycle 7/2 92/7.2 60/2 250/1 55/4 33/3.6 18/2 10/4 60(1)/6 25/2 34/1.6

4. Waste Gas 7/2 92/7.2 18/2 250/1 55/4 33/3.6 60/2 10/4 34/1.6 25/2 60(1)/6

5. Liquid Waste 7/2 92/7.2 18/2 250/1 55/4 33/3.6 60/2 10/4 34/1.6 25/2 60(1)/6

Catawba Nuclear Station UFSAR Table 12-31 (Page 2 of 2)

(22 OCT 2001)

Radiation Work Areas Personnel and Staff Man/Hrs per Week Maintenance Misc.

Operations Tech. Services

6. Solid Waste 7/1 92/4 34/1.6 250/.6 55/2 33/2 60/1 10/2 25/1 60(1)/4

7. Turbine Bldg 3/10 7/10 10/20 18/2 99/8 9/4 55/20 25/10 60/6 250/8 34/6 60(1)/6

8. Control Room 9/4 7/20 18/10 99/4 45/40 60/20 250/4

9. Service & Admin Bldg, Outside 36/40 5/40 14/40 40/40 8/40 214/36 58/20 52/20 250/20 3/20 99/20 9/20 Note:

1. 100% of time in office.

Catawba Nuclear Station UFSAR Table 12-32 (Page 1 of 2)

(15 NOV 2007)

Table 12-32. Routine Operation Dose Assessment HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Radiation Work Area Personnel and Staff Operations Tech. Services Maint.

Misc. SMS SSD Total Man-Rem Week Total Man-Rem Year Weekly Occupancy (Man Hrs/Week)

Dose Rate (R/Hr) = Man-Rem/Week

1. Aux. Bldg.

Corridors 958.*5.3E-4 =.51 234.*5.3E-4 =.13 871*5.3E-4 =.46 1320*5.3E-4 =

.70 1792*5.3E-4 =

.95 2.75 143.

2. Sample Rm.

& Hot Lab 36*2.E-4 =.01 117*2.E-4 =.02 826*2.E-4 =.17 114.4*2.E-4 =.02 100*2.E-4 =.02

.24 12.5

3. Letdown &

Recycle 234*4.E-4 =.09 871*4.E-4 =.35 570.4*4.E-4 =.23 250*2.E-3 =.50 1.17 60.8

4.

Waste Gas 234*2.E-4 =.05 871*2.E-4 =.17 570.4*2.5E-3 =

1.43 250*2.5E-3 =.63 2.28 118.6

5. Liquid Waste 234*1.E-3 =.23 871*1.E-3 =.87 570.4*2.E-3 =

1.14 250*2.E-3 =.50 2.74 142.5

6. Solid Waste 117*1.E-3 =.12 479*4.E-4 =.19 354.4*1.E-3 =.35 150*1.E-3 =.15

.81 42.1

7. Turbine Bldg 66*5.E-5 =.003 1170*5.E-5 =.06 450*5.E-5 =.02 960*5.E-5 =.05 2792*5.E-5 =.14

.27 14.0

8. Contron Area 36*5.E-5 =.002 1940*5.E-5 =.10 1380*5.E-5 =.07 1396*5.E-5 =.07

.24 12.5

9. Service &

Admin Bldg.,

Outside 9384*5.E-6 =.05 200*5.E-6 =.001 1720*5.E-6 =.01 2640*5.E-6 =.01 7300*5.E-6 =.04

.11 5.7 Work Group Exposure (Man-Rem) wk

.58

.80 2.24 4.0 3.0 TOTAL STATION DOSE NORMAL OPERATIONS

Catawba Nuclear Station UFSAR Table 12-32 (Page 2 of 2)

(15 NOV 2007)

Radiation Work Area Personnel and Staff Operations Tech. Services Maint.

Misc. SMS SSD Total Man-Rem Week Total Man-Rem Year Weekly Occupancy (Man Hrs/Week)

Dose Rate (R/Hr) = Man-Rem/Week 52 wks/year (Man-Rem) yr 30.2 41.6 116.5 208.

156.

552 MAN-REM YEAR Exposure Per Individual Per Year

.12

.37

.67

.98

.44

~5 REM PERSON-YEAR

Catawba Nuclear Station UFSAR Table 12-33 (Page 1 of 1)

(15 NOV 2007)

Table 12-33. Total Occupational Radiation Exposure Estimates (for one unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Activity Average Annual Exposure (man-rem/yr)

Reactor operations and surveillance 31.5 Routine maintenance 83.4 Waste processing 11.6 Refueling 43.6 Inservice inspection 16.3 Special maintenance 17.5 TOTAL 203.9

Catawba Nuclear Station UFSAR Table 12-34 (Page 1 of 2)

(15 NOV 2007)

Table 12-34. Occupational Radiation Exposure Estimate for Reactor Operations and Surveillance (for one unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose (man-rem)

Containment Building Routine patrols 0.025 39.8 0.99 Operations supervision Note 1 9.9 Inspect reactor coolant drain tank 0.100 0.25 Annual 0.025 Inspect accumulators, pressurizer, relief tanks, etc.

1.100/0.005 0.0025(2) 1/3/1(2)

Annual 0.115 Inspect post-accident hydrogen electric recombiner 0.0025 4

Annual 0.010 Reactor Auxiliary Building Routine patrols 0.0025 1650 4.12 Boron thermal regeneration system chiller and chiller pump units inspection 0.0025 0.033 Shift 0.09 Inspect letdown reheat, letdown chiller, letdown, moderating, and seal water heat exchangers, and associated pumps & valves 0.100 0.066 Shift 7.2 Inspect volume control tank valve room 0.100 0.017 Shift 1.9 Inspect centrifugal charging pumps and associated valves 0.100 0.033 Shift 3.6 Inspect demineralizer valve area 0.025 0.17 Shift 0.9 Inspect boric acid tank, pumps and valves, recycle evaporator, and transfer pumps 0.025 0.083 Shift 2.3 Inspect surge tank 0.0025 4

Monthly 0.12 Inspect boric acid batching tank 0.005 0.17 Shift 0.2 Inspect chemical mixing tank 0.0025 0.017 Shift 0.046 Inspect reactor makeup water pump 0.0025 0.017 Shift 0.046

Catawba Nuclear Station UFSAR Table 12-34 (Page 2 of 2)

(15 NOV 2007)

Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose (man-rem)

Notes:

1. All radiation areas.

2. X/Y dose rate and A/B time indicates A man-hours in X radiation field and B man-hours in Y radiation field.

Catawba Nuclear Station UFSAR Table 12-35 (Page 1 of 2)

(15 NOV 2007)

Table 12-35. Occupational Radiation Exposure Estimate For Routine Maintenance (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose (man-rem)

Containment Building Service reactor coolant drain tank pumps 0.100 9

Annual 0.9 Service reactor coolant drain tank heat exchangers 0.100 9

Annual 0.9 Service reactor coolant drain tank cooler 0.100 5

Annual 0.5 Service incore instrumentation drive systems 0.025 20 Annual 0.5 Inspect and service excess letdown and regenerative heat exchangers 0.100 13 Annual 1.3 Routine maintenance service

1. Pumps (except reactor coolant pumps) 0.025 168 Annual 4.2

2. Valves 0.100 172 Annual 17.2

3. Miscellaneous items 0.0025 360 Annual 0.9 Service reactor coolant pumps including oil change (4 pumps per year) and cartridge seal replacement (1 pump per year) 0.100 48 Annual 4.8 Service excore detectors 0.100 5

Annual 0.5 Reactor Auxiliary Building Service boron thermal regeneration system chiller pump 0.0025 9

Annual 0.02 Service centrifugal charging pumps 0.025 150 Annual 3.8 Service boric acid and recycle evaporator feed pumps 0.025 9

Annual 0.2 Chemical and volume control system filter cartridge replacement 0.10 41 Annual 4.1 Valve maintenance (general) of nuclear steam supply system components 0.100 6

Weekly 29 Service boron recycle evaporator package 0.100/0.0251 5/451 Annual 1.63 Integrated leak rate test of nuclear steam supply system fluid systems 0.005 400 Annual 2.0 Inspect and service RHR heat exchangers &

pumps 0.100 13 Annual 1.3 Inspect and service hydrostatic test pump 0.0025 12 Annual 0.03

Catawba Nuclear Station UFSAR Table 12-35 (Page 2 of 2)

(15 NOV 2007)

Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose (man-rem)

Inspect and service boron thermal regeneration system chillers and chiller surge tank 0.0025 10 Weekly 1.30 Inspect and service boron injection recirculation pump 0.0025 8

Monthly 0.24 Service boric acid filter and tanks 0.100 4

Monthly 4.80 Inspect and service boron monitoring system 0.0025 0.5 Shift 1.37 Inspect and service CCW heat exchangers, pumps & surge tank 0.0025 2.0 Weekly 0.26 Service reactor makeup water pump 0.0025 32 Annual 0.08 Service thermal regeneration demineralizers 0.100 16 Annual 1.6 Note:

1. X/Y dose rate and A/B time indicates A man-hours in X radiation field and B man-hours in Y radiation field.

Catawba Nuclear Station UFSAR Table 12-36 (Page 1 of 1)

(15 NOV 2007)

Table 12-36. Occupational Radiation Exposure Estimate For Waste Processing (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose (man-rem)

Inspect and service catalytic recombiner gas analyzer 0.005 16 Annual 0.08 Inspect waste evaporator system 0.100 0.17 Weekly 0.88 Inspect waste gas system 0.100 0.17 Weekly 0.88 Inspect chemical drain tank and pump 0.100 0.17 Weekly 0.88 Inspect high activity spent resin storage tank 0.100 0.17 Monthly 0.20 Service liquid waste processing system 0.100 27 Annual 2.70 Service spent resin sluice pump 0.050 17 Annual 0.85 Service floor drain tank pump 0.0025 9

Annual 0.02 Service waste evaporators 0.100 51 Annual 5.10

Catawba Nuclear Station UFSAR Table 12-37 (Page 1 of 2)

(15 NOV 2007)

Table 12-37. Occupational Radiation Exposure Estimate For Refueling (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Annual Dose (man-rem)

Clean cavity prior to refueling 0.025 40 1.0 Remove earthquake bars 0.025 8

0.2 Remove reactor vessel insulation 0.100 8

0.8 Remove blind flange 0.100 1

0.1 Disconnect control rod drive mechanism cables 0.025 7

0.18 Disconnect thermocouples (2) 0.500 1

0.5 Retract incore thimbles 0.025 24 0.60 Detension and remove reactor vessel studs 0.050 51 2.6 Install stud hole plugs 0.050 10 0.50 Install cavity seal ring 0.050 14 0.7 Attach main 0.025 4

0.1 Remove head and upper in-ternals and store 0.050 12 0.6 Perform fuel shuffle 6.0

1. Fuel handling in containment

a. Check out refueling equipment 0.100/0.005(1) 8/24(1) 0.9(1)

b. Perform fuel shuffle (64 assemblies) 0.005 600 3.0

c. Perform quality assurance on core reload 0.005 15 0.08

2. Fuel handling in fuel handling building

a. Check out refueling equipment 0.005/0.0025(1) 16/16(1) 0.12

b. Perform fuel shuffle

.0025 360 0.9

c. Inspect and change out spent fuel pool demineralizers 0.100 4

0.4

Catawba Nuclear Station UFSAR Table 12-37 (Page 2 of 2)

(15 NOV 2007)

Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Annual Dose (man-rem)

Clean, inspect, and test studs and tentioners 0.025 20 0.5 Change head O-rings 0.500 4

2.0 Install head and upper internals 0.050 12 0.6 Clean reactor cavity 0.050 50 2.5 Clean reactor vessel flange 0.500 10 5.0 Install incore thimbles 0.005 20 0.1 Remove stud hole plugs 0.050 16 0.8 Clean stud holes 0.050 16 0.8 Install and tension reactor vessel studs 0.050 153 8.0 Install blind flange 0.500 3

1.5 Reconnect control rod drive mechanism 0.025 4

0.1 Connect thermocouples(2) 0.500 2

1.0 Remove cavity seal ring 0.050 6

0.3 Install reactor vessel insulation 0.100 8

0.8 Install earthquake bars 0.025 12 0.3 Note:

1. X/Y dose rate and A/B time indicates A man-hours in X radiation field and B man-hours in Y radiation field.

Catawba Nuclear Station UFSAR Table 12-38 (Page 1 of 1)

(15 NOV 2007)

Table 12-38. Occupational Radiation Exposure Estimate For Inservice Inspection (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose Over 10-Year Period (man-rem)

Inservice inspection or reactor vessel and reactor coolant piping 0.100 580 1 per 10 years(1) 5.8 Insulation removal from reactor vessel nozzle and reactor coolant piping 0.100 200 1 per 10 years(1) 2.0 Snubber inspection of reactor coolant piping 0.005 2200 1 per 10 years(1) 1.1 Steam generator inservice inspection (4 steam generators) 0.125 470 1 per 10 years(1) 5.9 Steam generator eddy current inspection 0.015 600 Note 2

1.5 Notes

1. Inservice inspection is performed over a 10-year period on a schedule defined in the Technical Specifications.

2. Per Regulatory Guide 1.83, eddy current inspection for steam generator tubes would occur at year 1, year 2, year 5, and year 8. Two steam generators are inspected at year 1 and one steam generator is inspected in subsequent years.

Catawba Nuclear Station UFSAR Table 12-39 (Page 1 of 1)

(15 NOV 2007)

Table 12-39. Occupational Radiation Exposure Estimate For Special Maintenance1 (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Item Average Expected Dose Rate (rem/hr)

Time (man-hr)

Frequency Annual Dose Over 10-Year Period (man-rem)

Steam generator tube plugging 0.24 52 1 per 2 years 6.1 Steam generator tube plug welding 0.21 52 1 per 10 years 1.1 Sludge lancing 0.06 160 1 per year 9.8 Control rod drive mechanism repair 0.50 5

1 per 5 years 0.5 Note:

1. These data reflect dose estimates for projected special maintenance and repair tasks and do not include dose estimates for uniques tasks that may be performed on limited basis such as unforeseen major repair tasks or unusual inspection efforts.

Catawba Nuclear Station UFSAR Table 12-40 (Page 1 of 1)

(21 APR 2011)

Table 12-40. RCA Description and RCA Control Points Elevation Auxiliary Building RCA Control Points RCA Description Location Type 522' All of the elev. is inside RCA N/A N/A 543' All of the elev. is inside RCA N/A N/A 550' Unit 2 UHI Building. All of the elev. is inside RCA Unit 2 Yard Limited Access 3 560' All of the elev. is inside RCA with the following exceptions: Rooms 362, 363, 372, 373 and the diesel generator rooms.

BB 45, 69 Limited Access2 CC 53, 61 Limited Access2 577' All of the elev. is inside RCA U 36 (Service Bldg)

Main Entrance Exit Point 594' All of elev. is inside RCA with the following exceptions: Rooms 564, 573, 574, 575 and sections of 563 and 576.

HH 42, 72 Limited Access2 DD 60 Limited Access2 VV 58 Limited Access2 UU 47, 67 Limited Access2 VV 48, 55, 59, 60, 62 Limited Access2 AA 48, 66 Limited Access2 WW61 Normal Use1 609' All of elev. is inside RCA with the following exceptions: Chemistry/RP Office at North end.

RR 52 Limited Access2 Notes:

1. Normal use-Entrance/exit point

2. Limited Access-access controlled by Radiation Protection.

3. Temporary SPA for the MOX Fuel Project. Limited Access-access controlled by Radiation Protection.

Catawba Nuclear Station UFSAR Table 12-41 (Page 1 of 1)

(22 OCT 2001)

Table 12-41. Design Source Strengths for the Retired Steam Generator Storage Facility Radionuclide Curies Zr-95 8.44E-2 Nb-95m 3.45E-1 Tc-99 3.45E-1 Ru-103 6.33E-3 Ru-106 4.85E-1 Sb-124 3.52E-3 Sb-125 1.06E+0 Ce-144 1.16E+0 C14 1.20E-1 Cv-51 1.71E+0 Mn-54 3.46E+0 Fe-55 2.95E+0 Co-58 2.53E+1 Fe-59 1.05E-1 Co-60 3.25E+1 Co-57 1.13E-2 Total 6.97E+1 (Note: Each Steam Generator)

ML19189A264

Text

1.5 Notes

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