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1 to Updated Final Safety Analysis Report, Chapter 12, Tables
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Site:	Catawba
Issue date:	04/02/2020
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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)

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 3.4E4 2.2E4 4.2E3 2.0E3 1.8E2 1.2E2 Condensate Recycle Evaporator 1.6E5 8.4E5 3.7E5 4.5E4 3.5E3 2.0E3 Concentrate 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 - 3.4E7 8.9E6 - - -

Evaporator Feed Floor Drain Tank Laundry & Hot Shower Tank (primary & secondary carbon)

(22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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.

(22 OCT 2001)

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

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

Mechanical Penetration Recycle Evap. Feed Recycle Evap. Package Isotope Seal Water HX (1 Unit) (El. 543') (1 Unit) Pump (2 Units) (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 (22 OCT 2001)

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

Reciprocal Charging Isotope Centri. Charging Pump 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 (22 OCT 2001)

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

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

Filter 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 (22 OCT 2001)

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

Recycle Evap. Feed Demin.

Isotope 1A / 1B Letdown Reheat HX Letdown Chiller HX Waste Gas Comp.

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 1.4E-5 Unrestricted Area DAC (22 OCT 2001)

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

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 30 Restricted Area DAC H-3 (during refueling) 1.2E-6 (22 OCT 2001)

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

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 7.8E-7 Unrestricted Area DAC (22 OCT 2001)

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

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 1.7E-5 Restricted Area DAC (22 OCT 2001)

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

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 .07 Restricted Area DAC (22 OCT 2001)

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

Table 12-15. Design Radiation Zones HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Dose Rate Limit1 Zone (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 (15 NOV 2007)

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

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 (22 OCT 2001)

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

Table 12-17. Catawba Radiation Zones - Reactor Building Radiation Zone2 Accessible Design Figure Location1 Operation Refueling/Shutdown At Power Shutdown Special Considerations 12-1 1. Incore VII VII No No Accessible only when thimbles are Tunnel in core and prior to flux mapping process.

12-2 2. Inside VII VII Very No Radiation levels will greatly limit Cranewall Limited shutdown access.

3. Outside VII VI Very Yes Letdown, charging, seal water, Cranewall - Limited and RHR piping in tunnel.

pipe tunnel area

4. Annulus VII V Limited Yes 12-3 5. Inside VII Varies from VI to VII Very Limited Radiation levels will remain high Cranewall Limited during shutdown due to corrosion products.

6. Accumulator VII VII Very Limited Tank Limited

7. Refueling VII VII Limited Limited Canal

8. Outside VI VI Limited Limited Cranewall

9. Regenerative VII VI No Limited Radiation levels will remain high and Excess due to Corrosion Products.

Letdown Hx Rooms 116° (22 OCT 2001)

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

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

10. Annulus VII V Limited Yes 12-4 11. Steam VII VII Very Limited Generator Limited Area

12. Pressurizer VII VII Very Limited Area Limited

13. Inside VII VII Very Limited Cranewall Limited

14. Refueling VII VII Limited Limited Canal

15. Reactor VII VII No Very Limited Vessel Area

16. Outside VII VI Limited Yes Cranewall

17. Annulus VII V Limited Yes 12-5 18. Operating VI V Limited Yes Level Reactor Vessel Area

19. Reactor VI V Limited Yes Internals Stand Area

20. Steam VII VII Very Limited Generator Limited (22 OCT 2001)

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

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

21. Pressurizer VII VI Very Limited Area Limited

22. Outside VI V Limited Yes Cranewall

23. Inside VII VI Limited Limited Cranewall Operating Floor 12-5 24. Annulus VI V Limited Yes 12-6 25. Top of Steam VII VI Limited Yes Generator

26. Above VII V Limited Yes Control Rod Drive Shield

27. Outside VI V Limited Yes Cranewall

28. Annulus VI V Limited Yes 12-7 29. Inside V IV Limited Yes Containment Above Cranewall

30. Annulus VI V Limited Yes 12-8 1. Inside VII VI to VII Very Limited Cranewall Limited (22 OCT 2001)

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

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

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

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

4. Incore Inst. V V Limited Yes Rm.

5. Reactor VII VII Very Limited Coolant Limited Drain Tank Area EL.

552+0 12-8 6. Equipment Varies from Limited Yes Compartment V to VII (See s Outside plan views)

Cranewall

7. Above VI V Limited Yes Operating Floor

8. Upper V IV Limited Yes Building section Notes:

1. Location numbering corresponds to that on drawings.

2. Reference Table 12-15 for definition.

(22 OCT 2001)

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

Table 12-18. Catawba Radiation Zones - Auxiliary Building Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations 12-9 1. Residual Heat VI VI Limited (not Corrosion product buildup on pump and piping is Removal during significant.

Pump Rooms refueling) 53-54 FF-HH

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

FF-HH

3. Corridors IV IV Yes CS Piping crosses corridor.

4. Covered V VI Yes Trench may be crossed to access controls in Trench 56 FF- corridor. (Carries ND piping).

HH

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

6. Hot Side of VII VII No No access while Evap. Operating.

Recycle Evap.

Skid 55-57

7. Entrance to V V Yes Short term access while Evap. Operating, Recycle Evap. Concentrates transfer pump and heat exchanger Skid 55-57 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.

(15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations 12-12 1. Mechanical VII VI Very Limited Possible Airborne Contamination-High-Penetration maintenance equipment should not be located Area 51-53 here.

GG-KK

2. Mechanical VI VI Limited RHR Lines during refueling.

Penetration Area 52-53 GG-KK

3. Mechanical VI V Limited Penetration Area 50 KK

4. Hot Skid of VII VII No Process controlled.

Waste Evap. 52 KK-MM

5. Entrance to V V Limited Concentrates transfer pump and heat exchanger Waste Evap. operation may affect accessibility.

6. Recycle VII VII No No manually operated controls in room.

Holdup Tk Rooms 51-55 NN-QQ

7. Waste Evap. VII VII No No manually operated controls in room.

Feed Tk. Room 52-53 KK-LL

8. Waste Drain VII VII No No manaully operated controls in room.

Tk. Room 52-54 KK-LL

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

(15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

10. Charging Pump VII VII Only when Safety Injection piping in Recip. Charging Pump Rooms drained for Room.

53-54 JJ-JJ 54 repair 56 HH-KK

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

GG-JJ

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

13. Accident VI VI Limited Normal operation dead legs located in in this Sample Panel area.

Area 53-54 EE-FF

14. Pipe Trench V V Yes Radioactive piping in trench.

55-58 KK

15. Recycle Evap. VI VI Limited Design for maintenance considerations.

Feed Pump and Valve Rooms 55-57 PP-QQ

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

17. Corridor Areas IV IV Yes 12-13 1. Mechanical VII VI Very Limited Possible Airborne Contamination. High Penetration maintenance equipment should not be located Area 61-64 here.

GG-KK (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

2. Mechanical VI V Limited Accident recirculation lines in area.

Penetration Area 61-62 EE-GG

3. Mechanical VI V Limited Penetration Area

4. Waste Gas VII VII No No controls should be in area.

Decay Tk.

Room 59-63 NC-QQ

5. Waste Gas VII VII Limited Access for maintenance.

Valve Area 59-60 NN-QQ

6. Gas Anal. V V Processing controls radiation levels Rack-A Room 59-60 MM-NN

7. Hydrogen VI VI No Access limited due to operation of recombiner Recombiner and WG piping in trench.

Room 60-61 MM-NN

8. Gas Anal. VI VI Processing controls access. WG piping in trench Rack-B 60-61 limits access.

MM-NN

9. Hydrogen VI VI No Limited access when recombiner not opening.

Recomb. Room 61-62 MM-NN

10. Waste Gas VII VII No Serves both Units (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations Compressor Room 61-62 MM-NN

11. Waste Gas VII VII No Serves both Units.

Compressor Room 62-63 MM-NN

12. LHST Pump V V Limited Room 63 LL-MM

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

14. FDT & LHST VI VI Limited Room

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

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

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

LL-MM

18. Mixing and VI VI No Radiation levels vary dependent on material Settling Tank processed.

Room 59 KK-LL (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

19. Mixing And VI VI No Radiation levels vary dependent on material Settling Tank processed.

Room 59 KK-LL

20. Charging Pump VII VII No Limited access when not in service.

Rooms 58-61 HH-KK

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

22. Sample Hx VI VI Limited Corrosion add significantly to radiation level.

Area 61 EE-FF

23. Accident VI VI Limited Normal operation dead legs located in this area.

Sample Panel 60 EE-FF

24. Corridor Area IV IV Yes 12-14 1. Auxilliary III III Yes Feedwater Pump Area 49-53, 61-65, AA-DD 12-15 Refer to Figure 12-16 for similar zoning.

12-16 1. Mechanical VII VII Very Limited NV piping in area of VCT makes this a high radiation Penetration area.

Area 50-53 EE-KK (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

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

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

MPA & NV Valve Bodyarea 51 KK-MM + 53 KK-MM

4. RHR & CS 11x VII VII No Corrosion Product buildup important.

Rooms 51-52 KK-MM

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

6. Recycle VII VII No No operators should be in area.

Holdup Tank Rooms 51-55 NN-QQ

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

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

9. Boronometer VII VII Yes Deleted Per 2007 Update.

Room 53-54 FF (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

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 IV IV Yes Emergency Personnel Lock Area 67-69, 45-47 BB-DD

2. Electrical Penetration III III Yes Room 45-53, 61-69 AA-DD 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 VI V Limited NS supply piping in area.

Penetration Room 61-63 GG-KK

2. Mechanical V V Limited NS supply piping in area.

Penetration Room 62-64 JJ-MM

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

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

MM

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

KK (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

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

QQ

7. Evap. Conc. VII VII No Accessible when tank is drained and flushed.

Holdup 59 NN-PP

8. Radwaste VII VII No Accessible when tank is drained and flushed.

Batching Tank Room 59-60 NN-PP

9. Concentrates VII VII Limited Accessible when tank is drained and flushed.

Batch 59 PP-QQ

10. Radwaste Feed VII VII No Accessible when flushed.

Skid Room 59-60 PP-QQ

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

12. Fuel Pool Cooling VII VII No Accessible when demin. Is empty.

Demin. Room 63 NN-PP

13. Corridor Areas IV IV Yes

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

(15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

15. Filter Bunker Area Varies from IV Varies Limited Access to this area is limited due to spent radioactive filter to VII from IV storage as well as periodic transfer of radioactive spent to VII 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 III III Yes Room 45-53, 61-69 AA-DD 12-25 Refer to Figure 12-26 for similar area zoning.

12-26 1. Annulus Ventilation IV IV Yes Filter Area 50-53 GG-KK

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

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

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

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

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

7. Fuel Pool Exhaust IV IV Yes Filter Area 51-54 KK-QQ (15 NOV 2007)

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

Radiation Zone2 Accessible Design Refueling/

Figure Location1 Operation Shutdown At Power Special Considerations

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

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

10. Open Corridor Area IV IV Yes 12-27 Refer to Figure 12-26 for similar area zoning 12-28 1. Control Room Area II II Yes 53-60 AA-EE

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

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

1. Location numbering corresponds to that on drawings.

2. Reference Table 12-15 for definition.

(15 NOV 2007)

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

Table 12-19. Design Shield Thickness Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

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 560 DD-51 5.2 174 12-1,A/G 3.0 Exchanger Excess Letdown Heat 560 DD-51 4.3 214 12-1,D 3.0(8)

Exchanger (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

Note: 543 JJ-53 8 40 12-1,G 2.5 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.)

Centrifugal Charging 543 JJ-55 7 40 12-1,G 2.0 Pump Boric Acid Transfer 560 PP-59 3.5 10 (note 3) 1.5 Pump Letdown Heat 577 KK-53 11 197 12-1,D 2.5 Exchanger Seal Water Heat 560 GG-54 10 140 12-1,G 2.0 Exchanger 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 560 LL-53 15.75 43.75 12-2 4.0 (9)

Demineralizer Cation Bed 560 MM-53 12.75 36 12-2 4.0 Demineralizer Reactor Coolant Filter 560 KK-56 3 16.875 12-3 3.0 (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

Seal Water Return 560 LL-56 3 16.875 12-3 2.0 Filter Seal Water Injection 560 KK-56 1 19.5 12-3 2.5 Filter 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 560 QQ-57 15.5 43.75 12-2 4.0 Demineralizer Evaporator Feed Filter 560 NN-56 3 16.875 12-3 2.5 Evaporator Condensate 560 PP-57 12.75 36 12-2 1.5 Demineralizer Evaporator Condensate 560 PP-57 1 9.875 12-3 1.5 Filter Evaporator Concentrate 560 PP-56 1 9.875 12-3 2.0 Filter Boron Thermal Regeneration System Moderating Heat 577 JJ-53 9 212 12-1,F 2.5 Exchanger (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

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

Demineralizer 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 543 MM-54 4 18 12-1,D 3.0 Pump Evaporator 537 LL-52 21 119 12-1,L 3.0 Evaporator Condensate 560 KK-55 15.75 43.75 12-2 1.5 Demineralizer Evaporator Condensate 560 MM-56 1 9.875 12-3 2.0 Filter Reactor Coolant Drain 543 HH-49 18 80 12-1,D 3.0 Tank 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 (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

Laundry & Hot Shower 543 LL-63 64 178 12-1,I 1.5 Tank LHST Pump 543 LL-63 4 8 12-1,I 1.5 LHST Primary Filter, 560 LL-58 1 9.875 12-3 2.0 Secondary Filter LHST Carbon Filter 560 KK-63 1 9.875 12-3 2.0 Waste Monitor Tank 560 KK-59 1 9.875 12-3 1.0 Filter Waste Monitor Tank 560 MM-62 15.75 43.75 12-2 3.0 Demineralizer 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 543 KK-59 4 15 12-1,I 1.5 Pump Solid Radwaste System Chemical Drain Tank 537 LL-55 21 120 12-1,H 3.0 Chemical Drain Tank 537 LL-55 60 104 12-1,M 3.0 Pump Spent Resin Storage 543 LL-61 60 77 12-1,M 4.0 Tank (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

Spent Resin Sluice 560 KK-59 3 16.875 12-3 3.0 Filter Radwaste Batching 577 PP-60 29.75 70.67 12-1,N 4.0(9)

Tank Evaporator Concentrate 577 NN-59 42 126 12-1,L 3.0 Storage Tank 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 (24 APR 2006)

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

Unit 1 Location Source Dimension5 Component el. Column Lines R(in) H(in) Table/Flag Shield6 (ft)

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.

(24 APR 2006)

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

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°.

(22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (22 OCT 2001)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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.

(24 APR 2006)

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

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%."

(24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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).

(24 APR 2006)

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

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%."

(24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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).

(24 APR 2006)

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

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%."

(24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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 (24 APR 2006)

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

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 (24 APR 2006)

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

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.

(24 APR 2006)

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

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).

(24 APR 2006)

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

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%."

(24 APR 2006)

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

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.

(24 APR 2006)

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

Table 12-27. Filter System Design Parameters Carbon Bed (Minimum Heater Size System Depth, In.) (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 (22 OCT 2001)

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

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.

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.

(09 OCT 2019)

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

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.

(09 OCT 2019)

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

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 (09 OCT 2019)

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

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.

(09 OCT 2019)

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

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.

(09 OCT 2019)

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

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).

(09 OCT 2019)

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

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.

(09 OCT 2019)

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

Table 12-29. Area Radiation Monitoring System Detector Number Identification Location Sensitivity Range Accuracy 1EMF1 Auxiliary EL 522 FF, 57 counts / min 10 104 +/-15%

Building 120 mR/hr mR / hr Corridor 1EMF2 Sample Room EL 543 EE-FF, 54 counts / min 10 104 +/-15%

120 mR/hr mR / hr 1EMF3 Charging Pump EL 543 GG, 55 counts / min 10 104 +/-15%

Area 120 mR/hr mR / hr 1EMF5 Auxiliary EL 543 NN, 53 counts / min 10 104 +/-15%

Building 120 mR/hr mR / hr Corridor 1EMF7 Auxiliary EL 560 NN, 55 counts / min 10 104 +/-15%

Building 120 mR/hr mR / hr Corridor 1EMF9 Filter Hatch EL 577 LL, 55 counts / min 10 104 +/-15%

Area 120 mR/hr mR / hr 1EMF12 Control Room EL 594 CC, 57 counts / min 10 104 +/-15%

120 mR/hr mR / hr 1EMF16 Waste Shipping EL 594 RR, 58 counts / min 10 104 +/-15%

Area 120 mR/hr mR / hr 1EMF13 Hot Machine EL 594 VV, 55 counts / min 10 104 +/-15%

Shop 120 mR/hr mR / hr 1EMF14 Hot Chemistry EL 609 UU, 60 counts / min 10 104 +/-15%

Laboratory 120 mR/hr mR / hr 1EMF15 Refueling EL 605 + 10 counts / min 10 104 +/-15%

Bridge - Spent 120 mR/hr mR / hr Fuel Building 1EMF11 Incore EL 570 + 3 counts / min 10 104 +/-15%

Instrument 53'6", 90° 120 mR/hr mR / hr Room 1EMF17 Refueling EL 605 + 10 counts / min 10 104 +/-15%

Bridge - 120 mR/hr mR / hr Reactor Building 2EMF1 Sample Room EL 543 EE-FF, 60 counts / min 10 104 +/-15%

120 mR/hr mR / hr (21 OCT 2010)

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

Detector Number Identification Location Sensitivity Range Accuracy 1EMF4 Charging Pump EL 543 GG, 59 counts / min 10 104 +/-15%

Area 120 mR/hr mR / hr 1EMF6 Auxiliary EL 543 MM, 61-62 counts / min 10 104 +/-15%

Building 120 mR/hr mR / hr Corridor 1EMF8 Auxiliary EL 560 NN, 59 counts / min 10 104 +/-15%

Building 120 mR/hr mR / hr Corridor 1EMF10 Filter Hatch EL 577 LL, 58 counts / min 10 104 +/-15%

Area 120 mR/hr mR / hr 2EMF4 Refueling EL 605 + 10 counts / min 10 104 +/-15%

Bridge - Spent 120 mR/hr mR / hr Fuel Building 2EMF3 Incore EL 570 counts / min 10 104 +/-15%

Instrument 53'6", 90° 120 mR/hr mR / hr Room 2EMF2 Refueling EL 605 + 10 counts / min 10 104 +/-15%

Bridge - 120 mR/hr mR / hr Reactor Building 1EMF18 Reactor EL 568 KK, 56 1 x 10-10 Amps R/hr 10 104 +/-15%

Coolant Filter R/hr 1A 1EMF19 Reactor EL 568 KK-LL,56 1 x 10-10 Amps R/hr 10 104 +/-15%

Coolant Filter R/hr 1B 2EMF5 Reactor EL 568 KK-LL,58 1 x 10-10 Amps R/hr 10 104 +/-15%

Coolant Filter R/hr 2A 2EMF6 Reactor EL 568 KK-LL, 58 1 x 10-10 Amps R/hr 10 104 +/-15%

Coolant Filter R/hr 2B 1EMF20 New Fuel EL 610 VV, 51 counts / min 10 104 +/-15%

Storage Area 120 mR/hr mR / hr 1A 1EMF21 New Fuel EL 610 VV, 49 counts / min 10 104 +/-15%

Storage Area 120 mR/hr mR / hr 1B (21 OCT 2010)

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

Detector Number Identification Location Sensitivity Range Accuracy 2EMF7 New Fuel EL 611+11 VV, 65 counts / min 10 104 +/-15%

Storage Area 120 mR/hr mR / hr 2A 2EMF8 New Fuel EL 611+11 VV, 63 counts / min 10 104 +/-15%

Storage Area 120 mR/hr mR / hr 2B 1EMF22 Reactor EL 594 KK, 53 counts / min 10 104 +/-15%

Building Purge 120 mR/hr mR / hr Filter-Unit 1 2EMF9 Reactor EL 594 KK, 61 counts / min 10 104 +/-15%

Building Purge 120 mR/hr mR / hr Filter-Unit 2 EMF24 Technical EL 601 U, 26 counts / min 10 104 +/-15%

Support Center 120 mR/hr mR / hr EMF23 Waste EL 594 WW, 57A counts / min 10 104 +/-15%

Solidification 120 mR/hr mR / hr Pad 1EMF26 Main Steam EL 601 GG, 43 counts / min 10 104 +/-15%

Line Loop A 120 mR/hr mR / hr 1EMF27 Main Steam EL 601 GG, 53 counts / min 10 104 +/-15%

Line Loop B 120 mR/hr mR / hr 1EMF28 Main Steam EL 601 GG, 53 counts / min 10 104 +/-15%

Line Loop C 120 mR/hr mR / hr 1EMF29 Main Steam EL 601 GG, 44 counts / min 10 104 +/-15%

Line Loop D 120 mR/hr mR / hr 2EMF10 Main Steam EL 601 GG, 70 counts / min 10 104 +/-15%

Line Loop A 120 mR/hr mR / hr 2EMF11 Main Steam EL 601 GG, 61 counts / min 10 104 +/-15%

Line Loop B 120 mR/hr mR / hr 2EMF12 Main Steam EL 601 GG, 61 counts / min 10 104 +/-15%

Line Loop C 120 mR/hr mR / hr 2EMF13 Main Steam EL 601 GG, 70 counts / min 10 104 +/-15%

Line Loop D 120 mR/hr mR / hr EMF80 Waste Monitor MTB EL 594 D-1a counts / min 10 104 +/-10%

Tank Building 110 mR/hr mR / hr Pipe Chase (21 OCT 2010)

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

Detector Number Identification Location Sensitivity Range Accuracy EMF81 Waste Monitor MTB EL 594 F-2 counts / min 10 104 +/-10%

Tank Building 110 mR/hr mR / hr Sump Corridor EMF82 Waste Monitor MTB EL 594 B-4 counts / min 10 104 +/-10%

Tank Building 110 mR/hr mR / hr Truck Bay (21 OCT 2010)

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

Table 12-30. Estimated - Station Organization and Work Area Total Total Total per per per Work Work Work Area Area Area Personnel and Staff Technical Services Maintenance Office1: Manager 1 Office1: Superintendent 1 Office: Superintendent 1 Secretary 1 Licensing & Projects 1 Engr (I&E) 1 Superintendent 1 Performance Engr. 1 Maint. Engr. 1 Clerks 32 Chemist 1 Planning Engr. 1 Nurse 1 36 Radiation Protection 1 Materials Super. 1 Clerks 9 14 Materials Personnel 23 90/10(2): Security 214 214 Clerks 11 40 50/503: Engineering & 9 50/50: Engr (Licensing & 13 50/50: Engr & Supv (I&E) 18 18 Supervisors Proj) Engr & Supv 19 Safety Assts. 3 12 Engr (Performance) 12 25 (Maint)

Asst Chemist 16 Engr (Planning) 15 34 Asst R.P. 17 33 OPERATIONS Field: Tech (Performance) 10 10 Field: Tech. (I&E) 60 60 Tech (Chemist) 46 Tech. (Maint.) 55 Office: Superintendent 1 Tech (R.P.) 46 92 P.M. Personnel 5 60(1)

Clerks 4 5 50*/504: Operating Eng 4 MISC Asst Oper Eng 3 7 Control Shift Super 7 50/50: SSD 100 Area: Asst Shift Sup 13 Station Maint Sup 150 250 Control Oper 15 Janitorial 50 Asst Cntl Oper 10 45 Quality Assurance 39 Outside Vendors 10 99 Field: Operators 43 Office: Transmission 8 Enginering 12 55 (22 OCT 2001)

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

Total Total Total per per per Work Work Work Area Area 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 (22 OCT 2001)

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

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

Staff 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 (22 OCT 2001)

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

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

Staff 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.

(22 OCT 2001)

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

Table 12-32. Routine Operation Dose Assessment HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Personnel and Total Man- Total Man-Staff Operations Tech. Services Maint. Misc. SMS SSD Rem Week Rem Year Radiation Work Area Weekly Occupancy (Man Hrs/Week)

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

1. Aux. Bldg. 1320*5.3E-4 = 1792*5.3E-4 =

Corridors 958.*5.3E-4 = .51 234.*5.3E-4 = .13 871*5.3E-4 = .46 .70 .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. 570.4*2.5E-3 =

Waste Gas - 234*2.E-4 = .05 871*2.E-4 = .17 1.43 250*2.5E-3 = .63 2.28 118.6

5. Liquid 570.4*2.E-3 =

Waste - 234*1.E-3 = .23 871*1.E-3 = .87 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 (Man-Work Group Rem) TOTAL STATION DOSE

.58 .80 2.24 4.0 3.0 Exposure NORMAL OPERATIONS wk (15 NOV 2007)

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

Personnel and Total Man- Total Man-Staff Operations Tech. Services Maint. Misc. SMS SSD Rem Week Rem Year Radiation Work Area Weekly Occupancy (Man Hrs/Week)

Dose Rate (R/Hr) = Man-Rem/Week (Man-52 wks/year Rem) 30.2 41.6 116.5 208. 156.

yr 552 MAN-REM YEAR Exposure Per Individual Per .12 .37 .67 .98 .44 Year

~5 REM PERSON-YEAR (15 NOV 2007)

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

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

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Average Annual Exposure Activity (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 (15 NOV 2007)

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

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 Average Expected Dose Time Annual Dose Item Rate (rem/hr) (man-hr) Frequency (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, 1.100/0.005 pressurizer, relief tanks, etc. 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 (15 NOV 2007)

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

Average Expected Dose Time Annual Dose Item Rate (rem/hr) (man-hr) Frequency (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.

(15 NOV 2007)

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

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

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Average Expected Dose Rate Time Annual Dose Item (rem/hr) (man-hr) Frequency (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 (15 NOV 2007)

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

Average Expected Dose Rate Time Annual Dose Item (rem/hr) (man-hr) Frequency (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.

(15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-36 (Page 1 of 1)

Table 12-36. Occupational Radiation Exposure Estimate For Waste Processing (For One Unit)

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

Inspect and service catalytic recombiner gas 0.005 16 Annual 0.08 analyzer 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 (15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-37 (Page 1 of 2)

Table 12-37. Occupational Radiation Exposure Estimate For Refueling (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Average Item Expected Dose Time Annual Dose Rate (rem/hr) (man-hr) (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 0.025 7 0.18 mechanism cables Disconnect thermocouples (2) 0.500 1 0.5 Retract incore thimbles 0.025 24 0.60 Detension and remove reactor 0.050 51 2.6 vessel studs 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- 0.050 12 0.6 ternals and store Perform fuel shuffle - - 6.0

1. Fuel handling in containment

a. Check out refueling 0.100/0.005(1) 8/24(1) 0.9(1) equipment

b. Perform fuel shuffle (64 0.005 600 3.0 assemblies)

c. Perform quality 0.005 15 0.08 assurance on core reload

2. Fuel handling in fuel handling building

a. Check out refueling 0.005/0.0025(1) 16/16(1) 0.12 equipment

b. Perform fuel shuffle .0025 360 0.9

c. Inspect and change out 0.100 4 0.4 spent fuel pool demineralizers (15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-37 (Page 2 of 2)

Average Item Expected Dose Time Annual Dose Rate (rem/hr) (man-hr) (man-rem)

Clean, inspect, and test studs and 0.025 20 0.5 tentioners 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 0.050 153 8.0 studs Install blind flange 0.500 3 1.5 Reconnect control rod drive 0.025 4 0.1 mechanism 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.

(15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-38 (Page 1 of 1)

Table 12-38. Occupational Radiation Exposure Estimate For Inservice Inspection (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Average Annual Dose Expected Over 10-Year Dose Rate Time Period (man-Item (rem/hr) (man-hr) Frequency rem)

Inservice inspection or reactor vessel and 0.100 580 1 per 10 5.8 reactor coolant piping years(1)

Insulation removal from reactor vessel nozzle 0.100 200 1 per 10 2.0 and reactor coolant piping years(1)

Snubber inspection of reactor coolant piping 0.005 2200 1 per 10 1.1 years(1)

Steam generator inservice inspection (4 steam 0.125 470 1 per 10 5.9 generators) years(1)

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.

(15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-39 (Page 1 of 1)

Table 12-39. Occupational Radiation Exposure Estimate For Special Maintenance1 (For One Unit)

HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED Average Expected Annual Dose Over Dose Rate Time 10-Year Period Item (rem/hr) (man-hr) Frequency (man-rem)

Steam generator tube plugging 0.24 52 1 per 2 6.1 years Steam generator tube plug welding 0.21 52 1 per 10 1.1 years Sludge lancing 0.06 160 1 per year 9.8 Control rod drive mechanism repair 0.50 5 1 per 5 0.5 years 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.

(15 NOV 2007)

Catawba Nuclear Station UFSAR Table 12-40 (Page 1 of 1)

Table 12-40. RCA Description and RCA Control Points Auxiliary Building RCA Control Points Elevation 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 Unit 2 Yard Limited Access 3 inside RCA 560' All of the elev. is inside RCA with the BB 45, 69 Limited Access2 following exceptions: Rooms 362, 363, CC 53, 61 Limited Access2 372, 373 and the diesel generator rooms.

577' All of the elev. is inside RCA Main Entrance U 36 (Service Bldg) Exit Point 594' All of elev. is inside RCA with the HH 42, 72 Limited Access2 following exceptions: Rooms 564, 573, DD 60 Limited Access2 574, 575 and sections of 563 and 576.

VV 58 Limited Access2 UU 47, 67 Limited Access2 VV 48, 55, 59, 60, Limited Access2 62 AA 48, 66 Limited Access2 WW61 Normal Use1 609' All of elev. is inside RCA with the RR 52 Limited Access2 following exceptions: Chemistry/RP Office at North end.

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.

(21 APR 2011)

Catawba Nuclear Station UFSAR Table 12-41 (Page 1 of 1)

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)

(22 OCT 2001)

ML20106E935

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