ML20189A102

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8 to Updated Final Safety Analysis Report, Chapter 12, Appendix 12A. Tables
ML20189A102
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 06/29/2020
From:
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20189A066 List:
References
RA-20-0136
Download: ML20189A102 (6)
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Text

Oconee Nuclear Station UFSAR Appendix 12A. Tables Appendix 12A. Tables

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

(31 DEC 2000)

Table 12-1. Parameters Used for Shielding Analyses Core Thermal Power 2568 MWt Effective Core Diameter 128.9 in.

Active Fuel Length 144 in Thickness of Core Liner 0.75 in.

Thickness of Core Barrel 2 in.

Thickness of Thermal Shield 2 in.

Reactor Vessel I.D.

171 in.

Reactor Vessel O.D.

188 in.

Volume of Reactor Coolant 11,478 ft3 Normal Letdown Flow 1 reactor coolant system volume per day Time Between Shutdown and Fuel Handling 100 hrs.

Coolant Transit Times (Seconds):

Core Inlet to Core Exit 0.8 Core Exit to S.G. Inlet 2.8 S.G. Inlet to S.G. Outlet 5.2 S.G. Outlet to Core Inlet 4.0 Total Loop Time 12.8

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

(31 DEC 2000)

Table 12-2. Principal Shielding Reactor Building Component Concrete Thickness (ft)

Primary Shield (Below Flange)

(Above Flange) 5 4.5 Secondary Shield 4

Reactor Building Vertical Walls 3.75 Reactor Building Dome 3.25 Side Walls of Fuel Transfer Canal 4.5 End Walls of Fuel Transfer Canal 2.5,4 Floor of Fuel Transfer Canal 4

Nominal Water Over Active Fuel During Transfer 9

Auxiliary Building Component Concrete Thickness (ft)

Spent Resin Tanks 4

Evaporator Equipment 3.0-4.0 Purification Demineralizers 4

Deborating Demineralizers 4

Component Drain Pump 1.5-4.0 Spent Resin Transfer Pump 2-4 Spent Resin Sluicing Pump 2-4 Waste Transfer Pump 1-4 Low Pressure Injection Pumps 2.5-3.5 High Pressure Injection Pumps 1.5-4.0 Coolant Bleed Holdup Tanks 1.5-4.0 Concentrated Boric Acid Storage Tank 1.5-2.0 Waste Drumming Area 1.5-2.0 Low Pressure Injection Coolers 3

Letdown Storage Tanks 4

Waste Holdup Tank 2.0 Waste Gas Tank 3.0-3.5 Waste Gas Compressors 3.0-3.5 Bleed Evaporator Feed Tank 2.0-3.0

Oconee Nuclear Station UFSAR Table 12-2 (Page 2 of 2)

(31 DEC 2000)

Spent Fuel Coolant Pumps & Coolers 2.5-3.5 Side Walls of Storage Pool 3.5 End Walls of Storage Pool 5.5

Oconee Nuclear Station UFSAR Table 12-3 (Page 1 of 2)

(31 DEC 2004)

Table 12-3. Area Radiation Monitors RIA Detector Type Location Range Nominal Sensitivity RIA-1 G-M Control Room Unit 1&2, Unit 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-3 High Range G-M Ion Chamber Reactor Building Refueling Deck Shield Wall Unit 1, 2, 3 1E-1 to 1E4 mR/hr 1E2 to 1E7 mR/hr 100 cpm/mR/hr 1.2E-10 A/R/hr RIA-4 High Range G-M Ion Chamber Reactor Building Entrance Unit 1, 2, 3 1E-1 to 1E4 mR/hr 1E2 to 1E7 mR/hr 100 cpm/mR/hr 1.2E-10 A/R/hr RIA-5 G-M Incore Instrument Handling Area Unit 1, 2, 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-6 High Range G-M Ion Chamber Spent Fuel Building Wall Unit 1&2, Unit 3 1E-1 to 1E4 mR/hr 1E2 to 1E7 mR/hr 100 cpm/mR/hr 1.2E-10 A/R/hr RIA-7 G-M Hot Machine Shop 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-8 G-M Hot Laboratory 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-10 G-M Sample Area Unit 1, 2, 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-11 G-M Auxiliary Building Corridor Elevation 796 Unit 1&2, 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-12 G-M Chemical Addition Area Unit 1&2, Unit 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-13 G-M Waste Disposal Control Area Unit 1&2, Unit 3 1E-1 to 1E4 mR/hr 100 cpm/mR/hr RIA-15 High Range G-M Ion Chamber High Pressure Injection Pump Room Unit 1&2, Unit 3 1E-1 to 1E4 mR/hr 1E2 to 1E7 mR/hr 100 cpm/mR/hr 1.2E-10 A/R/hr RIA-16(1)

High Range G-M Ion Chamber Steam Generator A Main Steam Header Unit 1, 2, 3 1E-2 to 1E3 mR/hr 1E2 to 1E7 mR/hr 500 cpm/mR/hr 1.2E-10 A/R/hr RIA-17(1)

High Range G-M Ion Chamber Steam Generator B Main Steam Header Unit 1, 2, 3 1E-2 to 1E3 mR/hr 1E2 to 1E7 mR/hr 500 cpm/mR/hr 1.2E-10 A/R/hr RIA-32(2)

Plastic Beta Auxiliary Building Corridor Multi Point Sampler Elevation 771, Unit 1&2; Elevation 784, Unit 3 1E1 to 1E7 cpm 2.94E7 cpm/uCi/ml RIA-39(2)

Plastic Beta Control Room Air Ventilation Equipment Room, Unit 1, 3 1E1 to 1E7 cpm 2.94E7 cpm/uCi/ml

Oconee Nuclear Station UFSAR Table 12-3 (Page 2 of 2)

(31 DEC 2004)

RIA Detector Type Location Range Nominal Sensitivity RIA-41(2)

Plastic Beta Spent Fuel Pool Air Ventilation Equipment Room, Unit 1&2 Purge Equipment Room, Unit 3 1E1 to 1E7 cpm 2.94E7 cpm/uCi/ml RIA-56 Ion Chamber Unit Vent Unit 1, 2, 3

~1E0 to 1E8 R/hr 1E-11 A/R/hr RIA-57, -58 Ion Chamber Reactor Building/Penetration Room

~1E0 to 1E8 R/hr 1E-11 A/R/hr RIA-61(3) (4)

Radwaste Facility (RMF) Northside of column D-16 (RW-106)

RIA-62(3) (4)

Radwaste Facility Southside of col. D-17A (RW-106)

RIA-63(3) (4)

Radwaste Facility East wall of RW-108 RIA-64(3) (4)

Radwaste Facility East wall of RW-130 RIA-65(3) (4)

Radwaste Facility South wall of RW-219 RIA-66(3) (4)

Radwaste Facility Under Backwash Resin Tank-B RIA-67(3) (4)

Radwaste Facility Under Backwash Resin Tank-A Note:

1. These G-M/Ion Chamber detectors are used as Process Radiation Monitors, but are functionally similar to the Area Monitors and are contained in the same cabinets.
2. These beta scintillation detectors are process type RIAs, however they are used in an area monitoring situation.
3. Radwaste Facility Area Monitor. Because the Radwaste Facility is not used as originally designed, these monitors are not used in a personnel radiation protection capacity as originally intended. Therefore, only the number and location are provided for these RIAs.
4. Radwaste Facility Area Monitor. Area Monitors have been statused as inactive. Power has been removed and these area monitors are not in service.
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