ML20189A093

8 to Updated Final Safety Analysis Report, Chapter 9, Appendix 9A. Tables

ML20189A093
Person / Time
Site:	Oconee
Issue date:	06/29/2020
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20189A066	List: ML20181A118 ML20189A067 ML20189A068 ML20189A069 ML20189A070 ML20189A071 ML20189A072 ML20189A073 ML20189A074 ML20189A075 ML20189A076 ML20189A077 ML20189A078 ML20189A079 ML20189A080 ML20189A081 ML20189A082 ML20189A083 ML20189A084 ML20189A085 ML20189A086 ML20189A087 ML20189A088 ML20189A089 ML20189A090 ML20189A091 ML20189A092 ML20189A093 ML20189A094 ML20189A095 ML20189A096 ML20189A097 ML20189A098 ML20189A099 ML20189A100 ML20189A101 ML20189A102 ML20189A103 ML20189A104 ML20189A105 ML20189A106 ML20189A107 ML20189A108 ML20189A109 ML20189A110 ML20189A111 ML20189A112 ML20189A113 RA-20-0136, 8 to Updated Final Safety Analysis Report, Chapter 18, Appendix 18A. Tables
References
RA-20-0136
Download: ML20189A093 (35)

Text

Oconee Nuclear Station UFSAR Appendix 9A. Tables Appendix 9A. Tables

Oconee Nuclear Station UFSAR Table 9-1 (Page 1 of 2)

(31 DEC 2019)

Table 9-1. Spent Fuel Cooling System Data, Units 1, 2 System Design Pressure, psig 125 System Design Temperature, °F 215 Spent Fuel Coolers A&B Type Shell and tube Material Shell/Tube SS/SS Capacity, Btu/hr/cooler 27.2 x 106 Cooling Water Flow, lb/hr/cooler 5 x 105 Code ASME VIII, III-C Spent Fuel Cooler C Type Plate Material SS Capacity, Btu/hr 27.2 x 106 Cooling Water Flow, lb/hr 5 x 105 Code ASME III-3 Spent Fuel Pumps Type Horizontal, centrifugal Material SS Design Flow, gal/min 1,000 Design Head, ft H2O 100 (Pumps A&B) 110 (Pump C)

Motor Horsepower, hp 40 Spent Fuel Pool Volume, ft3 73,000 Spent Fuel Filters Design Flow, gal/min 180 Material SS Design Pressure, psig 150 Design Temperature, °F 200 Code ASME III-C Borated Water Recirculation Pump Type Vertical, inline, centrifugal Material SS Design Flow, gal/min 180 Design Head, ft H2O 140

Oconee Nuclear Station UFSAR Table 9-1 (Page 2 of 2)

(31 DEC 2019)

Motor Horsepower, hp 15 Design Pressure, psig 125 Design Temperature, °F 250 Spent Fuel Demineralizer Type Mixed bed Material SS Resin Volume, ft3 21 Design Flow, gal/min 180 Design Pressure, psig 125 Design Temperature, °F 250 Code ASME III-C

Oconee Nuclear Station UFSAR Table 9-2 (Page 1 of 2)

(31 DEC 2015)

Table 9-2. Spent Fuel Cooling System Data, Oconee 3 System Design Pressure, psig 125 System Design Temperature, °F 215 Spent Fuel Coolers A and B Type Tube and shell Material Tube/Shell SS/SS Design Heat Rate, BTU/hr/cooler 27.2 x 106 Cooling Water Flow, lb/h/cooler 5 x 105 Design Inlet Temp., °F 205 Design Outlet Temp., °F 150.6 Code ASME VIII/III-C Spent Fuel Cooler C Type Plate Material SS Capacity, Btu/hr 27.2 x 106 Cooling Water Flow, lb/hr 5.0 x 105 Code ASME III-3 Spent Fuel Pumps Type Horizontal, centrifugal Material SS Flow, gal/min 1,000 Design Head, ft H2O 100 Motor Horsepower, hp 40 Spent Fuel Pool Volume, ft3 50,000 Spent Fuel Filters Design Flow Rate, gal/min 180 Material SS Design Temperature, °F 200 Design Pressure, psig 125

Oconee Nuclear Station UFSAR Table 9-2 (Page 2 of 2)

(31 DEC 2015)

Code ASME III-C Borated Water Recirculation Pump Type Vertical, inline, centrifugal Material SS Flow, gal/min 180 Head, ft H2O 140 Motor Horsepower, hp 15 Design Temperature, °F 250 Design Pressure, psig 125 Spent Fuel Demineralizer Type Mixed bed Material SS Resin Volume, ft3 21 Flow, gal/min 180 Design Temperature, °F 250 Design Pressure, psig 125 Code ASME III-C

Oconee Nuclear Station UFSAR Table 9-3 (Page 1 of 1)

(31 DEC 2000)

Table 9-3. Component Cooling System Performance Data (For Normal Operation on a Per Oconee Basis)

Number of Component Cooling Pumps 2

Number of Pumps Normally Operating 1

Design Flow, gpm 766 Number of Component Coolers Oconee 1 and 2 1 + 1 Shared Spare Oconee 3 2

Number of Coolers Normally Operating 1

Design Heat Removal Requirements, Btu/h per cooler 19 x 106

Oconee Nuclear Station UFSAR Table 9-4 (Page 1 of 2)

(31 DEC 2000)

Table 9-4. Cooling Water Systems Component Data (Component Data on a Per Unit Basis)

Parameter Value Note: This table contains the original selected nominal design points for few key components. It is not intended to convey design limits or nominal operating conditions. It is not a comprehensive list of components.

Condenser Circulating Water Pumps 4 per unit Flow (per pump), gal/min 177,000 Design temperature, °F 90 Total Developed Head at Rated Flow, psig 12.4, at rated flow High Pressure Service Water Pumps 2 for all units Flow (per pump), gal/min 6,000 Design temperature, °F 75 Design pressure, psig 117 High Pressure Service Water Jockey Pump 1 for all units Flow (per pump), gal/min 500 Design temperature, °F 75 Design pressure, psig 117 Low Pressure Service Water Pumps 5 for all units Flow (per pump), gal/min 15,000 Design temperature, °F 75 Design pressure, psig 65 Recirculated Cooling Water Pumps (Units 1 & 2) 4 shared Flow (per pump), gal/min 2,400 Design temperature, °F 105 Design pressure, psig 100 Recirculated Cooling Water Pumps (Unit 3) 2 Flow (per pump), gal/min 2,050 Design temperature, °F 150 Design pressure, psig 100 Recirculated Cooling Water Heat Exchangers (Units 1 & 2) 4 shared Type Shell and tube Recirculating cooling water flow, each (shellside), gal/min 1,800

Oconee Nuclear Station UFSAR Table 9-4 (Page 2 of 2)

(31 DEC 2000)

Parameter Value Recirculating cooling water inlet temperature,

°F 105 Recirculating cooling water outlet temperature,

°F 90 Condenser circulating water inlet temperature,

°F 80°F Design pressure, shell/tube, psig 100/50 Design temperature, shell/tube, °F 200/200 Tube material Admiralty metal (SB-111)

Recirculated Cooling Water Heat Exchangers (Unit 3) 2 Type Flat plate Recirculating cooling water flow, each, gal/min 1,800 Recirculating cooling water inlet temperature,

°F 109 Recirculating cooling water outlet temperature,

°F 89 Condenser circulating water inlet temperature,

°F 80 Design pressure, psig 150 Design temperature, °F 150 Plate material SA-240 Shell material SA515-70 Essential Siphon Vacuum Pumps 3 per Unit Type Liquid ring Design flow 300 ACFM @ 2l" Hg. Vacuum

Oconee Nuclear Station UFSAR Table 9-5 (Page 1 of 3)

(31 DEC 2006)

Table 9-5. Chemical Addition and Sampling System Component Data Tanks Boric Acid Mix Tank Type Vertical cylindrical Volume, ft3 500 Design Pressure, psig Atmospheric Design Temperature, °F 250 Material Al Code USAS B96.1 Lithium Hydroxide Mix Tank Type Vertical cylindrical Volume, gal.

50 Design Pressure, psig Atmospheric Design Temperature, °F 140 Material SS Caustic Mix Tank Type Vertical cylindrical Volume, gal.

150 Design Pressure, psig Atmosphere Design Temperature, °F 200 Material SS Reactor Building TSP Baskets Number per unit 7

Mass of TSP per unit 16,000 lbs Material SS Pumps Boric Acid Pump Type Reciprocating, variable stroke Capacity, gal/min 10 Maximum Discharge Pressure, psig 75 Design Pressure, psig 100 Design Temperature, °F 200 Pump Material SS

Oconee Nuclear Station UFSAR Table 9-5 (Page 2 of 3)

(31 DEC 2006)

Boric Acid Pump (Core Flood Tanks)

Type Reciprocating, variable stroke Capacity, gal/min 1

Maximum Discharge Pressure, psig 630 Design Pressure, psig 700 Design Temperature, °F 300 Pump Material SS Lithium Hydroxide Pump Type Reciprocating, variable stroke Capacity, gal/hr 10 Maximum Discharge Pressure, psig 75 Design Pressure, psig 250 Pump Material SS Hydrazine Pump Type Reciprocating, variable stroke Capacity, gal/hr 10 Maximum Discharge Pressure, psig 100 Design Pressure, psig 100 Design Temperature, °F 200 Pump Material SS Caustic Pump Type Reciprocating, variable stroke Capability, gal/min 2

Maximum Discharge Pressure, psig 50 Design Pressure, psig 100 Design Temperature, °F 200 Pump Material SS Pressurizer Sample Cooler Type Shell and spiral tube Rated Capacity, Btu/h 2.1 x 105 Sample Flow Rate, lb/h 200 Maximum Sample Inlet Temperature, °F 650 Sample Outlet Temperature, °F 120

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

(31 DEC 2006)

Cooling Water Flow, lb/h 5,000 Design Temperature Shell/Tube, °F 250/670 Design Pressure Shell/Tube, psig 150/2,500 Code ASME Sec. III-C & VIII Steam Generator Sample Cooler Type Shell and spiral tube Rated Capacity, Btu/h 2.3 x 105 Sample Flow Rate, lb/h 500 Sample Inlet/Outlet Temperature, °F 535/100 Cooling Water Flow, lb/h 5,000 Design Temperature Shell/Tube, °F 300/600 Design pressure Shell/Tube, psig 150/1,050 Code ASME Sec. VIII

Oconee Nuclear Station UFSAR Table 9-6 (Page 1 of 1)

(31 DEC 2017)

Table 9-6. High Pressure Injection System Performance Data Letdown Orifice Design Flow, Cold, gal/min 45 Letdown Flow Maximum, Cold, gal/min 140 Seal Flow to Each Reactor Coolant Pump (excluding makeup), gal/min (Oconee 1) 8 Seal Inleakage to Reactor Coolant System per Reactor Coolant Pump, gal/min (Oconee 1) 5.8 (1A1, 1B2), 6.0 (1A2, 1B1)

Total Seal Flow to Each Reactor Coolant Pump, gal/min (Oconee 2, 3) 10 Seal Inleakage to Reactor Coolant System per Reactor Coolant Pump, gal/min (Oconee 2, 3) 8.5 Injection Pressure to Reactor Coolant Pump Seals, psig 2,190 Temperature to Seals, normal/maximum, °F 120/150 Purification Letdown Fluid Temperature, normal/maximum, °F 120/135 Letdown Storage Tank Normal Operating Pressure, psig 6.3-50 Letdown Storage Tank Volume Between Minimum and Maximum Operating Levels, ft3 250

Oconee Nuclear Station UFSAR Table 9-7 (Page 1 of 2)

(31 DEC 2005)

Table 9-7. High Pressure Injection System Component Data High Pressure Injection Pump Type Vertical, multistage, centrifugal, mechanical seal Capacity, gal/min (See Figure 6-16)

Head, ft H2O (at sp. gr. = 1)

(See Figure 6-16)

Motor Horsepower, nameplate hp 600 Pump Material SS wetted parts Design Pressure, psig 3,040/3,120 Design Temperature, °F 200/150 Letdown Cooler Type Shell and spiral tube Heat Transferred, Btu/h 16.0 x 106 Letdown Flow, lb/h 3.5 x 104 Letdown Cooler Inlet/Outlet Temperature, °F 555/120 Material, shell/tube CS/SS Design Pressure, psig 2,500 Design Temperature, °F 600 Component Cooling Water Flow (ea.), lb/h 2 x 105 Code ASME Sec. 111-C & VIII Reactor Coolant Pump Seal Return Cooler Type Shell and tube Heat Transferred, Btu/h 2.2 x 106 Seal Return Flow, lb/hr 1.25 x 105 Seal Flow Inlet/Outlet Temperature, °F 145/127 Material, shell/tube SS/SS Design Pressure, psig 150 Design Temperature, °F 286 (Unit 1), 200 (Units 2&3)

Recirculated Cooling Water Flow (ea.), lb/h 1.25 x 105 Code ASME Sec. III-C & VIII Letdown Storage Tank Volume, ft3 600 Design Pressure, psig 100 Design Temperature, °F 200

Oconee Nuclear Station UFSAR Table 9-7 (Page 2 of 2)

(31 DEC 2005)

Material SS Code ASME Sec. III-C Purification Demineralizer Type Mixed bed, boric acid saturated Material SS Resin Volume, ft3 50 Flow, gal/min 70 Vessel Design Pressure, psig 150 Vessel Design Temperature, °F 200 Code ASME Sec. III-C Letdown Filter Design Flow Rate, gal/min 80 Material SS Design Temperature 200 Design Pressure 150 Code ASME Sec. III-C Reactor Coolant Pump Seal Injection Filter Design Flow Rate, gal/min 50 Material SS Design Temperature, °F 200 Design Pressure, psig 3,050 @ 200°F / 3350 @ 150°F Code USAS B 31.7, class II Reactor Coolant Pump Seal Return Filter Design Flow Rate, gal/min 50 Material SS Design Temperature, °F 286 (Unit 1), 200 (Units 2&3)

Design Pressure, psig 150 Code ASME Sec. III-C

Oconee Nuclear Station UFSAR Table 9-8 (Page 1 of 1)

(31 DEC 2000)

Table 9-8. Low Pressure Injection System Performance Data Reactor Coolant Temperature at Startup of Decay Heat Removal, °F 250 Time to Cool Reactor Coolant System From 250°F to 140°F, hr 14 Refueling Temperature, °F 140 Fuel Transfer Canal Fill Time, hr Not Used Fuel Transfer Canal Drain Time, hr 8 (nominal)

Boron Concentration in Borated Water Storage Tanks, ppm Per Core Operating Limits Report

Oconee Nuclear Station UFSAR Table 9-9 (Page 1 of 2)

(31 DEC 2009)

Table 9-9. Low Pressure Injection System Component Data Pump (3 per unit)

Type centrifugal Single stage, Capacity, gal/min 3,000 Head at Rated Capacity, ft H2O 350 Motor Horsepower, hp 400 Material SS (wetted parts)

Design Pressure, psig 560/580 Design Temperature, °F 300/250 Cooler (each) (Oconee 1, 2) (2 per unit)

Type Shell and tube Capacity (at 140°F), Btu/hr 60 x 106 Reactor Coolant Flow, gal/min 6,000 Low Pressure Service Water Flow, gal/min 6,000 Low Pressure Service Water Inlet Temp, °F 75 Material, Shell/Tube CS/SS Design Pressure, Shell/Tube 150/515 (1) 150/370 (2)

Design Temperature, °F 250 (1) 300 (2)

Code, Shell/Tube ASME Section III-C, III, and VIII Cooler (each) (Oconee 3)

Type Shell and Tube Capacity (at 140°F), Btu/h 60 x 106 Reactor Coolant Flow, gpm 6,000 Low Pressure Service Water Flow, gpm 6,000 Low Pressure Service Water Inlet Temp. °F 75° Material, Shell/Tube CS/SS Shell Design Pressure, psig 150 Tube Design Pressure, psig 470/505 Shell Design Temperature, °F 300 Tube Design Temperature, °F 300/250 Code Shell/Tube ASME Section III-C, III, and VIII Borated Water Storage Tank (each)

Capacity, gal 388,000

Oconee Nuclear Station UFSAR Table 9-9 (Page 2 of 2)

(31 DEC 2009)

Material CS/Coated inside Design Pressure Vessel Full plus 10 ft Hydro Head Design Temperature, °F 150 Code AWWA D-100 Note:

1. A Cooler Units 1&2

2. B Cooler Units 1&2

Oconee Nuclear Station UFSAR Table 9-10 (Page 1 of 2)

(31 DEC 2000)

Table 9-10. Coolant Storage System Component Data (Component Quantities for Three Units)

Reactor Coolant Bleed Holdup Tank Number 6

Volume each, cu. ft.

11,000 Material Stainless Steel Design Pressure Vessel Full Plus 10 ft. Hydro Head Deborating Demineralizer1 Number 5

Resin Volume, cu. ft 62.8 Flow, gal/min 70 Design Pressure, psig 150 Concentrated Boric Acid Storage Tank Number 3

Volume each, cu. ft 3,000 Material Aluminum Design Vessel Full Plus 10 ft. Hydro Head Quench Tank Number 3

Volume each, cu. ft.

780 Material Stainless Steel Design Pressure, psig 55 Reactor Coolant Bleed Transfer Pump Number 6

Capacity each, gal/min 150 Diff. Head, ft.

220 Concentrated Boric Acid Storage Tank Pump Number 3

Capacity each, gal/min 50 Type Centrifugal Component Drain Pump Number 3

Capacity each, gal/min 100 Diff. Head, ft.

100

Oconee Nuclear Station UFSAR Table 9-10 (Page 2 of 2)

(31 DEC 2000)

Coolant Bleed Evaporator Demineralizer Number 2

Resin Volume, cu. ft.

11 Flow, gal/min 20 Design Pressure, psig 150 Condensate Demineralizer Number 2

Resin Volume, cu. ft.

2 Flow, gal/min 20 Design Pressure, psig 50 Coolant Bleed Evaporate Recirculating Pump Number 1

Capacity, gal/min 160 Diff. Head, ft.

53 Distillate Pump Number 1

Capacity, gal/min 7-12 Diff. Head, ft.

60 Coolant Bleed Evaporate Feed Pump Number 1

Capacity, gal/min 71/2 Diff. Head, ft.

60 Note:

1. These demineralizers may be loaded with mixed bed and used as purification demineralizers to support normal purification and boron/lithium coordination programs.

Oconee Nuclear Station UFSAR Table 9-11 (Page 1 of 2)

(31 DEC 2000)

Table 9-11. Ventilation System Major Component Data System Equipment Number Installed Number Required Normal Operation Control Room Zone Units 1 & 2 Air Handling Unit (1) 2 1

Air Handling Unit 1

1 Air Handling Unit 1

1 Air Handling Unit 2

2 Air Handling Unit 2

2 Booster Fan 2

0 Outside Air Filter Train 2

0 Cable Shaft Motorized Dampers 4

4 Control Room Zone Unit 3 Air Handling Unit (1) 2 1

Air Handling Unit 2

1 Air Handling Unit 2

1 Booster Fans 2

0 Outside Air Filter Train 2

0 Auxiliary Building Units 1 & 2 Ventilation Unit (2) (Spent Fuel Pool) 1 1

Exhaust Fan (Spent Fuel Pool) 2 1

Ventilation Unit 1

1 Ventilation Unit 1

1 Ventilation Unit 1

1 Exhaust Fan 2

1 Exhaust Fan 2

1 Exhaust Fan 3

2 Auxiliary Building Unit 3 Ventilation Unit (2) (Spent Fuel Pool) 1 1

Exhaust Fan (Spent Fuel Pool) 2 1

Ventilation Unit 2

1 Ventilation Unit 1

1 Exhaust Fans 3

2 Hot Machine Shop Exhaust Fans 3

2

Oconee Nuclear Station UFSAR Table 9-11 (Page 2 of 2)

(31 DEC 2000)

System Equipment Number Installed Number Required Normal Operation Air Handling Unit (3) 1 1

Air Handling Unit 1

1 Booster Fan 2

2 Outside Air Filter Train 2

2 Turbine Building Roof Exhaust Fans 12 12 Exhaust Fans 18 18 Note:

1. Air Handling Units consist of a fan, roughing filters, and chilled water coil.

2. Ventilation Units consist of a fan, service water coil, and steam heating coil.

3. Air Handling Units consist of a fan, roughing filters and direct expansion (DX) coil.

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

(31 DEC 2002)

Table 9-12. Deleted Per 2002 Update.

Oconee Nuclear Station UFSAR Table 9-13 (Page 1 of 2)

(31 DEC 2000)

Table 9-13. Component Cooling System Component Data (Component Data on a Per Unit Basis)

Parameter Value Component Cooling Pumps Type Centrifugal Rated Capacity, gpm 766 Rated Head, ft, H2O 220 Motor Nameplate Horsepower, hp 60 Casing Material CS Design Pressure, psig 150 Design Temperature, °F 225 Component Coolers (Oconee 1)

Type Shell and Tube Capacity, Btu/h 19 x 106 Component Cooling Water Inlet Temp, °F 150 Component Cooling Water Outlet Temp, °F 100 Code ASME Section VIII Component Coolers (Oconee 2, 3)

Type Shell and Tube Capacity, Btu/h 19 x 106 Component Cooling Water Inlet Temp, °F 150 Component Cooling Water Outlet Temp,

°F 100 Code ASME Section VIII Surge Tank Volume, ft3 50 Material CS Design Pressure, psig Atmospheric Design Temperature, F 200 Code AWWA D-100

Oconee Nuclear Station UFSAR Table 9-13 (Page 2 of 2)

(31 DEC 2000)

Parameter Value Control Rod Drive Filter Design Flow Rate, gal/min 140 Code ASME Section VIII

Oconee Nuclear Station UFSAR Table 9-14 (Page 1 of 4)

(31 DEC 2019)

Table 9-14. SSF System Main Components SSF RC Makeup Pump Quantity 1/Unit Design Pressure (psig) 2790 Design Temperature (°F) 220 Design Flow Rate (gpm) 29 design Design Head (psig) 2250 normal/ 2790 max.

Type Pos. Disp.

Material of Construction S. S.

Fluid Borated Water SSF RC Makeup Filter Quantity 1/Unit Design Pressure (psig) 2790 Design Temperature (°F) 220 Design Flow Rate (gpm) 78 Normal Flow Rate (gpm) 29 Retention for 5-Micron Particles (%)

98 Material of Construction S. S.

Fluid Borated Water SSF Auxiliary Service Water Pump Quantity 1/Station Nameplate Design Pressure (psig) 1440 Nameplate Design Temperature (°F) 150 Design Flow Rate (gpm) 1975 Design Head (ft) 2730 Type Material of Construction C. S.

Type Centrifugal Fluid River Water HVAC Service Water Pump Quantity 2/Station Nameplate Design Pressure (psig) 210 Nameplate Design Temperature (°F) 150

Oconee Nuclear Station UFSAR Table 9-14 (Page 2 of 4)

(31 DEC 2019)

Design Flow Rate (gpm) 55 Nameplate Design Head (ft) 365 @55 gpm, pump #1 365 @55 gpm, pump #2 Type Centrifugal Material of Construction C. S.

Fluid Strained River Water Diesel Engine Service Water Pump Quantity 1/Station Design Pressure (psig) 100 Design Temperature (°F) 110 Design Flow Rate (gpm) 500 Design Head (ft) 90 Type Centrifugal Material of Construction C. S.

Fluid Strained River Water SSF Service Water Strainer Quantity 1/Station Design Pressure (psig) 60 Design Temperature (°F) 110 Design Flow Rate (gpm) 600 Mesh Size (inch) 0.1 Deleted row(s) per 2010 Update Type Duplex Material of Construction C. S.

SSF Sump Pump Quantity 2/Station Nameplate Design Pressure (psig) 75 Design Temperature (°F) 100 Design Flow Rate (gpm) 100 Design Head from Pump Head Curve (ft) 44 Type Centrifugal, Vertical Cantilever Material of Construction C. S.

Fluid Floor Drain Liquid

Oconee Nuclear Station UFSAR Table 9-14 (Page 3 of 4)

(31 DEC 2019)

Diesel Engine Fuel Oil Storage Tank Quantity 1/Station Capacity (gal) 50,000 Material of Construction C. S.

Location Yard, Underground Fuel Oil Day Tank Quantity 1/Station Capacity (gal) 550 Material of Construction C. S.

Location SSF, Generator Room Diesel Engine Fuel Oil Transfer Pump Quantity 1/Station Nameplate Design Pressure (psig) 150 Nameplate Design Temperature (°F) 125 Design Flow Rate (gpm) 13.6 Differential Pressure (psid) 30 Type Rotary Material of Construction C. S.

Fluid No. 2 Diesel Fuel Oil SSF Fuel Oil Transfer Filter Quantity 2/Station Design Pressure (psig) 150 Design Temperature (°F) 125 Design Flow Rate (gpm) 20 Retention for 25-Micron Particles (%)

99 Maximum Pressure Drop @ 65% Plugged (ft) 32 Type Duplex Arrangement Material of Construction S. S.

Fuel Oil Recirculation Pump Quantity 1/Station Design Pressure (psig) 30 Design Temperature (°F) 90 Design Flow Rate (gpm) 30

Oconee Nuclear Station UFSAR Table 9-14 (Page 4 of 4)

(31 DEC 2019)

Design Head (ft) 32 Type Rotary Material of Construction C. I.

Fluid No. 2 Diesel Fuel Oil Fuel Oil Recirculation Filter Quantity 1/Station Design Pressure (psig) 30 Design Temperature (°F) 90 Design Flow Rate (gpm) 30 Retention for 25-Micron Particles (%)

100 Maximum Pressure Drop @ 65% Plugged (ft) 13.5 Type Simplex Material of Construction S. S.

Unloading Oil Spill Sump Pump Quantity 1/Station Design Pressure (psig) 35 Design Temperature (°F) 100 Design Flow Rate (gpm) 32 Type Centrifugal, Submersible Material of Construction C. I.

Fluid Groundwater and No. 2 Fuel Oil Spillage

Oconee Nuclear Station UFSAR Table 9-15 (Page 1 of 2)

(31 DEC 2010)

Table 9-15. SSF Primary Valves Valve No.

Control Room Control SSF Control SSF D/G Powered New Valve Description FDW-347 No Yes Yes Yes EFW to "B" OTSG CCW-269 No Yes Yes Yes EFW Crossover CCW-268 No Yes Yes Yes SSF ASW Throttle Valve CCW-287 No Yes Yes Yes SSF ASW Block Valve HP-3 Yes Yes Yes No Letdown HP-4 Yes Yes Yes No Letdown HP-20 Yes Yes Yes No RCP Seal Return HP-398 No Yes Yes Yes RCS Makeup Pump Discharge HP-405 No Yes Yes Yes RCS Makeup Test HP-417 No Yes Yes Yes RCS Makeup Recirculation HP-426 No Yes Yes Yes RCS Letdown to Fuel Pool HP-428 No Yes Yes Yes Fuel Transfer Tube RCMU Return Iso.

SF-82 No Yes Yes Yes RCS Makeup Pump Suction SF-97 No Yes Yes Yes Fuel Transfer Tube RCMU Supply Isol.

LP2 (1)

Yes No No No Decay Heat Line LP103 No Yes Yes No Alt. Decay Heat Line RC-4 Yes Yes Yes No PORV Block RC-5 Yes Yes Yes No Press. Stm. Sample Isol.

RC-6 Yes Yes Yes No Press. Wtr. Sample Isol.

RC-159 Yes No(2)

Yes(2)

No RC-160 Yes No(2)

Yes(2)

No

Oconee Nuclear Station UFSAR Table 9-15 (Page 2 of 2)

(31 DEC 2010)

Valve No.

Control Room Control SSF Control SSF D/G Powered New Valve Description Note:

1. This valve is closed, power is removed from the feeder breaker that supplies power to the motor operator, and the feeder breaker is locked during the MODES of Applicability for the SSF with respect to the applicable unit(s). Therefore, no power is required from the SSF power system to operate this valve. In addition to the above table, certain RCS vent lines should be isolated during an SSF event. Each line has two solenoid operated (control room control only) valves in series, a vent valve and a vent block valve. Closure of either the vent or the vent block valve is necessary.

These valves are:

a. RC-155 "A" OTSG Hot Leg Vent

b. RC-156 "A" OTSG Hot Leg Vent Block

c. RC-157 "B" OTSG Hot Leg Vent

d. RC-158 "B" OTSG Hot Leg Vent Block

e. RC-159 Reactor Vessel Head Vent

f. RC-160 Reactor Vessel Head Vent Block

2. Control of the RV head vent valves will be accomplished using a portable control panel.

Oconee Nuclear Station UFSAR Table 9-16 (Page 1 of 1)

(31 DEC 2011)

Table 9-16. SSF Instrumentation PARAMETER MONITORED INSTRUMENT NO.

RCS Loop A Pressure PT 225 RCS Loop B Pressure PT 226 SSF RC Makeup Pump Suction Pressure PT 223 Discharge Pressure PT 227 Suction Temperature RD 174 Discharge Flow FT 157 RC System Temperature RD-85A,-84A,-8A,-7B,-6A,-5B Pressurizer Water Level LT 72 Unit 1 Pressurizer Pressure 1RC PT0224, 1RC P0236 Unit 2 Pressurizer Pressure 2RC PT0224, 2RC P0236 Unit 3 Pressurizer Pressure 3RC PT0224, 3RC P0236 SSF Auxiliary Service Water Water Pump Suction Pressure PG 435 Discharge Pressure PG 430, PG 431 Unit 1 Discharge Pressure 1 PG 434 Unit 2 Discharge Pressure 2 PG 434 Unit 3 Discharge Pressure 3 PG 434 Discharge Test Flow FT 71 Suction Temperature TH 102 Unit 1 Flow 1 FT 225 (1 FE 226, 1P 353)

Unit 2 Flow 2 FT 225 (2 FE 226, 2P 353)

Unit 3 Flow 3 FT 225 (3 FE 226, 3P 353)

Minimum Flow Line Flow FE 230 (PG 867)

Unit 1 Steam Generator Levels A, B LT 66, LT 67 Unit 2 Steam Generator Levels A, B LT 66, LT 67 Unit 3 Steam Generator Levels A, B LT 66, LT 67 Underground Fuel Oil Storage Tank Level LT 50 Incore Thermocouples D/G Service Water Pump Discharge Flow FT 73 HVAC Service Water Pump Discharge Flow FT 72

Oconee Nuclear Station UFSAR Table 9-17 (Page 1 of 1)

(31 DEC 2000)

Table 9-17. Design Basis Tornado Missiles And Their Impact Velocities No.

Missile Descriptions Weight (lbs.)

Impact Area (sq. in.)

Design Impact Velocity (Ft/Sec)

Horizontal Vertical 1

WOOD PLANK, 3.62 in. x 11.37 in. x 12 ft.

115 41.2 272 190 2

STEEL PIPE, 6 in. diam. 15 ft. long, Schedule 40 287 34.5 171 120 3

STEEL ROD, 1 in. diam., 3 ft. long 8.8 0.79 167 117 4

UTILITY POLE, 13.5 in. diam., 35 ft. long 1124 143.1 180 126 5

STEEL PIPE, 12 in. diam., 15 ft. long, Schedule 40 750 127.68 154 108 6

AUTOMOBILE, 28 sq. ft. frontal area 3990 4032.0 194 136

Oconee Nuclear Station UFSAR Table 9-18 (Page 1 of 1)

(31 DEC 2000)

Table 9-18. Design Basis Tornado Missiles Minimum Barrier Thicknesses Modified Petry Formula Modified N.D.R.C. Formula Missile Penetration Depth Horiz Strike (D)

Min.

Thickness (3D)

Penetration Depth Vert.

Strike (D)

Min.

Thickness (3D)

Penetration Depth Horiz.

Strike (D)

Min.

Thickness (D)

Penetration Depth Vert.

Strike (D)

Min.

Thickness (D) 1 2.64 7.92 1.39 4.17 4.07 12.21 2.95 8.85 2

3.39 10.17 1.72 5.16 4.39 13.17 3.19 9.57 3

4.77 14.31 2.41 7.23 2.02 6.06 1.46 4.38 4

3.54 10.62 1.79 5.37 6.85 20.55 4.97 14.91 5

1.96 5.88 0.99 2.97 4.97 14.91 3.61 10.83 6

0.51 1.53 0.26 0.78 7.08 21.24 5.14 15.42 Note:

1. All Penetration Depths are calculated based on a concrete strength f'c of 5000 PSI.

2. All Penetration Depths and Minimum Barrier Thicknesses are in inches.

Oconee Nuclear Station UFSAR Table 9-19 (Page 1 of 1)

(31 DEC 2000)

Table 9-19. Codes and Specifications For Design of Category I Structures Structural Component Design Codes and Specifications Concrete ACI 318-71 Concrete Reinforcement ASTM A615-72, Grades 40 and 60 Cadwelds Regulatory Guide No. 1.10, Rev. 1 (1)

Structural Steel and Plates ASTM A-36 AISC, Seventh Edition Note:

1. Valid test results are used. A valid test is a test whose failure is in the Cadwell Splice and not in the bar or near testing machine grips. Test samples for B Series Splices will be sister Splices only.

Abbreviations:

ACI American Concrete Institute AISC American Institute of Steel Construction ASTM American Society for Testing and Materials

Oconee Nuclear Station UFSAR Table 9-20 (Page 1 of 1)

(31 DEC 2015)

Table 9-20. Reverse Osmosis System Data, Common to Units 1 & 2 Reverse Osmosis Feed Booster Pump Type Two Stages Horsepowerof Motor 2

Material SS Process Flow, Gal/min 65 (design)

Design Head, feet H2O 75 Reverse Osmosis Feed Pump Type Horizontal, Single Stage, gear-driven Horsepowerof Motor SS Material 40 Process Flow, Gal/min 65 (design)

Design Head, feet H2O 1025 Reverse Osmosis Membrane Filter Housings Quantity 6

Material SS Process Flow, Gal/min Varies (<65)

Design Pressure, psig 600 Code Inspection and Testing: ASME B31.1 Materials: ASME B&PV II