ML20189A075

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8 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3A, Tables
ML20189A075
Person / Time
Site: Oconee  Duke energy icon.png
Issue date: 06/29/2020
From:
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation
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ML20189A066 List:
References
RA-20-0136
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Oconee Nuclear Station UFSAR Appendix 3A. Tables Appendix 3A. Tables

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

Table 3-1. System Piping Classification Designed For Piping Class Design Criteria Seismic Loading A Class I, USAS B31.7(2) Yes B Class II, USAS B31.7 Yes C Class III, USAS B31.7 Yes D USAS B31.1.0 Yes (1)

E USAS B31.1.0 No F USAS B31.1.0 Yes G USAS B31.1.0 No H Good Industry Practice No Note:

1. Portions are considered a Class III system in accordance with FSAR Section 3.2.2.1.
2. Class I RCS piping was re-analyzed to the 1983 ASME Code (No Addenda) during the replacement steam generator analysis.

(31 DEC 2004)

Oconee Nuclear Station UFSAR Table 3-2 (Page 1 of 6)

Table 3-2. System Component Classification Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

Reactor Coolant System Reactor Vessel ASME III, Class A Yes - D Reactor Vessel Head ASME III, Class I, 1989 Edition, Yes - D No Addenda Pressurizer ASME III, Class A Yes - D Reactor Coolant Pump Casing ASME III, Class A (not code Yes - D stamped)

Steam Generator ASME III, Class A Yes - D High Pressure Injection System HP Injection Pump See Table 6-3 Yes - Note 1 Letdown Cooler ASME III-C & VIII Yes - D Seal Return Cooler ASME III-C & VIII Yes - Note 2 Letdown Storage Tank ASME III-C Yes - Note 2 Purification Demineralizer ASME III-C Yes - Note 2 Letdown Filter ASME III-C Yes - Note 2 RC Pump Seal Filter USAS B31.7, Paragraph 2-724, Yes - Note 3 Class II Chemical Addition and Sampling System Boric Acid Mix Tank USAS B96.1 No Lithium Hydroxide Mix Tank - No Caustic Mix Tank - No TSP Baskets AISC Yes -D Boric Acid Pump - No Lithium Hydroxide Pump - No Hydrazine Pump - No Caustic Pump - No Pressurizer Sample Cooler ASME III-C & VIII No Steam Generator Sample Cooler ASME VIII No Component Cooling System (31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-2 (Page 2 of 6)

Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

Component Cooling Pump - Yes - Note 1 Component Cooler ASME VIII Yes - Note 2 Component Cooling Surge Tank AWWA D-100 Yes - S CRD Cooling Coil Filter ASME VIII Yes - S Reactor Fuel Cooling System Spent Fuel Cooler ASME III-C & VIII Yes - Note 2 Spent Fuel Pump - Yes - Note 1 Spent Fuel Filter ASME III-C Yes - S Borated Water Recirculation Pump - Yes - Note 1 Spent Fuel Demineralizer ASME III-C Yes - Note 2 Fuel Transfer Tube ASME III-B Yes - D Incore Instrument Handling Tank AWWA D-100 Yes - D Low Pressure Injection System LP Injection Pump See Table 6-3 Yes - Note 1 LP Injection Cooler ASME III-C & VIII Yes - Note 2 Borated Water Storage Tank AWWA D-100 Yes - S Core Flooding Tank ASME III-C Yes - D Reactor Building Spray System Reactor Building Spray Pump See Table 6-3 Yes - Note 1 Reactor Building Penetration Room Ventilation System Penetration Room Filter See Section 6.5.1 Yes - S Penetration Room Fan See Section 6.5.1 Yes - Note 4 LP Service Water System LP Service Water Pump - Yes - Note 1 SSF Systems and Components See Section 9.6.4.5 Note 9 Reactor Building Cooling System Reactor Building Coolers See Section 6.2.2 Yes - D Recirculated Cooling Water System (31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-2 (Page 3 of 6)

Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

RCW Pump - No RCW Heat Exchanger U1/U2 ASME VIII Yes - Note 8 RCW Heat Exchanger U3 - No RCW Surge Tank ASME VIII (not code stamped) No Coolant Storage System Quench Tank ASME III-C Yes - Note 2 Quench Tank Cooler ASME III-C & VIII Yes - Note 2 Component Drain Pump - Yes - Note 1 Coolant Bleed Holdup Tank ASME VIII (not code stamped) Yes - S Bleed Transfer Pump - Yes - Note 1 Deborating Demineralizer ASME III-C Yes - Note 2 Concentrated Boric Acid Storage USAS B96.1 Yes - S Tank

- No Concentrated Boric Acid Storage Tank Pump Coolant Treatment System Coolant Bleed Evaporator ASME III-C Yes - Note 2 Demineralizer Coolant Bleed Evaporator Feed Tank AWWA D-100 Yes - S Coolant Bleed Evaporator ASME VIII (lethal) Yes - S Recirculating Pump - Yes - S Concentrate Cooler ASME VIII (lethal) Yes - S Separator ASME VIII (lethal) Yes - S Vapor Condenser ASME VIII (lethal) Yes - S Distillate Pump - Yes - S Distillate Cooler ASME VIII (lethal) Yes - S Condensate Test Tank USAS B96.1 Yes - S Condensate Test Tank Pump - Yes - Note 1 Condensate Demineralizer ASME III-C Yes - S Coolant Bleed Evaporator Feed - Yes - S Pump (31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-2 (Page 4 of 6)

Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

Steam & Power Conversion System (Pertinent Components Only)

Condenser - Yes - S Upper Surge Tank ASME VIII Yes - S Emergency Feedwater Pump - Yes - Note 1 Emergency Feedwater Pump Turbine - Yes - Note 1 Liquid Waste Disposal System High Activity Waste Tank Note 7 Yes - Note 5 High Activity Waste Tank Pump - No Low Activity Waste Tank Note 7 Yes - Note 5 Low Activity Waste Tank Pump - No Waste Holdup Tank AWWA D-100 Yes - S Waste Holdup Transfer Pump - Yes - Note 1 Spent Resin Storage Tank AWWA D-100 Yes - S Spent Resin Transfer Pump - Yes - Note 1 Spent Resin Sluicing Pump - Yes - Note 1 Waste Evaporator Feed Tank AWWA D-100 Yes - S Waste Evaporator ASME VIII (lethal) Yes - S Recirculating Pump - Yes - S Concentrate Cooler ASME VIII (lethal) Yes - S Separator ASME VIII (lethal) Yes - S Vapor Condenser ASME VIII (lethal) Yes - S Distillate Pump - Yes - S Distillate Cooler ASME VIII (lethal) Yes - S Reactor Building Sump Pump - Yes - Note 1 Waste Evaporator Feed Pump - Yes - S Gaseous Waste Disposal System (31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-2 (Page 5 of 6)

Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

Waste Gas Compressor - Yes - S Waste Gas Separator ASME VIII Yes - S Seal Water Cooler - Yes - S Waste Gas Tank ASME VIII-C Yes - S Waste Gas Filter - Yes - S Waste Gas Exhauster - No Condenser Cooling Water System Intake Structure - Yes - S CCW Pumps - Yes - S CCW Intake Pipe - Yes - S CCW Discharge Pipe - Yes - S ECCW Piping (Structural Portion) - Yes - S Condenser - Yes - S Essential Siphon Vacuum (ESV)

System ESV Pumps - Yes - Note 6 ESV Tanks ASME Secton VIII Yes - S (31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-2 (Page 6 of 6)

Designed For Seismic Loading (D=Dynamic Analysis) (S=Static Design Code Analysis)

Notes:

1. Vendor certification that component will meet seismic loading requirement.
2. Static and Dynamic Analyses performed.
3. Shock tested in lieu of analysis.
4. Vendor certification that component will meet seismic loading requirement will be furnished.
5. Tank meets loading requirement by its location in Auxiliary Building basement floor.
6. Seismic Adequacy evaluated using experience based criteria and procedures.
7. Stainless Steel Lining for Concrete Sump
8. Dynamic analysis performed. Static and/or dynamic analyses can be performed for future changes that affect the U 1/2 RCW Heat Exchanger. Seismic loads are applied to this U 1/2 Heat Exchanger since the attached CCW piping is Class D-seismic.
9. The SSF systems and components needed for safe shutdown are designed to withstand the safe shutdown Earthquake. See Sections 9.6.4.1 and 9.6.4.3
10. A separate PSW structure is provided for major electrical equipment. The PSW structure is designed to withstand the Maximum Hypothetical Earthquake (MHE) and tornado missiles, wind and differential pressure in accordance with Regulatory Guide 1.76 (Revision 1). Other components that receive backup power from the PSW System retain their existing seismic and quality classifications. See Section 9.7.

(31 DEC 2014)

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

Table 3-3. Summary of Missile Equations Missile Principle Symbolic Form of Equation Solution Category I Stored strain 2 energy equals v mV o g

Vo

kinetic energy 2 2 E 2

2 v mV o Note: The above equation was revised in 2004 update.

=

2E 2 II Work done is 2 2PA ol Converted to mVo Vo =

Fl = m kinetic energy 2 PA o l Note: The above equation was revised in 2004 update.

=

III Newton's second F = ma V V 2 law (1 ) 1n (1 ) = K1 F Vf Vf a=V & =X&& = r + X tan m o Note: The above equation was revised in 1995 update.

& = f A o Vf m V V A

V M Aj

( f

) K 1 = (1 Vo V K

) 1n (1 o ) + 2 Vf Vf ro Note: The above equation was revised in 1999 update. Note: The above equation was revised in 1999 update.

f A o A m K2 =

m tan Note:

1. Either graphical techniques or numerical methods must be used to obtain the solution to category III.

(31 DEC 2004)

Oconee Nuclear Station UFSAR Table 3-4 (Page 1 of 1)

Table 3-4. List of Symbols

= ultimate tensile stress, (lb/ft2)

= density of missile, (#/ft3)

= strain = /E, (in./in.)

E = modulus of elasticity, (lb/ft2) v = volume of missile, (ft3) m = mass of the missile, (lb-sec2/ft)

V = velocity of missile, (ft/sec) g = gravity constant, (ft/sec2)

F = force on the missile, (lb) l = stroke length, (ft)

P = system pressure, (lb/ft2)

Ao = missile area under pressure, throat area, (ft2) f = density of fluid, (#/ft3)

Vf = jet velocity, (ft/sec)

Am = projected area of missile, (ft2)

Aj = jet area, (ft2)

= angle of jet expansion, (°from normal)

X = distance missile travels, (ft)

Vo = initial velocity of missile, (ft/sec) ro = radius of throat (ft)

K2 = constant (31 DEC 2000)

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

Table 3-5. Properties of Missiles - Reactor Vessel & Control Rod Drive Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

I 1. Closure head nut [Note 1] 80 38 97 11,680

2. Closure stud w/nut [Note 1] 660 71 97 96,400
3. 1" Valve bonnet stud 0.5 0.6 73.5 42
4. C. R. nozzle flange bolt & nut 3.0 3.1 97 438 II 1. CRD closure cap 8.0 7.0 215 5,742 III 1. C. R. drive assembly 1000 64.0 90 125,777 Deleted row(s) per 2004 update Note:
1. These values are from the NSSS and Bechtel vendor calculations. HydraNuts have been established as acceptable alternate closure head nuts. Each HydraNut weighs approximately 108 lbs. This increase in weight and associated parameters in the table due to the use of the HydraNuts remains bounded by those of the control rod drive described in Section 3.5.1.1.

(31 DEC 2014)

Oconee Nuclear Station UFSAR Table 3-6 (Page 1 of 2)

Table 3-6. Properties of Missiles - Steam Generator Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

Original Steam Generator I 1. 11/2" Vent valve bonnet stud 2.0 .8 73.5 167

2. Feedwater inlet flange bolt 0.3 .6 67.5 21
3. 16" I.D. manway stud, tube side 8.0 2.1 67.5 566
4. 5" Inspection opening cover stud 1.5 1.2 73.5 125
5. 1" Valve bonnet stud 0.5 .6 73.5 42 II 1. 11/2" Vent valve stem & wheel 5.0 .45 44.5 154
2. Sample line 1" valve stem &

wheel 4.0 .3 35.8 80

3. Sample line 1" EMO valve stem and wheel 4.0 .3 35.8 80
1. 16" I.D. manway cover, tube III side 955 615 515 1,950,000
2. 16" I.D. manway cover, shell side 478 615 777 2,230,000
3. 5" I.D. inspection cover, tube side 80 150 515 160,000
4. 5" I.D. inspection cover, shell side 40 150 852 220,000
5. 11/2" Vent valve bonnet and assembly 24 38 371 51,180
6. Sample line 1" valve bonnet &

assy. 30 27 243 27,460

7. Sample line 1" EMO bonnet &

assy. 115 27 138 34,250 (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-6 (Page 2 of 2)

Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

Replacement Steam Generator I 1. 11/2" Vent valve bonnet stud 2.0 .8 73.5 167

2. Feedwater inlet flange bolt 0.3 .6 67.5 21
3. 16" I.D. manway stud, tube side 8.0 2.1 67.5 566
4. 6 Handhole opening cover stud 1.5 1.2 73.5 125
5. 1" Valve bonnet stud 0.5 .6 73.5 42 II 1. 11/2" Vent valve stem & wheel 5.0 .45 44.5 154
2. Sample line 1" valve stem &

wheel 4.0 .3 35.8 80

3. Sample line 1" EMO valve stem and wheel 4.0 .3 35.8 80
1. 16" I.D. manway cover, tube III side 955 615 515 1,950,000
2. 16" I.D. manway cover, shell side 478 615 777 2,230,000
3. 6 Handhole opening cover, tube side 80 150 515 160,000
4. 6 Handhole opening cover, shell side 40 150 852 220,000
5. 11/2" Vent valve bonnet and assembly 24 38 371 51,180
6. Sample line 1" valve bonnet &

assy. 30 27 243 27,460

7. Sample line 1" EMO bonnet &

assy. 115 27 138 34,250 (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-7 (Page 1 of 1)

Table 3-7. Properties of Missiles - Pressurizer Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

I 1. 4" Valve bonnet stud 3.0 1.8 73.5 250

2. 5" Valve bonnet stud 3.0 2.4 73.5 250
3. 16" Manway cover stud 7.5 3.1 67.5 530
4. Heater bundle stud 25.0 7.0 73.5 2100
5. 3/4" Valve stem stud 0.8 .45 73.5 67 II 1. Spray line 4" EMO valve stem 9 1.0 135.0 2560
2. Sample line 3/4" valve stem 4 .3 72.7 330
3. Sample line 3/4" EMO valve stem 4 .3 72.7 330 III 1. 16" I.D. manway cover 250 615 375 546,000
2. Heater bundle assembly 2500 850 375 5,400,000
3. Spray line 4" EMO valve bonnet and assembly 325 150 521 1,370,000
4. 21/2" x 6 Relief valve bonnet and assembly 175 65 232 146,000
5. Sample line 3/4" valve bonnet and assembly 20 21 364 41,150
6. Sample line 3/4" EMO valve bonnet and assembly 115 21 258 118,400 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-8 (Page 1 of 1)

Table 3-8. Properties of Missiles - Quench Tank and Instruments Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

QUENCH TANKS I 1. 11/2" Drain valve bonnet stud 0.6 .2 73.5 50

2. 4" Valve bonnet stud 2.0 .3 73.5 167 II 1. 11/2" EMO drain valve stem 5.0 .45 11.0 9
2. 4" EMO valve stem 9.0 1.0 21.5 65 III 1. 11/2" EMO drain valve & op.assy. 220 20 73.5 18,450
2. 11/2" Drain valve bonnet & assy. 20 20 73.5 1,670
3. 4" EMO valve bonnet & op. assy. 355 65 73.5 29,780 INSTRUMENTS III 1. RTE 1.0 .2 208 670
2. RTE & Plug 2.0 4.0 448 6230 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-9 (Page 1 of 2)

Table 3-9. Properties of Missiles - System Piping Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

Core Flooding Line I 14" C.V. bonnet stud 2.0 1.7 73.5 167 I 14" Valve bonnet stud 3.5 4.0 67.5 248 II 14" C.V. check pivot stud 10.0 1.75 249 9650 II 14" P.O. valve stem 98.0 5.0 143 31,100 III 14" C.V. bonnet & assembly 525.0 125 448 1,640,000 III 14" P.O. valve bonnet and assembly 1900.0 650 558 9,180,000 L.P. Injection Line I 12" C.V. bonnet stud 2.0 1.7 73.5 167 II 12" C.V. check pivot stud 10 1.75 249 9,650 III 12" C.V. bonnet and assy. 450 95 558 2,170,000 R.V. Outlet Line to L.P. System I 10" Valve bonnet stud 2.5 1.7 73.5 177 I Relief valve bonnet stud 0.5 .3 73.5 42 I Relief valve stem assy. 40 12.5 35.3 768 II 10" EMO valve stem 50 3.1 130 13,200 III 10" EMO valve bonnet & assy. 1270 415 558 6,140,000 R.V. Inlet Line from H.P. System I 4" C.V. bonnet stud 1.0 .8 73.5 83.5 II 4" C.V. check pivot stud 3.0 .8 158 1170 III 4" C.V. bonnet and assy. 30 19 558 145,000 S.G. Outlet Line to Pump Inlet I 1" Drain valve bonnet stud 0.8 .6 73.5 67 II 1" Drain valve stem assy. 4.0 .3 84 438 III 1" Drain valve & bonnet assy. 30.0 27 448 84,380 Pressurizer to C.A. System Line I 3/4" Valve bonnet stud 1.0 .45 73.5 83 II 3/4" Valve stem 4 .3 73 330 II 3/4" EMO valve stem 4 .3 73 330 III 3/4" Valve bonnet and assy. 20 21 425 56,250 (31 DEC 2000)

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

Kinetic Missile Weight Impact Velocity Energy Class Description (lbs.) Area (in2) (ft/sec) (Ft-lbs)

III 3/4" EMO valve bonnet and assy. 115 21 280 140,000 Primary Pump Seal Water Return to H.P. System Line I 3" EMO valve bonnet stud 1.0 1.0 73.5 83.5 II 3" EMO valve stem 25.0 .3 125.7 6150 III 3" EMO valve bonnet and assy. 285.0 85 507 1,137,000 Letdown Cooler Inlet & Outlet Lines I 11/2" EMO valve bonnet stud 2.0 .8 73.5 167 II 11/2" EMO valve stem 1.0 1.0 153.2 1830 III 11/2" EMO valve bonnet and assy. 250.0 38 320 397,000 Primary Pump Seal Water Inlet and Outlet Lines I 3" Inlet C.V. bonnet stud 1.0 .8 73.5 83.5 I 3" Outlet valve bonnet stud 2.0 1.0 73.5 167 II 3" C.V. check pivot stud 3.0 .8 158.4 1170 II 3" Outlet valve stem 25.0 2.4 125.7 6150 III 3" Inlet C.V. bonnet and assy. 25.0 85 558 120,800 III 3" Outlet valve bonnet and assy. 65.0 85 523 276,000 Primary Pump Vent & Drain Lines I 11/2" Vent & drain valve bonnet stud 2.0 .8 73.5 167 II 11/2" Vent & drain valve stem 5.0 1.0 153.2 1830 III 11/2" Vent & drain valve bonnet and 55.0 38 435.0 161,600 assy.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-10 (Page 1 of 1)

Table 3-10. Missile Characteristics Weight Impact Area 5944 lbs Side On - 8.368 sq ft End On - 3.657 sq ft Velocity Kinetic Energy Ft-Lbs Initial - 710 fps Initial - 46.5 x 106 Impact Impact Cylinder - 502 fps Cylinder - 23.25 x 106 Dome - 431 fps Dome - 18.0 x 106 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-11 (Page 1 of 1)

Table 3-11. Depth of Penetration of Concrete Case I Case II Case III Cylinder Dome Cylinder Dome Cylinder Dome 6" 51/2" 12 3/4" 121/4" 351/2" 25" (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-12 (Page 1 of 5)

Table 3-12. Containment Coatings Surface Coating Systems Dry Film Thickness Manufacturer Remarks

1. Carbon Steel Original System Note 1 0°F - 200°F Prime Coat Carbo Zinc 11 3.0 mils DFT Carboline Finish Coat Phenoline 305 Finish 4.0 mils DFT Carboline 7.0 mils DFT Maintenance System Note 2 over Original System DP-SP28 Power Tool Cleaning Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils DFT Carboline New System DP-SP5 White Metal Blast Cleaning 2.0 mils DFT Carboline Note 2 Prime Coat DP#12-1 Carbo Zinc 11 SG 5.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 7.0 mils DFT
2. Carbon Steel Original System Note 1 0°F - 200°F Prime Coat Carboline 191 Primer 2.0 mils DFT Carboline Finish Coat Phenoline 305 Finish 5.0 mils DFT Carboline 7.0 mils DFT Maintenance System Note 2 over Original System DP-SP28 Power Tool Cleaning Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils DFT Carboline New System DP-SP5 White Metal Blast Cleaning Note 2 Prime Coat DP#78-1 Carboline 890 2.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline 7.0 mils DFT (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-12 (Page 2 of 5)

Surface Coating Systems Dry Film Thickness Manufacturer Remarks

3. Carbon Steel Original System Note 1 0°F - 750°F Prime Coat Carbo Zinc 11 3.0 mils DFT Carboline New system DP-SP5 White Metal Blast Cleaning Note 2 Prime Coat DP#12-1 Carbo Zinc 11 SG 3.0-5.0 mils DFT Carboline
4. Carbon Steel New System DP-SP5 White Metal Blast Cleaning Note 2 0°F-250°F Prime Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin Tank Lining Intermediate Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin Finish Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin 12.0 mils DFT
5. Concrete Original System Note 1 Floors Prime Coat 195Epoxy Surfacer 8.0 mils DFT Carboline Finish Coat Phenoline 305 Finish 4.0-8.0 mils DFT Carboline 12.0-16.0 mils DFT Maintenance System Note 2 over Original System DP-SP25 Maintenance Coat DP#78-1 Carboline 890 Carboline New System Note 2 Prime Coat DP-SP25 Finish Coat DP#36-1 Starglaze 2011S Seal Concrete Carboline DP#78-1 Carboline 890 8.0 mils DFT Carboline 8.0 mils DFT (31 DEC 2000)

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

Surface Coating Systems Dry Film Thickness Manufacturer Remarks

6. Concrete Original System DP-SP17 Note 1 Walls Prime Coat DP#36-1 46-X-29-00 Epoxy Surfacer 8.0 mils DFT Carboline Finish Coat DP#69-1 76 Series-00 High Build Epoxy 4.0-8.0 mils DFT Carboline 12.0-16.0 mils DFT Maintenance System Note 2 over Original System DP-SP17 Maintenance Coat DP#78-1 Carboline 890 2.0 to 5.0 mils DFT Carboline New System DP-SP17 Seal Concrete Carboline Note 2 Prime Coat DP#36-1 Starglaze 2011S 5.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 8.0 mils DFT Notes:

HISTORICAL INFORMATION NOT REQUIRED TO BE REVISED

1. Original coating systems have satisfactorily withstood the following autoclave tests designed to simulate LOCA conditions with no loss of adherence or erosion of material from surface:

Carbon Steel

a. Test specimens: Coating system applied to sandblasted carbon steel coupons.
b. Water chemistry: 3000 ppm boron as boric acid in water; also 3% boric acid (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-12 (Page 4 of 5)

Surface Coating Systems Dry Film Thickness Manufacturer Remarks

c. Temperature:

For 3000 ppm boron 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 285°F-290°F 2 days at 200° F 6 days at 150°F 4 days at 130°F For 3% Boric Acid 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 75°F-300°F 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 300°F 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at 300°F-180° F 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> cooling to ambient Total 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cycle repeated ten times Concrete

a. Test specimens: Prepared concrete coupons.
b. Water Chemistry: 3000 ppm boron as boric acid in water; also 3% boric acid .
c. Temperature:

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 75°F - 300° F 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> at 300°F 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 75° F 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cooling to ambient

  • We understand testing performed by ANS Subcommittee for Protective Coatings for Reactor Containment Facilities and by Dr. C D Watson at Oak Ridge did not disclose any significant difference between results of static autoclave exposure and autoclave exposure using a spray of solution on panels. On this basis either static or dynamic exposure to spray solution is considered to be acceptable as basis for testing.
  • We do not have available test results on jet impingement effects; however, it is felt that there is no coating system available which would (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-12 (Page 5 of 5) withstand a high temperature, high velocity steam jet. We believe that the assumption of large scale, rapid LOCA by means of a double-ended pipe failure or otherwise, negates the possibility of concentrated local jet impinging on a coated steel area of substantial size.

Therefore, we believe the autoclave tests in which specimens were subjected to steam and water at elevated temperatures more nearly approximate overall building environment under LOCA conditions than would a local steam jet application.

  • We understand ANS subcommittee found no system for coating steel or concrete for resisting steam jet impingement and therefore has established no standards for this condition of exposure .
  • Decontamination factor for Phenoline 305 is 325. Test methods described in Oak Ridge National Laboratory Reports ORNL-3589, 3916 and others.
  • Carbo Zinc 11 withstands in excess of 3 x 109 Roentgens when irradiated in water. There is no serious damage to Phenoline 305 at 6 x 109 Roentgens when irradiated in air. Phenoline 305 withstands in excess of 2 x 109 Roentgens irradiated in water .
2. Maintenance coating over Original Coating Systems and New Coating Systems have satisfactorily withstood radiation and autoclave tests with no loss of adherence or erosion of material from surface.

Radiation Tolerance.

  • Coating specifications for shop and field application include the following: Scope, Coating System, Approved Materials, Application Procedures, Touchup Procedures, Workmanship Guide, Inspection Requirements, Record Requirements, and Product Data Sheets.
  • A Materials Certification of each batch of coating material procured is in accordance with ANSI N101.4 and is provided by the Manufacturer.
  • Distribution of Containment Coating Specifications and Coating Schedules are transmitted by Document Control.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-13 (Page 1 of 1)

Table 3-13. Service Load Combinations for Reactor Building

1. D + F + L + To
2. D + F + L + P + TA + E(or W)
3. D + F + L + P' Where:

D = Dead Load L = Appropriate Live Load F = Appropriate Prestressing Load P = Pressure Load (Varies with time from design pressure to zero pressure)

To = Thermal Loads Due to Operating Temperature TA = Thermal Loads Based on a Temperature Corresponding to a Pressure P E = Design Earthquake P' = Test Pressure = 1.15 P W = Wind Load (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-14 (Page 1 of 2)

Table 3-14. Accident, Wind, and Seismic Load Combinations and Factors for Class 1 Concrete Structures Y = 1/1.0D + 1.0P + 1.0T + E')

Y = 1/ (1.05D + 1.25P + 1.0T + 1.25E or W)

Y = 1/ (1.05D + 1.5P + 1.0T)

Y = 1/1.0D + 1.0Wt + 1.0Pi) for Tornado Forces.

(Use 0.95 where dead load subtracts from critical stress.) (Wind, W, to replace earthquake, E, in the above formula where wind stresses control)

Where Y = required yield strength of the structure as defined above.

D = dead loads of structure and equipment plus any other permanent loadings contributing stress, such as hydrostatic or soils. In addition, a portion of "live load" should be added when it includes piping, cable trays, etc. suspended from floors and an allowance should be made for future additional permanent loads.

P = design accident pressure.

T = thermal loads based on a temperature corresponding to the factored design accident pressure.

E = seismic load based on design earthquake.

E' = seismic load based on maximum hypothetical earthquake.

W = wind load.

Wt = stress induced by tornado wind velocity (drag, lift and torsion).

Pi = stress due to differential pressure.

= Concrete capacity reduction factor.

= 0.90 for concrete flexure.

= 0.85 for tension, shear, bond and anchorage in concrete.

= 0.75 for spirally reinforced concrete compression members.

= 0.70 for tied compression members.

= 0.90 for fabricated structural steel embedments.

= 0.90 for mild reinforcing steel (not prestressed) in direct tension excluding splices.

= 0.85 for mild reinforcing steel with mechanical splices (for lap splices, = 0.85 as above for bond and anchorage).

= 0.95 for prestressed tendons in direct tension.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-14 (Page 2 of 2)

Additional Notes:

The Class 1 structures are proportioned to maintain elastic behavior when subjected to various combinations of dead loads, accident loads, thermal loads and wind or seismic loads. The upper limit of elastic behavior is considered to be the yield strength of the effective load-carrying structural materials.

The yield strength for steel (including reinforcing steel) is considered to be the minimum given in the appropriate ASTM specification. Concrete structures are designed for ductile behavior wherever possible; that is, with steel stress controlling the design. The values for concrete, as given in the ultimate strength design portion of the ACI 318-63 Code, will be used in determining "Y", the required yield strength of the structure.

The design loads applied to the structures are increased by load factors based on the probability and conservatism of the predicted normal design loads.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-15 (Page 1 of 1)

Table 3-15. Inward Displacement of Liner Plate Factor of Nominal Plate Initial Inward Anchor Anchor Safety Thickness Displacement Spacing L1 Spacing L2 Against Case (In.) (In.) (In.) (In.) Failure I 0.25 0.125 15 15 37.0 II 0.25 0.125 15 15 19.4 III 0.25 0.125 15 15 9.9 IV 0.25 0.125 15 15 6.28 V 0.25 0.25 30 15 4.25 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-16 (Page 1 of 1)

Table 3-16. Stress Analysis Results (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-17 (Page 1 of 1)

Table 3-17. Stress Analysis Results (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-18 (Page 1 of 1)

Table 3-18. Stress Analysis Results (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-19 (Page 1 of 1)

Table 3-19. Stress Analysis Results (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-20 (Page 1 of 1)

Table 3-20. Stress Analysis Results (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-21 (Page 1 of 1)

Table 3-21. Stress Analysis Results (31 DEC 2003)

Oconee Nuclear Station UFSAR Table 3-22 (Page 1 of 1)

Table 3-22. Bent Wire Test Results STRESS Sample (psi)

Group No. 1 2 3 4 5 6 Bend Angle (Degrees) - 30 60 90 30 60 Bend Radius (inch) - 1.25 1.25 1.25 0 0 1 251,500 257,650 257,650 259,650 251,550 230,150 2 254,600 259,650 257,650 257,650 251,550 237,250 3 256,600 257,650 259,650 256,600 252,550 240,300 SERIES I Heat

  1. A67386 4 258,650 258,650 258,650 256,600 247,450 235,250 5 259,650 261,700 259,650 258,650 248,450 237,250 6 258,650 259,650 260,700 258,650 7 260,700 254,600 261,700 258,650 8 259,650 258,650 260,700 258,650 9 260,700 258,650 260,700 257,650 10 260,700 258,650 255,600 260,700 Average 258,850 258,550 259,250 258,350 250,300 236,050 11 252,550 249,500 249,500 243,400 229,100 12 252,550 249,500 251,550 243,400 227,100 13 249,500 249,500 248,450 243,400 229,100 SERIES II Heat
  1. A72005 14 248,450 249,500 250,500 242,350 227,100 15 247,450 250,500 248,450 241,350 228,100 16 250,500 249,500 248,450 17 254,600 253,550 252,550 18 251,550 251,550 251,550 19 252,550 251,550 249,500 20 249,500 254,600 249,500 Average 250,900 250,900 250,000 242,750 228,100 (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-23 (Page 1 of 1)

Table 3-23. Auxiliary Building Loads and Conditions AREA CONDITIONS Control Room A,B,C,D,E Cable Room A,B,C,D,E Electrical Equipment A,B,C,D,E Room Spent Fuel Pool A,B,C,D,E Blow out panels designed to relieve 3 psi differential pressure Spent Fuel Storage Racks A,D Inherently resistant to wind loads Spent Fuel Handling A,D,E Inherently resistant to wind loads. Hold down device Crane provided Penetration Room Frames A,B,D Physical separation provided for missile protection Cable Shaft A,B,C,D,E Elevator Steel Shaft A,D Main Steam Pipe A,B,D Supports Hot Machine Shop A,D Balance of Auxiliary A,B,D Frame designed for B, but not external walls above Building grade. Areas below grade are inherently protected against missiles in C and E.

A = All normal dead, equipment, live, and wind loads due to 95 mph wind or design basis earthquake.

B = Normal dead and equipment loads plus tornado wind load due to 300 mph wind.

C = Tornado missiles of (1) 8 in. diameter x 12 ft. long piece of wood, 200 pounds, 250 mph, and (2) 2,000 pound automobile, 100 mph, 20 sq. ft. impact area, for 25 ft. above grade.

D = Normal dead and equipment loads plus maximum hypothetical earthquake loads.

E = Turbine-generator missile, 5,944 pounds, 502 fps, kinetic energy of 23.25 x 106 ft.-lbs., side on impact area of 8.368 sq. ft. and end on impact area of 3.657 sq. ft.

Deleted row(s) Per 2009 Update (31 DEC 2009)

Oconee Nuclear Station UFSAR Table 3-24 (Page 1 of 1)

Table 3-24. Mark-BZ Fuel Assembly Seismic and Loca Results at 600°F Loading Case Allowable Impact Grid Deformation Allowable Grid Load (lbs) Deformation (in.)

SSE 2824 (1) None 0.0 LOCA Core Flood Line 2824 None 0.0 Guillotine LOCA Decay Heat 2824 None 0.0 Line Guillotine SSE and LOCA 2824 None 0.0 Note:

1. That the allowable load is actually higher than the elastic load limit given, since the criteria of SSE is to ensure control rod insertion. Therefore, the value given is conservative.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-25 (Page 1 of 1)

Table 3-25. Deleted per 1996 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-26 (Page 1 of 1)

Table 3-26. Stress Limits for Seismic, Pipe Rupture and Combined Loads Case Loading Combination Stress Limits I Design loads + operating basis earthquake Pm 1.0Sm loads (PL + Pb ) 1.5Sm II Design loads + safe shutdown earthquake Pm 1.2Sm loads (PL + Pb ) 1.2(1.5Sm )

III Design Loads + pipe rupture loads Pm 1.2Sm (PL + Pb ) 1.2(1.5Sm )

IV Design loads + safe shutdown earthquake Pm 2 / 3Su loads + pipe rupture loads (PL + Pb ) 2 / 3Su 1

where PL = Primary local membrane stress intensity Pm = Primary general membrane stress intensity Pb = Primary bending stress intensity Sm = Allowable membrane stress intensity Su = Ultimate stress for unirradiated material at operating temperature Note:

1. All symbols have the same definition or connotation as those in ASME B&PV Code Section III, Nuclear Vessels.
2. All components will be designed to insure against structural instabilities regardless of stress levels.

(31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3 3-67 (Page 1 of 3)

Table 3-27. Deleted Per 1999 Update Table 3-28. Deleted Per 2004 Update Table 3-29. Deleted Per 2004 Update Table 3-30. Deleted Per 2004 Update Table 3-31. Deleted Per 2004 Update Table 3-32. Deleted Per 2004 Update Table 3-33. Deleted Per 2004 Update Table 3-34. Deleted Per 2004 Update Table 3-35. Deleted Per 2004 Update Table 3-36. Deleted Per 2004 Update Table 3-37. Deleted Per 2004 Update Table 3-38. Deleted Per 2004 Update Table 3-39. Deleted Per 2004 Update Table 3-40. Deleted Per 2004 Update Table 3-41. Deleted Per 2004 Update Table 3-42. Deleted Per 2004 Update Table 3-43. Deleted Per 2004 Update Table 3-44. Deleted Per 2004 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3 3-67 (Page 2 of 3)

Table 3-45. Deleted Per 2004 Update Table 3-46. Deleted Per 2004 Update Table 3-47. Deleted Per 2004 Update Table 3-48. Deleted Per 2004 Update Table 3-49. Deleted Per 2004 Update Table 3-50. Deleted Per 2004 Update Table 3-51. Deleted Per 2004 Update Table 3-52. Deleted Per 2004 Update Table 3-53. Deleted Per 2004 Update Table 3-54. Deleted Per 2004 Update Table 3-55. Deleted Per 2004 Update Table 3-56. Deleted Per 2004 Update Table 3-57. Deleted Per 2004 Update Table 3-58. Deleted Per 2004 Update Table 3-59. Deleted Per 2004 Update Table 3-60. Deleted Per 2004 Update Table 3-61. Deleted Per 2004 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3 3-67 (Page 3 of 3)

Table 3-62. Deleted Per 2004 Update Table 3-63. Deleted Per 2004 Update Table 3-64. Deleted Per 2004 Update Table 3-65. Deleted Per 2004 Update Table 3-66. Deleted Per 2004 Update Table 3-67. Deleted Per 2004 Update (31 DEC 2000)

Oconee Nuclear Station UFSAR Table 3-68 (Page 1 of 8)

Table3-68. Electrical Equipment Seismic Qualification Equipment Identification Seismic Qualification Documentation Reference

1. Reactor Protective System Cabinets/Components Deleted Per 2013 Update.

Reactor Protective System Engineered Safeguards Protective System Replacement Equipment Qualification Report AREVA NP 66-5065212 (OM 201.N-0021.001); TXS Supplemental Equipment Qualification Summary Test Report AREVA NP 66-5015893 (OM 201.N-0021.017); Seismic Anchorage Calculation OSC-8743; Seismic Qualification of ES and RPS Cabinets AREVA NP 51-9002920; Seismic and Isolation Qualification Test Report of Phoenix Contact Relays AREVA NP 38-9057729; Test Report for Seismic Qualification of Additional Hardware for use within Teleperm XS System Areva NP 58-5066097 Deleted Per 2013 Update.

2. Engineered Safeguards Protective Cabinets/Components Deleted Per 2013 Update.

Reactor Protective System and Engineered Safeguards Protective System Replacement Equipment Qualification Report AREVA NP 66-5065212 (OM 201.N-0021.001); TXS Supplemental Equipment Qualification Summary Test Report AREVA NP 66-5015893 (OM 201.N-0021.017); Seismic Anchorage Calculation OSC-8743; Seismic Qualification of ES and RPS Cabinets AREVA NP 51-9002920; Seismic and Isolation Qualification Test Report of Phoenix Contact Relays AREVA NP 38-9057729; Test Report for Seismic Qualification of Additional Hardware for use within Teleperm XS System Areva NP 58-5066097 Deleted Per 2013 Update.

(31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 2 of 8)

Equipment Identification Seismic Qualification Documentation Reference

3. Reactor Protective System Sensors Rosemount Report 2758&127516 &D8400102 also B & W 58-0261-00 Rosemount Report 1177117A, and B & W 58-0082-00
1. RC Pressure Transmitters (NR)

B & W 58-0081-00 and Rosemount Report D8400102 Herron

2. RC Temperature RTD's Lab Report F-7040, and B & W 58-0080-00 (OM 360-0010)
3. RC Flow Transmitters Duke/Exide Test Report PH58644 WEED Instrument Report
4. RB Pressure Switches D6-8680-003(OM-357.-0008-0001)
5. RCP Power Monitors Deleted Per 2013 Update.

Wyle Test Report No. 52511-1, Seismic Test Report; NTS Environmental and Seismic Testing of Ancillary Equipment for Oconee ES/RPS Replacement AREVA NP 38-9004984; Seismic Qualification Report Lampbox and Switches AREVA NP 38-9005550

4. Engineered Safeguards Protective System Sensors Rosemount Test Report D830040(OM-0267.A-0114)

&D8400102 (OM-0267-0969) ITT-Barton Test Report R3-764-

1. RC Pressure Transmitters (WR) 9 (OM-0267.A-0041) ASCO Test Report AQR-101083 (OM-
2. RB Pressure Transmitters 0267.A-0050)
3. RB Pressure Switches
5. 4160 VAC Station Auxiliary Switchgear (1TC, 1TD, 1TE; ITE Report No. R-8793, and Gould Report No. 33-53719-SS 2, 3) (OM 302-0617)
6. 600 VAC Load Centers (1X8, 1X9, 1X10; 2, 3) Gould Report No. 33-53729-SSA (OM 301-0079)
7. Motor Control Centers (1XS1, 1XS2, 1XS3; 2; 3) Oconee Nuclear Station, Units 1-2-3 Motor Control Centers, DC Distribution Centers, DC Panelboards, Original QA
1. A.O. Smith Type "CY" Starters Documentation Files
2. Joslyn Clark Type "TM" Starters Seismic Qualification of size 1-4 Joslyn Clark Motor Starters
a. Oconee (1XS1, 1XS2, 1XS3j2;3) DPC-1393.00-00-0041
b. Keowee (1XA, 1XS, 2XA, 2XS)
8. DC Distribution Centers (1DCA, 1DCB; 2; 3) Oconee Nuclear Station, Units 1-2-3 Motor Control Centers, DC Distribution Centers, DC Panelboards, Original QA Documentation Files (31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 3 of 8)

Equipment Identification Seismic Qualification Documentation Reference

9. AC Panelboards (1KVIA, 1KVIB, 1KVIC, 1KVID; 2; 3) Wyle Lab Report 42729-1 (OM-304.0002) 1SKJ, 1SKK, 1SKL; 2,3 Square-D Report No. 8998-10.09-L31 (OM-0137)
10. DC Panelboard (1DIA, 1DIB, 1DIC, 1DID; 2; 3) Wyle Lab Report 42729-1 (OM-304.0002)
11. Control Batteries/Racks (1CA, 1CB; 2; 3) C & D Technologies, Environment and Seismic Qualification Report of 125 Volt Vital Instrumentation and Control Batteries, Model LCU-27 and RD-903-28EP3 Two Step Battery Racks (OM-1320.-101-001)
12. Battery Chargers (1CA, 1CB, 1CS; 2; 3) Wyle Lab Report 43185-2 (OM 346-0105-1)
13. Inverters (1DIA, 1DIB, 1DIC, 1DID; 2; 3) Wyle Lab Report 43185-2 (OM 346-0105-1)
14. Isolating Diode Assemblies (1ADA, 1ADB, 1ADC, 1ADD; Exide Power Systems Div. "Seismic Test of Diode Monitors" 2; 3)
15. Oconee Main Control Boards Wyle Lab Report WR 73-1 (OM 1393-0008), OSC-1525 (1),

OSC-3942(1), OSC-2509(1)

16. Engineered Safeguards Terminal Cabinets Wyle Lab Report WR 73-1 (OM 1393-0008)
17. Emergency Power Switching Logic Cabinets Wyle Lab Report WR 73-1 (OM 1393-0008)
18. Oconee Unit Boards Wyle Lab Report WR 73-1 (OM 1393-0008), OSC-1525(1),

OSC-3942(1), OSC-2509(1)

19. Oconee Vertical Boards Wyle Lab Report WR 73-1 (OM 1393-0008), OSC-1525(1),

OSC-3942(1), OSC-2509(1)

20. Oconee Auxiliary Boards Wyle Lab Report WR 73-1 (OM 1393-0008), OSC-1525(1),

OSC-3942(1), OSC-2509(1)

21. Keowee Emergency Start Cabinets Wyle Lab Report WR 73-1 (OM 1393-0008)
22. Keowee Control Boards Wyle Lab Report WR 73-1 (OM 1393-0008), Loose Parts, NLI-Nuclear Logistics INC. QR-29412516-4 (KM 303. --0045.001)
23. Keowee Miscellaneous Terminal Cabinets Wyle Lab Report WR 73-1 (OM 1393-0008)

(31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 4 of 8)

Equipment Identification Seismic Qualification Documentation Reference

24. Keowee Main Turbine - Generators ONS Emergency Power Source Seismic Evaluation Technical Position Paper
25. Keowee - Oconee Underground Power Circuit ONS Emergency Power Source Seismic Evaluation Technical Position Paper
26. Keowee Logic Cabinets Wyle Lab Report WR 73-1 (OM 1393-0008)
27. Keowee 125 VDC Battery Chargers OM 320-0167
28. Keowee 125 VDC Battery/Racks Keowee Battery Environmental Qualification Report (KM 320-16)
29. Keowee 125 VDC Distribution Centers Oconee Nuclear Station, Units 1-2-3 Motor Control Centers, DC Distribution Centers, DC Panelboards, Original QA Documentation Files
30. 230 KV Swyd Battery Chargers OM 320-0167
31. 230 KV Swyd Control Batteries C & D Charter Power Systems Report Number QR-27189-01 (OM-320-163)
32. 230 KV Swyd Distribution Centers Oconee Nuclear Station, Units 1-2-3 Motor Control Centers, DC Distribution Centers, DC Panelboards, Original QA Documentation Files
33. 230 KV Swyd Panelboards Wyle Lab Report 42729-1, (OM 304.0002)
34. Oconee/Keowee Overhead Power Path Equipment
a. Keowee Main Stepup Transformer G. E. letter to R. S. Thompson, 09-06-76, and G. E. letter to J.

E. Stoner, 04-03-77 (K-301)

b. Oconee Startup Transformers G. E. letter to R. S. Thompson, 09-06-76, and G. E. letter to J.

E. Stoner, 04-03-77 (OS-83-B)

c. 230 KV Disconnect Switches ITE letter & Attachment to R. S. Thompson, 08-26-76, (OS C) and OSC-926
d. 230 KV Power Circuit Breakers MEPPI Breakers (OM 323.0335.001), OSC-7895 (31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 5 of 8)

Equipment Identification Seismic Qualification Documentation Reference

e. 230 KV Swyd. Coupling Capacitor G. E. letter & Attachments to J. C. Papaspyrou, 08-18-76, (OS-96-D), OSC-926, OM-330-0033-001, and OSC-7895
f. 230 KV Swyd. Lightning Arrestors G. E. letter & Attachments to J. C. Papaspyrou, 08-06-76, (OS-96-E), and OSC-926
h. 230 KV Swyd. DC Panelboards ITE letter & Attachments to J. E. Stoner, 08-16-76, (OS-89)
i. 230 KV Swyd. Control Batteries/Racks C & D letter to C. J. Wylie, 09-02-76 (OS-93)
k. 230 KV Swyd. Relay House Lighting System J. P. Bultman letter to J. E. Stoner, 09-23-76, (OS-89)

(Anchoring Only)

l. 230 KV Swyd. Relay Panels/Equipment Wyle Lab Report WR 76-17 (OM 393-0006)
35. AC Control Rod Drive Breaker Cabinet FANP Qualfication Test Report QR 02 Cutler Hammer DSII Series Low Voltage AC Trip Circuit Breakers and Switchgear- Rev 03, dated 12-19-03. (OM 2201.M-0377.001)
36. Standby Shutdown Facility
a. Control Console Wyle Lab Report 45676-1 (OM 1393-0013), OSC-279(1)
b. Miscellaneous Equipment and Interconnecting Wyle Lab Report 45676-1 (OM 1393-0013), OSC-279(1)

Cabinets

c. Diesel Generator Flight Dynamics Inc. Report No. A-11-80 (OM 351-0206)
d. 4160 VAC Switchgear Gould Report No. 33-53566-SS(OM-302-0615)
e. 600 VAC Motor Control Centers GTE Seismic Report (OM 308-0361-001, -002, and 003)
f. 208 VAC Motor Control Centers GTE Seismic Report (OM 308-0361-001, -002, and -003)
g. 120 VAC/125 VDC Panelboards GTE Seismic Report (OM 308-0361-001, 002, and 003)
h. 600 VAC Load Centers Gould Report No. 33-53729-SSA (OM301-80)
i. Inverters SCI Seismic Evaluation (OM 320-0214-001)

(31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 6 of 8)

Equipment Identification Seismic Qualification Documentation Reference

j. Battery Chargers OM-320-0202.001 (Environmental and Seismic Qualification Report 125 VDC/500 AMP SSF Chargers CSF & CSFS)
k. Voltage Regulators Wyle Lab Report 44741-1 (OM 352-0012)
l. Control Batteries/Racks OM-320-0202.002 (Environmental and Seismic Qualification Report, 125 Volt SSf Batteries DCSf & DCSf-S Model LCR-21 on Two-Step and Single-Row Battery Racks)
m. SSF Transmitters Rosemount Test Reports D8400102, Rev. B (OM-267-0969)

D8300040 (OM-267.A-0114)

37. TMI Action Item Additions
a. Reactor Building High Range Radiation Monitors Victoreen Report No. 950-301 (OM 360-35)
b. Anticipatory Reactor Trip Pressure Switches and RPS B & W Report No. BWNP-20210-1 (OM-304-0001, OM-2304-Logic Equipment 0001) or Static-O-Ring Report Nos. 9058-102 (OM-267A-0124) and 9058-104 (OM-267-1284)
c. Hydrogen Analyzer Control Panel (Duke Portion) Wyle Lab Report No. 45477-1 (OM 1393-0009)
d. Post-Accident Monitoring Recorders Wyle Lab Report WR-80-48, Rev. 1 (OM 1393-0012)
e. Post-Accident Monitoring Indicators Wyle Lab Report WR-80-48, Rev. 1 (OM 1393-0012)
f. Emergency Feedwater Initiation Pressures Switches Custom Component Switches, Inc. Report No. QTR 604-01 (CG 3008.02-01, CG 3008.02-06) or Static-O-Ring Report Nos. 9058-102 (OM-267A-0124) and 9058-104 (OM-267-1284)
g. Normal and Emergency Sump Level Transmitters FCI Test Report No. 708143 (OM 267-0762)
h. RB Pressure Transmitters RMT Report No. D8400102 Rev. B (OM-267-0969)
i. Post Accident Sampling Solenoid Valves (Air) Valcor Test Report QR-70900-65 (CNM-1210.04-0394) Valcor Test Report QR-52600-5940-2 (OM 360-34)
j. Post Accident Sampling Solenoid Valves (Liquid) Target Rock Report No. 2375 (OM 360-32)
k. High Point Vent System Solenoid Valves Target Rock Report No. 2375 (OM-360-32)

(31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 7 of 8)

Equipment Identification Seismic Qualification Documentation Reference

l. RVLIS (Reactor Vessel Level Cabinets Instrumentation Westinghouse Reports WCAP-8687 EQTR-E53A (OM-311.B-System) 24), EQDP-ESE-4 (OM-311.B-25), WCAP8687 EQTR-E04A (OM-311.B-26), WCAP8687 EQAR-E61B (OM-311.B-32),

WCAP8687 EQTR-E02A (OM-311.B-35) and E04A-ADD1 (OM-311.B-40).

m. OTSG Level Control System Cabinets Wyle Lab Report No. 44662-1 (OM 393-0001).
38. Reactor Coolant Pump Monitor Cabinet Rochester Instrument Systems SN 909335 (OM 393-0007)
39. OSW Upgrade
1. Electrical Equipment in the ESV Bldg.
a. 600/240/120 VAC, Single-phase 7.5 kVA Technical Document No CGD-3014.04-01-0002 Transformer (1, 2, and 3SKMT, 3SKNT)
b. 600/240/120 VAC, Single-phase 2 kVA Transformer Technical Document No CGD-3014.04-01-0002 (1, 2, 3SKPT)
c. 240/120 VAC, Single-phase panelboards (1, 2, Technical Document No CGD-3014.01-24-0002 and 3SKM, N, P)
d. ESV Local Control Panels (1, 2, 3ESVLCP) Calc 7330 - Seismic Qualification of Service Water Equipment using NARE Guidelines
2. Electrical Equipment in the Plant Control Complex.
a. ESV Relay Panel (1, 2 ESV1 and 3ESV1, 2, 3) Calc 7330 - Seismic Qualification of Service Water Equipment using NARE Guidelines
b. Joslyn/Clark, size #2 "TM" Starter (1 ea. in MCCs 1, Seismic Qualification Test of a Joslyn/Clark Motor Starter DPC 2, 3XS1, 2, 3) 1393.00-00-0032.
40. Motor Control Centers (1, 2 and 3XS4, 3XS5, 3XS6) Qualification of Cutler Hammer MCCs. (OM 308.-0443.001)
41. 600VAC Load Centers (1, 2 and 3X10) Qualification of ABB Load Centers (OM 303.-0167.001)
42. Automatic Feedwater Isolation System (AFIS) Qualification Report of Modified Star Components (OM-1311.D.0020)

(31 DEC 2019)

Oconee Nuclear Station UFSAR Table 3-68 (Page 8 of 8)

Equipment Identification Seismic Qualification Documentation Reference

43. Keowee 13.8 kV Switchgear (KPF1, KPF2) NLI-Nuclear Logistics Inc. QR-29412516-1 (KM 303. --

0037.001)

44. Keowee Relay Panelboard (EB20) NLI-Nuclear Logistics Inc. QR-29412516-3 (KM 303. --

0042.001)

45. Generator Bus Transition Junction Box (GEN1, GEN2) NLI-Nuclear Logistics Inc. QR-29412516-2 (KM 303. --

0039.001)

46. PSW 125 VDC Panelboard (1A, 2A) Kinectrics K-115099-FR-0001 (KM 303. --0049.002)

Note:

1. Where past and current documentation is shown within the table, these calculations and reports represent the current qualification documents for the equipment.

(31 DEC 2019)

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