ML20309A740

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2 to Updated Final Safety Analysis Report, Chapter 9, Appendix 9A, Tables - Redacted
ML20309A740
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Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/08/2020
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Duke Energy Carolinas
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Office of Nuclear Reactor Regulation
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RA-19-0424
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McGuire Nuclear Station UFSAR Appendix 9A. Tables Appendix 9A. Tables

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

Table 9-1. Spent Fuel Cooling System Component Design Data

1. Fuel Pool Cooling Pumps Number per unit 2 Type Centrifugal Design pressure, psig 155 Design temperature, °F 200 Material of construction Stainless Steel Shutoff head, ft 345 Design flow range, gpm 2310-2900
2. Fuel Pool Cooling Heat Exchanger Number per unit 2 Type Straight tube, 2 passes Heat transfer rate at normal conditions, Btu/hr 15 x 106 Estimated UA, Btu/hr F 1.25 x 106 Shell Side Data:

Design pressure, psig 150 Design temperature, °F 200 Pressure drop (Allow/calc), psi 12/9 Nozzle size inches 10 Material of construction Carbon Steel Fluid circulated Component cooling water Tube Side Data:

Design pressure, psig 150 Design temperature, °F 200 Pressure drop (Allow/calc), psi 12/7 Nozzle size inches 8 Material of construction Stainless Steel Fluid circulated Fuel pool water Design Parameters:

Shell Tube Flow, gpm 2500 2900 Inlet temperature, °F 95 125 Outlet temperature, °F 107 110 (27 MAR 2002)

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

3. Fuel Pool Cooling Pre-Filter Number per unit 1 Type Disposable cartridge Design pressure, psig 200 Design temperature, °F 215 Design flow, gpm (operating condition) 310 Pressure loss of design flow, psid 5 (Unfouled), 50(Fouled)

Material of construction 100 percent Stainless Steel

4. Fuel Pool Cooling Demineralizer Number per unit 1 Type Flushable Resin type Nuclear Grade mixed bed (Contact Chemistry)

Design pressure, internal, psig 200 Design temperature, vessel, °F 200 3

Resin volume, ft 15-40 Vessel volume, ft3 80 Bed depth, ft 1.0-2.5 Bed diameter, ft 4.5 Design flow, gpm 310 Resin bed and vessel pressure drop for 310 gpm flow, 40 cft 35 (fouled condition) psid Upper retention screen U.S., mesh 50 Material of construction Stainless Steel

5. Fuel Pool Cooling Post-Filter Number per unit 1 Type Disposable cartridge Design pressure, psig 200 Design temperature, °F 215 Design flow, gpm (operating condition) 310 Pressure loss at design flow, psid 5 (Unfouled), 50(Fouled)

Material of construction 100 percent Stainless Steel

6. Fuel Pool Skimmer Strainer Number per unit 1 (27 MAR 2002)

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

Type Basket Design temperature, °F 200 Design pressure, psig 20 Design flow, gpm 100 Pressure loss at design flow negligible Strainer perforations dia. 7/64" Material of construction Stainless Steel

7. Fuel Pool Skimmer Pump Number per unit 1 Type Centrifugal Design pressure, psig 45 Design temperature, °F 200 Material of construction Stainless Steel Design flow, gpm 100 Design head, ft 55
8. Fuel Pool Skimmer Filter Number per unit 1 Type Disposable cartridge Design pressure, psig 150 Design temperature, °F 215 Design flow, gpm 100 Pressure loss at design flow, psid 5 (Unfouled), 20(Fouled)

Material of construction 100 percent Stainless Steel (27 MAR 2002)

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

Table 9-2. Spent Fuel Cooling System Failure Analysis Component Failure Comments and Consequences

1. Fuel pool cooling Rupture of a pump The casing and shell are designed for 155 psig and pump casing 200°F which equals or exceeds the maximum operating conditions. Pump can be isolated. Only one of the two pumps is required under normal conditions. The pump is located in the Auxiliary Building and protected against credible accidents.

Rupture is considered unlikely.

2. Fuel pool cooling Pump stops running Under normal operating conditions only one pump pump and cannot be restarted is required and the backup pump is started. With maximum spent fuel stored in the fuel pool, the heat generated does not increase the fuel pool temperature beyond 200°F during the time required for maintenance or temporary arrangement to provide adequate cooling.

Assured pool makeup water is provided by the Nuclear Service Water System.

3. Fuel pool cooling Suction strainer plugs Under normal conditions, standby pump and pump suction line are brought into operation. Strainer service or replacement is accomplished within an adequate period of time.
4. Fuel pool cooling Tube or shell rupture Rupture is considered unlikely. Heat exchanger heat exchanger can be isolated for maintenance. Only one of the two heat exchangers is required under normal conditions.
5. Fuel pool skimmer Component failure Spent fuel continues to be cooled by fuel pool loop cooling pumps and heat exchangers. Optical clarity of pool water may be decreased. Adequate time is available for restoration before unacceptable clarity is reached. Pool water can be clarified by passing it through the fuel pool cooling filter and demineralizer.
6. Fuel pool cooling Component failure Loop can be isolated from fuel pool cooling loop.

purification loop Spent fuel continues to be cooled by the fuel pool cooling pumps and heat exchangers. Purity of pool water may be decreased until loop is restored. Adequate time is available for restoration before unacceptable impurity level is reached.

7. Fuel pool cooling Pipe rupture Fuel pool cannot be drained below level providing loop adequate shielding. Sufficient time is available for restoration of cooling. Assured pool makeup water is provided by the Nuclear Service Water System.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-3 and 9-4 (Page 1 of 1)

Table 9-3. Deleted Per 2008 Update Table 9-4. Deleted Per 2008 Update (13 APR 2008)

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

Table 9-5. Peak Heat Loads and Pool Temperatures for the McGuire Units 1 & 2 Spent Fuel Pools Operating Condition Pool Temperatures (F°)

Cooling Heat Load Trains Case Design Basis1 Calculated (106 BTU/HR) Operating Normal Heat Load 20.8 2 120 116 20.8 1 140 136 Maximum Heat Load 42.2 2 140 137 42.2 1 <212 180 Note:

1. Thermal Hydraulic Analysis assumes a more conservative maximum of 150°F when the cooling system is operational. Structural calculations use a 140°F maximum.

(14 OCT 2000)

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

Table 9-6. Time to Boiling Following Loss of Forced Cooling Under Design Basis Conditions for McGuire Units 1 & 2 Spent Fuel Pools Heat Load (106 BTU/HR) Initial Pool Temperature (°F) Heat Up Time (HRS) 20.8 120 11.9 20.8 140 9.4 42.2 140 4.6 (14 OCT 2000)

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

Table 9-7. Recirculated Cooling Water System-Component Design Parameters Recirculated Cooling Water Pumps Manufacturer Worthington Type Centrifugal Number 3 per station Design Flow Rate 2000 gpm Design Head 160 Feet Recirculated Cooling Water Heat Exchangers Manufacturer American Standard Type Shell and Tube Number 4 per station Flow, shell/tube 1333 gpm/1667 gpm Design Pressure, shell/tube 150 psig/50 psig Design Temperature, shell/tube 125°F/80°F Pressure drop, shell/tube 7.0 psi/2.0 psi Recirculated Cooling Water Storage Tank Manufacturer Midland Steel Corp.

Volume 15,000 gal.

Design Pressure 9.6 psig Design Temperature 110°F (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-8 (Page 1 of 3)

Table 9-8. Nuclear Service Water Flow Requirements (gpm per channel per Unit)

LOCA P 20 Hour Component or Service Normal LOCA S Signal Signal Cooldown

1. Component Cooling Surge Tank Assured Makeup 0 501 501 0
2. Nuclear Service Water Pump Motor Cooler 40 40 40 40
3. Nuclear Service Water (RN) Strainer Supply Flow 400.5 4005 4005 4005.
4. Nuclear Service Water (RN) Strainer Backwash 300 200 200 300 Discharge Flow
5. Diesel Generator Cooling (KD) Heat Exchanger 0 600 600 0 7 7 7
6. Component Cooling (KC) Pump Motor Cooler 40 40 40 408
7. Component Cooling (KC) Heat Exchanger 3800 3700 3700 45006
8. Control, Cable and Equipment Room A/C (YC) 6204 6403,4 6403,4 6204 Condenser
9. Fuel Pool (KF) Assured Makeup 0 861 861 0
10. E. S. Fan Coil Unit - Fuel Pool Cooling (KF) Pump/Motor 16 16 16 16
11. Containment Spray (NS) Heat Exchanger 0 0 3300 0
12. Centrifugal Charging (NV) Pump Bearing Oil Cooler 3 3 3 3
13. Centrifugal Charging (NV) Pump Speed Increaser Oil 7 7 7 7 Cooler
14. Centrifugal Charging (NV) Pump Motor Cooler 30 30 30 30
15. E. S. Fan Coil Unit - Containment Spray (NS) 0 0 26 0 Pump/Motor
16. E. S. Fan Coil Unit - Residual Heat Removal (ND) 0 26 26 26 Pump/Motor
17. Safety Injection (NI) Pump Motor Cooler 0 20 20 0
18. Safety Injection (NI) Pump Bearing Oil Cooler 0 15 15 0 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-8 (Page 2 of 3)

LOCA P 20 Hour Component or Service Normal LOCA S Signal Signal Cooldown

19. Auxiliary Feedwater (CA) Pump Motor Cooler 0 30 30 30 2 2
20. Auxiliary Feedwater (CA) Assured Supply 0 1350 560 0
21. Reciprocating Charging Pump Bearing Oil Cooler 0 0 0 0
22. Reciprocating Charging Pump Fluid Drive Oil Cooler 0 0 0 0
23. Reactor Coolant (NC) Pump Motor Air Coolers 800 800 0 800
24. Diesel Generator Cooling Water (KD) Surge Tank 0 301. 301. 0 Assured Makeup
25. Diesel Generator Starting Air Compressor After Coolers 25 25 25 25 Continuous Total Supply Required 5681 7542 9278 10977 Intermittent Total Supply Required 6081 8108 9844 11377 The following can be supplied by the RN System pump or RV System pumps, but always discharge into the NSW discharge lines, hence they are considered on Figure 9-31.
1. Lower Containment Ventilation Units 2000 0 0 2000
2. Upper Containment Ventilation Units 540 0 0 540
3. Auxiliary and Fuel Building Ventilation Units 600 0 0 600 Continuous Total Discharge 8821 7542 9278 14117 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-8 (Page 3 of 3)

LOCA P 20 Hour Component or Service Normal LOCA S Signal Signal Cooldown Notes:

1. Not normally used, so these numbers are not included in total.
2. 1350 gpm is a nominal value based on the nominal capacities of one Motor-Driven (450 gpm) Auxiliary Feedwater pump and the Turbine-Driven (900 gpm) Auxiliary Feedwater Pump, with the assumption that only one train of Nuclear Service Water is available to supply the pumps. 560 gpm is a nominal value based on the minimum flow for one Motor-Driven (200 gpm)

Auxiliary Feedwater pump and the Turbine-Driven (360 gpm) Auxiliary Feedwater Pump.

3. This flow is supplied by either of the two units, but not both.
4. Flow through condenser modulated by self regulating refrigerant operated control valve. This valve does not receive an Ss or Sp signal and is always throttled.
5. Intermittent nominal value based on strainer operation.
6. Total flow of 9000 gpm is made up of 4500 gpm per train with two trains required.
7. Total flow of 40 gpm is made up of two KC pumps running per unit.
8. Total flow of 80 gpm is made up of two KC pumps running per unit with two units in service, i.e., four pump operations.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-9 (Page 1 of 1)

Table 9-9. Main Supply and Discharge Valve Position for Nuclear Service Water System The following table lists valve positions as if both units were operating, and flow were required in both an A channel and a B channel. Only butterfly valves are listed, check valves can be assumed to be open in the direction of flow. The B channel of CCW supply has had all automatic isolation features removed. It is no longer an allowed configuration. See Figure 9-31.

All of the following valves are shared between units.

O = Open, C = Closed CCW Supply CCW Lo-Level Supply Pond Supply Pond Conditions Return CCW Return Return Valve Nos.

1RN1 O O O 0RN2 B O C C 0RN3 A O C C 0RN4 A,C O O O 0RN5 B C C C 0RN7 A C C O 0RN9 B C C O 0RN10 A,C C O C 0RN11 B C O C1 0RN12 A,C C O C 0RN13 A C O C1 0RN14 A Crossover C C C 0RN15 B Crossover C C C 0RN147 A,C O O C 0RN148 A,C O O C1 0RN149 A C C O 0RN150 A Crossover C C C 0RN151 B Crossover C C C 0RN152 B C C O 0RN283 A,C O O C 0RN284 B O O C 0RN301 A,C O O O 0RN302 B O O O Note: These valves provide redundant isolation. During normal operation these valves are open, however, during abnormal or emergency operation these valves are closed.

(09 OCT 2015)

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

Table 9-10. Nuclear Service Water System Component Design Data NUCLEAR SERVICE WATER PUMPS Quantity: Unit 1:2 Unit 2:2 Total: 4 Temperature: Maximum 102°F Operating 45°F - 70°F Minimum 40°F At NPSH 90°F available Capacity and Head Design: 17,500 gpm at 130 ft.

Maximum: 17,500 Minimum: Minimum flow = 2700 gpm continuous Shutoff Head: 230 ft.

Required NPSH 27 ft at 17,500 Maximum Pump Spd: 1185 RPM Type of Pump Horizontal Centrifugal Applicable Code: ASME Boiler and Pressure Vessel Code Section III, Class 3 NUCLEAR SERVICE WATER STRAINER Quantity: Unit 1:2 Unit 2:2 Total: 4 Type: Kinney AP-1 Continuous/Automatic Backflush Nozzle Size 30" Temperature: Maximum 125°F Operating 45°F - 70°F Minimum 40°F Flow: 17,500 gpm Perforations: 3/16" diameter NUCLEAR SERVICE WATER STRAINER BACKWASH PUMPS Quantity: Unit 1:2 Unit 2:2 Total: 4 Temperature: Maximum 102°F Operating 45°F - 70°F Capacity: Design: 200 gpm Head: Design: 64 ft (1A/2A), 60 ft (1B/2B)

Maximum Pump Spd: 1750 RPM Type of Pump Centrifugal (09 OCT 2015)

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

Applicable Code ASME Boiler and Pressure Vessel Code Section III, Class 3 (09 OCT 2015)

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

Table 9-11. Nuclear Service Water System Failure Analysis Component Malfunction Comment and Consequences

1. Lake Norman Loss of Dam a. During normal station operation: Isolate supply and return lines to Lake Norman and use Standby Nuclear Water Pond for station cooling.
b. During postulated LOCA: Channel B of the Nuclear Service Water System will already have been automatically aligned with supply and return to the SNSWP, and the redundant trains of equipment isolated from each other. Channel A will have been automatically aligned to low level intake, and would lose supply upon loss of lake. Channel A could then be manually aligned to have redundant train of supply and discharge lines and heat exchangers to back up the Channel B.
2. Operating Train Rupture or plug or a. If opposite train NSW supply line from NSW supply line to seismic event disabling CCW crossover is available, change over NSW pumps from CCW piping to opposite train NSW Pump and HX CCW crossover train operation, using opposite train CCW supply and return lines, or
b. Isolate channel A and B CCW supplies with corresponding HX trains and discharge to Lake Norman, or
c. Isolate supply and return to Lake Norman and use Standby Nuclear Service Water Pond for plant cooling.
3. Either Operating Any failure that would Start opposite train pump and supply opposite NSW pump curtail normal train heat exchangers until repairs are made.

operation of the pump including failure of motor cooler.

4. Any Operating Tube rupture or plug or a. Shut down the Operating NSW pump, use train safety related shell rupture redundant train NSW Pump and heat heat exchanger exchangers, or
b. If opposite train NSW pump unavailable, open crossovers and supply opposite train heat exchangers with operating pump.
5. Operating NSW Rupture or plug Use opposite train pump and heat exchangers until pump discharge repairs can be made.

header (30 NOV 2012)

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

Component Malfunction Comment and Consequences

6. Either Operating Plug (includes strainer Isolate strainer and associated Operating NSW NSW pump strainer drum and backwash) pump, use opposite train pump to satisfy unit cooling water requirements.
7. Any non-safety Any failure which will Isolate component and perform required related component curtail normal maintenance.

operation of the component

8. NSW return header Rupture or plug or Isolate and use Standby Nuclear Service Water to CCW crossover seismic event disabling Pond supply and return.

CCW piping (30 NOV 2012)

McGuire Nuclear Station UFSAR Table 9-12 (Page 1 of 2)

Table 9-12. Nuclear Service Water System Instrumentation and Control

1. Indicators
a. Temperature Local Control Room
1) Essential Header 1A and 1B X X
2) Safety Related Pump Motor High X Temperature Alarms
3) Standby Nuclear Service Water Pond X
b. Pressure
1) Essential Headers 1A and 1B X X
2) Pond Supply A X
3) Strainer Differential Pressure A and B X X
c. Level
1) Lake Norman X
2) Standby Nuclear Service Water Pond X
d. Status
1) Nuclear Service Water Pumps X
2) All Class 3 Motor Operated Valves X
3) NSW Strainer Backwash Pumps X
e. Radioactivity
1) Return from Containment Spray Heat X Exchanger
f. Flow
1) NSW Pump Discharge X
2) Component Cooling HX Outlet X X
3) Diesel Generator Cooling Water HX X Outlet
4) Containment Spray HX Outlet X
2. Regulators Pressure
a. Control, Cable and Equipment Rm A/C X Condenser head pressure self regulating control valves (YC condenser pressure)
3. Test Points a. Temperature
1) On outlets of each heater exchanger where practical for performance testing.
2) Non-essential header (30 NOV 2012)

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

b. Pressure
3) Non-essential header
4) Differential pressure across heat exchangers provided for testing purposes.

(30 NOV 2012)

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

Table 9-13. Chemistry Specifications Nuclear Service Water Range pH 5.5-8.5 Turbidity, JTU 3-80 Total Dissolved solids, ppm 30-70 Suspended solids, ppm 5-225 Total Hardness, ppm as CaCO3 12-22 Silica, ppm SiO2 4-12 Conductivity, micromhos30-100 Total iron, ppm Fe 0.03-5 Manganese, ppm Mn 0-1 Color, APHA 1-5 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-14 (Page 1 of 2)

Table 9-14. Worst 1, 4 and 30-Day Cooling Periods Dry Bulb Dew Point Wind Speed Solar Radiation Day (°F) (F) (mph) (Langleys/day)

Worst 1-Day Period 6/27/52 91 71 3.6 679 Worst 4-Day Period 6/24/52 85 71 2.9 636 6/25/52 89 70 2.9 611 6/26/52 89 72 3.0 659 6/27/52 91 71 3.6 679 Worst 30-Day Period 6/5/52 80 67 4.9 482 6/6//52 78 65 5.0 716 6/7/52 83 66 4.3 687 6/8/52 85 68 4.8 632 6/9/52 82 67 6.5 628 6/10/52 78 68 7.2 521 6/11/52 82 61 6.5 735 6/12/52 71 58 4.5 336 6/13/52 75 65 2.6 696 6/14/52 76 70 5.5 441 6/15/52 80 72 3.7 572 6/16/52 81 72 4.9 564 6/17/52 79 72 8.1 408 6/18/52 79 72 3.0 726 6/19/52 83 67 4.2 704 6/20/52 82 67 5.1 725 6/21/52 78 69 6.2 597 6/22/52 81 71 6.3 544 6/23/52 81 72 3.4 619 (09 OCT 2015)

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

Dry Bulb Dew Point Wind Speed Solar Radiation Day (°F) (F) (mph) (Langleys/day) 6/24/52 85 71 2.9 636 6/25/52 89 70 2.9 611 6/26/52 89 72 3.0 659 6/27/52 91 71 3.6 679 6/28/52 83 72 7.3 653 6/29/52 79 71 4.4 379 6/30/52 83 71 4.2 392 7/1/52 72 61 8.1 733 7/2/52 73 58 5.2 805 7/3/52 75 60 3.9 800 7/4/52 77 62 6.0 733 (09 OCT 2015)

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

Table 9-15. Worst 1,4 and 30-Day Evaporation Periods Dry Bulb Dew Point Wind Speed Solar Radiation Day (°F) (F) (mph) (Langleys/day)

Worst 1-Day Period 11/6/52 56 21 6.6 300 Worst 4-Day Period 3/3/68 43 18 11.2 492 3/4/68 42 8 9.3 450 3/5/68 45 13 6.5 439 3/6/68 49 24 9.6 297 Worst 30-Day Period 2/6/68 44 18 6.5 359 2/7/68 43 20 6.6 352 2/8/68 43 23 11.5 287 2/9/68 40 21 9.1 306 2/10/68 36 10 9.0 372 2/11/68 31 12 7.3 392 2/12/68 29 5 8.6 395 2/13/68 34 9 9.1 403 2/14/68 35 11 7.0 392 2/15/68 41 21 7.9 215 2/16/68 39 21 5.3 395 2/17/68 42 20 8.5 393 2/18/68 34 5 4.3 230 2/19/68 35 3 6.6 413 2/20/68 44 21 12.5 279 2/21/68 38 16 12.0 363 2/22/68 31 6 9.6 411 2/23/68 34 9 6.2 235 2/24/68 39 13 6.5 348 (09 OCT 2015)

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

Dry Bulb Dew Point Wind Speed Solar Radiation Day (°F) (F) (mph) (Langleys/day) 2/25/68 37 12 8.5 426 2/26/68 36 7 4.9 438 2/27/68 41 16 4.5 398 2/28/68 40 24 8.9 327 2/29//68 34 29 7.8 79 3/1/68 33 13 11.4 459 3/2/68 45 26 10.8 455 3/3/68 43 18 11.2 492 3/4/68 42 8 9.3 450 3/5/68 45 13 6.5 439 3/6/68 49 24 9.6 297 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-16 (Page 1 of 2)

Table 9-16. Heat Transfer Rates to Standby Nuclear Service Water Pond. From LOCA Unit Loads and Controlled Shutdown Unit Loads Along with Associated Station Auxiliary Loads Over Thirty Days. This represents a sample of data only. See Ref #15.

LOCA Unit Heat Hours After LOCA Load 106 BTU/Hr. Cont.Shut.Unit Heat Total Heat Loads and C.S. Event Note 1 Load 106 BTU/Hr. 106 BTU/Hr.

0 0 0 0 1 215 0 215 2 316 0 316 3 291 0 291 4 278 0 278 5 201 134 334 6 197 127 325 7 180 122 302 8 177 117 295 9 174 113 287 10 170 110 281 11 167 108 275 12 164 105 270 13 161 103 265 14 159 101 260 15 157 100 256 16 154 98 252 17 153 96 249 18 151 95 246 19 149 94 243 20 147 93 240 21 146 77 223 25 141 73 215 30 137 70 207 40 131 65 196 50 126 61 186 60 121 57 179 80 115 52 166 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-16 (Page 2 of 2)

LOCA Unit Heat Hours After LOCA Load 106 BTU/Hr. Cont.Shut.Unit Heat Total Heat Loads and C.S. Event Note 1 Load 106 BTU/Hr. 106 BTU/Hr.

100 110 47 157 168 99 39 138 175 99 38 137 180 98 38 136 185 98 37 135 200 97 36 133 300 92 32 124 400 89 29 118 500 87 27 114 600 86 25 111 700 84 24 108 720 84 24 108 Note 1: Auxiliary Loads are included from both units.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-17 (Page 1 of 5)

Table 9-17. Computer Program for McGuire Nuclear Station SNSWP Thermal Analysis (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-17 (Page 2 of 5)

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-17 (Page 3 of 5)

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-17 (Page 4 of 5)

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-17 (Page 5 of 5)

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-18 (Page 1 of 2)

Table 9-18. McGuire Nuclear Station SNSWP Thermal Analysis Computer Model Parameters Variable Value Description S1 46 Number of horizontal layers. Each layer is 1 ft. deep.

T1 720 Total number of hours of input and output for the computer model, i.e.

30 days as required by RG 1.27.

L1 20 Number of unit volumes. This number is arbitrary, and the selected number represents the point beyond which a further increase has no impact on results.

K2 20 Output check spacing, an internal counter used within the program.

E1 88 Equilibrium temperature, °F. The equilibrium temperature is calculated based on the worst 30-day meteorological period identified from the meteorological record.

K1 150 Exchange coefficient, BTU/ft²/°F/day. The exchange coefficient is calculated based on the worst 30-day meteorological period identified from the meteorological record.

I Variable The number of iterations.

J Variable An iteration counter used in multiple applications during the program.

S(I,1) Variable Stage volumes (acre-ft). This is based on the area/volume curve in UFSAR Figure 9-42. S(I,1) is converted to thousand cubic feet (TCF) for use in calculation.

S(I,2) Variable Stage temperatures (°F). The assigned temperatures correspond to an initial vertical temperature profile that envelopes the periodic profiles that have been measured during the life of the plant.

T(I,1) 88 Equilibrium temperature. The constant value E1 is required for each hour of the simulation, therefore T(I,1) = E1 for a total number of T1 matrix values.

T(I,2) 150 Exchange coefficient. The constant value K1 is required for each hour of simulation, therefore T(I,2) = K1/24s for a total number of T1 matrix values.

T(I,3) 56,000 Input flows (gallons per minute) used in the calculation of time that a unit volume remains at the pond surface, T2.

T(I,4) Variable Heat inputs (MBTU/Hr), as developed in calculations.

T(I,5) Variable, Delta-T (°F), the incremental increase in temperature applied to the calculated bottom layer as it is drawn into the plant for each hour of the simulation.

V1 Calculated Unit layer volume.

V2 Calculated V2 is the cumulative volume of all unit layers below the layer of interest (acre-ft).

S2 Calculated S2 is the cumulative volume calculated by stage rather than by unit (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-18 (Page 2 of 2)

Variable Value Description volume.

L(I,1) Calculated Vertical position of unit layers above the bottom of the pond (ft).

L(I,2) Calculated Temperature of unit volume (°F), equal to the temperature of the stage (S(I,2)) at the bottom of the unit volume.

H1 Calculated Depth of the unit volume at the pond surface (ft.).

T2 Calculated Time that a unit volume remains at the surface of the pond (hr).

T5 Calculated Total simulation time elapsed (hr).

T3 Calculated Discharge temperature (°F).

T9 Calculated Heat transfer to the environment (°F).

T4 Calculated Reduction in the discharge temperature T3 (°F) due to surface cooling T9.

A Calculated The average temperature calculated in the event that the temperature of one of the unit volumes below the pond surface exceeds the temperature of the surface layer after cooling (°F).

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 1 of 14)

Table 9-19. Sample Run of McGuire Nuclear Station SNSWP Thermal Analysis Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 1 2.424484 89.67088 .4223756 89.9165 12 89.9165 82 3 4.848967 92.38245 1.10782 91.27463 20 91.27463 82 6 7.273451 93.59552 1.414468 92.18105 20 92.18105 82 8 9.697934 92.52516 1.143897 91.78116 19 91.78116 82 11 12.12242 91.81159 .9635162 91.42126 17 91.42126 82 13 14.5469 91.4548 .8733251 91.2533 16 91.2533 82 16 16.97138 90.99098 .7560778 91.08357 15 91.08357 82.49 18 19.39587 91.26691 .8258295 90.99179 14 90.99179 83.71 20 21.82035 92.27284 1.080114 91.19273 20 91.19273 86.15 23 24.24484 93.92792 1.498493 92.42943 20 92.42943 87.37 25 26.66932 95.04089 1.779836 93.26105 20 93.26105 88.59 28 29.09381 96.08248 2.043137 94.03934 20 94.03934 89.9165 30 31.51829 97.30196 2.351402 94.95055 20 94.95055 89.9165 33 33.94277 97.19492 2.324346 94.91057 19 94.91057 89.9165 35 36.36726 97.08788 2.297287 94.87057 18 94.87057 89.9165 37 38.79174 97.01653 2.27925 94.83725 17 94.83725 89.9165 40 41.21622 96.90949 2.252193 94.80125 16 94.80125 89.9165 42 43.64071 96.83813 2.234155 94.76837 15 94.76837 89.9165 45 46.06519 96.7311 2.207098 94.73346 14 94.73346 89.9165 47 48.48968 96.65974 2.18906 94.70061 13 94.70061 89.9165 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 2 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 49 50.91416 96.58839 2.171022 94.66914 12 94.66914 90.99179 52 53.33865 97.59232 2.424801 95.16751 20 95.16751 90.99179 54 55.76313 97.52096 2.406763 95.14085 19 95.14085 90.99179 57 58.18761 97.4496 2.388725 95.1142 18 95.1142 90.99179 59 60.6121 97.37824 2.370687 95.08754 17 95.08754 90.99179 62 63.03658 97.30688 2.352648 95.06087 16 95.06087 90.99179 64 65.46107 97.27121 2.34363 95.03866 15 95.03866 90.99179 66 67.88555 97.19985 2.325592 95.01517 14 95.01517 91.19273 69 70.31004 97.32943 2.358347 95.00967 13 95.00967 92.42943 71 72.73452 98.53046 2.66195 95.86851 20 95.86851 93.26105 74 75.159 99.32639 2.863152 96.46324 20 96.46324 94.03934 76 77.58349 100.069 3.050876 97.01814 20 97.01814 94.66914 79 80.00797 100.6275 3.192041 97.43542 20 97.43542 94.66914 81 82.43246 100.5918 3.183022 97.42209 19 97.42209 94.66914 83 84.85694 100.5561 3.174004 97.40876 18 97.40876 94.66914 86 87.28143 100.4847 3.155965 97.38876 17 97.38876 94.66914 88 89.70591 100.4491 3.146947 97.37144 16 97.37144 94.66914 91 92.13039 100.4134 3.137927 97.35545 15 97.35545 94.66914 93 94.55488 100.3777 3.128909 97.34021 14 97.34021 94.66914 96 96.97936 100.342 3.119888 97.32545 13 97.32545 94.66914 98 99.40385 100.3064 3.11087 97.31102 12 97.31102 95.00967 100 101.8238 100.6112 3.18793 97.42326 20 97.42326 95.00967 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 3 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 103 104.2528 100.5755 3.178912 97.40993 19 97.40993 95.00967 105 106.6773 100.5398 3.169891 97.39661 18 97.39661 95.00967 108 109.1018 100.5042 3.160873 97.38328 17 97.38328 95.00967 110 111.5263 100.4685 3.151854 97.36995 16 97.36995 95.00967 113 113.9508 100.4328 3.142836 97.32927 6 97.32927 95.00967 115 116.3752 100.4328 3.142836 97.32681 5 97.32681 95.00967 117 118.7997 100.3971 3.133817 97.32307 4 97.32307 95.86851 120 121.2242 101.2203 3.3419 97.87839 20 97.87839 96.46324 122 123.6487 101.7793 3.483222 98.29612 20 98.29612 97.01814 125 126.0732 102.2986 3.614473 98.68409 20 98.68409 97.32307 127 128.4977 102.6035 3.691553 98.91193 20 98.91193 97.32307 129 130.9221 102.5678 3.682535 98.89861 19 98.89861 97.32307 132 133.3466 102.5321 3.673515 98.88528 18 98.88528 97.32307 134 135.7711 102.5321 3.673515 98.87861 17 98.87861 97.32307 137 138.1956 102.4965 3.664497 98.86928 16 98.86928 97.32307 139 140.6201 102.4965 3.664497 98.86305 15 98.86305 97.32307 142 143.0446 102.4608 3.655478 98.8548 14 98.8548 97.32307 144 145.469 102.4251 3.646459 98.84528 13 98.84528 97.32307 146 147.8935 102.4251 3.646459 98.83788 12 98.83788 97.32307 149 150.318 102.3894 3.637441 98.82929 11 98.82929 97.32307 151 152.7425 102.3894 3.637441 98.82227 10 98.82227 97.32307 154 155.167 102.3537 3.628421 98.81419 9 98.81419 97.32307 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 4 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 156 157.5915 102.3537 3.628421 98.80735 8 98.80735 97.32307 159 160.0159 102.3181 3.619403 98.79959 7 98.79959 97.32307 161 162.4404 102.2824 3.610382 98.78438 5 98.78438 97.32307 163 164.8649 102.2824 3.610382 98.77776 4 98.77776 97.32307 166 167.2894 102.2824 3.610382 98.77189 3 98.77189 97.87839 168 169.7139 102.802 3.741741 99.06029 20 99.06029 98.29612 171 172.1384 103.2198 3.847339 99.37242 20 99.37242 98.77189 173 174.5629 103.6598 3.958586 99.70126 20 99.70126 98.77189 176 176.9873 103.6598 3.958586 99.70126 19 99.70126 98.77189 178 179.4118 103.6242 3.949568 99.69238 18 99.69238 98.77189 180 181.8363 103.6242 3.949568 99.68793 17 99.68793 98.77189 183 184.2608 103.6242 3.949568 99.68526 16 99.68526 98.77189 185 186.6853 103.5885 3.940548 99.67904 15 99.67904 98.77189 188 189.1098 103.5885 3.940548 99.6746 14 99.6746 98.77189 190 191.5342 103.5885 3.940548 99.67127 13 99.67127 98.77189 193 193.9587 103.5528 3.93153 99.66572 12 99.66572 98.77189 195 196.3832 103.5528 3.93153 99.66127 11 99.66127 98.77189 197 198.8077 103.5528 3.93153 99.65763 10 99.65763 98.77189 200 201.2322 103.5171 3.922509 99.65238 9 99.65238 98.77189 202 203.6567 103.5171 3.922509 99.64793 8 99.64793 98.77189 205 206.0811 103.5171 3.922509 99.64411 7 99.64411 98.77189 207 208.5056 103.4815 3.913491 99.63905 6 99.63905 98.77189 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 5 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 210 210.9301 103.4815 3.913491 99.63461 5 99.63461 98.77189 212 213.3546 103.4815 3.913491 99.63071 4 99.63071 98.77189 214 215.7791 103.4815 3.913491 99.62723 3 99.62723 99.06029 217 218.2036 103.7342 3.977376 99.7568 20 99.7568 99.37242 219 220.6281 104.0463 4.056279 99.99003 20 99.99003 99.62723 222 223.0525 104.3011 4.12069 100.1804 20 100.1804 99.62723 224 225.477 104.2654 4.11167 100.1671 19 100.1671 99.62723 226 227.9015 104.2654 4.11167 100.1627 18 100.1627 99.62723 229 230.326 104.2654 4.11167 100.1604 17 100.1604 99.62723 231 232.7505 104.2654 4.11167 100.1591 16 100.1591 99.62723 234 235.175 104.2298 4.102653 100.1538 15 100.1538 99.62723 236 237.5994 104.2298 4.102653 100.15 14 100.15 99.62723 239 240.0239 104.2298 4.102653 100.1471 13 100.1471 99.62723 241 242.4484 104.2298 4.102653 100.1449 12 100.1449 99.62723 243 244.8729 104.2298 4.102653 100.1431 11 100.1431 99.62723 246 247.2974 104.1941 4.093633 100.1392 10 100.1392 99.62723 248 249.7219 104.1941 4.093633 100.136 9 100.136 99.62723 251 252.1463 104.1941 4.093633 100.1332 8 100.1332 99.62723 253 254.5708 104.1941 4.093633 100.1309 7 100.1309 99.62723 256 256.9953 104.1941 4.093633 100.1289 6 100.1289 99.62723 258 259.4198 104.1584 4.084615 100.1254 5 100.1254 99.62723 260 261.8442 104.1584 4.084615 100.1224 4 100.1224 99.62723 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 6 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 263 264.2687 104.1584 4.084615 100.1197 3 100.1197 99.7568 265 266.6932 104.288 4.117368 100.1706 20 100.1706 99.99003 268 269.1176 104.5212 4.176325 100.3449 20 100.3449 100.1197 270 271.5421 104.6152 4.200084 100.4151 20 100.4151 100.1197 273 273.9666 104.6152 4.200084 100.4151 19 100.4151 100.1197 275 276.3911 104.6152 4.200084 100.4151 18 100.4151 100.1197 277 278.8155 104.6152 4.200084 100.4151 17 100.4151 100.1197 280 281.24 104.6152 4.200084 100.4151 16 100.4151 100.1197 282 283.6645 104.6152 4.200084 100.4151 15 100.4151 100.1197 285 286.0889 104.5795 4.191066 100.4113 14 100.4113 100.1197 287 288.5134 104.5795 4.191066 100.4084 13 100.4084 100.1197 290 290.9379 104.5795 4.191066 100.4062 12 100.4062 100.1197 292 293.3623 104.5795 4.191066 100.4044 11 100.4044 100.1197 294 295.7868 104.5795 4.191066 100.403 10 100.403 100.1197 297 298.2113 104.5795 4.191066 100.4018 9 100.4018 100.1197 299 300.6357 104.5438 4.182045 100.3987 8 100.3987 100.1197 302 303.0602 104.5438 4.182045 100.3961 7 100.3961 100.1197 304 305.4847 104.5438 4.182045 100.3938 6 100.3938 100.1197 306 307.9091 104.5438 4.182045 100.3918 5 100.3918 100.1197 309 310.3336 104.5438 4.182045 100.39 4 100.39 100.1197 311 312.7581 104.5438 4.182045 100.3884 3 100.3884 100.1706 314 315.1826 104.5591 4.185895 100.3876 2 100.3876 100.3449 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 7 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 316 317.607 104.7333 4.22995 100.5034 20 100.5034 100.3876 319 320.0315 104.7761 4.240758 100.5353 20 100.5353 100.3876 321 322.456 104.7761 4.240758 100.5353 19 100.5353 100.3876 323 324.8804 104.7761 4.240758 100.5353 18 100.5353 100.3876 326 327.3049 104.7761 4.240758 100.5353 17 100.5353 100.3876 328 329.7294 104.7761 4.240758 100.5353 16 100.5353 100.3876 331 332.1538 104.7404 4.231738 100.5309 15 100.5353 100.3876 333 334.5783 104.7404 4.231738 100.5277 14 100.5277 100.3876 336 337.0028 104.7404 4.231738 100.5253 13 100.5253 100.3876 338 339.4272 104.7404 4.231738 100.5235 12 100.5235 100.3876 340 341.8517 104.7404 4.231738 100.522 11 100.522 100.3876 343 344.2762 104.7404 4.231738 100.5208 10 100.5208 100.3876 345 346.7007 104.7047 4.222719 100.5165 8 100.5165 100.3876 348 349.1251 104.7047 4.222719 100.514 7 100.514 100.3876 350 351.5496 104.7047 4.222719 100.5119 6 100.5119 100.3876 353 353.9741 104.7047 4.222719 100.51 5 100.51 100.3876 355 356.3985 104.7047 4.222719 100.5084 4 100.5084 100.3876 357 358.823 104.7047 4.222719 100.5069 3 100.5069 100.3876 360 361.2475 104.7047 4.222719 100.5056 2 100.5056 100.3876 362 363.6719 104.7047 4.222719 100.5045 1 100.5045 100.5045 365 366.0964 104.7859 4.24323 100.5426 20 100.5426 100.5045 367 368.5209 104.7859 4.24323 100.5426 19 100.5426 100.5045 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 8 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 370 370.9453 104.7859 4.24323 100.5426 18 100.5426 100.5045 372 373.3698 104.7859 4.24323 100.5426 17 100.5426 100.5045 374 375.7943 104.7859 4.24323 100.5426 16 100.5426 100.5045 377 378.2188 104.7859 4.24323 100.5426 15 100.5426 100.5045 379 380.6432 104.7859 4.24323 100.5426 14 100.5426 100.5045 382 383.0677 104.7502 4.234212 100.5393 13 100.5393 100.5045 384 385.4922 104.7502 4.234212 100.5367 12 100.5367 100.5045 386 387.9166 104.7502 4.234212 100.5347 11 100.5347 100.5045 389 390.3411 104.7502 4.234212 100.533 10 100.533 100.5045 391 392.7656 104.7502 4.234212 100.5315 9 100.5315 100.5045 394 395.19 104.7502 4.234212 100.5303 8 100.5303 100.5045 396 397.6145 104.7502 4.234212 100.5293 7 100.5293 100.5045 399 400.039 104.7502 4.234212 100.5284 6 100.5284 100.5045 401 402.4634 104.7145 4.225194 100.5217 1 100.5217 100.5217 403 404.8879 104.7317 4.229547 100.5207 1 100.5207 100.5207 406 407.3124 104.7308 4.229304 100.5198 1 100.5198 100.5198 408 409.7368 104.7298 4.229067 100.5188 1 100.5188 100.5188 411 412.1613 104.7289 4.228824 100.5179 1 100.5179 100.5179 413 414.5858 104.7279 4.228584 100.517 1 100.517 100.517 416 417.0103 104.727 4.228354 100.516 1 100.516 100.516 418 419.4347 104.7261 4.228124 100.5151 1 100.5151 100.5151 420 421.8592 104.7252 4.227896 100.5143 1 100.5143 100.5143 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 9 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 423 424.2837 104.6886 4.21865 100.512 1 100.512 100.512 425 426.7081 104.6864 4.218087 100.5098 1 100.5098 100.5098 428 429.1326 104.6842 4.217538 100.5077 1 100.5077 100.5077 430 431.5571 104.6821 4.21699 100.5055 1 100.5055 100.5055 433 433.9815 104.6799 4.216448 100.5034 1 100.5034 100.5034 435 436.406 104.6778 4.215914 100.5013 1 100.5013 100.5013 437 438.8305 104.6757 4.215384 100.4993 1 100.4993 100.4993 440 441.2549 104.6737 4.214872 100.4973 1 100.4973 100.4973 442 443.6794 104.6716 4.214355 100.4953 1 100.4953 100.4953 445 446.1039 104.634 4.204836 100.492 1 100.492 100.492 447 448.5284 104.6307 4.204004 100.4887 1 100.4887 100.4887 450 450.9528 104.6274 4.203177 100.4855 1 100.4855 100.4855 452 453.3773 104.6242 4.202365 100.4823 1 100.4823 100.4823 454 455.8018 104.621 4.201565 100.4792 1 100.4792 100.4792 457 458.2262 104.6179 4.20077 100.4761 1 100.4761 100.4761 459 460.6507 104.6148 4.199982 100.473 1 100.473 100.473 462 463.0752 104.6117 4.199206 100.47 1 100.47 100.47 464 465.4996 104.6087 4.198442 100.467 1 100.467 100.467 466 467.9241 104.6057 4.197686 100.464 1 100.464 100.464 469 470.3486 104.567 4.187914 100.4598 1 100.4598 100.4598 471 472.773 104.5628 4.186842 100.4556 1 100.4556 100.4556 474 475.1975 1040.5586 4.18578 100.4514 1 100.4514 100.4514 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 10 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 476 477.622 104.5545 4.184735 100.4474 1 100.4474 100.4474 479 480.0464 104.5504 4.183706 100.4433 1 100.4433 100.4433 481 482.4709 104.5464 4.182688 100.4394 1 100.4394 100.4394 483 484.8954 104.5424 4.181686 100.4355 1 100.4355 100.4355 486 487.3199 104.5385 4.180697 100.4316 1 100.4316 100.4316 488 489.7443 104.5346 4.179717 100.4277 1 100.4277 100.4277 491 492.1688 104.5308 4.178741 100.4239 1 100.4239 100.4239 493 494.5933 104.527 4.177781 100.4202 1 100.4202 100.4202 496 497.0177 104.4875 4.167816 100.4152 1 100.4152 100.4152 498 499.4422 104.4825 4.166551 100.4102 1 100.4102 100.4102 500 501.8667 104.4776 4.165298 100.4053 1 100.4053 100.4053 503 504.2911 104.4727 4.164056 100.4005 1 100.4005 100.4005 505 506.7156 104.4678 4.162827 100.3957 1 100.3957 100.3957 508 509.1401 104.463 4.161617 100.391 1 100.391 100.391 510 511.5645 104.4583 4.160426 100.3863 1 100.3863 100.3863 513 513.989 104.4536 4.159245 100.3817 1 100.3817 100.3817 515 516.4135 104.4491 4.158089 100.3772 1 100.3772 100.3772 517 518.838 104.4445 4.156946 100.3727 1 100.3727 100.3727 520 521.2625 104.4401 4.155814 100.3683 1 100.3683 100.3683 522 523.687 104.4357 4.154699 100.3639 1 100.3639 100.3639 525 526.1115 104.3956 4.144576 100.3583 1 100.3583 100.3583 527 528.536 104.39 4.143147 100.3527 1 100.3527 100.3537 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 11 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 530 530.9605 104.3844 4.141738 100.3472 1 100.3472 100.3472 532 533.385 104.3789 4.140353 100.3418 1 100.3418 100.3418 534 535.8095 104.3735 4.138982 100.3364 1 100.3364 100.3364 537 538.234 104.3681 4.137626 100.3311 1 100.3311 100.3311 539 540.6585 104.3628 4.136288 100.3259 1 100.3259 100.3259 542 543.083 104.3576 4.134962 100.3208 1 100.3208 100.3208 544 545.5075 104.3524 4.13366 100.3157 1 100.3157 100.3157 547 547.932 104.3473 4.13237 100.3106 1 100.3106 100.3106 549 550.3565 104.3423 4.131102 100.3057 1 100.3057 100.3057 551 552.781 104.3373 4.129849 100.3008 1 100.3008 100.3008 554 555.2055 104.2968 4.11959 100.2946 1 100.2946 100.2946 556 557.63 104.2906 4.118026 100.2885 1 100.2885 100.2885 559 560.0545 104.2845 4.116488 100.2825 1 100.2825 100.2825 561 562.479 104.2785 4.114966 100.2765 1 100.2765 100.2765 563 564.9035 104.2725 4.113459 100.2706 1 100.2706 100.2706 566 567.328 104.2666 4.11197 100.2648 1 100.2648 100.2648 568 569.7525 104.2608 4.11051 100.2591 1 100.2591 100.2591 571 572.177 104.2551 4.109063 100.2535 1 100.2535 100.2535 573 574.6015 104.2495 4.10763 100.2479 1 100.2479 100.2479 576 577.026 104.2439 4.106218 100.2423 1 100.2423 100.2423 578 579.4505 104.2383 4.10482 100.2369 1 100.2369 100.2369 580 581.875 104.2329 4.103441 100.2315 1 100.2315 100.2315 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 12 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 583 584.2995 104.2275 4.102077 100.2262 1 100.2262 100.2262 585 586.724 104.1865 4.091716 100.2196 1 100.2196 100.2196 588 589.1485 104.1799 4.090053 100.2131 1 100.2131 100.2131 590 591.573 104.1734 4.088409 100.2067 1 100.2067 100.2067 593 593.9975 104.167 4.086794 100.2004 1 100.2004 100.2004 595 596.422 104.1607 4.085196 100.1941 1 100.1941 100.1941 597 598.8465 104.1545 4.083617 100.188 1 100.188 100.188 600 601.271 104.1483 4.082055 100.1819 1 100.1819 100.1819 602 603.6955 104.1422 4.08052 100.1759 1 100.1759 100.1759 605 606.12 104.1362 4.079 100.17 1 100.17 100.17 607 608.5445 104.1303 4.077503 100.1641 1 100.1641 100.1641 610 610.969 104.1244 4.076026 100.1583 1 100.1583 100.1583 612 613.3935 104.1187 4.074568 100.1527 1 100.1527 100.1527 614 615.818 104.113 4.07313 100.147 1 100.147 100.147 617 618.2425 104.0716 4.06268 100.1401 1 100.1401 100.1401 619 620.667 104.0647 4.060933 100.1333 1 100.1333 100.1333 622 623.0915 104.0579 4.059211 100.1265 1 100.1265 100.1265 624 625.516 104.0512 4.057506 100.1199 1 100.1199 100.1199 627 627.9405 104.0445 4.055822 100.1133 1 100.1133 100.1133 629 630.365 104.038 4.05417 100.1069 1 100.1069 100.1069 631 632.7895 104.0315 4.052534 100.1005 1 100.1005 100.1005 634 635.214 104.0251 4.050916 100.0941 1 100.0941 100.0941 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 13 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 636 637.6385 104.0188 4.049317 100.0879 1 100.0879 100.0879 639 640.063 104.0125 4.047743 100.0817 1 100.0817 100.0817 641 642.4875 104.0064 4.046185 100.0757 1 100.0757 100.0757 643 644.912 104.0003 4.04465 100.0697 1 100.0697 100.0697 646 647.3365 103.9586 4.034116 100.0624 1 100.0624 100.0624 648 649.761 103.9514 4.032284 100.0553 1 100.0553 100.0553 651 652.1855 103.9442 4.030471 100.0482 1 100.0482 100.0482 653 654.61 103.9371 4.028681 100.0412 1 100.0412 100.0412 656 657.0345 103.9302 4.026917 100.0343 1 100.0343 100.0343 658 659.459 103.9233 4.025173 100.0275 1 100.0275 100.0275 660 661.8835 103.9165 4.023457 100.0208 1 100.0208 100.0208 663 664.308 103.9097 4.021751 100.0141 1 100.0141 100.0141 665 666.7325 103.9031 4.020074 100.0076 1 100.0076 100.0076 668 669.157 103.8965 4.018421 100.0011 1 100.0011 100.0011 670 671.5815 103.8901 4.016786 99.99472 1 99.99472 99.99472 673 674.006 103.8837 4.015169 99.9884 1 99.9884 99.9884 675 676.4305 103.8774 4.013571 99.98216 1 99.98216 99.98216 677 678.855 103.8354 4.002975 99.97467 1 99.97467 99.97467 680 681.2795 103.8279 4.001081 99.96728 1 99.96728 99.96728 682 683.704 103.8206 3.999212 99.96 1 99.96 99.96 685 686.1285 103.8133 3.997372 99.9528 1 99.9528 99.9528 687 688.553 103.8061 3.995553 99.94569 1 99.94569 99.94569 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-19 (Page 14 of 14)

Time Real Plant T-Lost Surface Mixed Mixed Plant Increment Time Discharge TO-Atmos Temp Depth Temp Intake 690 690.9775 103.799 3.993756 99.93866 1 99.93866 99.93866 692 693.402 103.7919 3.991978 99.93172 1 99.93172 99.93172 694 695.8265 103.785 3.990225 99.9249 1 99.9249 99.9249 697 698.251 103.7782 3.988499 99.91815 1 99.91815 99.91815 699 700.6755 103.7714 3.986794 99.91149 1 99.91149 99.91149 702 703.1 103.7648 3.98511 99.9049 1 99.9049 99.9049 704 705.5245 103.7582 3.983443 99.89841 1 99.89841 99.89841 707 707.949 103.7517 3.981804 99.89197 1 99.89197 99.89197 709 710.3735 103.7452 3.980175 99.88562 1 99.88562 99.88562 711 712.798 103.7389 3.97857 99.87934 1 99.87934 99.87934 714 715.2225 103.7326 3.976983 99.87314 1 99.87314 99.87314 716 717.647 103.7264 3.975415 99.86704 1 99.86704 99.86704 719 720.0715 103.7203 3.973874 99.86102 1 99.86102 99.86102 (09 OCT 2015)

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

Table 9-20. Conventional Low Pressure Service Water System COMPONENT DESIGN PARAMETERS CONVENTIONAL SERVICE WATER PUMPS Manufacturer Ingersoll-Rand Type Centrifugal Number 3 per station Design Flow Rate 4500 gpm Design Head 56 ft.

MAIN TURBINE LUBE OIL COOLERS Manufacturer Westinghouse Type Shell and Tube Number 2 per unit Flow, Tube Side 3400 gpm Design Pressure, Tube Side 125 psig Design Pressure, Shell Side 50 psig Shell Material Steel Tube Material Admiralty Brass Design Inlet Temp., Tube Side 95°F Tube Side Pressure Drop 12 psi CONVENTIONAL SERVICE WATER STRAINER Manufacturer Zurn Type and Size Duplex with 1/4" openings Number 1 Design Flow 9000 gpm Design Pressure 125 psi Estimated Pressure Drop, Clean 1.35 psi Estimated Pressure Drop, 35% Clogged 2.4 psi Estimated Pressure Drop, 65% Clogged 2.95 psi (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-21 (Page 1 of 2)

Table 9-21. Component Cooling System Component Design Data Component Cooling Pumps Number per Unit 4 Type Centrifugal Design Pressure, psig 150 Design Temperature, °F 160 Design Flow, gpm 3500 Design Head, feet 179 Max. Flow Rate, gpm 4300 Head at Max. Flow, feet 130 Shutoff Head, feet 260 Min. Flow Rate, gpm 200 NPSH Required at Max. Flow, feet1 28 Material of Construction Carbon Steel Component Cooling Heat Exchangers Number per Unit 2 Design Pressure, psig 150 Design Temperature, °F 200 Estimated UA, Btu/Hr/°F 3.84 x 106 (Note 2)

Design Flow (Shell Side), gpm 6704 Design Flow (Tube Side), gpm 10000 Shell Side Inlet Temp., °F 155 (Note 2)

Shell Side Outlet Temp., °F 110 (Note 2)

Tube Side Inlet Temp., °F 78 (Note 2)

Tube Side Outlet Temp., °F 108 (Note 2)

Max. Pressure Loss, psi 15 Shell Side Fouling Factor .0005 Tube Side Fouling Factor .002 Shell Side Material Carbon Steel Tube Side Material Inhibited Admiralty (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-21 (Page 2 of 2)

Component Cooling Surge Tank Number per Unit 1 Total Volume, Gal. 7100 Normal Water Volume, Gal. 5852 Maximum Water Volume, Gal. 6600 Normal Pressure, psig 0 Design Pressure, psig 15 Design Temperature, °F 200 Material of Construction 304 Stainless Steel Component Cooling Drain Tank Number 1 Total Volume, Gal. 205 Design Pressure, psig 40 Design Temperature, °F 180 Material of Construction 304 Stainless Steel Component Cooling Drain Tank Pump Number 1 Design Flow, gpm 20 Design Head, feet 95 Shutoff Head, feet 100 NPSH Required at Design Flow, feet 6 Notes:

1. NPSH required at pump floor level
2. Values expected during normal operation (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-22 (Page 1 of 9)

Table 9-22. Component Cooling System Nominal Heat Loads and Flows Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Operating Condition - Unit Startup ND HX's 1 37.4 37.4 5000 5000 1 ND Pumps 1 .075 .075 5 10 3 Letdown HX 1 16.0 16.0 1000 1000 Sealwater HX 1 1.6 1.6 250 250 KF HX's 1 8.7 8.7 2500 2500 4 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond. 1 7.93 7.93 600 600 WL Dist. Cooler 1 .75 .75 150 150 WL Vent Cond. 1 .225 .225 30 30 WL Seal Hx. 1 .03 .03 10 10 WG Compressors 2 .135 .27 50 100 WG Hyd. Recombiners 2 .15 .30 27 54 RCDT HX - - - 225 225 2 Excess Ltdn. HX 1 5.2 5.2 250 250 RCP Thermal Barriers 4 .246 .984 40 160 RCP Motor Lower Brg. 4 .031 .124 5 20 RCP Motor Upper Brg. 4 .923 3.692 160 640 TOTAL 93.715 11887 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 2 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Notes:

1. Discontinued after RCP's started. The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation, operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.
2. Receives cooling flow though not in service.
3. Both pumps receive cooling although only one is in service.
4. Only one KF HX assumed in service. However, KC flow capacity is available to place both HX's in service if necessary.

Operating Condition - Normal Unit Operation ND HX's ND Pumps - - - 5 5 1 Letdown HX 1 16.0 16.0 1000 1000 Sealwater HX 1 1.6 1.6 250 250 KF HX's 1 8.5 8.5 2500 2500 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond. 1 7.93 7.93 600 600 WL Dist. Cooler 1 .75 .75 150 150 WL Vent Cond. 1 .225 .225 30 30 WL Seal Hx. 1 .03 .03 10 10 WG Compressors 2 .135 .27 50 100 WG Hyd. Recombiners 2 .15 .30 27 54 RCDT HX 1 1.0 1.0 225 225 Excess Ltdn. HX RCP Thermal Barriers 4 .246 .984 40 160 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 3 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

RCP Motor Lower Brg. 4 .031 .124 5 20 RCP Motor Upper Brg. 4 .923 3.692 160 640 TOTAL 51.84 6632 1 KC Heat Exchanger(s) in service.

2 KC Pump(s) in service.

Note:

1. One pump receives flow although neither is in service.

Operating Condition - Fast Unit Shutdown At 4 Hours ND HX's 2 118.59 237.18 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX's 3 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 3 NB Dist. Cooler 3 NB Vent Cond. 3 NB Seal Hx. 3 WL Evap. Cond. 3 WL Dist. Cooler 3 WL Vent Cond. 3 WL Seal Hx. 3 WG Compressors 2 .14 .28 50 100 WG Hyd. Recombiners 2 .15 .30 27 54 RDCT HX 1 1.6 1.6 225 225 Excess Ltdn. HX 3 RCP Thermal Barriers 1 .246 .246 40 160 2 RCP Motor Lower Brg. 1 .031 .031 5 20 2 RCP Motor Upper Brg. 1 .923 .923 160 640 2 TOTAL 244.16 11857 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 4 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s) 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Heat load determined as follows:

Core decay heat load 116.38 x 106 BTU/HR Reactor Coolant System sensible 100.5 x 106 BTU/HR heatload (2.01 x 106 BTU/HR/°F at 50°F/HRcooldown rate) 1 RCP heat input 20.3 x 106 BTU/HR Total 237.18 x 106 BTU/HR The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

2. All pumps receive cooling flow although only one pump in service.
3. Equipment normally valved out of service to maximize cooldown rate.

Operating Condition - Fast Unit Shutdown At 20 Hours ND HX's 2 36.65 73.3 5000 10000 3 ND Pumps 2 .075 .15 5 10 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX 's 2 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 2 NB Dist. Cooler 2 NB Vent Cond. 2 NB Seal Hx. 2 WL Evap. Cond. 2 WL Dist. Cooler 2 WL Vent Cond. 2 WL Seal Hx. 2 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 5 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

WG Compressors - - - 50 100 1 WG Hyd. Recombiners - - - 27 54 1 RCDT HX 1 1.6 1.6 225 225 Excess Ltdn. HX 2 RCP Thermal Barriers - - - 40 160 1 RCP Motor Lower Brg. - - - 5 20 1 RCP Motor Upper Brg. - - - 160 640 1 TOTAL 78.5 11857 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Note:

1. Receive cooling flow although not in service.
2. Equipment normally valved out of service to minimize cooldown rate.
3. The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

Operating Condition - Unit Shutdown At 4 Hours (LOCA on Other Unit)

ND HX's 1 136.68 136.68 5000 5000 2 ND Pumps 1 .075 .075 5 5 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX 's 1 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 NB Dist. Cooler 1 NB Vent Cond. 1 NB Seal Hx. 1 WL Evap. Cond. 1 WL Dist. Cooler 1 WL Vent Cond. 1 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 6 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

WL Seal Hx. 1 WG Compressors 1 WG Hyd. Recombiners 1 RCDT HX 1 Excess Ltdn. HX 1 RCP Thermal Barriers 1 .246 .246 40 160 3 RCP Motor Lower Brg. 1 .031 .031 5 20 3 RCP Motor Upper Brg. 1 .923 .923 160 640 3 TOTAL 141.405 6473 1 KC Heat Exchanger(s) in service.

2 KC Pump(s) in service.

Note:

1. Equipment valved out of service to reduce heat load and flow requirements.
2. Heat load requirement is removal of core decay heat plus heat input of one RCP as follows:

Core decay heat load 116.38 x 106 BTU/HR 1 RCP heat input 20.3 x 106 BTU/HR Total 136.68 x 106 BTU/HR Unit cooldown will be accomplished slowly as decay heat load decreases.

The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

3. All pumps receive cooling flow although only one pump is in service.

Operating Condition - Refueling ND HX's 2 20.95 41.9 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX - - - 300 300 2 Sealwater HX - - - 250 250 2 KF HX 's 1 - - 2500 2500 3 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 7 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors - - - 50 100 2 WG Hyd. Recombiners - - - 27 54 2 RCDT HX - - - 225 225 2 Excess Ltdn. HX RCP Thermal Barriers - - - 40 160 2 RCP Motor Lower Brg. - - - 5 20 2 RCP Motor Upper Brg. - - - 160 640 2 TOTAL 52.49 15147 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Heat load is core decay heat at 4 days after zero power, at which time transfer of fuel assemblies to the fuel pool is estimated to begin.

The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

2. Equipment receives cooling flow although not in service. Cooling flow may be blocked to reduce system flow requirements.
3. One KF HX placed in service for normal 3/8 core removal. If two KF HX's are required for 1 3/8 core removal cooling flow should be blocked to equipment not in service (see 2.).

Operating Condition - Engineered Safety Features (Safety Injection)

ND HX's 2 - - 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 8 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Sealwater HX KF HX 's Sample HX's NB Evap. Cond.

NB Dist. Cooler NB Vent Cond.

NB Seal Hx.

WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors WG Hyd. Recombiners RCDT HX Excess Ltdn. HX RCP Thermal Barriers 2 RCP Motor Lower Brg. 2 RCP Motor Upper Brg. 2 TOTAL .15 10010 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Flow supplied although no cooling is required by the ND HX's during the safety injection mode of operation.
2. These components continue to receive cooling flow until containment high- high pressure signal is received at which time flow is blocked automatically.

Operating Condition - Engineered Safety Features (Recirculation)

ND HX's 2 70. 140 5000 10000 1,2 ND Pumps 2 .075 .15 5 10 Letdown HX Sealwater HX (13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 9 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

KF HX 's Sample HX's NB Evap. Cond.

NB Dist. Cooler NB Vent Cond.

NB Seal Hx.

WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors WG Hyd. Recombiners RCDT HX Excess Ltdn. HX RCP Thermal Barriers RCP Motor Lower Brg.

RCP Motor Upper Brg.

TOTAL 140.15 10010 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Two ND HX's shown in service although only one is required operative under accident conditions.
2. Heat load is approximate initial value. Load is dependent on KC supply temperature and sump water temperature and decreases with time as decay heat generation decreases.

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 9-22 (Page 1 of 9)

Table 9-22. Component Cooling System Nominal Heat Loads and Flows Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Operating Condition - Unit Startup ND HX's 1 37.4 37.4 5000 5000 1 ND Pumps 1 .075 .075 5 10 3 Letdown HX 1 16.0 16.0 1000 1000 Sealwater HX 1 1.6 1.6 250 250 KF HX's 1 8.7 8.7 2500 2500 4 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond. 1 7.93 7.93 600 600 WL Dist. Cooler 1 .75 .75 150 150 WL Vent Cond. 1 .225 .225 30 30 WL Seal Hx. 1 .03 .03 10 10 WG Compressors 2 .135 .27 30 60 WG Hyd. Recombiners 2 .15 .30 10 20 RCDT HX - - - 225 225 2 Excess Ltdn. HX 1 5.2 5.2 250 250 RCP Thermal Barriers 4 .246 .984 40 160 RCP Motor Lower Brg. 4 .031 .124 5 20 RCP Motor Upper Brg. 4 .923 3.692 160 640 TOTAL 93.715 11813 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 2 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Notes:

1. Discontinued after RCP's started. The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation, operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.
2. Receives cooling flow though not in service.
3. Both pumps receive cooling although only one is in service.
4. Only one KF HX assumed in service. However, KC flow capacity is available to place both HX's in service if necessary.

Operating Condition - Normal Unit Operation ND HX's ND Pumps - - - 5 5 1 Letdown HX 1 16.0 16.0 1000 1000 Sealwater HX 1 1.6 1.6 250 250 KF HX's 1 8.5 8.5 2500 2500 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond. 1 7.93 7.93 600 600 WL Dist. Cooler 1 .75 .75 150 150 WL Vent Cond. 1 .225 .225 30 30 WL Seal Hx. 1 .03 .03 10 10 WG Compressors 2 .135 .27 30 60 WG Hyd. Recombiners 2 .15 .30 10 20 RCDT HX 1 1.0 1.0 225 225 Excess Ltdn. HX RCP Thermal Barriers 4 .246 .984 40 160 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 3 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

RCP Motor Lower Brg. 4 .031 .124 5 20 RCP Motor Upper Brg. 4 .923 3.692 160 640 TOTAL 51.84 6558 1 KC Heat Exchanger(s) in service.

2 KC Pump(s) in service.

Note:

1. One pump receives flow although neither is in service.

Operating Condition - Fast Unit Shutdown At 4 Hours ND HX's 2 118.59 237.18 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX's 3 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 3 NB Dist. Cooler 3 NB Vent Cond. 3 NB Seal Hx. 3 WL Evap. Cond. 3 WL Dist. Cooler 3 WL Vent Cond. 3 WL Seal Hx. 3 WG Compressors 2 .14 .28 30 60 WG Hyd. Recombiners 2 .15 .30 10 20 RDCT HX 1 1.6 1.6 225 225 Excess Ltdn. HX 3 RCP Thermal Barriers 1 .246 .246 40 160 2 RCP Motor Lower Brg. 1 .031 .031 5 20 2 RCP Motor Upper Brg. 1 .923 .923 160 640 2 TOTAL 244.16 11783 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 4 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s) 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Heat load determined as follows:

Core decay heat load 116.38 x 106 BTU/HR Reactor Coolant System sensible 100.5 x 106 BTU/HR heatload (2.01 x 106 BTU/HR/°F at 50°F/HRcooldown rate) 1 RCP heat input 20.3 x 106 BTU/HR Total 237.18 x 106 BTU/HR The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

2. All pumps receive cooling flow although only one pump in service.
3. Equipment normally valved out of service to maximize cooldown rate.

Operating Condition - Fast Unit Shutdown At 20 Hours ND HX's 2 36.65 73.3 5000 10000 3 ND Pumps 2 .075 .15 5 10 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX 's 2 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 2 NB Dist. Cooler 2 NB Vent Cond. 2 NB Seal Hx. 2 WL Evap. Cond. 2 WL Dist. Cooler 2 WL Vent Cond. 2 WL Seal Hx. 2 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 5 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

WG Compressors - - - 30 60 1 WG Hyd. Recombiners - - - 10 20 1 RCDT HX 1 1.6 1.6 225 225 Excess Ltdn. HX 2 RCP Thermal Barriers - - - 40 160 1 RCP Motor Lower Brg. - - - 5 20 1 RCP Motor Upper Brg. - - - 160 640 1 TOTAL 78.5 11783 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Note:

1. Receive cooling flow although not in service.
2. Equipment normally valved out of service to minimize cooldown rate.
3. The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

Operating Condition - Unit Shutdown At 4 Hours (LOCA on Other Unit)

ND HX's 1 136.68 136.68 5000 5000 2 ND Pumps 1 .075 .075 5 5 Letdown HX 1 1.2 1.2 300 300 Sealwater HX 1 .75 .75 250 250 KF HX 's 1 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 NB Dist. Cooler 1 NB Vent Cond. 1 NB Seal Hx. 1 WL Evap. Cond. 1 WL Dist. Cooler 1 WL Vent Cond. 1 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 6 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

WL Seal Hx. 1 WG Compressors 1 WG Hyd. Recombiners 1 RCDT HX 1 Excess Ltdn. HX 1 RCP Thermal Barriers 1 .246 .246 40 160 3 RCP Motor Lower Brg. 1 .031 .031 5 20 3 RCP Motor Upper Brg. 1 .923 .923 160 640 3 TOTAL 141.405 6473 1 KC Heat Exchanger(s) in service.

2 KC Pump(s) in service.

Note:

1. Equipment valved out of service to reduce heat load and flow requirements.
2. Heat load requirement is removal of core decay heat plus heat input of one RCP as follows:

Core decay heat load 116.38 x 106 BTU/HR 1 RCP heat input 20.3 x 106 BTU/HR Total 136.68 x 106 BTU/HR Unit cooldown will be accomplished slowly as decay heat load decreases.

The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

3. All pumps receive cooling flow although only one pump is in service.

Operating Condition - Refueling ND HX's 2 20.95 41.9 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX - - - 300 300 2 Sealwater HX - - - 250 250 2 KF HX 's 1 - - 2500 2500 3 Sample HX's 7 .212 1.5 14 98 NB Evap. Cond. 1 7.93 7.93 600 600 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 7 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

NB Dist. Cooler 1 .75 .75 150 150 NB Vent Cond. 1 .225 .225 30 30 NB Seal Hx. 1 .03 .03 10 10 WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors - - - 30 60 2 WG Hyd. Recombiners - - - 10 20 2 RCDT HX - - - 225 225 2 Excess Ltdn. HX RCP Thermal Barriers - - - 40 160 2 RCP Motor Lower Brg. - - - 5 20 2 RCP Motor Upper Brg. - - - 160 640 2 TOTAL 52.49 15703 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Heat load is core decay heat at 4 days after zero power, at which time transfer of fuel assemblies to the fuel pool is estimated to begin.

The design basis cooling water flow rate for the ND Heat Exchangers is 5000 GPM. This flow rate is required for Operating Condition-Engineered Safety Features (Safety Injection) and Operating Condition-Engineered Safety Features (Recirculation) with all non-essential headers isolated. For other modes of operation operator action can be assumed to adjust the travel stops on control valves 1/2 KC 57 and 1/2 KC 82 to get a flow rate of 5000 GPM.

2. Equipment receives cooling flow although not in service. Cooling flow may be blocked to reduce system flow requirements.
3. One KF HX placed in service for normal 3/8 core removal. If two KF HX's are required for 1 3/8 core removal cooling flow should be blocked to equipment not in service (see 2.).

Operating Condition - Engineered Safety Features (Safety Injection)

ND HX's 2 - - 5000 10000 1 ND Pumps 2 .075 .15 5 10 Letdown HX (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 8 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

Sealwater HX KF HX 's Sample HX's NB Evap. Cond.

NB Dist. Cooler NB Vent Cond.

NB Seal Hx.

WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors WG Hyd. Recombiners RCDT HX Excess Ltdn. HX RCP Thermal Barriers 2 RCP Motor Lower Brg. 2 RCP Motor Upper Brg. 2 TOTAL .15 10010 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Flow supplied although no cooling is required by the ND HX's during the safety injection mode of operation.
2. These components continue to receive cooling flow until containment high- high pressure signal is received at which time flow is blocked automatically.

Operating Condition - Engineered Safety Features (Recirculation)

ND HX's 2 70. 140 5000 10000 1,2 ND Pumps 2 .075 .15 5 10 Letdown HX Sealwater HX (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-22 (Page 9 of 9)

Heat Total Req'd Load Heat Flow Total No. In Each (106 Load (106 Each Flow Component Service BTU/HR) BTU/HR) (GPM) (GPM) Note(s)

KF HX 's Sample HX's NB Evap. Cond.

NB Dist. Cooler NB Vent Cond.

NB Seal Hx.

WL Evap. Cond.

WL Dist. Cooler WL Vent Cond.

WL Seal Hx.

WG Compressors WG Hyd. Recombiners RCDT HX Excess Ltdn. HX RCP Thermal Barriers RCP Motor Lower Brg.

RCP Motor Upper Brg.

TOTAL 140.15 10010 2 KC Heat Exchanger(s) in service.

4 KC Pump(s) in service.

Notes:

1. Two ND HX's shown in service although only one is required operative under accident conditions.
2. Heat load is approximate initial value. Load is dependent on KC supply temperature and sump water temperature and decreases with time as decay heat generation decreases.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-23 (Page 1 of 2)

Table 9-23. Component Cooling System Valve Alignment for Various Modes of Operations Unit Shutdown At 4 hrs Normal Fast Unit Fast Unit (LOCA on ESF Valve Unit Unit Shutdown Shutdown Other Safety ESF Recircu-Number1 Startup Operation At 4 hrs At 20 hrs Unit) Refueling Injection lation Figure 1KC1A O O O O O O X X 9-57 1KC3A O O O O O O X2 X2 9-57 1KC50A O O O O O O X X 9-57 2 2 1KC230A O O O O O O X X 9-57 1KC56A O X O O O O O O 9-57 1KC320A O O O O O O X X 9-57 1KC332B O O O O O O X X 9-57 1KC333A O O O O O O X X 9-57 1KC305B O X X X X X X X 9-57 1KC315B O X X X X X X X 9-57 1KC338B O O O O O O X2 X2 9-57 1KC424B O O O O O O X2 X2 9-57 2 2 1KC425A O O O O O O X X 9-57 1KC429B O O O O O O X X 9-57 1KC430A O O O O O O X X 9-57 1KC464 O O O O O O X X 9-57 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 9-23 (Page 2 of 2)

Unit Shutdown At 4 hrs Normal Fast Unit Fast Unit (LOCA on ESF Valve Unit Unit Shutdown Shutdown Other Safety ESF Recircu-Number1 Startup Operation At 4 hrs At 20 hrs Unit) Refueling Injection lation Figure Note:

Nomenclature: O - open X - closed

1. Valves listed in this table are isolation valves which are regularly manipulated to align the system for its various modes of operation. All other isolation valves remain in the position indicated on the flow diagram except for changes required for maintenance, or emergency situations.
2. Valves close on Phase B Containment Isolation Signal.

(24 APR 2014)

McGuire Nuclear Station UFSAR Table 9-24 (Page 1 of 1)

Table 9-24. Component Cooling System Malfunction Analysis Component Malfunction Comments and Consequences

1. Component cooling Rupture of pump casing Isolate pump and start redundant pump.

water pump

2. Component cooling Pump fails to start Isolate pump and start redundant pump.

water pump

3. Component cooling Manual valve on a This is prevented by prestartup and operational water pump pump suction line checks. Further, during normal operation each closed pump is checked on a periodic basis which should show that a valve was closed.
4. Component cooling Stop valve on discharge Valves are checked open by prestartup and water pump line closed or check operational checks.

valve sticks closed

5. Component cooling Loss of normal electric Switch to emergency diesel power.

water pump power

6. Component cooling Tube or shell rupture Isolate leaking heat exchanger and valve in spare heat exchanger heat exchanger.
7. Component cooling Left Open This is prevented by prestartup and operational heat exchanger vent checks.

or drain valve

8. Valves and piping Rupture Isolate equipment supplied and start redundant equipment or isolate entire header and start equipment on redundant header.
9. Component Failure of baffle plate Channel separation would be lost, but single Cooling Surge failure dictates no other malfunction anywhere Tank else in this system.
10. Component Failure of one outside Isolate channel affected and start up redundant Cooling Surge wall channel.

Tank (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-25 (Page 1 of 2)

Table 9-25. Refueling Water System Component Design Data Refueling Water Storage Tank Number per unit 1 Internal Volume, gallons 395,000 Usable Volume, gallons 350,000 Design pressure, internal ATM Design temperature, °F 120 Material of Construction Lined Carbon Steel Type Vertical, field constructed Refueling Water Pumps Number per unit 1 Type Centrifugal Design pressure, psig 200 Design temperature, °F 200 Material of Construction Stainless Steel Design flow, gpm Condition 1: 310 Condition 2: 195 Design head, ft Condition 1: 220 Condition 2: 300 Refueling Water Pump Strainer Number per unit 1 Type Basket Design pressure, psig 50 Design temperature, °F 150 Design flow, gpm 310 Pressure loss at design flow Negligible Strainer openings, inches 1/16 Refueling Water Recirculation Pumps Number per unit 2 Type Centrifugal Design pressure, psig 50 Design temperature, °F 150 Material of construction Stainless Steel (06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-25 (Page 2 of 2)

Design flow, gpm 100 Design head, ft 35 Refueling Water Pipe Trench Sump Pumps Number Per Unit 2 Type Centrifugal Design temperature, °F 130 Design flow, gpm 20 Design head, ft 23 (06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-26 (Page 1 of 1)

Table 9-26. Normal Sampling of Secondary Side for Radioactivity Location Method of Sampling Frequency Method of Analysis Unit 1 Turbine Room Sump grab sample 1/Week Gross Gamma Unit 2 Turbine Room Sump grab sample 1/Week Gross Gamma (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-27 (Page 1 of 1)

Table 9-27. Deleted Per 1992 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-28 (Page 1 of 3)

Table 9-28. Compressed Gas Vessel Design Parameters Vessel Parameter

1. Oxygen Number (For welding) 16/Station Design Pressure 3775 psig Operating Pressure 2300-2500 psig Total energy released if vessel should rupture 1232 Btu Location (Note 1, 2 and 3) Maintenance shop and yard
2. Nitrogen:

Number 9/Station Design Pressure 2450 psig Operating Pressure 2300 psig Total energy released if vessel should rupture 58,000 Btu Location (Note 1, 2 and 3) Yard

3. Hydrogen:

Number 9/Station Design Pressure 2450 psig Operating Pressure 2300 psig Total energy released if vessel should rupture 57,500 Btu Location (Note 1, 2 and 3) Yard

4. Chlorine:

Number 0/Station Design Pressure 525 psig Operating Pressure 120-170 psig Total energy released if vessel should rupture 1800 Btu Location (Note 1, 2 and 3) Yard

5. Carbon Dioxide:

Number 16/Station Design Pressure 3000 psig Operating Pressure 700-1000 psig Total energy released if vessel should rupture 1435 Btu Location (Note 1, 2 and 3) Turbine Building

6. Instrument Air Receivers:

(24 APR 2014)

McGuire Nuclear Station UFSAR Table 9-28 (Page 2 of 3)

Vessel Parameter Number 3/Station Design Pressure 115 psig Operating Pressure 100 psig Total energy released if vessel should rupture 8650 Btu Location (Note 1, 2 and 3) Service Building

7. Diesel Generator Starting Air:

Number 2/Diesel Design Pressure 250 psig Operating Pressure 230 psig Total energy released if vessel should rupture 6550 Btu Location (Note 1, 2 and 4) Diesel Building

8. Acetylene:

Number 8/Station Design Pressure 3775 psig Operating Pressure 2300-2500 psig Total energy released if vessel should rupture 2750 Btu Location (Note 1, 2 and 3) Maintenance Shop

9. Instrument Compressed Air Tanks Number 4/Station Design Pressure 115 psig Operating Pressure 100 psig Total energy released if vessel should rupture 2440 Btu Location Note 1, 2 and 3) Auxiliary Building
10. Oxygen:

Number (Bulk Storage) 4/Station Design Pressure 2450 psig Operating pressure 2300 psig Total energy released if vessel should rupture 58,200 Btu Location (Note 1, 2 and 3) Yard

11. Station Air Receivers Number 2/Station Design Pressure 125 psig (24 APR 2014)

McGuire Nuclear Station UFSAR Table 9-28 (Page 3 of 3)

Vessel Parameter Operating Pressure 100 psig Total energy released if vessel should rupture 8650 Btu Location (Note 1, 2 and 3) Service Building

12. High Pressure Station Air Receivers Number 2/Station Design Pressure 200 psig Operating Pressure 100-140 psig Total energy released if vessel should rupture 710 Btu Location (Note 1, 2 and 3) Service Building
13. High Pressure Breathing Air Receiver Number 1/Station Design Pressure 125 psig Operating Pressure 115 psig Total energy released if vessel should rupture 890 BTU Location (Note 1, 2 and 3) Service Building
14. Reactor Coolant Drain Tank Hydrogen Storage Cylinder Number 4/Station Design Pressure 3775 psig Operating Pressure 2265 psig Total energy released if vessel should rupture 1540 Btu Location (Note 1, 2 and 3) Yard Notes:
1. ASME codes apply; therefore, designed against rupture.
2. OSHA 29CFR 1910 applies.
3. Tanks separated from essential equipment.
4. The diesels are separated from each other by missile barriers.

(24 APR 2014)

McGuire Nuclear Station UFSAR Table 9-29 (Page 1 of 5)

Table 9-29. Compressed Air Design Parameters Instrument Air, Centrifugal Air Compressors D, E, F Number per Station 3 Design Pressure, PSIG 115 Design Flow, ICFM (Nominal) 1550 Normal Operating Pressure, PSIG 100 Instrument Air, Reciprocating Air Compressors A, B, C Number per Station 3 Design Pressure, PSIG 115 Design Temperature, °F 350 Design Flow, SCFM 650 Normal Operating Pressure, PSIG 100 Instrument Air, Diesel Powered Air Compressors Number Per Station 2 Design Pressure, PSIG 100 Design Flow, SCFM (Outlet) 1200 Normal Operating Pressure, PSIG 100 Instrument Air Centrifugal Compressor Inlet Filter, D Number per Station 1 Design Flow, CFM 1550 (min)

Filter Retention, Microns (primary/secondary) 10 @ 99.97% efficiency/ 2 98% efficiency Instrument Air Centrifugal Compressor Inlet Filter, E & F Number per Station 2 Design Flow, CFM 1550 (min)

Filter Retention, Microns 4 @ 98% efficiency Instrument Air Reciprocating Compressor Inlet Filter, A, B, C Number per Station 3 Design Flow, SCFM 1,320 Filter Retention, Microns 10 Instrument Air, Reciprocating Air Compressor Aftercoolers (22 APR 2017)

McGuire Nuclear Station UFSAR Table 9-29 (Page 2 of 5)

Number, Both Units 2 Design Flow, SCFM 1,800 Design Pressure, PSIG 115 Design Temperature, °F 105 Normal Operating Pressure, PSIG 100 Maximum Operating Temperature, °F 95 Terminal Difference, °F 15 Instrument Air, Air Receivers Number per Station 3 Storage Capacity, ft3 312 Design Pressure, PSIG 115 Normal Operating Pressure, PSIG 100 Instrument Air, Air Dryers A, B, C Number per Station 1 Dew Point, °F -40 Design Flow, SCFM 200 Design Pressure, PSIG 115 Design Temperature, °F 105 Instrument Air, Pre-Filters A, B, C Number per Station 3 Design Flow, SCFM 1800 Design Pressure Drop, PSID 10 Filter Retention, Microns 1 Particulate/0.3 Coalescing Instrument Air, After Filters A, B, C Number per Station 3 Design Flow, SCFM 1800 Design Pressure Drop, PSID 10 Filter Retention, Microns 0.9 Instrument Air, Pre-Filter E Number per Station 1 Design Flow, SCFM 300 Design Pressure Drop, PSID 0.15 (22 APR 2017)

McGuire Nuclear Station UFSAR Table 9-29 (Page 3 of 5)

Filter Retention, Microns 1.0 Instrument Air, After Filters E Number per Station 1 Design Flow, SCFM 350 Design Pressure Drop, PSID 1.2 Filter Retention, Microns 5 Instrument Air, Dryer Bypass Filter Number per Station 1 Design Flow, SCFM 2400 Design Pressure Drop, PSID 10 Filter Retention, Micron 1.0 Instrument Compressed Air Tanks Number per Station 4 3

Storage Capacity, ft 96 Design Pressure, PSIG 115 Normal Operating Pressure, PSIG 100 Station Air, Oil Remover Filter Number per Station 2 Design Flow, SCFM 900 Design Pressure, PSIG 200 Filter Retention (solid/oil) Microns 0.6 micron 99.95% eff./ 0.1 micron 99.75% eff.

Station Air, Air Receivers Number per Station 2 3

Storage Capacity, ft 312 Design Pressure, PSIG 125 Normal Operating Pressure, PSIG 100 Station Air, High Pressure Air Compressors Number per Station 2 Design Flow, SCFM 26 Design Pressure, PSIG 200 Station Air, High Pressure Air Filters Number 2 Design Flow, SCFM 26 (22 APR 2017)

McGuire Nuclear Station UFSAR Table 9-29 (Page 4 of 5)

Filter Retention, Microns 10 Station Air, High Pressure Air Receivers Number per Station 2 Storage Capacity, gal Tank 'A' 80 Tank 'B' 120 Design Pressure, PSIG 200 Normal Operating Pressure, PSIG 140 Breathing Air, Air Compressors Number per Station 2 Design Pressure, PSIG 125 Design Flow, SCFM 450 Normal Operating Pressure, PSIG 115 Breathing Air, Purifiers Number per Station 2 Design Outlet Flow, SCFM @ 125 psig inlet pressure 464 Design Pressure, PSIG 150 Breathing Air, Air Receiver Number per Station 1 Storage Capacity, Ft3 32 Design Pressure, PSIG 125 Normal Operating Pressure, PSIG 115 Station Air, Air Compressors Number per Station 1 Design Pressure, PSIG 115 Design Temperature, °F 350 Design Flow, SCFM 750 Normal Operating Pressure, PSIG 100 Station Air, Air Filters Number per Station 1 Design Flow, SCFM 750 Filter Retention, Microns 10 Station Air, Air Compressor Aftercoolers (22 APR 2017)

McGuire Nuclear Station UFSAR Table 9-29 (Page 5 of 5)

Number per Station 1 Design Flow, SCFM 750 Design Pressure, PSIG 115 Design Temperature, °F 105 Normal Operating Pressure, PSIG 100 Maximum Temperature °F 95 Terminal Difference, °F 15 (22 APR 2017)

McGuire Nuclear Station UFSAR Table 9-30 (Page 1 of 4)

Table 9-30. Valves Aligned to Blackout Air Supply Blackout Air Header Number Location Alignment Valve Name 1CA36AB AB B Aux FDWP No 1 Disch to Stm Gen 1D Control 1CA40B AB B Aux FDWP 1B Disch to Stm Gen 1D Control 1CA44B AB B Aux FDWP 1B Disch to Stm Gen 1C Control 1CA48AB AB A Aux FDWP No 1 Disch to Stm Gen 1C Control 1CA52AB AB A Aux FDWP No 1 Disch to Stm Gen 1B Control 1CA56A AB A Aux FDWP 1A Disch to Stm Gen 1B Control 1CA60A AB A Aux FDWP 1A Disch to Stm Gen 1A Control 1CA64AB AB A Aux FDWP No 1 Disch to Stm Gen 1A Control 1CA162B AB B U1 CA Pump FLEX Suct Auto Supply Isol 1NC32B RB B Pressurizer No 1 Power Operated Safety Relief 1NC34A RB A Pressurizer No 1 Power Operated Safety Relief 1NC36B RB B Pressurizer No 1 Power Operated Safety Relief 1NV1A RB A NC Letdown Isol to Regenerative HX No 1 1NV2A RB A NC Letdown Isol to Regenerative HX No 1 1NV13B RB B NV Supply to NC Loop 1 Isolation 1NV16A RB B NV Supply to NC Loop 4 Isolation 1NV21A RB A NV Aux Spray Supply to Pressurizer Isolation INV24B RB B 1C NC Loop to Excess LD HX Isol 1NV25B RB B NC Loop 3 Supply to Excess letdown HX No 1 Isolation 1NV26B RB B Excess Letdown HX No 1 Tube Outlet Control 1NV35A RB A Letdown Orifice 1A Outlet Containment Isolation 1NV124 AB A Low Pressure Letdown Control 1NV137A AB A NC Filters Outlet Three Way Control (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-30 (Page 2 of 4)

Blackout Air Header Number Location Alignment Valve Name 1NV238 AB A Centrifugal Charging Pumps Disch Control 1NV241 AB B Regenerative HX No 1 Tube Inlet Control 1NV267A AB A Boric Acid to Boric Acid Blender Control 1NV457A RB A Letdown Orifice 1C Outlet Containment Isolation 1NV458A RB A Letdown Orifice 1B Outlet Containment Isolation 1NV459 RB A Letdown Orifice 1A Outlet Deleted Per 2011 Update 1SM1AB DH A Main Steam 1D Isolation 1SM3ABC DH B Main Steam 1C Isolation 1SM5AB DH B Main Steam 1B Isolation 1SM7AB DH A Main Steam 1A Isolation 1SV1AB DH A Main Steam 1D Power Operated Relief 1SV7ABC DH B Main Steam 1C Power Operated Relief 1SV13AB DH B Main Steam 1B Power Operated Relief 1SV19AB DH A Main Steam 1A Power Operated Relief Deleted Per 2011 Update 1RV79A AB A Upper Cont Vent Unit Supply Cont Isolation 1RV80B RB B Upper Cont Vent Unit Supply Cont Isolation 1RV101A RB A Upper Cont Vent Unit Discharge Cont Isolation 1RV102B AB B Upper Cont Vent Unit Discharge Cont Isolation 1RF821A AB A U1 Cont Fire Protection Supply Cont Isolation 2CA36AB AB B Aux FDWP No 2 Disch to Stm Gen 2D Control 2CA40B AB B Aux FDWP 2B Disch to Stm Gen 2D Control 2CA44B AB B Aux FDWP 2B Disch to Stm Gen 2C Control 2CA48AB AB A Aux FDWP No 2 Disch to Stm Gen 2C Control 2CA52AB AB A Aux FDWP No 2 Disch to Stm Gen 2B Control (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-30 (Page 3 of 4)

Blackout Air Header Number Location Alignment Valve Name 2CA56A AB A Aux FDWP 2A Disch to Stm Gen 2B Control 2CA60A AB A Aux FDWP 2A Disch to Stm Gen 2A Control 2CA64AB AB A Aux FDWP No 2 Disch to Stm Gen 2A Control 2CA162B AB A U2 CA Pump FLEX Suct Auto Supply Isol 2NC32B RB B Pressurizer No 2 Power Operated Safety Relief 2NC34A RB A Pressurizer No 2 Power Operated Safety Relief 2NC36B RB B Pressurizser No 2 Power Operated Safety Relief 2NV1A RB A NC Letdown Isol to Regenerative HX No 2 2NV2A RB A NC Letdown Isol to Regenerative HX No 2 2NV13B RB B Unit 2 NV Supply to 2A NC Loop Isolation 2NV16A RB A Unit 2 NV Supply to 2D NC Loop Isolation 2NV21A RB A NV Aux Spray Supply to Pressurizer Isolation 2NV24B RB B 2C NC Loop to Excess LD HX Isol 2NV25B RB B 2C NC Loop to Excess LD HX Isol 2NV26B RB B Excess Letdown HX No 2 Tube Outlet Control 2NV35A RB A Letdown Orifice 2A Outlet Containment Isolation 2NV124 AB A Low Pressure Letdown Control 2NV137A AB A NC Filters Outlet Three Way Control 2NV238 AB A Centrifugal Charging Pumps Disch Control 2NV241 AB B Regenerative HX No 2 Tube Inlet Control 2NV267A AB A Boric Acid to Boric Acid Blender Control 2NV457A RB A Letdown Orifice 2C Outlet Containment Isolation 2NV458A RB A Letdown Orifice 2B Outlet Containment Isolation 2NV459 RB A Letdown Orifice 2A Outlet 2SM1AB DH A Main Steam 2D Isolation 2SM3ABC DH B Main Steam 2C Isolation (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-30 (Page 4 of 4)

Blackout Air Header Number Location Alignment Valve Name 2SM5AB DH B Main Steam 2B Isolation 2SM7AB DH A Main Steam 2A Isolation 2SV1AB DH A Main Steam 2D Power Operated Relief 2SV7ABC DH B Main Steam 2C Power Operated Relief 2SV13AB DH B Main Steam 2B Power Operated Relief 2SV19AB DH A Main Steam 2A Power Operated Relief 2RV79A AB A Upper Cont Vent Unit Supply Cont Isolation 2RV80B RB B Upper Cont Vent Unit Supply Cont Isolation 2RV101A RB A Upper Cont Vent Unit Discharge Cont Isolation 2RV102B AB B Upper Cont Vent Unit Discharge Cont Isolation 1RF832A AB A U2 Cont Fire Protection Supply Cont Isolation (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 9-31 (Page 1 of 1)

Table 9-31. Valves Aligned to Blackout Air Supply General Seal water supply flow rate, for four reactor coolant pumps, nominal, gpm 32 Seal water return flow rate, for four reactor coolant pumps, nominal, gpm 12 Letdown Flow:

Normal, gpm ~75 - 120 Maximum mixed bed demineralizer purification , gpm 150 1 Charging Flow (excludes seal water):

Normal, gpm ~55 - 100 Normal operational limit, gpm 144 2 Temperature of letdown reactor coolant entering system, °F 556 Temperature of charging flow directed to Reactor Coolant System, °F 514 Temperature of effluent directed to Boron Recycle System, °F 115 Centrifugal charging pump bypass flow (each), gpm 60 Amount of 4% boric acid solution required to meet cold shutdown requirements at the See COLR end of a core cycle with the most reactive control rod stuck out of the core, gallons Maximum pressurization required for hydrostatic testing of Reactor Coolant System, 3107 psig Notes:

1. Based on single mixed bed demineralizer alignment.
2. Higher flows are allowed for infrequent operation (e.g. start-up, shutdown,..)

as limited by the regenerative heat-exchange design.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-32 (Page 1 of 5)

Table 9-32. CVCS Component Data Summary Reciprocating Charging Pump Number 1 (per unit)

Design pressure, psig 3200 Design temperature, °F 300 Design flow, gpm 98 Design head, ft. 5800 Material Austenitic stainless steel Maximum operating pressure, psig 3125 (for Reactor Coolant System hydrotest purposes)

Centrifugal Charging Pumps Number 2 (per unit)

Design pressure, psig 2800 Design temperature, °F 300 Design flow, gpm 150 Design head, ft 5800 Material Austenitic stainless steel Boric Acid Transfer Pump Number 2 per unit Design pressure, psig 150 Design temperature, °F 250 Design flow, gpm 75 Design head, ft 235 Material Austenitic stainless steel Deleted per 2003 update.

Regenerative Heat Exchanger Number 1 (per unit)

Heat transfer rate at design conditions, Btu/hr 11.0 x 106 Tube Side Design pressure, psig 2735 Design temperature, °F 650 Fluid Borated reactor coolant Material Austenitic stainless steel (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-32 (Page 2 of 5)

Shell Side Design pressure, psig 2485 Design temperature, °F 650 Fluid Borated reactor coolant Material Austenitic stainless steel Shellside (Letdown)

Flow, lb/hr 37,200 - 59,500 Inlet temperature, °F 560 Outlet temperature, °F 288 Tube Side (Charging)

Flow, lb/hr 27,300 - 49, 600 Inlet temperature, °F 130 Outlet temperature, °F 514 Letdown Heat Exchanger Number 1 (per unit)

Heat transfer rate at design conditions, Btu/hr 16.0 x 106 Shell Side Design pressure, psig 150 Design temperature, °F 250 Fluid Component cooling water Material Carbon Steel Tube Side Design pressure, psig 600 Design temperature, °F 400 Fluid Borated reactor coolant Material Austenitic stainless steel Shell Side

~ 120 gpm letdown ~ 75 gpm letdown Flow, lb/hr 498,000 200,000 Inlet temperature, °F 95 95 Outlet temperature, °F 127 128 Tube Side (Letdown)

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-32 (Page 3 of 5)

~ 120 gpm letdown ~ 75 gpm letdown Flow, lb/hr 59,600 1 37,200 Inlet temperature, °F 380 290 Outlet temperature, °F 115 114 Excess Letdown Heat Exchanger Number 1 (per unit)

Heat transfer rate at design conditions, Btu/hr 5.2 x 106 Shell Side Tube Side Design pressure, psig 150 2485 Design temperature, °F 250 650 Design flow, lb/hr 125,000 12,500 Inlet temperature, °F 95 560 Outlet temperature, °F 137 165 Fluid Component cooling Borated reactor coolant Material Carbon steel Austenitic stainless steel Seal Water Heat Exchanger Number 1 (per unit)

Heat transfer rate at design conditions, Btu/hr 1.6 x 106 Shell Side Tube Side Design pressure, psig 150 150 Design temperature, °F 250 250 Design flow, lb/hr 125,000 66,000 Inlet temperature, °F 95 139 Outlet temperature, °F 108 115 Fluid Component cooling Borated reactor water coolant Material Carbon steel Austenitic stainless steel Volume Control Tank Number 1 (per unit)

Volume, ft3 400 Design pressure, psig 75 (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-32 (Page 4 of 5)

Design temperature, °F 250 Material Austenitic stainless steel Boric Acid Tanks Number 1 per unit2 Capacity, gal 46,000 Design pressure Atmospheric Design temperature, °F 200 Material Austenitic stainless steel Batching Tank Number 1 (shared)

Capacity, gal 800 Design pressure Atmospheric Design temperature, °F 300 Material Austenitic stainless steel Mixed Bed Demineralizers Number 2 (per unit)

Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 150 Material, (vessel) Austenitic stainless steel Seal Water Injection Filters Number 2 (per unit)

Design pressure, psig 2735 Design temperature, °F 200 Design flow, gpm 80 Retention for 5-micron particles, percent 98 Material, (vessel) Austenitic stainless steel Seal Water Return Filter Number 1 (per unit)

Design pressure, psig 300 Design temperature, °F 250 (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-32 (Page 5 of 5)

Design flow, gpm 150 Retention for 25-micron particles, percent 98 Material, (vessel) Austenitic stainless steel Boric Acid Filter Number 1 (per unit)

Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 150 Retention for 25-micron particles, percent 98 Material, (vessel) Austenitic stainless steel Boric Acid Blender Number 1 (per unit)

Design pressure, psig 150 Design temperature, °F 250 Material Austenitic stainless steel Letdown Orifice 45 gpm Number 1 (per unit)

Design flow, lb/hr 22,230 Differential pressure at design flow, psi 1900 Design pressure, psig 2485 Design temperature, °F 650 Material Austenitic stainless steel Note:

1. Value is nominal design. Higher allowable flows (1.25-2.0 factor higher) are permissable for non-steady state operation (short duration for start-up/shutdown auxiliary letdown operation).
2. One tank is normally aligned with each unit. However, connections are provided to allow either tank to supply either unit.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 9-33 (Page 1 of 2)

Table 9-33. Boron Thermal Regeneration System Component Data The Boron Thermal Regeneration System has been functionally disabled and will be decommissioned at a later date. This information is provided as historical reference only.

Chiller Pumps Number 3 (one per unit plus one shared)

Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 400 Design head, feet 150 Material Carbon Steel Moderating Heat Exchanger Number 1 (per unit)

Design heat transfer, BTU/hr 2.53 x 106 Shell Tube Design pressure, psig 300 300 Design temperature, °F 200 200 Design flow, lb/hr 59,640 59,650 Design inlet temperature (boron storage mode), °F 50 115 Design outlet temperature (boron storage mode), °F 92.4 72.6 Inlet temperature (boron release mode), °F 140 115 Outlet temperature (boron release mode), °F 123.7 131.3 Fluid circulated Reactor Coolant Reactor Coolant Material Stainless Steel Stainless Steel Letdown Chiller Heat Exchanger Number 1 (per unit)

Design heat transfer, BTU/hr 1.65 x 106 Shell Tube Design pressure, psig 150 300 Design temperature, °F 200 200 Design flow, lb/hr 175,000 59,640 Design inlet temperature (boron storage mode), °F 39 72.6 Design outlet temperature (boron storage mode), °F 48.4 45 Inlet temperature (boron release mode), °F 90 123.7 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-33 (Page 2 of 2)

Outlet temperature (boron release mode), °F 99.4 96.1 Fluid circulated Chromated Water Reactor Coolant Material Carbon Steel Stainless Steel Number 1 (per unit)

Design heat transfer, BTU/hr 1.49 x 106 Shell Tube Design pressure, psig 300 600 Design temperature, °F 200 400 Design flow, lb/hr 59,640 44,730 Inlet temperature, °F 115 280 Outlet temperature, °F 140 246.7 Fluid circulated Reactor Coolant Reactor Coolant Material Stainless Steel Stainless Steel Chiller Surge Tank Number 1 (per unit)

Volume, gal 500 Design pressure, psig Atmospheric Design temperature, °F 200 Material Carbon Steel Thermal Regeneration Demineralizers Number 5 (per unit)

Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 120 Resin volume, ft3 70 Material of construction Stainless Steel Chillers Number 3 (one per unit plus one shared)

Capacity, BTU/hr 1.66 x 106 Design flow, gpm 352 Inlet temperature, °F 48.4 Outlet temperature, °F 39 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-34 (Page 1 of 4)

Table 9-34. Boron Recycle System Component Data Summary Recycle Evaporator Feed Pumps Number 2 Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 30 Design head, ft 320 Material Stainless steel Recycle Holdup Tanks Number 2 Capacity, gal 112,000 Design pressure Atmospheric Design temperature, °F 200 Material Stainless steel Recycle Evaporator Reagent Tank Number 1 Capacity, gal 5 Design pressure 150 Design temperature, °F 200 Material Stainless steel Recycle Evaporator Feed Demineralizers Number 2 Design pressure, psig 200 Design temperature, °F 250 Design flow, gpm 120 Resin volume, ft3 39 Material Stainless steel Recycle Evaporator Condensate Demineralizer Number 1 Design pressure, psig 200 Design temperature, °F 250 Design flow, gpm 18 (min)/75 (max)

Resin volume, ft3 27 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-34 (Page 2 of 4)

Material Stainless steel Recycle Evaporator Feed Filters Number 2 Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 150 Particle retention 98% of 5 micron size Material, (vessel) Stainless steel Recycle Evaporator Condensate Filter Number 1 Design pressure, psig 200 Design temperature, °F 250 Design flow, gpm 35 Particle retention 98% of 25 micron size Material, (vessel) Stainless steel Recycle Evaporator Concentrates Filter Number 1 Design pressure, psig 200 Design temperature, °F 250 Design flow, gpm 35 Particle retention 98% of 25 micron size Material, (vessel) Stainless steel Recycle Evaporator Package Number 1 Design pressure, psig 15 Concentration of Concentrate (boric acid), wt percent 4 Concentration of Condensate <10 ppm boron as H3BO3 Material Stainless steel Recycle Holdup Tank Vent Eductor Number 1 Design pressure, psig 150 Design temperature, °F 200 Suction flow, SCFM 1 of H2 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-34 (Page 3 of 4)

Motive flow, SCFM 40 of N2 Material Stainless steel Reactor Makeup Water Storage Tanks Number for Both Units 2 (1 per unit)

Usable Volume, Gallons 112,000 Total Volume, Gallons 125,000 Tank Design Pressure1 Atmospheric Tank Design Temperature, °F 200 Tank Operating Temperature, °F 110 Material of Construction Lined Carbon Steel 1

Not including hydrostatic head.

Recycle Evaporator Concentrates Pump Number 1 Type Double mechanical seal Design pressure, psig 150 Design temperature, °F 250 Material of construction Stainless steel Design flow, gpm 35 Head at design flow, ft. 125 Seal cooling water requirements Flow, gpm 1 min Temperature, °F 110 max.

Supply head, ft 90 min Mechanical Seal Cooling Water Pump Number 1 Type Gear Design pressure, psig 150 Design temperature, °F 140 Material of construction Bronze Design flow, gpm 2 Head at design flow, ft. 200 Mechanical Seal Cooling Water Heat Exchanger (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-34 (Page 4 of 4)

Number 1 Type Coil Heat transfer rate at normal conditions, 3.0 x 104 BTU/hr Shell Side Data Design pressure, psig 150 Design temperature, °F 140 Normal inlet temperature 95 Normal outlet temperature 101 Design flow rate, gpm 10 Pressure loss of normal operating conditions 4 psid Material of construction Carbon steel Tube Side Data Design pressure, psig 150 Design temperature, °F 140 Normal outlet temperature less than 110 Design flow rate, gpm 2 Pressure loss at normal operating conditions 2 psid Material of construction Stainless steel Mechanical Seal Cooling Water Tank Number 1 Internal volume, gal 8.9 Design pressure, internal, psig Atmospheric Design pressure, external, psig Atmospheric Material of construction Stainless steel Mechanical Seal Cooling Water Filter Number 1 (for both units)

Type Disposable synthetic cartridge Design pressure, psig 100 Design temperature, °F 140 Design flow, gpm 2 Pressure drop, psid Negligible Retention, percent at 5 micron particle size 98 Material of construction Stainless steel (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-35 (Page 1 of 1)

Table 9-35. Reactor Makeup Water Specifications

1. Electrical Conductivity Less than 2.0 µmhos/cm at 25 C
2. Oxygen Less than or equal to 1.0 ppm
3. Chloride Less than 0.15 ppm
4. Fluoride Less than 0.15 ppm
5. Specific Activity Less than 0.005 µc/cc Beta-Gamma, excluding tritium which is maintained

@ 2.5 µc/cc or less

6. Boron Less than 10 ppm as boron (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-36 (Page 1 of 1)

Table 9-36. Auxiliary Building Fuel Handling Area Ventilation System Failure Analysis Component Failure Comments and Consequences

1. Fuel Handling Area Fan fails to start or Fuel handling will not be initiated or will be Fan stops running and terminated upon loss of one or both of the fans.

cannot be restarted

2. Fuel Handling Filter Filter Failure Filter failure is considered unlikely. Fuel Train handling will not be initiated unless filter train is acceptable. Filter failure during fuel handling will terminate handling operation.
3. Damper Damper closes fails to Fuel handling operation terminated on loss of reopen flow in filter train.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-37 (Page 1 of 4)

Table 9-37. Comparison of Auxiliary Building Fuel Handling Area Exhaust System with Regulatory Guide 1.52, Revision O Paragraph Compliance Status C-1-a In compliance with exception of relative humidity, see Exceptions and Comments section of this table C-1-b See Exceptions and Comments section of this table C-1-c In compliance C-1-d In compliance C-1-e In compliance C-2-a See Exceptions and Comments section of this table C-2-b See Exceptions and Comments section of this table C-2-c Filter Train proper (Prefilters, HEPA's and Carbon Adsorber) is Seismic Category 1. See Exceptions and Comments section of this table C-2-d See Exceptions and Comments section of this table C-2-e In compliance C-2-f See Exceptions and Comments section of this table C-2-g See Exceptions and Comments section of this table C-2-h See Exceptions and Comments section of this table C-2-i See Exceptions and Comments section of this table C-2-j See Exceptions and Comments section of this table C-2-k In compliance C-2-l See Exceptions and Comments section of this table C-2-m In compliance C-3-a See Exceptions and Comments section of this table C-3-b See Exceptions and Comments section of this table C-3-c In compliance C-3-d In compliance C-3-e See Exceptions and Comments section of this table C-3-f In compliance C-3-g In compliance C-3-h In compliance C-3-i In compliance C-3-j In compliance C-3-k In compliance (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-37 (Page 2 of 4)

Paragraph Compliance Status C-3-l In compliance C-3-m See Exceptions and Comments section of this table C-3-n In compliance C-4-a In compliance C-4-b In compliance C-4-c See Exceptions and Comments section of this table C-4-d See Exceptions and Comments section of this table C-4-e In compliance C-4-f In compliance C-4-g In compliance C-4-h In compliance C-4-i In compliance C-4-j In compliance C-4-k In compliance C-4-l In compliance C-4-m In compliance C-5-a See Exceptions and Comments section this table C-5-b In Compliance C-5-c See Exceptions and Comments section this table C-5-d See Exceptions and Comments section this table C-6-a See Exceptions and Comments section this table C-6-b See Exceptions and Comments section this table C-1-a No method is provided to control the relative humidity of the air entering the clean-up system; i.e., clean-up system heaters are not provided.

C-1-b Services are not shielded from the atmosphere clean-up system.

C-2-a Passive system elements (filter units and ductwork) are not redundant. The atmosphere clean-up systems consists of prefilters, HEPA filters before the adsorber, gasketless-type iodine adsorber, ducts and dampers, fans and necessary instrumentation. No demisters, HEPA filters after the adsorbers, or heaters are included.

C-2-b The fans are separated by a distance of approximately 10 feet. The only rotating machinery in the immediate area are the fans serving the filter unit. Due to the physical arrangement of the fans relative to each other, the internal energy of the wheel would cause any missile generated by one wheel to move in a direction away from the other fan. Further, the wheels are contained in the fan scroll themselves and separated by a common, steel intake plenum. In effect, the generation of missiles has been considered in the design arrangement.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-37 (Page 3 of 4)

Paragraph Compliance Status C-2-c Filter train and all of its internal components are seismic Category 1. External components (fans, ductwork, dampers) are of a heavy-duty, industrial design but are not qualified to seismic Category 1 conditions.

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

C-2-f The volumetric air flow rate is 35,000 cfm. The arrangement is six HEPA filters wide and four HEPA filters high.

C-2-g Fuel Pool Exhaust air flow rate, fan status and filter unit fire alarm are located in the Control Room. Filter unit pressure drops are indicated locally.

C-2-h Neither the power, electrical distribution system, instrumentation nor control is Class 1E.

C-2-i A dampered by-pass is provided around the Fuel Pool exhaust filter train. By-pass position is indicated both locally and in the Control Room. When a radiation signal is received by the radiation monitors sampling the incoming exhaust air, the dampers are automatically positioned such that the air is processed by the filter train. Reset of the bypass and monitor is accomplished manually.

C-2-j Filter train will not be removable as an intact unit. Gasketless iodine adsorbers will be used - the design of which permits the fluidizing of carbon for external filling and removal which permits a minimum of exposure to operating personnel.

C-2-l The filter unit will not be located in a high radiation zone nor will it be subject to any DBA pressure surges.

C-3-a The filter train contains no demisters.

C-3-b The filter train contains no heaters.

C-3-e HEPA filters reach a maximum height of approximately 10 feet above the filter train floor level as does the adsorber. However, since the adsorber is of the gasketless design, no material handling problems will be encountered due to this height as the carbon is fluidized for filling and removing. The HEPA filter section includes permanent galleries for ease of servicing.

C-3-m Ductwork is designed to meet or exceed the requirements of the SMACNA High Velocity Duct Construction Manual, 1969.

C-4-c Minimum access door size will be 20" x 50" in the filter train. No vacuum breakers are provided to aid in door opening.

C-4-d It is recognized that 5'-0" is needed upstream of carbon tray designs. However, design is of the gasketless type which does not require 5'-0" upstream for servicing. There is approximately 4'-0" from the HEPA mounting rack to the nearest obstacle. Compliance with the 5'-0" separation requirement is not practical because space allocations for the filter train were established before the issuance of Regulatory Guide 1.52.

C-5-a The ANSI N510-1975, Appendix "A", "check list for visual inspection" was used as a guideline to develop the visual inspection checklist used at MNS. Applicability to all items is impractical because the design of the filter train was established prior to the issuance of Regulatory Guide 1.52.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-37 (Page 4 of 4)

Paragraph Compliance Status C-5-c The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." Silicone sealants are used as gasket material for bolted/flanged joints as found in ductwork to equipment (i.e., dampers, fans, etc.) joints.

C-5-d The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." After the adsorber bypass leakage test is complete, the filtration system will be operated for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to purge the filter media of refrigerant gas.

C-5-a Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

C-5-b In lieu of the sample canister method, carbon test samples will be extracted by deep bed sampling, using a grain theft method. Also, Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-38 (Page 1 of 4)

Table 9-38. Comparison of Auxiliary Building Filtered Ventilation Exhaust System with Regulatory Guide 1.52, Revision 0 Paragraph Compliance Status C-1-a In compliance with exception of relative humidity, see Exceptions and Comments section of this table C-1-b See Exceptions and Comments section of this table C-1-c In compliance C-1-d In compliance C-1-e In compliance C-2-a See Exceptions and Comments section of this table C-2-b See Exceptions and Comments section of this table C-2-c Filter Train proper (Prefilters, HEPA's and Carbon Absorber) is Seismic Category 1. See Exceptions and Comments section of this table C-2-d See Exceptions and Comments section of this table C-2-e In compliance C-2-f See Exceptions and Comments section of this table C-2-g See Exceptions and Comments section of this table C-2-h See Exceptions and Comments section of this table C-2-i See Exceptions and Comments section of this table C-2-j See Exceptions and Comments section of this table C-2-k In compliance C-2-l See Exceptions and Comments section of this table C-2-m In compliance C-3-a See Exceptions and Comments section of this table C-3-b See Exceptions and Comments section of this table C-3-c In compliance C-3-d In compliance C-3-e See Exceptions and Comments section of this table C-3-f In compliance C-3-g In compliance C-3-h In compliance C-3-i In compliance C-3-j In compliance C-3-k In compliance (06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-38 (Page 2 of 4)

Paragraph Compliance Status C-3-l In compliance C-3-m See Exceptions and Comments section of this table C-3-n In compliance C-3-o In compliance C-4-a In compliance C-4-b In compliance C-4-c See Exceptions and Comments section of this table C-4-d See Exceptions and Comments section of this table C-4-e In compliance C-4-f In compliance C-4-g In compliance C-4-h In compliance C-4-i In compliance C-4-j In compliance C-4-k In compliance C-4-l In compliance C-4-m In compliance Note: The following paragraphs have been compared to Regulatory Guide 1.52 Revision 2.

C-5-a See Exceptions and Comments section this table C-5-b In Compliance C-5-c See Exceptions and Comments section this table C-5-d See Exceptions and Comments section this table C-6-a See Exceptions and Comments section this table C-6-b See Exceptions and Comments section this table Exceptions and Comments:

C-1-a No method is provided to control the relative humidity of the air entering the clean-up system; i.e., clean-up system heaters are not provided.

C-1-b Services are not shielded from the atmosphere clean-up system.

C-2-a Passive system elements (filter units and ductwork) and the filter bypass damper are not redundant. The atmosphere clean-up systems consists of prefilters, HEPA filters before the adsorber, gasketless-type iodine adsorber, ducts and dampers, fans and necessary instrumentation. No demisters, HEPA filters after the adsorbers, or heaters are included.

(06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-38 (Page 3 of 4)

Paragraph Compliance Status C-2-b Two fans, each 50% capacity (at design flow rate), serve each filter unit. Should one fan be out of service for any reason, a flow rate of approximately 66% would still be maintained through the filter train. Since the Auxiliary Building is common to both reactor units, should the loss of both fans be experienced, the other unit's filter train and fans would be available to process the Auxiliary Building environment before release to the unit vent. The only rotating machinery in the immediate area are the fans serving the Auxiliary Building Fuel Handling Area Supply and Exhaust Ventilation Systems.

The closest any of these fans is to the Auxiliary Building Filtered Ventilation Exhaust System is approximately 25 feet. The physical arrangement of the fan systems to each other is such that the internal energy of a wheel would cause any missile generated by the wheel to move in a direction away from the other fan systems. Also, the initial impact would be taken by the fan scrolls themselves which would absorb the majority of the energy generated by the missile. Therefore, the generation of missiles and system redundancy has been considered in the system design.

C-2-c Filter train and all of its internal components are seismic Category 1. External components (fans, ductwork, dampers) are of a heavy-duty, industrial design but are not qualified to seismic Category 1 conditions.

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

C-2-f The volumetric air flow rate is 45,700 cfm for Unit 1 and 40,500 cfm for Unit 2. The arrangement is seven HEPA filters wide and five HEPA filters high.

C-2-g Exhaust fan flow status and filter unit fire alarm are located in the Control Room. Filter unit pressure drops and flow rate are indicated locally.

C-2-h The power supply, electrical distribution system and the control system which provides the safety function for the Auxiliary Building Filtered Ventilation Exhaust system meet all applicable requirements for Class 1E systems. The fan motors for this system were not originally purchased as Class 1E motors; however, they have since been replaced with Class 1E motors in order to maintain electrical system integrity.

C-2-i A dampered by-pass is provided around the Auxiliary Building Filtered Ventilation Exhaust System. By-pass position is indicated both locally and in the Control Room.

When a radiation signal is received by the radiation monitors sampling the incoming exhaust air, the dampers are automatically positioned such that the air is processed by the filter train. Under LOCA conditions the bypass is automatically positioned to allow flow through the filter train. Reset of the bypass and monitor is accomplished manually.

C-2-j Filter train will not be removable as an intact unit. Gasketless iodine adsorbers will be used - the design of which permits the fluidizing of carbon for external filling and removal which permits a minimum of exposure to operating personnel.

C-2-l The filter unit will not be located in a high radiation zone nor will it be subject to any DBA pressure surges.

C-3-a The filter train contains no demisters.

C-3-b The filter train contains no heaters.

(06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-38 (Page 4 of 4)

Paragraph Compliance Status C-3-e HEPA filters reach a maximum height of approximately 12 feet above the filter train floor level as does the adsorber. However, since the adsorber is of the gasketless design, no material handling problems will be encountered due to this height as the carbon is fluidized for filling and removing. The HEPA filter section includes permanent galleries for ease of servicing.

C-3-m Ductwork is designed to meet or exceed the requirements of the SMACNA High Velocity Duct Construction Manual, 1969.

C-4-c Minimum access door size will be 20" x 50" in the filter train. No vacuum breakers are provided to aid in door opening.

C-4-d It is recognized that 5'-0" is needed upstream of carbon tray designs. However, design is of the gasketless type which does not require 5'-0" upstream for servicing. There is approximately 4'-6" from the HEPA mounting rack to the nearest obstacle. Compliance with the 5'-0" separation requirement is not practical because space allocations for the filter train were established before the issuance of Regulatory Guide 1.52.

C-5-a The ANSI N510-1975, Appendix "A", "check list for visual inspection" was used as a guideline to develop the visual inspection checklist used at MNS. Applicability to all items is impractical because the design of the filter train was established prior to the issuance of Regulatory Guide 1.52.

C-5-c The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." Silicone sealants are used as gasket material for bolted/flanged joints as found in ductwork to equipment (i.e., dampers, fans, etc.) joints.

C-5-d The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." After the adsorber bypass leakage test is complete, the filtration system will be operated for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to purge the filter media of refrigerant gas.

C-6-a Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

C-6-b In lieu of the sample canister method, carbon test samples will be extracted by deep bed sampling, using a grain theft method. Also, Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

(06 OCT 2003)

McGuire Nuclear Station UFSAR Table 9-39 (Page 1 of 1)

Table 9-39. Purge System Isolation Valve Design and Test Criteria Design: Pressure 15 psig Differential Pressure 15 psi Temperature 250°F Radiation 1 x 107 rads Deleted Per 2008 Update Tests: Valve stem ultrasonically tested Hydrotest to 150% of design pressure 5 cycles open and shut by operator followed by a leak test across valve for zero leakage Valve minimum wall measurement Deleted Per 2008 Update (13 APR 2008)

McGuire Nuclear Station UFSAR Table 9-40 (Page 1 of 4)

Table 9-40. Comparison of Reactor Building Containment Purge Exhaust System with Regulatory Guide 1.52 Rev. 1 Paragraph Compliance Status C-1-a In compliance with exception of relative humidity, see Exceptions and Comments section of this table C-1-b See Exceptions and Comments section of this table C-1-c In compliance C-1-d In compliance C-1-e In compliance C-2-a See Exceptions and Comments section of this table C-2-b See Exceptions and Comments section of this table C-2-c Filter Train proper (Prefilters, HEPA's and Carbon Absorber) is Seismic Category 1. See Exceptions and Comments section of this table C-2-d See Exceptions and Comments section of this table C-2-e In compliance C-2-f See Exceptions and Comments section of this table C-2-g See Exceptions and Comments section of this table C-2-h See Exceptions and Comments section of this table C-2-i See Exceptions and Comments section of this table C-2-j In compliance C-2-k In compliance C-3-a See Exceptions and Comments section of this table C-3-b See Exceptions and Comments section of this table C-3-c In compliance C-3-d In compliance C-3-e In compliance C-3-f See Exceptions and Comments section of this table C-3-g In compliance C-3-h In compliance C-3-i In compliance C-3-j In compliance C-3-k In compliance C-3-l In compliance C-3-m In compliance (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-40 (Page 2 of 4)

Paragraph Compliance Status C-3-n See Exceptions and Comments section of this table C-3-o In compliance C-4-a and C-4-b See Exceptions and Comments section of this table.

C-4-c See Exceptions and Comments section of this table C-4-d In compliance C-4-e In compliance C-4-f In compliance C-4-m In compliance C-5-a See Exceptions and Comments section this table C-5-b In Compliance C-5-c See Exceptions and Comments section this table C-5-d See Exceptions and Comments section this table C-6-a See Exceptions and Comments section this table C-6-b See Exceptions and Comments section this table Exceptions and Comments:

C-1-a No method is provided to control the relative humidity of the air entering the clean-up system; i.e., clean-up system heaters are not provided.

C-1-b Services are not shielded from the atmosphere clean-up system.

C-2-a Passive system elements (filter units and ductwork) are not redundant. The atmosphere clean-up systems consists of prefilters, HEPA filters before the adsorber, gasketless-type iodine adsorber, ducts and dampers, fans and necessary instrumentation. No demisters, HEPA filters after the adsorbers, or heaters are included.

C-2-b Each filter train is a separate unit with its own fan. The fans are separated by a distance of approximately 25 feet. The only rotating machinery in the immediate area are the fans serving the filter units. Due to the physical arrangement of the fans relative to each other, the internal energy of the wheel would cause any missile generated by one wheel to move in a direction away from the other fan. Further, the wheels are contained in the fan scroll. In effect, the generation of missiles has been considered in the design arrangement.

C-2-c Filter train and all of its internal components are seismic Category 1. External components (fans, ductwork, dampers) are of a heavy-duty, industrial design but are not qualified to seismic Category 1 conditions.

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

Containment isolation valves which are closed except during purging, prevent the pressure surge from reaching the filter train.

C-2-f The volumetric air flow rate is 10,500 cfm. The arrangement is five HEPA filters wide and two HEPA filters high.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-40 (Page 3 of 4)

Paragraph Compliance Status C-2-g Purge exhaust air flow rate and fan status are located on the main control panel outside the Control Room. Filter unit fire alarm and fan status are located in the Control Room.

Filter unit pressure drops are indicated locally.

C-2-h Niether the power, electrical distribution system, instrumentation nor control is Class 1E.

C-2-i Filter train will not be removable as an intact unit. Gasketless iodine adsorbers will be used - the design of which permits the fluidizing of carbon for external filling and removal which permits a minimum of exposure to operating personnel. Adequate space has been provided for servicing the equipment.

C-3-a The filter train contains no demisters.

C-3-b The filter train contains no heaters.

C-3-f HEPA filters reach a maximum height of approximately 6'-2" above the filter train floor level as does the adsorber. However, since the adsorber is of the gasketless design, no material handling problems will be encountered due to this height as the carbon is fluidized for filling and removing. The HEPA filter section includes permanent galleries for ease of servicing.

C-3-n Ductwork is designed to meet or exceed the requirements of the SMACNA High Velocity Duct Construction Manual, 1969.

C-4-a and The filter train casing has been designed as a seismic Category 1 Unit. The ductwork is C-4-b designed to meet or exceed the requirements of the SMACNA High Velocity Duct Construction Manual 1969. The adsorber is of the gasketless design, no material handling problems will be encountered due to physical dimensions as the carbon is fluidized for filling and removing. The HEPA filter section includes permanent galleries for ease of servicing.

C-4-c It is recognized that 3'-0" is needed upstream of carbon tray designs. However, design is of the gasketless type which does not require 3'-0" upstream for servicing. There is 2'-6" from the HEPA filters to the nearest obstacle. Compliance with the 3'-0" separation requirement is not practical because space allocations for the filter train were established before the issuance of Regulatory Guide 1.52. for the filter train were established before the issuance of Regulatory Guide 1.52.

C-5-a The ANSI N510-1975, Appendix "A", "check list for visual inspection" was used as a guideline to develop the visual inspection checklist used at MNS. Applicability to all items is impractical because the design of the filter train was established prior to the issuance of Regulatory Guide 1.52.

C-5-c The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." Silicone sealants are used as gasket material for bolted/flanged joints as found in ductwork to equipment (i.e., dampers, fans, etc.) joints.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-40 (Page 4 of 4)

Paragraph Compliance Status C-5-d The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." After the adsorber bypass leakage test is complete, the filtration system will be operated for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to purge the filter media of refrigerant gas.

C-5-a Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

C-5-b In lieu of the sample canister method, carbon test samples will be extracted by deep bed sampling, using a grain theft method. Also, Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-41 (Page 1 of 1)

Table 9-41. Single Failure Analysis for Total Communication System Component Malfunction Comments and Consequences

1. Station- Totally disabled Direct line may be used until interface is restored.

Commercial Interface

2. Station-Microwave Totally disabled Direct line may be used until interface is restored.

Interface

3. Station Telephone- Totally disabled, P.A. handsets may be used for paging. Telephone P.A. Interface leaving short or open system still in service without paging ability.

circuit to special preamplifier.

4. Supply to Power interrupted. Dedicated diesel generator will automatically start Rectifier/Battery to accept the load. If the diesel generator fails, the Inverter 4-hour battery backup will supply the switch.

Combination

5. Telephone Switch Totally disabled Public Address System may be used for internal communications. Direct lines may be used for commercial and microwave calls.
6. Public Address Totally disabled, Station telephones are located throughout the System leaving a short or open station. This system is sufficient until P.A.

circuit to station system is restored.

telephone-p.a.

interface.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-42 (Page 1 of 1)

Table 9-42. Failure Analysis for Lighting Systems Component Malfunction Comments Normal Turbine Loss of Power Undervoltage sensing relays mounted on Building Lighting individual normal lighting panelboards in the areas of selected stairs and corridors automatically energize the emergency 250 volt dc lighting system to provide lighting to the selected stairs and corridors until normal lighting is restored.

Normal Auxiliary Loss of Power Undervoltage sensing relays mounted on Building Lighting individual normal lighting panelboards in the areas of selected stairs and corridors automatically energize the emergency 250 volt dc lighting to the selected stairs and corridors until normal lighting is restored. Undervoltage sensing relays mounted on a selected normal lighting panelboard automatically energizes the emergency ac lighting system to provide lighting to the Cable Room and Equipment Room stairs and exits, Hot Machine Shop, Fuel Pool, Fuel Unloading Area, Diesel Rooms, Pump Rooms, Tank Rooms, Fan Rooms, Decontamination Rooms, Penetration Rooms, Purge Rooms and selected stairs, exits and corridors.

Containment Loss of Power The normal Containment lighting system is powered by two independent 600 volt ac sources.

In the event that either one or both of these sources is lost, undervoltage sensing relays on the respective normal lighting panelboards automatically energize the emergency dc lighting system which provides lighting for selected stairs and corridors inside of the Reactor Building until normal lighting is restored. Undervoltage sensing relays monitoring a selected 208Y/120VAC normal lighting panelboard automatically energize the emergency ac lighting system to provide lighting to selected stairs and platforms.

Normal Control Room Loss of Power The normal Control Room lighting system is Lighting powered by two independent 600 volt ac sources.

In the event that either one or both of these sources is lost, undervoltage sensing relays automatically energize the emergency dc lighting system and the emergency ac lighting system to provide lighting in the Control Room until normal lighting is restored.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-43 (Page 1 of 1)

Table 9-43. Diesel Generator Fuel Oil System Single Failure Analysis Security-Related Information - Figure Withheld Under 10 CFR 2.390 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 9-44 (Page 1 of 1)

Table 9-44. Deleted Per 2018 Update (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 9-45 (Page 1 of 1)

Table 9-45. Containment Ventilation Cooling Water System Component Design COMPONENT DESIGN PARAMETERS Containment Ventilation Cooling Water System Pumps Type, Number Centrifugal, 3 (shared)

No. Stages 1 Design Capacity 3200 gpm Required NPSH at design capacity 18 feet Design TDH 175 feet Shutoff head 240 feet Design temperature 150°F Minimum flow 700 gpm Motor HP 200 Voltage 575 volts Containment Ventilation Cooling Water System Suction Strainer Type, Number Duplex, 1 (shared)

Perforation 1/4 inch diameter Design flow 8000 gpm Estimated pressure drop at design flow, clean 1.5 psi Design temperature 150°F Design pressure 135 psig (05 APR 2011)

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