ML24159A204
| ML24159A204 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/30/2024 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML24159A261 | List:
|
| References | |
| AEP-NRC-2024-20 | |
| Download: ML24159A204 (1) | |
Text
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CHEMICAL AND VOLUME CONTROL SYSTEM CODE REQUIREMENTS1 Regenerative heat exchanger ASME III 2, Class C Letdown heat exchanger ASME III, Class C, Tube Side, ASME VIII, Shell Side Mixed bed demineralizers ASME III, Class C Reactor coolant filter ASME III, Class C Volume control tank ASME III, Class C Seal water heat exchanger ASME III, Class C, Tube Side, ASME VIII, Shell Side Excess letdown heat exchanger ASME III, Class C, Tube Side, ASME VIII, Shell Side Cation bed demineralizer ASME III, Class C Seal water injection filters ASME III, Class C Boric acid filter ASME III, Class C Evaporator condensate demineralizers ASME III, Class C Concentrates filter ASME III, Class C Evaporator feed ion exchangers ASME III, Class C Ion exchanger filter ASME III, Class C Condensate filter ASME III, Class C Piping and valves USAS B31.13, ASME III Appendix F 4
1 Repairs and replacements for pressure retaining components within the code boundary, and their supports, are conducted in accordance with ASME Section XI.
2 ASME III - American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section III, Nuclear Vessels.
3 USAS B31.1 - Code for Pressure Piping, USA Standards, and special nuclear cases where applicable 4 The evaluation criteria of ASME III Appendix F (faulted conditions) is applicable to: 1) RCP seal leak -off return line penetration piping between inside and outside containment isolation valves (CPN 37) and 2) Piping from the RCP seal bypass line check valves to the normally closed QRV -150 valve in the common discharge header.
I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 20.1 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 9.2-2 U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT Page: 1 of 1
CHEMICAL AND VOLUME CONTROL SYSTEM DESIGN PARAMETERS
General
Original plant design life, years 40 1 Seal water supply flow rate:
Normal, gpm 32 Maximum, gpm Note 2 Seal water return flow rate:
Normal, gpm 12 Maximum gpm Note (1)
Letdown flow:
Normal, gpm 75 Minimum, gpm 45 Maximum, gpm 120 Charging flow:
Normal, gpm 132 3 Minimum, gpm 25 Maximum, gpm 150 (3)
Temperature of letdown reactor coolant entering system, °) 8QLW WR
8QLW WR
&HQWULIXJDOSXPSPLQLIORZ JSP HDFK
7HPSHUDWXUHRIFKDUJLQJIORZGLUHFWHGWR5HDFWRU&RRODQW6\\VWHP °F 495 Temperature of effluent directed to holdup tanks, °F 127
(volumetric flow rates in gpm are based upon 130° F and 2350 psig)
1 Licensed life is 60 years in accordance with Chapter 15 of the UFSAR.
2 This quantity is calculated, see Technical Specification #3.4.6.2e.
3 Flow measured at QFI -200 (common discharge before RCP seal injection)
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 32
Principal Component Data Summary Regenerative Heat Exchanger Number 1 (per unit)
Heat transfer rate at design conditions, Btu/hr 10.3x106
Shell Side Design pressure, psig 2485 Design temperature, °F 650 Fluid Borated reactor coolant Material of construction Austenitic stainless steel
Normal Maximu m (Design) Purification Heatup Flow, lb/hr 37,050 59,280 59,280 Inlet temperature, °F 545 545 547 Outlet temperature, °F 290 287 366 UFSAR Revision 32.0
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Principal Component Data Summary Regenerative Heat Exchanger (cont)
Tube Side Design pressure, psig 2735 Design temperature, °F 650 Fluid Borated reactor coolant Material of construction Austenitic stainless steel
Normal Maximu m Heatup (Design) Purification Flow, lb/hr 27,170 49,400 29,640 Inlet temperature, °F 130 130 130 Outlet temperature, °F 495 461 521 UFSAR Revision 32.0
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Principal Component Data Summary Letdown Orifice Design pressure, psig 2485 Design temperature, °F 650 Normal operating inlet pressure, psig 2235 Normal operating temperature, °F 290 Material of construction Austenitic stainless steel
45 gpm 75 gpm Number 1 (per unit) 2 (per unit)
Design flow, lb/hr 22,230 37,050 Differential pressure at design flow, psig 1900 1900 UFSAR Revision 32.0
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Principal Component Data Summary
Letdown Heat Exchanger Number 1 (per unit)
Heat transfer rate at design conditions (heatup),
Btu/hr 14.8 x 106 Shell Side Design pressure, psig 150 Design temperature, °F 250 Fluid Component cooling water1 Material of construction Carbon steel
Normal Heatup Maximum (Design) Purification Flow, lb/hr 203,000 492,000 510,926 Inlet temperature, °F 95 95 95 Outlet temperature, °F 125 125 125
1 The plant has been evaluated for a CCW Hx outlet temperature range of 60 °F to 105° F. It is acceptable for the CCW temperature to rise to 120°F during cooldown and post -LOCA conditions. See Section 9.2.2.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 32
Principal Component Data Summary Letdown Heat Exchanger Tube Side Design pressure, psig 600 Design temperature, °F 400 Fluid Borated reactor coolant Material of construction Austenitic stainless steel
Normal Heatup Maximum (Design) Purification Flow, lb/hr 37,050 59,280 59,280 Inlet temperature, °F 290 380 (max.) 380 (max.)
Outlet temperature, °F 127 127 127 UFSAR Revision 32.0
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Principal Component Data Summary Mixed Bed Demineralizers Number 2 (per unit)
T ype Flushable Vessel design pressure:
Internal, psig 200 External, psig 15 Vessel design temperature, °F 250 Resin volume, each, ft3 30
Vessel volume, each, ft3 43 Design flow rate, gpm 120 Minimum decontamination factor as measured b y I-131 removal 2 10 Normal operating temperature, °F 127 Normal operating pressure, psig 150 Resin type Cation and anion Material of construction Austenitic stainless steel
2 Assuming one per -cent of fuel containing clad defects.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 32
Principal Component Data Summary Reactor Coolant Filter General:
Number 1 (per unit)
T ype Disposable Cartridge Flow rate, Nominal, gpm 120 Maximum, gpm 150
Vessel:
Design pressure, psi 200 Design temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design ' Pressure, psi 75 Design Temperature °F 180 Absolute Retention Size, micron 6 UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 32
Principal Component Data Summary Volume Control Tank Number 1 (per unit)
Internal volume, ft3 400
Design pressure:
Internal, psig 75 External, psig 15 Design temperature, °F 250 Operating pressure range, psig 0-40 Spray nozzle flow (maximum), gpm 120 Material of construction Austenitic stainless steel UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 32
Principal Component Data Summary Centrifugal Charging Pumps Number 2 (per unit)
T ype Horizontal centrifugal Design pressure, psig 2800 Design temperature, °F 300 Shutoff head, psi 2530 Normal suction temperature, °F 115 Design flow rate, gpm 150 Design head, ft. 5800 Available NPSH, ft. 30 Material Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Positive Displacement Charging Pump Number 1 (per unit)
T ype Positive displacement with variable speed drive Design head, ft. 5800 Design temperature, °F 250 Design pressure, psig 3200 Design flow rate*, gpm 98
Available net positive suction head, ft. 40 Suction temperature, ° F 127 Discharge pressure at 130°F, psig 2500 Material of construction Austenitic stainless steel Hydrostatic test pressure, psig 3125
- At 130° F, 2500 psig UFSAR Revision 32.0
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Principal Component Data Summary Chemical Mixing Tank Number 1 (per unit)
Capacity, gal 5 Design pressure, psig 150 Design temperature, °F 200 Normal operating temperature Ambient Material of construction Austenitic stainless steel
Boric Acid Tank Number 3 (shared)
Capacity (each), gal 11,000 Design pressure Atmospheric Design temperature, °F 250 Normal operating temperature, °F 110-120 Material of construction Austenitic stainless steel
Boric Acid Tank Electric Immersion Heater Number (two per tank) 6 Heat transfer rate, each, kW 10 Material of construction Austenitic stainless steel sheath UFSAR Revision 32.0
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Principal Component Data Summary Batching Tank and Batching Tank Heater Jacket Number 1 (shared)
T ype Cylindrical with jacketed base Capacity, gal 800 Design pressure Atmospheric Design temperature, °F 300 Steam temperature, °F 250 Steam pressure, psig 15 Initial ambient temperature 32 Final fluid temperature, ° F 120 Heatup time, hrs 3 (approximately)
Tank material of construction Austenitic stainless steel Jacket material of construction Carbon steel
Batching Tank Agitator Number 1 (shared)
Fluid handled, boric acid, wt% 12 Service Continuous Operating temperature, °F 120 Operating pressure Atmospheric Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Excess Letdown Heat Exchanger Number 1 (per unit)
Heat transfer rate at design conditions, Btu/hr 4.61x106
Shell Side Tube Side Design pressure, psig 150 2485 Design temperature, °F 250 650 Design flow rate, lb/hr 115,000 12,380 Inlet temperature, °F 95 545 Outlet temperature, °F 135 195 Fluid Component cooling water3 Borated reactor coolant Material of construction Carbon steel Austenitic stainless steel
3 The plant has been evaluated for a CCW Hx outlet temperature range of 60 °F to 105° F. It is acceptable for the CCW temperature to rise to 120°F during cooldown and post -LOCA conditions. See Section 9.2.2.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 14 of 32
Principal Component Data Summary Seal Water Heat Exchanger Number 1 (per unit)
Heat transfer rate at design conditions, Btu/hr 2.49 x106
Shell Side Tube Side Design pressure, psig 150 150 Design temperature, °F 250 250 Design flow, lb/hr 99,500 160,600 Normal operating flow, lb/hr (includes miniflow) 99,500 36,000 Design operating inlet temperature, ° F 95 143 Design operating outlet temperature, °F 120 127 Fluid Component Borated cooling water4 reactor coolant Material of construction Carbon steelAustenitic stainless steel
4 The plant has been evaluated for a CCW Hx outlet temperature range of 60 °F to 105° F. It is acceptable for the CCW temperature to rise to 120°F during cooldown and post -LOCA conditions. See Section 9.2.2.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 32
Principal Component Data Summary Seal Water Filter General:
Number 1 (per unit)
T ype Disposal Cartridge Flow Rates, Nominal, gpm 12 Maximum, gpm 325
Vessel:
Design pressure, psi 200 Design Temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design ' Pressure, psi 80 Design Temperature, °F 200 Nominal Retention Size, micron 25 UFSAR Revision 32.0
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Principal Component Data Summary Boric Acid Filter General:
Number 1 (per unit)
T ype Disposable Cartridge Design Flow Rate, gpm 150
Vessel:
Design pressure, psi 200 Design Temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design, ' Pressure, psi 150 Design Temperature, °F 250 Nominal Retention Size, micron 20 UFSAR Revision 32.0
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Principal Component Data Summary Boric Acid Transfer Pu mp Number 4 (shared)
T ype Two-speed horizontal centrifugal Design flow rate, each, gpm 75 at high speed Design pressure, psig 150 Design discharge head, ft. 235 Design temperature, °F 250 Temperature of pumped fluid, °F 120 NPSHA at 135°F and 87.4 gpm, ft 11.75 NPSHR at 135°F and 87.4 gpm, ft.. 7.24 Material of construction Austenitic stainless steel
Boric Acid Blender Number 1 (per unit)
Design pressure, psig 150 Design temperature, °F 250 Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Cation Bed Demineralizer Number 1 (per unit)
T ype Flushable Vessel design pressure:
Internal, psig 200 External, psig 15 Vessel design temperature, °F 250 Resin volume, ft3 20
Vessel volume, ft3 30 Normal operating temperature, °F 127 Normal operating pressure, psig 150 Design flow, gpm 72 Resin type Cation Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Chemical Mixing Tank Orifice Number 1 (per unit)
Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 2 Material of construction Austenitic stainless steel
Boric Acid Tank Orifice Number 3 (shared)
Design pressure, psig 150 Design temperature, °F 200 Design flow, gpm 3 Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Deborating Demineralizers Number 2 (per unit)
T ype Fixed bed Vessel design pressure, psig Internal 200 External 15 Vessel design temperature, °F 250 Resin Volume, ft3 43
Vessel volume, ft3 56 Normal flow, gpm 120 Normal operating temperature, °F 127 Normal operating pressure, psig 150 Resin type Anion Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Seal Injection Filters General:
Number 2 (per unit)
T ype Disposal Cartridge Flow Rates, Nominal, gpm 32 Maximum, gpm 80
Vessel:
Design pressure, psig 2735 Design temperature, °F 200 Material of construction Austenitic stainless steel Cartridge:
Cartridge:
Maximum Design ' Pressure, psi 75 Design Temperature, °F 180 Absolute Retention Size, micron d 6
No. 1 Seal By-Pass Orifice Number 4 (per unit)
Design pressure, psig 2485 Design temperature, °F 250 Design flow, gpm 1.0 Differential pressure at design flow, psi 300 UFSAR Revision 32.0
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Principal Component Data Summary Holdup Tanks Number 5 (shared)
- T ype Horizontal, cylindrical Capacity, each tank, gal. 64,000 Design pressure, psig 15 Normal operating pressure, psig 3 Design temperature, °F 200 Normal operating Temperature, ° F 130 Material of construction Austenitic stainless steel
- Two pairs of tanks plus single tank.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revision: 27.0 D. C. COOK NUCLEAR PLANT Table: 9.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 23 of 32
Principal Component Data Summary Boric Acid Reserve Tank Number 1 (shared)
T ype Horizontal, cylindrical Capacity, gal. 64,000 Design pressure, psig 15 Normal operating pressure, psig 2 Design Temperature, °F 200 Normal Operating Temperature, °F 115 Material of construction Austenitic stainless steel
Recirculation Pump Number 1 (shared)
T ype Centrifugal Design flow, gpm 500 Available NPSH at 130° F, ft. 15 Design head, ft. 100 Design pressure, psig 150 Design temperature, °F 200 Normal operating temperature, °F 150 Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Boric Acid Evaporator Feed Pumps Number 3 (shared)
T ype Canned Design flow, gpm 30 Design head (TDH), ft. 320 Design pressure, psig 150 Design temperature, °F 200 Normal fluid temperature, °F 115 Material of construction Austenitic stainless steel NPSH at 115°F, ft. 15
Boric Acid Evaporator Package Number 1 (other used for radwaste)
Design flow/unit; gas stripper feed, gpm 30 Evaporator condensate, gpm 30 Evaporator concentrates (batch flow), gpm 45 Decontamination factors (design):
Gas stripper Approx. 105(for gas)
Evaporator Approx. 106 (for liquid)
Concentration of concentrates, boric acid, wt% 4
<10 ppm boron as H3BO3 Concentration of distillate Conductivity 2.0 umhos/cm
Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Evaporator Condensate Demineralizers Number 1 (other used for radwaste)
T ype Fixed bed Design temperature, °F 250 Design pressure:
Internal, psig 200 External, psig 15 Resin volume, each, ft3 20
Vessel volume, each, ft3 30 Design flow, gpm 72 Normal operating pressure, psig 50 Normal operating temperature, °F 130 Resin type (south) Anion Resin type (north) As required Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Monitor Tanks Number 2 (shared)
(other 2 shared for radwaste)
T ype Diaphragm, C ylindrical Volume, each, gal. 21,600 Design pressure Atmospheric Design temperature, °F 150 Normal operating temperature, °F 120 Material of construction Stainless steel
Monitor Tank Pumps Number 2 (shared)
T ype Centrifugal Design flow, gpm 150 Design head, ft. 200 Design pressure, psig 150 Design temperature, °F 200 Material of construction Austenitic stainless steel NPSH, ft 15 UFSAR Revision 32.0
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Principal Component Data Summary Evaporator Feed Ion Exchangers Number 4 (shared)
T ype Flushable Design temperature, °F 250 Design pressure:
Internal, psig 200 External, psig 15 Resin volume, each, ft3 20 (2 of 4 units), 27 (2 of 4 units)
Vessel volume, each, ft 3 30 (2 of 4 units)
Normal flow, gpm 30 Normal operating temperature, °F 130 Normal operating pressure, Psig 75 Resin type Cation (2 of 4 units),
Mixed Bed (2 of 4 units)
Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Concentrates Filter General:
Number 2 (shared)
T ype Disposable Cartridge Design Flow Rate, gpm 40
Vessel:
Design pressure, psi 200 Design Temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design, ' Pressure, psi 75 Design Temperature, °F 200 Nominal Retention Size, micron 25 or Absolute Retention Size, micron 0.1 to 25 UFSAR Revision 32.0
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Principal Component Data Summary Concentrates Holding Tank Number 1 (shared)
T ype Cylindrical, heated Volume, gal. 2,000 Design Pressure Atmospheric Design temperature, °F 250 Normal operating temperature, °F 150 Material of construction Austenitic stainless steel
Concentrates Holding Tank Electric Heater Number 1 (shared)
Heat transfer rate, KW 6.0 Material of construction Austenitic stainless steel
Concentrates Holding Tank Transfer Pump Number 2 (shared)
T ype Centrifugal can Design flow rate, gpm 40 Design head, ft. 150 Design temperature, °F 250 Design pressure, psig 150 Available NPSH at 180° F, ft. 10 Material of construction Austenitic stainless steel UFSAR Revision 32.0
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Principal Component Data Summary Ion Exchanger Filter General:
Number 2 (shared)
T ype Disposable Cartridge Design Flow Rate, gpm 35
Vessel:
Design pressure, psig 200 Design temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design ' Pressure, psi 75 Design Temperature, °F 200 Nominal Retention Size, micron 25 or Absolute Retention Size, micron 0.1 to 25 UFSAR Revision 32.0
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Principal Component Data Summary Condensates Filter General:
Number 2 (shared)
T ype Disposable Cartridge Design Flow Rate, gpm 35
Vessel:
Design pressure, psi 200 Design Temperature, °F 250 Material of construction Austenitic stainless steel
Cartridge:
Maximum Design ' Pressure, psi 80 Design Temperature, °F 200 Nominal Retention Size, micron 25 UFSAR Revision 32.0
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Principal Component Data Summary
Fluid Inlet Set Back Pressure Relief Valves No. Fluid Temperature Pressure psig Capacity Discharged °F psig Constant Buildupgpm
Letdown line Water-(HP) 1 Steam 385 (max.) 600 3 50 98,000 lb/hr Mixture
Seal water return line 1 Water 150 150 3 50 225
Charging pump's 1 Water 130 2735 15 75 100 discharge
Letdown line
( LP ) 1 Water 127 200 15 12 200
Volume control Hydrogen, tank 1 nitrogen 130 75 3 12 350 or water
Holdup tanks 3 Nitrogen water 130 12 3 3 235
Boric Acid Reserve Tank 1 Nitrogen Water 115 12 3 3 187 I NIN DD II AA NN AA AA NN DD MM II CC HH II GG AA NN PP OO WW EE RR Revision: 17 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 9.2-4 U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT Page: 1 of 1
FAILURE ANALYSIS OF THE CHEMICAL AND VOLUME CONTROL SYSTEM
Component Failure Comments and Consequences
- a. Letdown Rupture in the line The remote air-operated valve located near the main coolant loop is Line inside the reactor closed on low pr essurizer level to prevent supplementary loss of containment coolant through the letdown line rupture. The containment isolation valves in the letdown line are automatically closed by the containment isolation signal initiated by the concurrent loss-of-coolant accident.
The closure of these valves prevents any leakage of the reactor containment atmosphere outside the reactor containment.
- b. Normal and See above The check valves located near the main coolant loops prevent alternate supplementary loss of coolant through the line rupture. The check Charging valve located at the boundary of the reactor containment prevents any Line leakage of the reactor containment atmosphere outside the reactor containment.
- c. Seal Water See above The motor-operated isolation valves located inside and outside the Return Line containment are manually closed or are automatically closed by the containment isolation signal initiated by the concurrent loss-of-coolant accident. The closure of that valve prevents any leakage of the reactor containment atmosphere outside the reactor containment.
- d. Letdown Rupture in the line Any break between containment and the letdown heat exchanger Line outside the would potentially result in flashing hot letdown fluid and would be containment identified by lo flow in the letdown line and other system indications.
The increase in letdown flow caused by abreak downstream of the letdown flow indicator would be matched by an automatic increase in the charging flow and a HI Letdown Flow Alarm. An operational level in the pressurizer would, therefore, be maintained. Ultimately, the operator would be alerted by a Lo Lo level alarm in the volume control tanks. (Other indications would be an increased charging flow and falling volume control tank level. Also, the area monitors in the auxiliary building would detect any increase in activity). By observing the flow meter on the letdown line, the operator could detect the increase in flow, depending on the location of the break. The break could then be isolated by closing the redundant isolation valves in the letdown lines. Any spillage would be drained and collected in the Radioactive Waste Disposal System, while residual gases from any flashed coolant would be circulated through particulate filters before being discharged to the atmosphere through the plant vent.
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RESIDUAL HEAT REMOVAL SYSTEM CODE REQUIREMENTS 1
Residual Heat Exchangers (Tube Side) ASME B&PV Code Section III, Class C
(Shell Side) ASME B&PV Code Section VIII
Residual Heat Removal System Piping and Valves USAS B31.1, 1967 Edition
1 Repairs and replacements for pressure retaining components within the code boundary, and their supports, are conducted in accordance with ASME Section XI.
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RESIDUAL HEAT REMOVAL SYSTEM DESIGN PARAMETERS
General
Original plant design life, years 40 1 Component cooling water supply temperature design, ° F 95 Reactor coolant temperature at startup of decay heat removal °F 350 Time to cool Reactor Coolant System from 350°)WR °) KUV
GHVLJQEDVLV
5HIXHOLQJZDWHUVWRUDJHWHPSHUDWXUH PLQLPXP ° F 70
Decay heat generation at 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after shutdown, Btu/hr 77x106 H3BO3 concentration in refueling water storage tanks, ppm boron 2400 to 2600 (Modes 1, 2, 3 & 4) 2400 (Modes 5 & 6)
COMPONENTS
Residual Heat Exchangers
Number 2 (per unit)
Design heat transfer, Btu/hr 41.1x106 Shell Tube Design pressure, psig 150 600 Design temperature, °F 200 400 Design flow rate, lb/hr 2.475x106 1.48x106 Design outlet temperature, °F 111.6 112.3 Design inlet temperature, °F 95 140 Fluid Component cooling water Reactor coolant (borated 2 demineralized water)
Material of construction Carbon steel Austenitic stainless steel
1 Licensed life is 60 years in accordance with Chapter 15 of the UFSAR.
2 The plant has been evaluated for a CCW Hx outlet temperature range of 60 °F to 105° F. It is acceptable for the CCW temperature to rise to 120° F during cooldown and post-LOCA conditions. See Section 6.2.2.
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RESIDUAL HEAT REMOVAL SYSTEM DESIGN PARAMETERS
Residual Heat Removal P umps
Number 2 (per unit)
Type Vertical in-line, single stage, centrifugal Design pressure, psig 600 Design temperature, °F 400 Shutoff head, psig 170 Design flow rate, gpm 3,000 Design head, ft. 350
Temperature of pump fluid, ° F 70 - 350 Design Speed, rpm 1780 Motor Rating, HP 400 Normal fluid Reactor coolant Fluid during LOCA recirculation phase Radioactive borated water with H2 and NaOH in solution Material of construction Austenitic stainless steel
Piping and Valves
Residual heat removal loop (piping and valves in isolated loop):
Design pressure, psig 600 Design temperature, °F 400 Residual heat removal loop isolation valves and piping:
Design pressure, psig 2,485 Design temperature, °F 650
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RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTIONANALYSIS
Component Malfunction Comments and Consequences
- 1. Residual heat Rupture of a pump The casing and shell are designed for 600 psig and 400° F. The removal pumps casing pump is protected from overpressuriza tion by two normally closed valves in the pump suction line and by a relief line, containing a relief valve, back to the pressurizer relief tank.
The pump is inspectable and is located in the auxiliary building protected against credible missiles. Rupture is considered unlikely but in any event the pump can be isolated.
- 2. Residual heat Pump fails to start One operating pump furnishes removal pump half of the flow Removal pump required to meet design cooldown rate. Failure of the other pump to start increases the time necessary for plant cooldown.
- 3. Residual heat Manual valve on pump This is prevented by pre startup and operational check. The removal pump suction is closed valve is normally locked or sealed open.
- 4. Residual Heat Stop valve on removal pump discharge line closed Stop valve is locked or sealed open. Prestartup and operational or check valve sticks checks confirm position of valves.
closed.
- 5. Remote Valve fails to open In the improbable event that one of the remote operated valves operated valves on the suction line to the residual heat removal pumps is inside inoperable, an attempt will be made to open it manually. If this containment in is impossible, the plant will be cooled to about 280 °F with pump suction steam dump from the team generators, and kept at that line temperature for several weeks until decay heat could be matched by the letdown heat exchangers and by feed and bleed.
Feed and bleed through the CVCS will done intermittently to prevent heat transfer through the regenerative heat exchanger.
The pressurizer level will be to minimum during the bleed operation and to maximum during the feed operation. It is estimated that plant cooldown be accomplished within a month.
- 6. Remote Valve fails to open Pump discharge pressure gage shows pump shut-off head operated valves indicating no flow. An alternate return line may be opened inside and utilized to direct flow to the RCS.
containment on pump discharge line
- 7. Residual heat Tube or shell rupture Rupture is considered unlikely, but in any event the faulty heat exchanger exchanger may be isolated.
- 8. Residual heat Left open This is prevented by prestartup operational checks.
exchanger vent or drain valve
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SPENT FUEL POOL COOLING SYSTEM CODE REQUIREMENTS 1
Spent Fuel Pool Heat Exchanger (tube side) ASME B&PV Code Section III, Class C
(shell side) ASME B&PV Code Section VIII
Spent Fuel Pool Filter ASME B&PV Code Section III, Class C
Spent Fuel Pool Piping and Valves USAS B31.1
1 Repairs and replacements for pressure retaining components within the code boundary, and their supports, are conducted in accordance with ASME Section XI.
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SPENT FUEL POOL COOLING SYSTEM COMPONENT DESIGN DATA
System cooling capacity, Btu/hr 29.8x106
Spent fuel pool heat exchanger
Number 2 (Shared)
Design heat transfer, Btu/hr 14.9x106
Shell Tube Design pressure, psig 150 150
Design temperature, ° F 200 200
Design flow rate, lb/hr 1.49x106 1.14x106
Design inlet temperature, °F 95 120
Design outlet temperature, °F 105 106.9 Fluid Component Cooling Spent fuel pool (borated Water1 demineralized water)
Spent fuel pool pump
Number 2 (shared)
Design pressure, psig 150
Design temperature, ° F 200
Design flow rate, gpm 2300
Minimum developed head, ft. 125
Temperature of pumped fluid, °F, 80 - 180
Fluid Spent fuel pool water(borated demin. water)
NPSH, ft. (available/required) 30/10
Material Austenitic Stainless Steel
1 The plant has been evaluated for a CCW Hx outlet temperature range of 60° F to 105° F. It is acceptable for the CCW temperature to rise to 120°F during cooldown and post -LOCA conditions. See Section 9.4.2.
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SPENT FUEL POOL COOLING SYSTEM COMPONENT DESIGN DATA
Spent fuel pool skimmer pump Number 1 (Shared Design pressure, psig 50 Design temperature, °F 200 Design flow rate, gpm 100 Minimum developed head, ft. 50 Temperature of pumped fluid, °F 75 - 150 Fluid Spent fuel pool water NPSH, ft. (available/required) 30/2 Material Austenitic Stainless Steel
Refueling water purification pump Number 1 Design pressure, psig 600 Design temperature, ° F 200 Design flow rate, gpm Nom. 100, Max 150 Minimum developed head, ft. 130 Fluid Refueling water NPSH, Ft. (available/required) @ 100gpm 30/5,
@ 150 gpm 43/7 Material Austenitic stainless steel
Spent fuel pool demineralizer Number 1 (Shared)
T ype Flushable Vessel design pressure, psig Internal - 200 External - 15 Vessel design temperature, °F 250 Design flow rate, gpm Maximum 150
Normal flow, gpm 100, Max 150 Normal operating temperature, °F 120 Normal operating pressure, psig Approx. 50 Resin type anion and cation I NIN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR Revision: 17 D.D. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT Table: 9.4-2 U PUP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS R ERE PP OO RR TT Page: 3 of 4
SPENT FUEL POOL COOLING SYSTEM COMPONENT DESIGN DATA
Spent fuel pool filter Number 1 (Shared)
T ype Replaceable (Cellulose and/or glass resin)
Internal design pressure, psig 200 Design temperature, ° F 250 Design flow rate, gpm Nom. 100, Max. 150 Filtration requirement 98% retention of particles above 5 micron
Spent fuel pool skimmer filter Number 1 (Shared)
T ype Replaceable (Cellulose and/or glass resin)
Internal design pressure, psig 200 Design Temperature, oF 250 Design flow rate, gpm 150 Filtration requirement 98% retention of particles above 5 micron
Refueling water purification filter Number 1 (Shared)
T ype Replaceable (Cellulose and/or glass resin)
Internal design pressure, psig 200 Design temperature, ° F 250 Design flow rate, gpm Nom. 100, Max. 150 Particle size retained, minimum, micron 5
Spent fuel pool strainer 2 (Shared)
Design flow rate, gpm 2300 Fluid Borated demineralized water
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SPENT FUEL POOL COOLING SYSTEM COMPONENT DESIGN DATA
Spent fuel pool skimmer strainer Number 1 (Shared)
T ype Basket
Design flow rate, gpm 100
Design pressure, psig 50
Design temperature, ° F 200
Spent fuel pool skimmers
Number 2 (Shared)
Design flow rate per unit, gpm 50
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SPENT FUEL POOL COOLING SYSTEM MALFUNCTION ANALYSIS
Component Malfunction Comments and Consequences
- 1. Spent fuel pool Rupture of a pump The casing is designed for 150 psig and 200 °)ZKLFKH[FHHGV
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COMPONENT COOLING SYSTEM CODE REQUIREMENTS 1
Component cooling heat exchangers ASME B&PV Code Section VIII 1968 Edition 2
Component cooling surge tank ASME B&PV Code Section VIII 1968 Edition
Component cooling loop piping and valves USAS B31.1 1967 Edi tion
1 Repairs and replacements for pressure retaining components within the code boundary, and their supports, are conducted in accordance with ASME Section XI.
2 The component cooling water heat exchanger was designed and fabricated in accordance with ASME B&PV Code,Section VIII, 1968 edition requirements. Installation was in accordance with USAS B31.1, 1967 Edition.
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COMPONENT COOLING WATER SYSTEM FLOW REQU IREMENTS PER TRAIN (GPM) 1
Service Normal LOCA LOCA Cooldown 2 Operation Injection Recirculation Safeguards Train 3 RHR Heat Exchanger - 4 - 5 5000 6 4950 CCP PP Hx 45 26 45 45 SI PP Hx 7 20 24 -
RHR PP Hx - 5 10 10 CTS PP Hx 8 - 3 3 -
Subtotal 45 54 5082 5005 Miscellaneous Train BA Evaporator 1442 9 - - -
SFP Hx 10 2980 - -
Waste Gas Compressors 11 42.5 - 42.5
1 The values in this table are for the operating point described. Plant procedures may consider uncertainty as appropriate. See Section 9.5.
2 Cooldown refers to the operation that takes the reactor plant from hot shutdown (350 ° F) and pressure to cold (140 ° F) conditions. Once below 200 ° F, which will preclude boiling, the CCW flow to the RHR heat exchanger may be reduced to accommodate the reduced RHR heat load.
3 The flows shown reflect the use of one safeguard's train. The second safeguard train may be placed in service provided the necessary equipment is operable. Single train operation results in minimum safeguard's requirements and a minimum cooldown.
4 This path is normally valved off with no flow through the path.
5 The flow through this path satisfies the miniflow requirements for the CCW Pump; there is no RHR heat load on CCW during LOCA injection.
6 UFSAR Chapter 14.3.4, Containment Peak Pressure Transient, input assumption #21, provides the explanation of this input to the containment accident analysis of record.
7 Flow to the SI PP Hx and CTS PP Hx is not specified during the Normal or Cooldown mode since the SI PP and CTS PP are not required to operate during these modes of operation. However, the flow paths to the SI PP Hx and CTS PP Hx are open to permit flow.
8 Flow to the SI PP Hx and CTS PP Hx is not specified during the Normal or Cooldown mode since the SI PP and CTS PP are not required to operate during these modes of operation. However, the flow paths to the SI PP Hx and CTS PP Hx are open to permit flow.
9 Maximum flow; may be significantly reduced as necessary to control process temperatures.
10 SFP Hx is assumed to be on the non-accident unit.
11 Each of two, Waste Gas Compressor cooling can be aligned to either unit.
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COMPONENT COOLING WATER SYSTEM FLOW REQU IREMENTS PER TRAIN (GPM) 1
Service Normal LOCA LOCA Cooldown 2 Operation Injection Recirculation Sample Coolers (U1/U2) 139/169 12 - 139/169 13 Post Accident Sampling System - - 8.5/32.5 -
(U1/U2) 14 Letdown Hx 15 984 16 - - 984 17 Seal Water Heat Exchanger 199 4 4 199
Ctmt. Pen. Cooling 300 - - 300 CEQ Fan Mtrs 18 - 15 15- -
RCP Motors 404 - - 404 RCP Thermal Barrier Hxs 140 - 140 Reactor Support Clrs 40 - - 40 Subtotal (U1/U2) 6670.5/6700.5 15/15 23.5/47.5 2248.5/2278.5 Totals (U1/U2) 6715.5/6745.5 69/69 5105.5/5129.5 7253.5/7283.5
12 Maximum f low; may be significantly reduced as necessary to control process temperatures.
13 Maximum flow; may be significantly reduced as necessary to control process temperatures.
14 The 8.5/32.5 gpm (U1/U2) flow is based on the use of 3 model QC-563 (8 gpm ea. Unit 2) and 1 model QC-501 (8.5 gpm) sample coolers (Unit 1 and Unit 2).
15 The Letdown Hx is assumed to be inservice. The excess letdown Hx is placed inservice if the letdown Hx is unavailable. The excess letdown Hx's design flow rate is 230 gpm.
16 Maximum flow; may be significantly reduced as necessary to control process temperatures.
17 Maximum flow; may be significantly reduced as necessary to control process temperatures.
18 For LOCA Injection and Recirculation only one CEQ fan is required. An analysis was performed which determined acceptable performance at a reduced flow of 15 gpm for 1 fan.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 9.5-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Component Cooling System Component Design Data
Component Cooling Pumps Quantity 5 (incl. 1 Maintenance spare)
T ype Horizontal, centrifugal Rated capacity, gpm 9000 Rated head, TDH, ft 190 Rated motor horsepower, HP 500 Rated motor speed, rpm 1170 Casing material Cast iron Design pressure, psig 150 Design temperature, °F 200 Component Cooling Heat Exchangers Quantity 4 T ype Shell and Tube Heat transferred, Btu/hr 76x106 Shell side Component cooling water outlet Temp., °F 951 Component cooling water inlet Temp., °)
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2 These data reflect the original design of the components. The system has been evaluated for an ESW pump discharge temperature of 88.9°F.
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COMPONENT COOLING SYSTEM MALFUNCTION ANALYSIS
Component Malfunction Comments and Consequences
- 1. Component cooling water pump Rupture of a pump Isolate pump and start redundant pump. Minimum safeguards requirements casing only one out of two pumps.
- 2. Component cooling water pump Pump fails to start One operating pump will supply sufficient flow. Redundancy is sufficient to provide ample flow for any condition.
- 3. Component cooling water pump Manual valve on a pump This will be prevented by pre-startup and operational checks. Further, during suction line closed normal operation, each pump will be checked on a periodic basis, which would show that a valve was closed.
- 4. Component cooling water pump Stop valve on discharge Stop valve will be checked open by pre-startup and operational checks. The stop line closed or check valve and the check valve will be checked by periodic operation of the standby valve sticks closed pump during normal operation.
- 5. Component cooling heat exchanger Tube or shell rupture Isolate and valve in standby train.
- 6. Component cooling heat exchanger vent or Left open This will be prevented by pre-startup and operational checks. On the in service drain valve heat exchangers such a situation would be readily asses sed by makeup requirements to system. On the out -of-service heat exchangers such a situation would be assessed during periodic inspection of general area.
- 7. Thermal Barrier Heat Exchanger Tube Leak or Rupture See Section 9.5.4 Detection by CCW Radiation Monitor or Surge Tank level.
Redundant containment isolation valves provide means to isolate if a leak is detected (isolation would require plant shutdown).
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MODULE DATA
Module I.D. Quantity Array Cell Size Total Cell Count for the Module Type
A* 5 13x14 910
B 4 12x14 672
C 4 13x12 624
D 2 12x12 288
E 4 13x11 572
F 2 12x11 264
G 1 12x10 120
H** 1 13x14 - (8x2) 166
Total 23 3616
- Three of the A modules have one triangle cell to accommodate pool corner curvature.
COMMON MODULE DATA
Storage cell inside dimension: 8.75" + 0.04"
Storage cell height (above the baseplate): 168 + 1/16"
Baseplate thickness: 0.75" (nominal)
Support leg height: 5.25" (nominal)
Support leg type: Remotely adjustable legs
Number of support legs: 4 (minimum)
Remote lifting and handling provision: Yes
Poison material: Boral
Poison length: 144"
Poison width: 7.5"
Cell Pitch: 8.97" (nominal)
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1100 ALLOY ALUMINUM PHYSICAL AND MECHANICAL PROPERTIES
Dens i t y 0.098 lb/cu. in.,
2.713 gm/cc Melting Range 1190-1215 °F, 643-657 °C Thermal Conductivity (77 °F) 128 BTU/hr/sq ft/°F/ft, 0.53 cal/sec/sq cm/°C/cm Coef. of Thermal Expansion (68-212 °F) 13.1x10-6/°F, 23.6x10-6/°C Specific heat (221 °F) 0.22 BTU/lb/°F, 0.23 cal/gm/°C
Modulus of Elasticity 10x106 psi
Tensile Strength (75 °F) 13,000 psi annealed, 18,000 psi as rolled
Yield Strength (75 ° F) 5,000 psi annealed, 17,000 psi as rolled
Elongation (75 ° F) 35-45% annealed, 9-20% as rolled
Hardness (Brinell) 23 annealed, 32 as rolled
Annealing Temperature 650 °F, 343 °C
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CHEMICAL COMPOSITION(BY WEIGHT) - ALUMINUM (1100 ALLOY)
99.00% min. Aluminum
1.00% max. Silicone and Iron
0.05-0.20% max. Copper
.05% max. Manganese
.10% max. Zinc
.15% max. others each
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BORON CARBIDE CHEMICAL COMPOSITION, WEIG HT %
Total boron 70.0 min.
B10 isotopic content in natural boron 18.0
Boric oxide 3.0 max.
Iron 2.0 max.
Total boron plus total carbon 94.0 min.
BORON CARBIDE PHYSICAL PROPERTIES
Chemical formula B4C
Boron content (weight) 78.28%
Carbon content (weight) 21.72%
Crystal Structure rombohedral
Density 2.51 gm./cc -0.0907 lb/cu. in.
Melting Point 2450° C (4442 °F)
Boiling Point 3500° C (6332 °F)
Microscopic thermal-neutron cross-section 600 barn
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SUMMARY
OF CRITICALITY SAFETY ANALYSES
NORMAL STORAGE CONFIGURATION
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SUMMARY
OF CRITICALITY SAFETY ANALYSES
INTERIM CHECKERBOARDLOADING
0 in Region 1, Design Basis burnups at 4.95% +/-0.05% initial enrichment 50 in Region 2, Region 3 - CHECKERBOARD, (FRESH FUEL AND EMPTY)
Temperature for analysis 20° C (68 °F)
Reference K (KENO-5a) 0.9168
Calculational bias, k 0.0090
Axial burnup effect 0.0037
UNCERT AINTIES (Assumed same as the reference case)
Bias statistics (95%/95%) +/-0.0021
KENO-5a statistics (95%/95%) +/-0.0012
Manufacturing tolerances +/-0.0064
Water-gap +/-0.0045
Fuel enrichment +/-0.0034
Fuel density +/-0.0035
Burnup (38 MWD/KgU) NA
Burnup (50 MWD/KgU) +/-0.0047
Eccentricity +/-0.0019
Statistical combination of uncertainties1 +/-0.0108
Maximum reactivity (k ) 0.940
1 Square root of sum of squares.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 30.0 D. C. COOK NUCLEAR PLANT Table: 9.8-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Power Block Definition
Power Block Structure Fire Area(s)
AA1, AA3, AA5/6, AA7, AA8, AA9, AA10, AA11, AA12, AA13, AA14, AA15, AA23, Auxiliary Building AA24, AA25, AA26, AA27, AA29, AA30, AA31, AA34, AA35, AA36/42, AA37, AA38, AA39A, AA39B, AA40, AA41, AA43, AA44, AA45A, AA45B, AA54, AA55
Unit 1 Containment Building AA56
Unit 2 Containment Building AA58
Turbine Building AA2, AA2C, AA16, AA17, AA18, AA19, AA20, AA21, AA22 Control Rooms, Cable Vaults, & HVAC AA46, AA47, AA48, AA50, AA51, AA52, Equipment Areas AA57A, AA57B Service & Office Build AA2 (Containment Cooling Area Only)
Fuel Handling Areas AA3
Screenhouse, ESW Pump & Tunnel Areas and AA2, AA2C, AA32, AA33, YD Water Intake & Discharge System
Fire Pump House YD
Offsite power distribution equipment (i.e., unit auxiliary and reserve transformers), portions of the non-safety power distribution system (i.e., YD main generator step up transformer, 745-345 and 34.5 kv switchyard transformers), and the Supplemental Diesel Generator Area.
Make Up Plant (MUP) Container Complex (Five C Van Containers and Electrical Support: (3) YD Ultra Filtration, (1) Chemical and (1) Ancillary)
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COMPRESSED AIR SYSTEM DESCRIPTIVE INFORMATION1
PLANT AIR SYSTEM PLANT AIR COMPRESSOR Number 2 (one for each unit)
Type Centrifugal Discharge Pressure, psig 100 Discharge Temperature (approximate)° F 266 Capacity, icfm (with inlet conditions of 14.3 psia and 110 oF) 1,485
PLANT AIR COMPRESSOR AFTERCOOLER
Number 1 per compressor Type Shell & Tube Tube Side Flow, icfm (air) 1,500 Shell Side Flow, gpm (water) 23 Shell Side Design Pressure, psig 150 Tube Side Design Pressure, psig 150 Shell Material Carbon Steel Tube Material Admiralty Design Code ASME B&PV Code Section VIII
PLANT AIR RECEIVER Number 2 (one for each unit)
Capacity, ft3 200 Design Pressure, psig 125 Design Temperature, °F 300 Operating Pressure, psig 100 Operating Temperature, °F 105 Material Carbon Steel Design Code ASME B&PV Code Section VIII
1 The information in this Table reflects manufacturer equipment ratings and specifications for the compressed air systems components. These values do not necessarily reflect design basis values for the compressed air systems.
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COMPRESSED AIR SYSTEM DESCRIPTIVE INFORMATION
CONTROL AIR SYSTEM
CONTROL AIR COMPRESSOR Number 2 (one for each unit)
Type Reciprocating Nominal Discharge Pressure, psig 100 Discharge Temperature, °F 320 Capacity, icfm 338, @29.92 in HgA inlet, 480 RPM, 100 psig discharge
CONTROL AIR COMPRESSOR AFTERCOOLER Number 1 per compressor Type Shell & Tube Tube Side Flow, icfm(air) 338 Shell Side Flow, gpm (w ater) 5 Shell Side Design Pressure, psig 150 Tube Side Design Pressure, psig 150 Shell Material Carbon Steel Tube Material Admiralty Design Code ASME B&PV Code Section VIII
CONTROL AIR RECEIVER (WET CONTROL AIR)
Number 2 (one for each unit)
Capacity, ft3 500 Design Pressure, psig 125 Design Temperature, °F 300 Operating Pressure, psig 100 Operating Temperature, °F 95 Material Carbon Steel Design Code ASME B&PV Code Section VIII
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COMPRESSED AIR SYSTEM DESCRIPTIVE INFORMATION
CONTROL AIR SYSTEM (CONT'D)
CONTROL AIR PREFILTER Number 4 (two for each unit in parallel strings)
Capacity, scfm 325 Inlet pressure, psig 100
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CONTROL AIR DRIER Number 8 (four for each unit in two parallel strings)
Capacity, scfm 325 Dew Point at 100 psig, °F -40 Type Convection
CONTROL AIR AFTER FILTER Number 4 (two for each unit in parallel)
Capacity, scfm 840 Retention Size, microns 4 Type Adsorbent
CONTROL AIR RECEIVER (DRY CONTROL AIR)
Number 4 (two for each unit in parallel strings)
Capacity, ft3 500 Design Pressure, psig 125 Design Temperature, °F 300 Operating Pressure, psig 100 Operating Temperature, ° F 105 Material Carbon Steel
Design Code ASME B&PV Code Section VIII I NN DD II AA NN AA MM II CC HH II GG AA NN PP OO WW EE RR I Revision: 17 D.. CC.. CC OO OO KK NN UU CC LL EE AA RR PP LL AA NN TT D Table: 9.8-2 U PP DD AA TT EE DD FF II NN AA LL SS AA FF EE TT YY AA NN AA LL YY SS II SS U
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COMPRESSED AIR SYSTEM DESCRIPTIVE INFORMATION
CONTROL AIR SYSTEM (CONT'D)
BACKUP PLANT AIR COMPRESSOR WITH INTEGRAL SKID MOUNTED AIRCOOLED AFTERCOOLER Number 1 (common for both units)
Type Rotary Screw Nominal Discharge Pressure 100 Discharge Temperature (approximate)oF 108 Capacity, icfm (with inlet conditions of 14.5 psia and 668 80oF)
BACKUP PLANT AIR COMPRESSOR AIR RECEIVER Number 1 Capacity, ft3 100 Design Pressure, psig 150 Design temperature, oF 450 Operating Pressure, psig 100 Operating Temperature, oF 105 Material Carbon Steel Design Code ASME B PV Code section VIII
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 9.8-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Service Water Systems Components Design Data
Non-Essential Service Water Pumps
Quantity 4 T ype Horizontal Centrifugal Rated TDH (ft.) 175 Rated Capacit y - (GPM) 4,500 Rated Motor Horsepower (HP) 250 Rated Motor Speed 1800 (nominal)
Casing material Cast Steel Non-Essential Service Water Strainers
Quantity 4 T ype Automatic - Self Cleaning Essential Service Water Pumps
Quantity 4 T ype Vertical Rated TDH (ft.) 145 Rated Capacit y - (GPM) 10,0001 Rated Motor Horsepower (HP) 450 Rated Motor Speed 900 (nominal)
Casing material Cast iron or Cast steel Essential Service Water Strainers
Quantity 4 T ype Duplex-automatic backwashing
1 Flow rates up to 12,200 gpm have been evaluated as acceptable.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 30.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 4
Non-Essential Service Water Requirements 1
Quantity Flow - GPM
Service Installed Min N o r m Min. Normal Maxi mum Station Cont. or Remarks Req'd Req'd Design Design Expected Black-Out Inter. Serv.
Unit No. 1 Main Oil Coolers 2 1 1 1000 1000 1258 - C
Unit No. 2 Main Oil Coolers 4 2 2 1056 1056 1056 - C
Unit No. 1 FPT Oil Coolers 4 2 2 270 270 270 - C
Unit No. 2 FPT Oil Coolers 4 2 2 354 354 354 - C
Unit No. 1 Main Turbine and Feed 1 1 1 60 60 60 - C Pump EHC Control Fluid Coolers Unit No. 2 Main Turbine and Feed Pump EHC Control Fluid 1 1 1 60 60 60 - C Coolers Unit 1 Containment Chiller 3 2 2 2900 2900 2900 2900 C Condensers
1 Water requirements based on 76°F maximum lake temperature except as noted. The system has been evaluated f or operation with an NESW cooling water
temperature of 88.9° F UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 30.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 4
Non-Essential Service Water Requirements 1
Quantity Flow - GPM
Service Installed Min N o r m Min. Normal Maxi mum Station Cont. or Remarks Req'd Req'd Design Design Expected Black-Out Inter. Serv.
Unit 2 Containment Chiller 3 2 2 2900 2900 2900 2900 C Condensers
Unit No. 2 Generator Seal Oil Coolers 2 2 2 160 160 160 - C Based on 95°)
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'RHVQRWLQFOXGHWKH WK DQG WK DLU FRROHGXQLWV UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 30.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 4
Non-Essential Service Water Requirements 1
Quantity Flow - GPM
Service Installed Min N o r m Min. Normal Maxi mum Station Cont. or Remarks Req'd Req'd Design Design Expected Black-Out Inter. Serv.
Shared System &
Ice Machines 3 2 2 10 50 75 I Used During Ice Loading Only.
Shared System &
Air Cooler Stage 1 1 1 1 20 20 20 I Used During Ice Loading Only.
Air Cooling Condensing Units Shared System &
Stage 2 & 3 2 2 2 20 30 30 I Used During Ice Loading Only.
Mixed Borated Water Shared System &
Condensing Unit 1 1 1 20 30 30 I Used During Ice Loading Onl y.
Plant Air Compressors 3 2 1 1 80 80 160 160 C Shared System
Control Air Compressors 4 2 0 0 0 0 10 10 I Shared System
3 Includes compressor oil cooler, aftercooler and 1st and 2nd stage intercoolers.
4 Includes compressor jacket cooler and aftercooler.
UFSAR Revision 32.0
INDIANA MICHIGAN POWER Revised: 30.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 4
Non-Essential Service Water Requirements 1
Quantity Flow - GPM
Service Installed Min N o r m Min. Normal Maxi mum Station Cont. or Remarks Req'd Req'd Design Design Expected Black-Out Inter. Serv.
Degassifier Vacuum Pump 1st Stage 1 1 1 25 25 25 - C Shared System
Degassifier Vacuum Pumps 2nd Stage 2 1 1 50 50 50 - C Shared System
Demineralizer Make-Up System 1 0 1 0 1093 1515 - I Shared System Heating Boiler Blowdown Flash Tank 1 0 0 110 110 110 - I Shared System
Bearing cooling Unit No. 1 Auxiliary Feed Pumps 3 3 3 6 6 6 - I water for turbine and motor-driven pumps Bearing cooling Unit No. 2 Auxiliary Feed Pumps 3 3 3 6 6 6 - I water for turbine and motor-driven pumps Miscellaneous Sealing and Cooling - - - - - 300 - C Water System (MSCW)
Totals 9,5645 10,787 12,062
5 Actual operational data with cold NESW temperatures indicate nominal minimal flow is approximately 8000 gpm INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4A UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Chilled Water Subsystem Nominal Design Flow Rates (Actual Values May Vary)
Containment Ventilation: Unit No. 1 Upper Units 93.9
Containment Ventilation: Unit No. 1 Lower Units 912
Containment Ventilation: Unit No. 2 Upper Units 93.9
Containment Ventilation: Unit No. 2 Lower Units 912
Unit No. 1 Instr. Room Vent 9.2
Unit No. 2 Instr. Room Vent 9.2
Unit No. 1 RCP Motor Air Coolers 148
Unit No. 2 RCP Motor Air Coolers 148
Chilled water can also be directed to the Steam Generator Blowdown Heat Exchanger at a design flow rate of 65 gpm and to the Steam Generator Blowdown Sample Heat Exchanger at a design flow rate of 14.1 gpm
INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 9.8-4B UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Nominal Design Flow Rates for Alternate Configuration of NESW Directly To Containment AHUs:
Containment Ventilation: Unit No. 1 Upper Units 320
Containment Ventilation: Unit No. 1 Lower Units 1760
Containment Ventilation: Unit No. 2 Upper Units 320
Containment Ventilation: Unit No. 2 Lower Units 1760
Unit No. 1 Instr. Room Vent 50
Unit No. 2 Instr. Room Vent 50
Unit No. 1 RCP Motor Air Coolers 440
Unit No. 2 RCP Motor Air Coolers 440
Unit No. 1 Steam Generator Blowdown Sample Heat 11 changer
Unit No. 2 Steam Generator Blowdown Sample Heat 11 Exchanger
Unit No. 1 Steam Generator Blowdown Heat Exchanger 160
Unit No. 2 Steam Generator Blowdown Heat Exchanger 160
With less than design temperature NESW, actual flow rates may be lower and still provide adequate cooling.
INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 9.8-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
Essential Service Water System Flow Requirements per Train (GPM)
Service 1 Normal LOCA Injection LOCA Cooldown Operation Recirculation CCW H; 700 5000 2 5000 2 9100
2400 (U2) 3 CTS HX - - 2100 (U1) 4 -
EDG CLRS - 540 540 -
AFW SYS 5 - 450 450 -
AFP Enclosure 102 102 102 102 CLRS 6
CRAC7 85 85 85 85
Totals 8887 6177 8277 - 8577 9287
1 The flows shown reflect the use of one ESW train in service corresponding to one CCW safeguard's train. The second ESW train may be placed in service provided the necessary equipment is operable or the second CCW safeguard train is operating. Single train operation results in minimum safeguard's requirements and a minimum cooldown rate.
2 Per update Westinghouse analyses, WCAP-14285, Revision 1, May, 1995.
3 Per update Westinghouse analyses, WCAP-15302, December 13, 1999.
4 Per EC-0000048860.
5 This flow path is aligned manually and required only as a backup to the normal condensate supply to the Auxiliary
Feedwater System.
6 Auxiliary Feedwater Pump Enclosure Coolers will be provided with a continuous supply of ESW in all modes of
operation. Flow is nominal based on cooler rated heat capacity. Different flows are allowable based on engineering analysis, provided required heat removal is achieved.
7 Per FCN-51362-026 (U1-N), FCN-51362-016 (U1-S), FCN-51363-015 (U2-N), & FCN-51363-025 (U2-S)
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ESSENTIAL SERVICE WA TER SYSTEM MALFUNCTION ANALYSIS
COMPONENT MALFUNCTION COMMENTS AND CONSEQUENCES
- 1. Essential service water pumps Rupture of a pump casing Isolate pump and start a redundant pump. Minimum requirements need only two out of four pumps.
One operating pump will supply sufficient flow for one
- 2. Essential service water pumps Pump fails to start operating Unit. Redundancy is sufficient to provide ample flow for any condition.
Stop valve on discharge line The stop valve and the check valve will be checked by
- 3. Essential service water pump closed or check valve sticks periodic operation of the off-duty pumps during normal closed operation.
- 4. Essential service water pump strainer Strainer casing rupture Isolate and valve in spare train.
This will be prevented by prestartup and operational
- 5. Essential service water pump strainer vent or drain valve. Left open checks. On the out-of-service strainer, such a situation would be assessed during periodic checks.
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CONTROL ROOM VENTILATION SYSTEM MALFUNCTION ANALYSIS
COMPONENT MALFUNCTION COMMENTS AND CONSEQUENCES
- 1. Normal Intake Dampers Failure to close Two dampers in series ensure isolation of outside air normal intake.
- 2. Pressurization/Cleanup Failure to open Parallel dampers ensure outside air intake Intake Dampers opens.
Fully open or One damper partially open is correct multiple dampers alignment. A single failure may result in open one damper fully open or 2 dampers partially open. Other failures are no t considered credible.
- 3. Pressurization/Cleanup Failed to closed All air flowing through the filter is from Recirculation Damper position the intake and air cleanup is limited to a single pass. Control Room dose consequences may increase. The position of the recirculation damper is administratively controlled so it does not need to change position in response to a radiological accident.