ML21257A255
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CALVERT CLIFFS UFSAR 1.3-1 Rev. 47 1.3 COMPARISON WITH OTHER PLANTS Table 1-1 presents a summary of the original design characteristics of the CCNPP. The table includes similar data for Maine Yankee Unit 1, Turkey Point Units 3 and 4 and Palisades Unit 1.
Bechtel Power Corporation (Bechtel) and CE are identified as contractors in Section 1.8. The Palisades plant is included in the table because its coolant system is similar to that of Calvert Cliffs, and because both Bechtel and CE were Palisades contractors. Maine Yankee is selected because its core is similar to that of Calvert Cliffs and it is a plant of vintage similar to Calvert Cliffs with which CE is associated. In particular, the reactor regulating system, the reactor coolant pressure regulating system, and the pressurizer level regulating system are essentially identical in design and function to the Maine Yankee systems except in the adaptation to the lesser number of similar inputs for a two-loop plant. Turkey Point is included because it is another comparable plant with which Bechtel is associated.
CALVERT CLIFFS UFSAR 1.3-2 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 HYDRAULIC AND THERMAL DESIGN PARAMETERS Total Core Heat Output, MWt 2560 2440 2200 2200 Total Core Heat Output, Btu/hr 8740x106 8328x106 7479x106 7509x106 Heat Generated in Fuel, %
97.5 97.5 97.4 97.5 Maximum Overpower, %
12 12 12 12 System Pressure, Nominal psia 2250 2250 2250 2100 System Pressure, Minimum Steady State, psia 2200 2200 2220 2050 Hot Channel Factors, Overall Heat Flux, Fq 3.00 2.89 3.23 3.80 Enthalphy Rise, FWH 1.65 1.62 1.77 2.51 DNB Ratio at Nominal Conditions 2.18 2.45 1.81 2.00 Coolant Flow Total Flow Rate, lb/hr 122x106 122x106 101.5x106 125x106 Effective Flow Rate for Heat Transfer, lb/hr 117.5x106 117.5x106 97.0x106 121.25x106 Effective Flow Rate for Heat Transfer, ft2 53.5 53.5 41.8 58.7 Average Velocity Along Fuel Rods, ft/sec 13.6 13.9 14.3 12.7 Average Mass Velocity, lb/hr-ft2 2.20x106 2.9x106 2.32x106 2.07x106 Coolant Temperatures, °F Nominal Inlet 543.5 538.9 546.2 545 Maximum Inlet due to Instrumentation Error and Deadband, °F 548 546 550.2 548 Average Rise in Vessel, °F 52 51.1 55.9 46 Coolant Temperatures, °F Average Rise in Core, °F 54 53.1 58.3 47 Average in Core, °F 570.4 565.4 575.4 568.5 Average in Vessel 569.5 564.4 574.2 568 Nominal Outlet of Hot Channel 643 636 642 642.8 Average Film Coefficient, Btu/hr-ft2-°F 5240 5300 5400 4860 Average Film Temperature Difference, °F 33.5 33 31.8 30
CALVERT CLIFFS UFSAR 1.3-3 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 Heat Transfer at 100% Power Active Heat Transfer Surface Area, ft2 48,416 47,700 42,460 51,400 Average Heat Flux, Btu/hr-ft2 176,000 170,200 171,600 142,400 Maximum Heat Flux, Btu/hr-ft2 527,900 502,300 554,200 541,200 Average Thermal Output, kW/ft 5.94 5.74 5.5 4.63 Maximum Thermal Output, kW/ft 17.5 16.7 17.9 17.6(c)
Maximum Clad Surface Temperature at Nominal Pressure, °F 657 657 657 648 Fuel Center Temperature, °F Maximum at 100% Power 3780 3640 4030 4040 Maximum at Over Power 4070 3940 4300 4350 CORE MECHANICAL DESIGN PARAMETERS Thermal Output, kW/ft at Maximum Over Power 19.6 18.7 20.0 19.7(c)
Fuel Assemblies Design CEA CEA RCC Cruciform Rod Pitch, in.
0.58 0.580 0.563 0.550 Cross-section Dimensions, in.
7.98x7.98 7.98x7.98 0.563 8.1135x8.1135 Fuel Weight (as UO2), lbs 207,269 203,934 176,200 210,524 Total Weight, lbs 282,570 279,235 226,200 295,800 Number of Grids per Assembly 8
8 7
8 Fuel Rods Number 36,896 36,352 32,028 43,168 Outside Diameter, in.
0.440 0.440 0.422 0.4135 Diametral Gap, in.
0.0085 0.0085 0.0065 0.0065 Clad Thickness, in.
0.026 0.026 0.0243 0.022 Clad Material Zircaloy Zircaloy Zircaloy Zircaloy Fuel Pellets Material UO2 Sintered UO2 Sintered UO2 Sintered UO2 Sintered Diameter, in.
0.3795 0.3795 0.367 0.359 Length, in.
0.650 0.650 0.600 0.600
CALVERT CLIFFS UFSAR 1.3-4 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 Control Assemblies Neutron Absorber B4C/SS/Cd-In-Ag B4C/SS/Cd-In-Ag Cd-In-Ag (5-15-80%)
Cd-In-Ag (5-15-80%)
Cladding Material Inconel Inconel 304 SSO Cold Worked Stainless Clad Thickness, in.
0.040 0.040 0.019 0.016 Control Assemblies Number of Assemblies, full/part length 77/8 77/8 53 4 1/4 Cruciform Rods Number of Rods per Assembly 5
5 20 117 Tubes per Rod Core Structure Core Barrel ID/OD, in.
148/149.75 148/149.75 133.875/137.875 149.75/152.5 Thermal Shield ID/OD, in.
None 156/162 142.625/148.0 None NUCLEAR DESIGN DATA Structural Characteristics Core Diameter, inches (Equivalent) 136.0 136.0 119.5 136.71 Core Height, inches (Active Fuel) 136.7 136.7 144 132 Reflector Thickness & Composition Top - Water plus steel, in.
10 10 10 10 Bottom - Water plus steel, in.
10 10 10 10 Side - Water plus steel, in.
15 15 15 15 H2O/U, Unit Cell (Cold) 3.44 3.44 4.18 3.50 Number of Fuel Assemblies 217 217 157 204 UO2 Rods per Assembly, unshimmed/shimmed 204 212/208 Batch A 176 176 Batch B 164 160 Batch C (176/164/164)
(176/164/160)
Structural Characteristics Performance Characteristics 3 Batch Mixed 3 Batch Mixed 3 Regions 3 Batch Mixed Loading Technique Central Zone Central Zone Non-Uniform Central Zone Fuel Discharge Burnup, MWD/MTU Average First Cycle 13,775 13,795 13,000 10,180 First Core Average 22,550 30,000 24,500 17,600
CALVERT CLIFFS UFSAR 1.3-5 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 Feed Enrichments wt%
Region 1 2.05 2.01 1.85 1.65 Region 2 2.45 2.40 2.55 2.08/2.54 Region 3 2.99 2.95 3.10 2.54/3.20 Control Characteristics Effective Multiplication (beginning of life)
Cold, No Power, Clean 1.194 1.170 1.180 1.212 Hot, No Power, Clean 1.152 1.129 1.38 1.175 Hot, Full Power, Xe Equilibrium 1.094 1.075 1.077 1.111 Control Assemblies Material B4C/SS-Cd-In-Ag B4C/SS-Cd-In-Ag Cd-In-Ag (5-15-80%)
Cd-In-Ag (5-15-80%)
Number of Control Assemblies 85 85 53 45 Cruciform Number of Absorber Rods per CEA (or RCC)
Assembly 5
5 20 117 Tubes Welded to Form 13.5 in. Span Total Rod Worth (Hot), %
9.6 9.9 7
8.6 Boron Concentrations To shut reactor down with no rods inserted, clean, Cold/Hot, ppm 1120/1095 945/935 1250/1210 1180/1210 To control at power with no rods inserted, clean/equilibrium xenon, ppm 960/725 820/590 1000/670 1070/830 Kinetic Characteristics, Ranger Over Life Moderator Temperature Coefficient k/k/F
-0.20x10-4 to
-1.96x10-4
-0.04x10-4 to 2.20x10-4
+0.3x10-4 to
-3.5x10-4
-0.08x10-4 to
-2.25x10-4 Moderator Pressure Coefficient, /psi Hot, Operating Beginning-of-Life End-of-Cycle
+0.3x10-6 to 2.6x10-6
+0.65x10-6 to
+2.39x10-6
-0.3x10-6 to
+3.4x10-6
+0.10x10-6 to
+1.7x10-6
CALVERT CLIFFS UFSAR 1.3-6 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 Moderator Pressure Coefficient, Void,
/% Void Hot, Operating Beginning-of-Life
-0.1x10-3
-0.41x10-3 to
+0.5x10-3 to 0.06x10-3 to End-of-Cycle
-1.3x10-3 1.43x10-3
-2.5x10-3
-1.0x10-3 Doppler Coefficient(d)
-1.46x10-5
-1.45x10-5
-1.0x10-5
-1.56x10-5 k/k/F
-1.06x10-5
-1.07x10-5 1.6x10-5
-1.46x10-5 REACTOR COOLANT SYSTEM - CODE REQUIREMENTS Reactor Vessel(f)
ASME III Class A ASME III Class A ASME III Class A ASME III Class A Steam Generator Tube Side ASME III Class A ASME III Class A ASME III Class A ASME III Class A Shell Side ASME III Class A ASME III Class A ASME III Class C ASME III Class A Pressurizer ASME III Class A ASME III Class A ASME III Class A ASME III Class C Pressurizer Relief (or Quench) Tank ASME III Class C ASME III Class C ASME III Class C ASME III Class C Pressurizer Safety Valves ASME III ASME III ASME III ASME III Reactor Coolant Piping ANSI B 31.7 ANSI B 31.1 ANSI B 31.1 ANSI B 31.1 PRINCIPAL DESIGN PARAMETERS OF THE REACTOR VESSEL Operating Pressure, psig 2235 2235 2235 2085 Reactor Inlet Temperature, °F 544.5 540 546.2 545 Reactor Outlet Temperature, °F 599.4 592.8 602.1 591.1 Number of Loops 2
3 3
2 Design Pressure, psig 2485 2485 2485 2485 Design Temperature, °F 650 650 650 650 Hydrostatic Test Pressure (cold), psig 3110 3110 3107 3110 Total Coolant Volume - cu.ft.
11,101 11,026 9,088 10,809
CALVERT CLIFFS UFSAR 1.3-7 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 PRINCIPAL DESIGN PARAMETERS OF THE STEAM GENERATORS Material SA-533, Grade B, Class 1, low alloy steel, internally clad with Type 304 austerities SS equivalent SA-533, Grade E Class 1 steel, forgings-A-508-64 Class 2, cladding-weld deposited 304 SS equivalent SA-302, Grade B, low alloy steel internally clad with type 304 austerities SS equivalent SA-302, Grade B low alloy steel internally clad with Type 304 austerities SS equivalent Design Pressure, psig 2485 2485 2485 2485 Design Temperature, °F 650 650 650 650 Operating Pressure, psig 2235 2235 2235 2085 Inside Diameter of Shell, in.
172 172 155.5 172 Outside Diameter Across Nozzles, in.
253 266-5/8 236 254 Overall Height of Vessel and Enclosure Head to Top of CRDM Nozzle, ft.-in.
41-11-3/4 42-1-3/8 41-6 40-1-13/16 Minimum Clad Thickness, in.
1/8 1/8 5/32 3/16 Number of Units 2
3 3
2 Type Vertical U-Tube with integral moisture separator Vertical U-Tube with integral moisture separator Vertical U-Tube with integral moisture separator Vertical U-Tube with integral moisture separator Tube Material Inconel Inconel Inconel Inconel Shell Material SA-533, Gr. B, Class 1 and SA-516 Gr 70 SA-533, Gr. B, Class 1 and SA-516 Gr 70 Carbon Steel Carbon Steel PRINCIPAL DESIGN PARAMETERS OF THE REACTOR COOLANT PUMPS Tube Side Design Pressure, psig 2485 2485 2485 2485 Tube Side Design Temperature, °F 650 650 650 650 Tube Side Design Flow, lb/hr 61x106 40.67x106 33.93x106 62.5x106 Shell Side Design Pressure, psig 985 985 1085 985 Shell Side Design Temperature, °F 550 550 556 550 Operating Pressure, Tube Side, Nominal, psig 2235 2235 2235 2085 Operating Pressure, Shell Side, Maximum, psig 885 885 1020 885 Maximum Moisture at Outlet at Full Load, %
0.2 0.2 1/4 0.2
CALVERT CLIFFS UFSAR 1.3-8 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 Hydrostatic Test Pressure, Tube Side (cold), psig 3110 3110 3107 3110 Steam Pressure, psia, at full power 850 815 745 770 Steam Temperature, °F, at full power 525.2 520.3 510 513.8 Number of Units 4
3 3
4 Type Vertical, single stage centrifugal with bottom suction and horizontal discharge Vertical, single stage centrifugal with bottom suction and horizontal discharge Vertical, single stage radial flow with bottom suction and horizontal discharge Vertical, single stage radial flow with bottom suction and horizontal discharge Design Pressure, psig 2485 2485 2485 2485 Design Temperature, °F 650 650 650 650 Operating Pressure, nominal psig 2235 2235 2235 2085 Suction Temperature, °F 543.4 538.9 546.5 545 Design Capacity, gpm 81,200 108,000 89,500 83,000 Design Head, ft.
300 290 260 260 Hydrostatic Test Pressure, (cold), psig 3110 3110 3107 3110 Motor Type A-C Induction Single Speed A-C Induction Single Speed A-C Induction Single Speed A-C Induction Single Speed Motor Rating, hp 7200 (cold) 9000 6000 6250 (cold)
PRINCIPAL DESIGN PARAMETERS OF THE REACTOR COOLANT PIPING Material SA516-gr 70 with SS clad SA516-gr 70 with SS clad Austenitic SS SA516-gr 70 clad with SS Hot Leg - ID, in.
42 33.5 29 42 Cold Leg - ID, in.
30 33.5 27 1/2 30 Between Pump & Steam Generator - ID, in.
30 33.5 31 30
CALVERT CLIFFS UFSAR 1.3-9 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 CONTAINMENT SYSTEM PARAMETERS UNIT 1 Type Steel-lined, pre-stressed post tensioned concrete cylinder, curved dome roof Steel-lined, reinforced concrete flat bottom and hemispherical dome Steel-lined pre-stressed post tensioned concrete cylinder, hemispherical domed roof Steel-lined pre-stressed post tensioned concrete cylinder, hemis-cylinder curved dome roof Design Parameters Inside Diameter, ft.
130 135 116 116 Height, ft.
181-2/3 169-1/2 169 190 Free Volume, ft3 2,000,000 1,855,000 1,550,000 1,600,000 Reference Incident Pressure, psig 50 55 59 55 Concrete Thickness, ft.
Vertical Wall 3-3/4 4-1/2 3-3/4 3
Dome 3-1/4 2-1/2 3-1/4 2-1/2 Containment Leakage Prevention & Mitigation Systems Leak-tight pene-tration &
continuous steel liner. Automatic isolation where required. The exhaust from penetration rooms to vent Leak-tight pene-tration &
continuous steel liner. Automatic isolation where required.
Leak-tight pene-tration &
continuous steel liner. Automatic isolation where required.
Leak-tight pene-tration &
continuous steel liner. Automatic isolation where required.
Gaseous Effluent Purge Discharge through vent Discharge through stack Through particulate filter and monitors part of main exhaust system.
Discharge through stack
CALVERT CLIFFS UFSAR 1.3-10 Rev. 47 TABLE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS(a)
CALVERT CLIFFS UNITS 1 & 2 MAINE YANKEE(b)
TURKEY POINT UNITS 3 & 4(b)
PALISADES UNIT 1 ENGINEERED SAFETY FEATURES Safety Injection System No. of High Head Pumps 3
3 (Charging) 4 (Shared) 3 No. of Low Head Pumps 2
2 2
2 Containment Fan Coolers No. of Units 4
6 3
3 Air Flow Capacity, each at emergency condition, cfm 55,000 Not Applicable 25,000 25,000 Containment Spray No. of Pumps 2
3 2
2 Emergency Power Diesel Generator Units 3 total for both units(e) 2 2 total for both units 4
Safety Injection Tanks, Number 4
3 3
4 (a)
The current design characteristics for Calvert Cliffs Units 1 and 2 may differ from those shown in this table.
(b)
The values listed for these plants were taken from public documentation.
(c)
Based on total heat output of the core rather than heat generated in the fuel alone.
(d)
Values shown are for hot, zero power/beginning-of-life, full power conditions.
(e)
The current design characteristics show four total emergency power diesel generators for both units.
(f)
See Table 4-9 for the design code of the replacement RVCH.