ML22340A154
Text
UFSAR Revision 31.0 IND IANA M ICH IG AN POW ER Revised: 28.0 D . C. COOK NU CLEAR PLANT Table: 5.1-1 Page: 1 of 3 U PD ATED F INAL SAF ETY ANALYSIS REPORT Potential M issiles Consid ered in Class I ( Seismic) Structure D esig n Imp act Item D escrip tion We igh t Velocity Orig in Area B olted Wood Decking 12' x 12' x 4 " 4 50 lbs 20 0 mph 4 ft2 Tornado B orne Corrugated Siding 4 ' x 4 ' 10 0 lbs 225 mph 0 .25 ft2 Tornado B orne 50 mph traveling on the Passenger Car - 4 0 0 0 lbs 10 ft2 Tornado B orne ground Schedule 4 0 Pipe 1 2 1/ 2" Dia x 8 ' 4 6 lbs 19 5 ft/ sec 6.5 in2 Tornado B orne Reactor Control Rod Drive 25 fps for 3 ft travel to Reactor Coolant Pressure Driven after R. C.
- 1623 lbs 11.3 in2 Mechanism missile shield Housing Mech. Failure U nit 1 Turb ine 2 3 V ane of Last Stage B ucket - 54 lbs 117 0 ft/ sec 0 .8 2 ft2 Mech. Failure During Turbine Overspeed Last Stage Wheel Segment 120 ° Segment 8 264 lbs 4 0 9 ft/ sec 8 .4 3 ft2 Mech. Failure During Turbine Overspeed 1
Considered as a missile only for design of the Aux iliary B uilding east of Spent Fuel Storage Pool.
2 Impact area for turbine items is the average of the minimum and max imum cross-section areas.
3 The missile information in this table is for the removed General Electric low pressure turbines as this analysis bounds other Unit 1 rotating elements. The current missile analysis for the low pressure turbines is based on the missile probability analysis discussed in Section 1.4 .7 .
UFSAR Revision 31.0 IND IANA M ICH IG AN POW ER Revised: 28.0 D . C. COOK NU CLEAR PLANT Table: 5.1-1 Page: 2 of 3 U PD ATED F INAL SAF ETY ANALYSIS REPORT Potential M issiles Consid ered in Class I ( Seismic) Structure D esig n Imp act Item D escrip tion We igh t Velocity Orig in Area U nit 2 Turb ine 2 4 V ane of Last Stage B ucket - 168 lbs 1135 ft/ sec 1.8 7 ft2 Mech. Failure During Turbine Overspeed Disc 1 Segment 120 ° Segment 13,350 lbs 634 ft/ sec 15.0 8 ft2 Mech. Failure During Turbine Overspeed Disc 2 Segment 120 ° Segment 12,10 0 lbs 57 4 ft/ sec 13.9 2 ft2 Mech. Failure During Turbine Overspeed Disc 3 Segment 120 ° Segment 8 ,360 lbs 551 ft/ sec 13.2 ft2 Mech. Failure During Turbine Overspeed Disc 4 Segment 120 ° Segment 16,60 0 lbs 59 5 ft/ sec 15.7 ft2 Mech. Failure During Turbine Overspeed 4
In 20 16, the B rown-B overi turbines were retro-fitted with turbines manufactured by Alstom Power, Inc. Probability analysis ( Reference 1.4 .11.17 ) for the Alstom Unit 2 turbines indicates the probability of generation of a turbine missile ( including overspeed conditions) is less than the NRC limit. Therefore, no additional missile analysis is required for the Unit 2 Alstom turbines. However, the missile information is still provided for the ( removed) B rown-B overi turbines, as these analyses are used in structural design criteria analysis that bounds other Unit 2 rotating elements as shown in Table 5.1-1.
The postulated turbine missile information in this table is for the removed B rown B overi low pressure turbine that was considered in Class I ( Seismic) structure design. The current missile analysis for the Unit 2 low pressure turbines is based on missile probability analysis discussed in Section 1.4 .7 .
UFSAR Revision 31.0 IND IANA M ICH IG AN POW ER Revised: 28.0 D . C. COOK NU CLEAR PLANT Table: 5.1-1 Page: 3 of 3 U PD ATED F INAL SAF ETY ANALYSIS REPORT Note:
- 1. Miscellaneous missiles such as valve stems, bonnets, instruments wells, thimbles, and pipe rupture whip were considered in the design of the structures where applicable; however, tornado generated and turbine missiles, or radiation and structural considerations, generally, were the determining factors in the design of Class I structures.
- 2. The population of missiles used in the TORMIS analysis was based on a physical walk down of non-safety-related buildings, trailers, fencing, trees and parking lots within a 20 0 0 feet radius of the plant. Also included were missiles from plant buildings with siding not designed for tornado winds. This walk down resulted in a potential missile population in ex cess of 55,0 0 0 obj ects.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 5.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 WIND VELOCITIES AND VELOCITY PRESSURES Ungusted Wind Gusted Wind Velocity Velocity Pressure (Gusted Height (ft)
Velocity (mph) (mph) Wind) (psf) 0-50 90 99 25 50-150 115 126 41 150-400 145 159 65
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 5.2-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 3 SITE SOIL RESISTIVITY MEASUREMENTS DATA TAKEN APRIL 10 AND 11, 1969 Elevation Pin Spacing Reading Average Location Direction Multiplier (Feet) (Feet) (Ohms) Ohm-Cm Unit No. 1 Reactor North-South 584 50 2.2 191.5 21,000 40 5.8 191.5 44,400 30 9.9 191.5 56,900 20 18.0 69,000 10 100.0 191,500 Unit No. 2 Reactor North-South 584 50 1.4 191.5 13,400 40 2.0 191.5 15,300 30 8.0 191.5 46,000 20 25.0 191.5 95,900 10 130.0 191.5 249,000 Between No. 1 and 2 Reactors East-West 584 50 70.0 191.5 727,000 40 19.0 191.5 145,600 Average Ohm-Cm = Reading Pin Spacing x Multiplier
Actually Ohms per cubic centimeter
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 5.2-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 3 SITE SOIL RESISTIVITY MEASUREMENTS DATA TAKEN APRIL 10 AND 11, 1969 Elevation Pin Spacing Reading Average Location Direction Multiplier (Feet) (Feet) (Ohms) Ohm-Cm 30 22.0 191.5 126,500 20 26.0 191.5 99,700 10 91.0 191.5 174,200 Unit No. 2 Turbine North-South 589 50 4.3 191.5 41,100 40 7.8 191.5 59,800 30 22.0 191.5 126,500 20 46.0 191.5 176,300 10 110.0 191.5 210,800 Unit No. 1 Turbine North-South 589 50 No. Reading 191.5 ----
40 4.9 191.5 36,800 30 18.0 191.5 103,500 20 40.0 191.5 153,300 10 112.0 191.5 214,300
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 5.2-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 3 SITE SOIL RESISTIVITY MEASUREMENTS DATA TAKEN APRIL 10 AND 11, 1969 Elevation Pin Spacing Reading Average Location Direction Multiplier (Feet) (Feet) (Ohms) Ohm-Cm Unit No. 1 Turbine East-West 589 50 8.0 191.5 76,500 30 21.0 191.5 120,800 10 104.0 191.5 199,300 On Beach Near Water (Sand) North-South 580 50 7.05 191.5 67,500 40 5.40 191.5 41,400 30 8.50 191.5 48,900 20 13.0 191.5 49,800 10 18.0 191.5 34,500
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.6 D. C. COOK NUCLEAR PLANT Table: 5.2-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 ELECTRICAL PENETRATION - PROTOTYPE TESTS PENETRATIONS1 5 Kv Power 600 Volt Power & Instrumentation Test & Sequence Penetration Control Penetration Penetration High Potential2 X X X Leakage 2 X X X Ampacity X X Accident Operating Environment X X X Short Circuit X X 1
Prototype testing compliance was allowed to be demonstrated by the submittal of test data from tests conducted on penetrations of equivalent type and design as those furnished for Donald C. Cook nuclear Plant.
2 Conducted after Ampacity, Accident Operating Environment, and Short Circuit Tests.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 29.0 D. C. COOK NUCLEAR PLANT LANT Table: 5.2-4 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 1 REPORT TAB LE OF D AM PING VALU ES Percent of Critical D amp ing D esig n B asis Ty p e of Structure Op erating B asis Earth quak e Earth quak e Containment Structure and all internal concrete structures 4 %
, 2%
7 %
, 5%
Other conventionally reinforced concrete structures above grade, such as shear walls or rigid 2% 5%
frames Welded structural steel assemblies 1% 1%
B olted or riveted steel assemblies 2% 2%
Piping 0 .5% 0 .5%
Analyz ed with accident conditions
Analyz ed without accident conditions Note 1: See Section 5 .3 .3. 7 for the damping values utiliz ed in the seismic qualification of the Ice Condenser.
Note 2: For the Dry Cask Storage Proj ect, the East Aux iliary B uilding crane, crane rails and the Aux iliary B uilding columns supporting the crane rails were reanalyz ed utiliz ing the guidance provided in Regulatory Guide 1.60 , Rev.1 and the damping values specified in Regulatory Guide 1.61, Rev. 1 to increase the main hoist Max imum Critical Load ( MCL) tol4 5 tons.
Note 3 : See WCAP-7 332-L and WCAP-128 28 for the damping values utiliz ed in the seismic qualification of the reactor internals.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17 D. C. COOK NUCLEAR PLANT Table: 5.2-5 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2
SUMMARY
OF ANALYSES-JET FORCES IMPACTING ON INTERNAL STRUCTURES Normal Operating Pressure Source Diameter Elevation Jet Travel (ft) Critical Target Jet Effect Remarks Psia.
Break #1 29"I.D. 614'-0" Note 1 (2) 2250 c
- 2 27.5"I.D. 614'-0" Note (1) (2) 2250 c
- 3 29"I.D. 615'-0"+ 23.02 Crane Wall 2250 c
- 4 31"I.D. 612'-9"+ 37.0 (2)
Operating Deck 2250 d
- 5 31"I.D. 607'-9"+ 42.0 (2)
Operating Deck 2250 d
- 6 27.5"I.D. 614'-0" 11.0 (2)
Crane Wall 2250 d
- 7 29"I.D. 615'-3+ 39.5 (2)
Operating Deck 2250 c
- 8 31"I.D. 607'-9"+ 42.0 (2)
Operating Deck 2250 d 603- 8
- 9 31"I.D. 13.0(2) Crane Wall 2250 d 1/4
- 10 27.5"I.D. 614'-0" 14.0 Crane Wall 2250 d
- 113 29"I.D. 614'-0" 19.54 Crane Wall 2250 c
- 125 29"I.D. 614'-0" 20.0 Crane Wall 2250 c Pressurizer
- 13 11"I.D. 620'-0"+ 6.0(4) 2250 d Slab 686'-10 Steam Gen.
- 14 30"I.D. 16.0 1020 d 3/16" Encl 1
Jet blocked; restraints prevent further movement.
2 This break does not require consideration of Jet Forces since LBB methodology adopted. Maintained for historical purposes.
3 Surge line connection on loop 3 only.
4 Unit 2 only. LBB accepted for Unit 1.
5 14 connection on loop 2 only.
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SUMMARY
OF ANALYSES-JET FORCES IMPACTING ON INTERNAL STRUCTURES Normal Operating Pressure Source Diameter Elevation Jet Travel (ft) Critical Target Jet Effect Remarks Psia.
- 15 28"I.D. 635'-0" 4.0 Containment 1020 d Wall
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 16.1 D. C. COOK NUCLEAR PLANT Table: 5.2-6 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 (Refer to Fig. 5.2.2-6)
SUMMARY
OF DYNAMIC MOTIONS O.B.E. D.B.E Relative Differential Of Horizontal Relative Differential Of Relative Differential Of Motion Relative Differential Of Horizontal Motion At Point Vertical Motion Vertical Motion X Direction Y Direction X Direction Y Direction A 0.185" 0.234" 0.227" 0.253" 0.374" 0.344" B 0.225" 0.234" 0.227" 0.321" 0.374" 0.344" C 0.097" 0.149" 0.149" 0.187 0.322" 0.289" D 0.041" 0.180" 0.173" 0.071" 0.360" 0.330" Betw. Aux. Bldg. &
0.094" 0.180" 0.173" 0.176" 0.360" 0.330" Turbine Bldg. E Betw. Aux. Bldg. &
0.136" 0.169" 0.162" 0.276" 0.362" 0.299" Diesel Bldg. E Betw. Diesel Bldg. &
0.094" 0.149" 0.149" 0.182" 0.322" 0.289" Turbine Bldg. E
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17 D. C. COOK NUCLEAR PLANT Table: 5.2-7 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 DYNAMIC ROTATIONS O.B.E. D.B.E.
Structure X Earthquake Y Earthquake X Earthquake Y Earthquake Containment 17.6 (10-5) Radians 17.6 (10-5) Radians 22.7 (10-5) Radians 22.7 (10-5) Radians Aux. Building 3.05 (10-5) Radians 1.43 (10-5) Radians 6.10 (10-5) Radians 2.81 (10-5) Radians Turbine Building 0.2 (10-5) Radians 1.91 (10-5) Radians 0.31 (10-5) Radians 3.03 (10-5) Radians Diesel Building 3.78 (10-5) Radians 8.0 (10-5) Radians 8.85 (10-5) Radians 15.1 (10-5) Radians (Switchgear)
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.1 D. C. COOK NUCLEAR PLANT Table: 5.2-8 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1 CONTAINMENT INTERNAL STRUCTURAL ELEMENT DESIGN PRESSURES TMD ANALYSIS (SECTION STRUCTURAL ELEMENT DESIGN 14.3.4.2)
PRESSURE CAPABILITY SUBCOMPARTMENT NODES Unit 1 Elevation 640 slab (upward pressure) Fan/Accumulator 27-42 17.19 psid 1 Unit 1 Elevation 640 slab (downward pressure) Loop 40-27 10.5 psid 1 Unit 2 Elevation 640 slab (upward pressure) Fan/Accumulator 27-42 16.02 psid 1 Unit 2 Elevation 640 slab (downward pressure) Loop 40-27 10.4 psid 1 Unit 1 Azimuth 54 wall (CEQ Fan Room Wall) Fan/Accumulator 57-25 14.99 psid 1 Unit 1 Azimuth 126 wall (CEQ Fan Room Wall) Fan/Accumulator 57-25 13.42 psid 1 Unit 1 Azimuth 234 wall (Non-Divider Barrier) Fan/Accumulator 27-29 15.60 psid 1 Unit 1 Azimuth 307 wall (Non-Divider Barrier) Fan/Accumulator 27-29 24.91 psid 1 Unit 2 Azimuth 54 wall (CEQ Fan Room Wall) Fan/Accumulator 57-25 15.16 psid 1 Unit 2 Azimuth 126 wall (CEQ Fan Room Wall) Fan/Accumulator 57-25 15.27 psid 1 Unit 2 Azimuth 234 wall (Non-Divider Barrier) Fan/Accumulator 27-29 16.25 psid 1 Unit 2 Azimuth 307 wall (Non-Divider Barrier) Fan/Accumulator 27-29 27.24 psid 1 Unit 1 & 2 Steam Generator Enclosure (uniform) N/A N/A 35.1 psi 1 Unit 1 & 2 Steam Generator Enclosure (stratified) Steam Generator 55-25 50.3 psid 1 Unit 1 & 2 Operating Deck Loop 1-25, 6-25 20.2 psid 1 Upper Crane Wall (above 640 slab) Loop 7,8,9 - 25 11.8 psid 1 Lower Crane Wall (below 640 slab) Loop 1-25, 6-25 20.2 psid 1 Upper Reactor Cavity (Primary Shield Wall) Reactor Cavity 38-51 72.4 psid 1 Lower Reactor Cavity Reactor Cavity 2 20.8 psig Ice Condenser End Wall at Lower Plenum Loop 40-25 14.8 psid 1 Ice Condenser End Wall for Lower 16 Feet of Ice Bed Loop 7-25 11.8 psid 1 Ice Condenser End Wall for Middle 16 Feet of Ice Bed Loop 8-25 9.2 psid 1 Ice Condenser End Wall for Top 16 Feet of Ice Bed Loop 9-25 7.4 psid 1 Reactor Missile Shield & Vertical Bulkhead Reactor Cavity 38-59 53.9 psid 1 Pressurizer Enclosure Pressurizer 46-25 80 psid 2 Reactor Cavity Reactor Vessel Annulus Reactor Cavity 1-3 1000 psid 2 RCS Loop Piping Annulus Through Primary Shield Reactor Cavity 1-46 2000 psid 2 Wall 1
Equivalent Design Pressure Capability Determined During 2001 Re-Analysis (The capabilities given in this Table represent the relative equivalent pressure capacities for the currently calculated accident pressures as given in Unit 1 UFSAR Section 14.3.4.2, when factored per the requirements of UFSAR Section 5.2 2
Design Pressure Capability Determined During Initial Plant Licensing
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17 D. C. COOK NUCLEAR PLANT Table: 5.3.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2 ICE CONDENSER DESIGN PARAMETERS Reactor Containment Volume (net free volume)
Upper Compartment, ft3 745,896 Ice Condenser, ft3 126,940 Lower Compartment (active), ft 3 306,800 Total Active Volume, ft3 1,179,636 Lower Compartment (dead-ended), ft 3 61,702 Total Containment volume, ft3 1,241,338 Reactor Containment Air Compression Ratio 1 1.41 Reactor power, MWt (design basis) 3391 Design Energy Release to Containment Initial blowdown mass release, lb 549,000 Initial blowdown energy release, Btu 346.7 x 106 Allowance for undefined energy release in addition to core residual heat, Btu 50 x 106 Ice Condenser parameters Required weight of ice in condenser, lb REFER TO TECHNICAL SPECIFICATIONS Dimensions of ice condenser O.D., ft 115 I.D., ft. 89 Average Arc length, ft 267 Width (less insulation panels), ft 11 Ice bed height, ft 48 Inlet door flow area, ft2 1000 Ice condenser flow area, ft2 1326 Ice Condenser inlet door opening pressure, lb/ft2 1/2 to 1.0 Ice boron concentration, ppm boron 1800-2300 Refrigeration cooling capacity (current as of 1/82) 1 Defined in Section 14.3.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17 D. C. COOK NUCLEAR PLANT Table: 5.3.2-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2 ICE CONDENSER DESIGN PARAMETERS Installed cooling capacity for compartment, Tons 75 Maximum compartment heat input, Tons (per unit) 35 Total cooling capacity for plant, Tons (capacity shared by two units) 250
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Load Elastic Analysis Limit Analysis Test Combination Mechanical(3) Mechanical & Thermal Fatigue (Load Factors)(2) (Load Factors)
D + OBE S(44) 3S AISC-69 1.7 1.87 Part I D + DBA 1.33 S N/A N/A 1.3 1.43 D + DBE 1.33 S N/A N/A 1.3 1.43 D + DBE + 1.65 S N/A N/A 1.18 1.3 DBA 1
For particular components that do not meet these limits specific justification shall be provided on a case by case basis.
2 For mechanical loads only. Mechanical plus thermal expansion, combination and fatigue shall satisfy the elastic analysis limits.
3 Membrane (direct) stresses shall be less than or equal to 0.7 Su (70% of ultimate stress).
4 S = Allowable stresses as defined in Sections 1.5 and 1.6 of the AISC-69 Part I Specification.
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SUMMARY
OF RESULTS FOR WEAR SLAB STRUCTURAL ANALYSIS Stress Loading Condition Stress Ratio1 Basis Wear Slab Bending -
D+ DBE+DBA 1.0 A Tension on Top Wear Slab Bending -
Defrost 1.0 A Tension on Bottom Shear on Bottom Plate Shear Defrost 1.0 B Connections Tie-Down Bolt Tension D+DBE+DBA 1.0 B Shear in Grout at D+DBE+DBA 1.0 A Tie-Down Bolts Pipe Stress Due to Defrost 1.0 B Slab Loading Compression of Foam D+DBE+DBA 1.0 C Concrete NOTES:
A. Allowable stress per ACI 318-71 B. Allowable stress per AISC-69 C. Vendor Qualification Test 1
Max Calculated Stress Code Allowable Stress
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SUMMARY
OF RESULTS FOR WALL PANELS1 Item Stress Ratio2 Basis Maximum general membrane 1.0 Allowable from Section 5.3.4.3.2 stress Maximum local membrane stress 1.0 Allowable from Section 5.3.4.3.2 Load on Each Leg of Corrugated 1.0 Critical load by Formula of Reference 5 Core 1
For conservatism, a DBA pressure of 21.7 psig was used in the analysis. The DBA pressure of 21.7 psig includes a 20% margin. The dynamic load factor (DLF) is 1.53.
2 Max. Calculated Stress Code Allowable Stress
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SUMMARY
OF RESULTS FOR WALL PANEL TRANSVERSE BEAM STRESS Loading Conditions D + OBE D + DBE D + DBE + DBA Allowable Stress l.0S 1.33S 1.65S Criteria, Section 5.3.4.3.2 Bending Allowable Stress (Psi) 33,000 43,890 54,450 1.00 Combined Stress Ratio1 1.00 1.00 1
Max. Calculated Stress Code Allowable Stress
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SUMMARY
OF STRESS RESULTS FOR LATTICE FRAME D + OBE D + DBA D + DBE D + DBA + DBE Criteria S per AISC-69 1.33S 1.33S 1.65S Bending Allowable Stress(psi) 37,5001 49,875(1) 49,875(1) 68,0602 Combined Stress Ratio 3 1.00 1.00 1.00 1.00 1
ASTM-A441 with minimum yield strength = 50 K/in2 2
ASTM-A441 with actual yield strength = 55 K/in2 3
Max. Calculated Stress Code Allowable
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SUMMARY
OF RESULTS OF FATIGUE ANALYSIS FOR LATTICE FRAME 1 Member Type Stress Ratio2 Allowable Stress range 3,psi Radial Stringers 1.0 60,000 Fillet Welds 1.0 22,500 1
Based on 400 OBE cycles 2
Max. Calculated Stress Code Allowable Stress 3
AISC-69 specification, Appendix B
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SUMMARY
OF RESULTS FOR MEMBER STRESSES IN LOWER SUPPORT STRUCTURE COMPARED TO DESIGN ALLOWABLE MEMBER STRESSES DESCRIPTION MAXIMUM STRESSES MAXIMUM STRESSES REMARKS 1
D+DBE+DBA D+OBE 2 allowable Stress allowable Stress allowable Stress allowable Stress ksi Ratio ksi Ratio ksi Ratio ksi Ratio 3 (3) (3) (3)
Columns Line 1 - 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Inner Columns Line 1 - 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Middle Columns Line 1 - 40.5 .1.0 23.4 .1.0 27.0 .1.0 18.0 .1.0 Outer Columns Line 2 - 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Inner Columns Line 2 - 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Middle Columns Line 2 - 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Outer Circumferential 40.5 1.0 26.6 1.0 27.0 1.0 18.0 1.0 BEAMS - Inner Circumferential 40.5 1.0 26.6 1.0 27.0 1.0 18.0 1.0 Beams - Middle Circumferential 40.5 1.0 26.6 1.0 27.0 1.0 18.0 1.0 Beams - Outer Radial Beam 1 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 2 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 3 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 4 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 5 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 6 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 7 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Radial Beam 8 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 1
Columns, Line 1 - Odd column lines starting at the end wall Columns, Line 2 - Even column lines starting at the end wall Radial Beams - numbers from column line 1 2
All Stresses Are Within Allowable Values 3
Max. Calculated Stress Code Allowable Stress
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SUMMARY
OF RESULTS FOR MEMBER STRESSES IN LOWER SUPPORT STRUCTURE COMPARED TO DESIGN ALLOWABLE MEMBER STRESSES DESCRIPTION MAXIMUM STRESSES MAXIMUM STRESSES REMARKS 1
D+DBE+DBA D+OBE 2 allowable Stress allowable Stress allowable Stress allowable Stress ksi Ratio ksi Ratio ksi Ratio ksi Ratio 3 (3) (3) (3)
Radial Beam 9 45.0 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Horizontal 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Bracing - Inner Platform Horizontal 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Bracing - Outer Platform Vertical Cross- 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Bracing Ice Basket Hold- 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Down Bars Turning Vane 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Assembly Mounting Plate -
Column 1 Turning Vane 40.5 1.0 23.4 1.0 27.0 1.0 18.0 1.0 Assembly Mounting Plate -
Column 2
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SUMMARY
OF RESULTS FOR LOWER PERSONNEL ACCESS DOOR ANALYSES DUE TO LOCA Item Load Stress Ratio1 Basis2 1 Shear stress of anchor rod 1.0 A 2 Shear stress of frame 1.0 A 3 Compressive stress of inner door panel 1.0 A Compressive stress of U channel (door panel 4 1.0 A bracing) 1.0 5 Compressive stress of wedges A 1
Max. Calculated Stress Code Allowable Stress 2
A - Allowable stress from Section 5.3.4.3.2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.2 D. C. COOK NUCLEAR PLANT Table: 5.3.5.9-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
SUMMARY
OF RESULTS FOR INLET DOOR STRUCTURAL ANALYSIS - LOCA STRESS ITEM AREA BASIS2 RATIO1 1 Bending of FRP Plate 1.0 D 2 Tension + Bending of Reinforcing Ribs 1.0 A 3 Slip of Plate/Rib Bolts 1.0 C 4 Compression + Bending of Compr. Sleeves 1.0 A 5 Bearing in Fiber Reinforced Plastic (FRP) Plate at Bolts 1.0 D 6 Pullout of Bolts from FRP Plate 1.0 D 7 Crushing of Foam Insulation 1.0 E 8 Shear of Foam Insulation 1.0 E 9 Tension in Hinge Adapter 1.0 A 10 Shear in Adapter/Rib Weld 1.0 A 11 Bending + Shear of Hinge Bar 1.0 A 12 Bearing Loads in Hinge Bearing 1.0 B 13 Bending + Shear + Torsion of Hinge Bracket 1.0 A 14 Tension in Bearing Housing 1.0 A 15 Unloading of Bracket/Frame Bolts 1.0 C 16 Bending of Door Frame 1.0 A 17 Pullout of 1 Anchor Bolts 1.0 E 18 Bending of Tie Bars 1.0 G 19 Extension of Proportioning Springs 1.0 F 20 Bending of Spring Housing Supports 1.0 A 21 Tension of Tie Bar Bolts 1.0 G 22 Bending of Frame Center Beam 1.0 A 23 Shear of Center Beam Connecting Bolts 1.0 A 24 Shear of Center Beam 1/2 Anchor Bolts 1.0 E 1
Max. Calculated Stress Code Allowable Stress 2
Bases a). Allowable value per AISC-69 limits.
b). Anti-Friction Bearing Manufacturers Association (AFBMA) Basic Dynamic Capacity.
c). Side load to overcome pre-tensioning.
d). Design load per manufacturers recommendations.
e). Strength values per manufacturers literature.
f). Stress to permanent set.
g). Allowable stress from Section 5.3.4.3.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.2 D. C. COOK NUCLEAR PLANT Table:5.3.5.10-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
SUMMARY
OF RESULTS FOR TOP DECK DOOR STRUCTURAL ANALYSIS - LOCA Item Area Stress Ratio1 Basis2 1 Hinge band direct tension 1.0 B 2 Hinge bar - bending 1.0 A 3 Anchor bolts - tension 1.0 A 4 Floor grating - bending 1.0 C 5 Insulation tip stress - tear 1.0 C 6 Insulation tip stress - tensile 1.0 C 1
Max Calculated Stress Code Allowable Stress 2
Basis A. Allowable value per Section 5.3.4.3.2 B. ASTM-177 minimum tensile with AISC allowable C. Strength values per Manufacturer's literature
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.2 D. C. COOK NUCLEAR PLANT Table:5.3.5.10-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
SUMMARY
OF RESULTS FOR TOP DECK STRUCTURE (STRESS LEVELS WITHIN THE ICE CONDENSER)
Description Of Member Load Combination Allowable Stress Ratio1 Stress (ksi)
Radial Beam Blowdown 36.0 1.0 Pressure (DL + DBA)
Radial Beam Service Load 27.0 1.0 (DL+OBE)
Radial Beam Service Load 81.0 1.0 (DL+Thermal Load+OBE)
Radial Beam Design Load 36.0 1.0 (DL+DBE)
Radial Beam Design Load 45.0 1.0 (DL+DBA+DBE)
Crane Rails DL+LL 21.6 1.0 Crane Rails DL+LL+Thermal 21.6 1.0 Circumferential Struts DL+LL+Thermal 21.6 1.0 (A-36 steel)
Circumferential Struts DBA + DL 21.6 1.0 Circumferential Struts DL+OBE 21.6 1.0 Circumferential Struts DL+TH+OBE 21.6 1.0 Circumferential Struts DL+DBE 21.6 1.0 Circumferential Struts DL+DBA+DBE 21.6 1.0 Radial Beam2 Service Load 27.0 1.0 (Dead Load+OBE)
Radial Beam(2) Design Load 36.0 1.0 (Dead Load+DBE) 1 Max Calculated Stress Code Allowable Stress 2
Stress levels outside the ice condenser - crane mass located outside ice condenser compartment
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.2 D. C. COOK NUCLEAR PLANT Table:5.3.5.10-3 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
SUMMARY
OF RESULTS FOR INTERMEDIATE DECK AND DOOR ASSEMBLY STRUCTURAL ANALYSIS - LOCA Item Area Stress Ratio1 Basis2 1 Bending of main support beams 1.0 A 2 Tension and bending hinge arm 1.0 A 3 Bending and shear of hinge pin 1.0 A 4 Hinge bracket bolts - tension 1.0 A 5 Hinge arm - tension across hole 1.0 A 6 Shear, hinge arm to box beam 1.0 A 7 Box beam bending 1.0 A 8 Shear of foam insulation 1.0 B 9 Skin plug welds - shear 1.0 A 10 Bending - door frame angles 1.0 A 11 Bending - door frame tie beam 1.0 A 1
Max. Calculated Stress Code Allowable Stress 2
Basis A. Allowable value per Section 5.3.4.3.2 B. Strength values per manufacturer's literature
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 17.2 D. C. COOK NUCLEAR PLANT Table:5.3.5.12-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1
SUMMARY
OF RESULTS FOR AIR HANDLING UNIT SUPPORT BEAMS (A500 GR B STEEL)
Load Allowable Stress Ratio1 Combination Stress, ksi DBA + DL 27.6 1.0 DL+OBE 27.6 1.0 DL+TH+OBE 27.6 1.0 DL+DBE 27.6 1.0 DL+DBA+DBE 27.6 1.0 1
Max.Calculated Stress Code Allowable Stress
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-1 G Blind Flange N/A 1 Fuel Transfer Tube 20 N/A CPN-2 F N/A 2 N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-3 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-4 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-5 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-6 F N/A (2) N/A (2) Steam Generator No.1 Blowdown Outlet 2 N/A CPN-7 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-8 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-9 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-10 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-11 D Closed System CS-442-1 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-12 D Closed System CS-442-2 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-13 D Closed System CS-442-3 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-14 D Closed System CS-442-4 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-15 D Closed System SI-189 Check R.C. Relief Valve Vent Header 4 N/A CPN-16 D Closed System ICM-111 Residual Heat Removal Inlet to R.C. Cold Legs 12 N/A Remote Manual MOV CPN-16 D Closed System SV-102 Residual Heat Removal Inlet to R.C. Cold Legs 12 N/A CPN-17 A WCR-900 WCR-901 Non-Essential Service Water to Lower 6 10 Auto Trip AOV 3 Auto Trip AOV (3) Containment Ventilation Unit #1 1
Not required, 2 seals on inner flange per FSAR Q5.118.
2 Not Required, extension of Containment Liner per FSAR Appendix Q.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-18 A WCR-904 WCR-905 Non-Essential Service Water to Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #2 CPN-19 A WCR-908 WCR-909 Non-Essential Service Water to Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #3 CPN-20 A WCR-912 WCR-913 Non-Essential Service Water to the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #4 CPN-21 A WCR-902 WCR-903 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #1 CPN-22 A WCR-906 WCR-907 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #2 CPN-23 A WCR-910 WCR-911 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #3 CPN-24 A WCR-914 WCR-915 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #4 CPN-25 D Closed System CCM-431 Component Cooling Water from the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-25 D Closed System CCR-440 Component Cooling Water from the Main Steam 1.5 N/A Remote Manual AOV Penetrations.
CPN-25 D Closed System CCW-244-25 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations CPN-25 D Closed System CCW-243-25 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations 3
Exception in Class A piping functional class applies to this penetration.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 3 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-25 D Closed System CCM-430 Component Cooling Water to the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-26 A WCR-923 WCR-922 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #1 CPN-26 A WCR-955 WCR-945 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #1 Motor Air Cooler CPN-26 A WCR-920 WCR-921 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #1 CPN-26 A WCR-941 WCR-951 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #1 Motor Air Cooler CPN-27 A WCR-927 WCR-926 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #2 CPN-27 A WCR-956 WCR-946 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #2 Motor Air Cooler CPN-27 A WCR-924 WCR-925 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #2 CPN-27 A WCR-942 WCR-952 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #2 Motor Air Cooler CPN-28 Spare Welded Closed N/A Spare 18 in sleeve N/A CPN-29 A PA -343 PCR-40 Service Air 2 10 Check Valve MOV CPN-29 A XCR-103 XCR-102 Instrument Air 1 10 Auto Trip AOV Auto Trip AOV CPN-30 Spare Welded Cap N/A N/A N/A N/A
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 4 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-30 E NPX-151-V1 N/A Dead Weight Test Connection 0.5 N/A Manual CPN-31 A N-160 DCR-207 Nitrogen Supply to the Reactor Coolant Drain 1 10 Check Valve Auto Trip AOV Tank CPN-31 A DCR-201 DCR-203 Vents from the Reactor Coolant Drain Tank and 1 10 Auto Trip AOV Auto Trip AOV the Pressurizer Relief Tank CPN-31 A DCR-611 DCR-610 Drain from the Ice Condenser Vent 3 10 Auto Trip AOV Auto Trip AOV CPN-31 A DCR-621 DCR-620 Drain from the Containment Ventilation Units 1 10 Auto Trip AOV Auto Trip AOV CPN-31 A ECR-33 ECR-35 Containment Air Particulate and Noble Gas 1 10 Auto Trip AOV Auto Trip AOV Detector Sample Return CPN-32 A SI-171 or SI-172 SI-194 Safety Injection Test Line and Accumulator Test 0.75 N/A Manual Valves Manual Valve Line CPN-32 A N-102 GCR-314 Nitrogen Supply to the Accumulators 1 10 Check Valve Auto Test AOV CPN-32 A ECR-31 ECR-32 Sample Line to the Containment Air Particulate 1 10 Auto Trip AOV Auto Trip AOV and Noble Gas Detector CPN-32 A ECR-535 ECR-536 Sample Line to the Containment Air Particulate 0.5 10 Auto Trip AOV Auto Trip AOV and Radio Gas Detector -Lower Containment CPN-33 Spare Plugged N/A Spare N/A N/A CPN-33 A PW-275 NCR-252 Primary Water Supply to the Pressurizer Relief 3 10 Check Valve Auto Trip AOV Tank CPN-34 A QCR-301 QCR-300 Letdown Line (CVCS) 2 10 Auto Trip AOV Auto Trip AOV
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 5 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-35 D Closed System CS-321 Charging Line (CVCS) 3 N/A Check Valve CPN-36 A SF-153 SF-151 Refueling Water Supply to the Refueling Cavity 2.5 N/A Manual Valve Manual Valve CPN-36 A 1-QCR-920 1-QCR-919 Demineralized Water to the Refueling Cavity 2 10 Auto Trip AOV (3)
Auto Trip AOV (3)
CPN-37 A QCM-250 QCM-350 R.C. Pumps Seal Water & Excess Letdown Heat 4 15 Auto Trip MOV Auto Trip MOV Exchanger Discharges CPN-38 A CCM-459 CCM-458 R.C.Pump Motor and Thermal Barrier Cooling 8 60 Auto Trip MOV Auto Trip MOV Water Supply CPN-39 A CCM-451 Auto Trip CCM-452 Auto Trip R.C.Pump Motor and Thermal Barrier Cooling 8 60 MOV MOV Water Discharge CPN-40 A DCR-205 DCR-206 Reactor Coolant Drain Tank Pump Suction 4 10 Auto Trip AOV (3) Auto Trip AOV (3)
CPN-41 A DCR-600 DCR-601 Containment Sump Pump Discharge to Waste 3 10 Auto Trip AOV (3)
Auto Trip AOV (3) Disposal CPN-42 A SF-159 SF-160 Refueling Cavity Drain to Purification System 3 N/A Manual Valve Manual Valve CPN-43 D Closed System ICM-260 Safety Injection to the RCS Hot/Cold Legs 4 N/A Remote Manual MOV
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 6 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-44 D Closed System ICM-250 Boron Injection Inlet 3 N/A Remote Manual MOV or ICM-251 Remote Manual MOV CPN-45 D Closed System ICM-305 Residual Heat Removal Suction from Recirc 18 N/A Remote Manual MOV Sump CPN-46 D Closed System ICM-306 Residual Heat Removal Suction from Recirc 18 N/A Remote Manual MOV Sump CPN-47 D Closed System ICM-129 Residual Heat Removal Inlet to RHR Pumps 14 N/A Remote Manual MOV CPN-47 D Closed System SV-103 Residual Heat Removal Inlet to RHR Pumps 14 N/A Relief Valve CPN-48 D Closed System ICM-321 Residual Heat Removal to R.C. Hot Legs - Low 8 N/A Remote Manual MOV Head S.I.
CPN-49 D Closed System ICM-311 Residual Heat Removal to R.C. Hot Legs - Low 8 N/A Remote Manual MOV Head S.I.
CPN-50 D Closed System RH-142 RHR to Containment Spray 8 N/A Check Valve CPN-51 D Closed System RH-141 RHR to Containment Spray 8 N/A Check Valve CPN-52 D Closed System CTS-131W Upper Containment Spray Inlet 8 N/A Check Valve CPN-53 D Closed System CTS-131E Upper Containment Spray Inlet 8 N/A Check Valve
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 7 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-54 D Closed System CTS-127W Lower Containment Spray Inlet 6 N/A Check Valve CPN-55 D Closed System CTS-127E Check Lower Containment Spray Inlet 6 N/A Valve CPN-56 A VCR-21 VCR-20 Glycol to Ice Condenser Fan Coolers 3 10 Auto Trip AOV or Auto Trip AOV R157 Check Valve CPN-57 G Blind Flange Blind Flange Ice Loading Line 4 N/A CPN-58 A CCM-453 CCM-454 Reactor Coolant Pump Thermal Barrier Cooling 4 30 Auto Trip MOV Auto Trip MOV Water Discharge CPN-59 A VCR-105 VCR-205 Upper Containment Purge Air Inlet 30 5 Auto Trip AOV Auto Trip AOV CPN-60 A VCR-106 VCR-206 Upper Containment Purge Air Outlet 24 5 Auto Trip AOV Auto Trip AOV CPN-61 A VCR-101 VCR-201 Purge Air Inlet (Instrumentation Room) 14 5 Auto Trip AOV Auto Trip AOV CPN-62 A VCR-102 VCR-202 Purge Air Outlet (Instrumentation Room) 14 5 Auto Trip AOV Auto Trip AOV CPN-63 A VCR-104 VCR-204 Lower Containment Purge Air Outlet 30 5 Auto Trip AOV Auto Trip AOV CPN-64 A VCR-103 VCR-203 Lower Containment Purge Air Inlet 24 5 Auto Trip AOV Auto Trip AOV CPN-65 A VCR-107 VCR-207 Upper Containment Pressure Relief Line 12 5 Auto Trip AOV Auto Trip AOV
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 8 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-66 A NCR-105 NCR-106 Sample Line from the RCS Hot Legs 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 A NCR-107 NCR-108 Sample Line from the Pressurizer Liquid Space 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 A NCR-109 NCR-110 Sample Line from the Pressurizer Steam Space 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 F N/A (2) N/A (2) Steam Generator #1 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #2 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #3 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #4 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #1 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #2 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #3 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #4 Steam Space Steam Sample 0.5 N/A CPN-67 A ECR-416 ECR-417 Post Accident Sampling System 0.5 10 Auto Trip AOV Auto Trip AOV CPN-67 A NS - 357 ECR-496 or ECR-497 Post Accident Sampling System Return 0.5 10 Check Valve Auto Trip AOV CPN-68 D Closed System ICM-265 Safety Injection to the RCS Hot/ColdLegs 4 N/A Remote Manual MOV CPN-69 Spare Welded Closed N/A Spare 18 in sleeve N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 9 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 A SM-1 ECR-36 Radiation Monitor ERS-2400 Isolation Valve 1 10 Check Valve Auto Trip AOV CPN-71 G Blind Flange Hinged Flange Containment Service Penetration 18 N/A CPN-72 D Closed System CCM-433 Component Cooling Water from the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-72 D Closed System CCR-441 Component Cooling Water from the Main Steam 2 N/A Remote Manual MOV Penetrations.
CPN-72 D Closed System CCW-244-72 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations CPN-72 D Closed System CCW-243-72 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations CPN-72 D Closed System CCM-432 Component Cooling Water to the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-73 A WCR-960 WCR-961 Non-Essential Service Water to the Instrument 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Room Ventilation Unit E CPN-73 A WCR-962 WCR-963 Non-Essential Service Water from the 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Instrument Room Ventilation Unit E CPN-73 A WCR-964 WCR-965 Non-Essential Service Water to the Instrument 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Room Ventilation Unit W CPN-73 A WCR-966 WCR-967 Non-Essential Service Water from the 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Instrument Room Ventilation Unit W
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 10 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-74 A XCR-100 XCR-101 Instrument Air 1 10 Auto Trip AOV Auto Trip AOV CPN-74 A N-159 GCR-301 Nitrogen Supply to the Pressurizer Relief Tank 0.75 10 Check Valve Auto Trip AOV CPN-75 C Closed System CCR-460 Excess Letdown Heat Exchanger Component 4 10 Auto Trip AOV Cooling Water Outlet CPN-75 C Closed System CCR - 462 Auto Trip Excess Letdown Heat Exchanger Component 4 10 AOV Cooling Water Inlet CPN-76 G Blind Flange Blind Flange Incore Flux Detection System 8 N/A CPN-77 F N/A (2) N/A (2) Steam Generator No.2 Blowdown Outlet 2 N/A CPN-78 F N/A (2) N/A (2) Steam Generator No.3 Blowdown Outlet 2 N/A CPN-79 F N/A (2) N/A (2)- Steam Generator No.4 Blowdown Outlet 2 N/A CPN-80 G Blind Flange Blind Flange Ice Loading Return 5 N/A CPN-81 A RCR-100 RCR-101 Sample Line from the Pressurizer Relief Tank to 0.5 10 Auto Trip AOV Auto Trip AOV the Gas Analyzer CPN-81 A DCR-202 DCR-204 Sample Line from the Reactor Coolant Drain 0.5 10 Auto Trip AOV Auto Trip AOV Tank to the Gas Analyzer CPN-81 A ICR-5 ICR-6 Sample Line from the Accumulators 0.5 10 Auto Trip AOV Auto Trip AOV CPN-82 A CCR-456 CCR-457 Reactor Support Cooling Water Outlet 2.5 10 Auto Trip AOV Auto Trip AOV CPN-82 A CCW-135 CCR-455 Reactor Support Cooling Water Inlet 2.5 10 Check Valve Auto Trip AOV CPN-83 G Hinged Flange Hinged Flange Containment Service Penetration N/A N/A
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 11 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-84 A WCR-954 WCR-944 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #4 Motor Air Cooler CPN-84 A WCR-948 WCR-958 Auto Trip Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV (3) AOV (3) Coolant Pump #4 Motor Air Cooler CPN-84 A WCR-933 WCR-932 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #4 CPN-84 A WCR-934 WCR-935 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #4 CPN-85 A WCR-953 WCR-943 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #3 Motor Air Cooler CPN-85 A WCR-947 WCR-957 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Coolant Pump #3 Motor Air Cooler CPN-85 A WCR-929 WCR-928 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #3 CPN-85 A WCR-930 WCR-931 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #3 CPN-86 A VCR-11 VCR-10 Glycol Supply from Ice Condenser Fan Coolers 3 10 Auto Trip AOV or Auto Trip AOV R156 Check Valve CPN-87 Spare Welded Closed N/A Spare 6 in sleeve N/A CPN-88 Spare Welded Closed N/A Spare 6 in sleeve N/A CPN-89 A SM-8 SM-10 Upper Containment Radiation Sampling System 0.5 N/A Manual Valve Manual Valve CPN-90 Spare Welded Closed N/A Spare 6 in sleeve N/A
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 12 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-91 E Membrane (Sensor HI 4 Reactor Vessel Level Instrumentation System 1- 0.5 N/A Bellows) NLS-111 CPN-91 E Membrane (Sensor HI (4) Reactor Vessel Level Instrumentation System 1- 0.5 N/A Bellows) NLS-121 CPN-91 E Membrane (Sensor HI (4) Reactor Vessel Level Instrumentation System 1- 0.5 N/A Bellows) NLS-131 CPN-91 E PPP-302-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-91 Spare Welded Closed N/A Spare 0.5 N/A CPN-91 Spare Welded Closed N/A Spare 0.5 N/A CPN-92 E PPP-301-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-92 A SM-6 SM-4 Instrument Room Air Sample Piping 0.5 N/A Manual Valve Manual Valve CPN-93 A ECR-14 ECR-24 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 4 CPN-93 A ECR-16 ECR-26 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 6 CPN-93 A ECR-17 ECR-27 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 7 CPN-93 A ECR-18 ECR-28 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 8 4
Hydraulically Isolated (HI)
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 13 of 27 UNIT 1 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-93 A ECR-19 ECR-29 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 9 CPN-94 E PPP-300-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-94 E Membrane (Sensor HI (4) Reactor Vessel Level Instrumentation System 1- 0.5 N/A Bellows) NLS-120 CPN-95 A ECR-11 ECR-21 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 1 CPN-95 A ECR-12 ECR-22 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 2 CPN-95 A ECR-13 ECR-23 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 3 CPN-95 A ECR-15 ECR-25 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 5 CPN-95 A ECR-10 NS-283 Check Valve Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Hydrogen Sample Return or ECR-20 Auto Trip AOV CPN-96 E PPP-303-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-96 E PPX-301-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-97 E PPA-310-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve
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Number CPN-97 E Membrane HI (4) Reactor Vessel Level Instrumentation System 0.5 N/A (Sensor Bellows) 1-NLS-130 CPN-98 E PPA-312-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-98 E Membrane HI (4) Reactor Vessel Level Instrumentation System 0.5 N/A (Sensor Bellows) 1-NLS-110
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 15 of 27 UNIT 2 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-1 G Blind Flange N/A (1) Fuel Transfer Tube 20 N/A CPN-2 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-3 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-4 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-5 F N/A (2) N/A (2) Steam Generator Main Steam Outlet 30 N/A CPN-6 F N/A (2) N/A (2) Steam Generator No.1 Blowdown Outlet 2 N/A CPN-7 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-8 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-9 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-10 F N/A (2) N/A (2) Steam Generator Feedwater Inlet 14 N/A CPN-11 D Closed System CS-442-1 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-12 D Closed System CS-442-2 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-13 D Closed System CS-442-3 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-14 D Closed System CS-442-4 Check Reactor Coolant Pump Seal Water Supply 2 N/A CPN-15 D Closed System SI-189 Check R.C.Relief Valve Vent Header 4 N/A CPN-16 D Closed System ICM-111 Remote Residual Heat Removal Inlet to R.C. Cold Legs 12 N/A Manual MOV CPN-16 D Closed System SV-102 Residual Heat Removal Inlet to R.C. Cold Legs 12 N/A CPN-17 A WCR-901 WCR-900 AutoTrip Non-Essential Service Water to Lower 6 10 Auto Trip AOV (3) AOV (3) Containment Ventilation Unit #1 CPN-18 A WCR-905 WCR-904 Auto Trip Non-Essential Service Water to Lower 6 10 Auto Trip AOV (3) AOV (3) Containment Ventilation Unit #2
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Number CPN-19 A WCR-909 WCR-908 Auto Trip Non-Essential Service Water to Lower 6 10 Auto Trip AOV (3) AOV (3) Containment Ventilation Unit #3 CPN-20 A WCR-913 WCR-912 Auto Trip Non-Essential Service Water to the Lower 6 10 Auto Trip AOV (3) AOV (3) Containment Ventilation Unit #4 CPN-21 A WCR-902 WCR-903 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #1 CPN-22 A WCR-906 WCR-907 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #2 CPN-23 A WCR-910 WCR-911 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #3 CPN-24 A WCR-914 WCR-915 Non-Essential Service Water from the Lower 6 10 Auto Trip AOV (3) Auto Trip AOV (3) Containment Ventilation Unit #4 CPN-25 D Closed System CCM-431 Remote Component Cooling Water from the Pressure 1.5 N/A Manual MOV Equalizing Fans CPN-25 D Closed System CCR-440 Remote Component Cooling Water from the Main Steam 1.5 N/A Manual AOV Penetrations.
CPN-25 D Closed System CCW-244-25 Check Component Cooling Water to the Main Steam 1 N/A Valve Penetrations CPN-25 D Closed System CCW-243-25 Check Component Cooling Water to the Main Steam 1 N/A Valve Penetrations CPN-25 D Closed System CCM-430 Remote Component Cooling Water to the Pressure 1.5 N/A Manual MOV Equalizing Fans CPN-26 A WCR-922 WCR-923 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #1
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Number CPN-26 A WCR-945 WCR-955 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #1 Motor Air Cooler CPN-26 A WCR-921 WCR-920 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #1 CPN-26 A WCR-951 WCR-941 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #1 Motor Air Cooler CPN-27 A WCR-926 WCR-927 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #2 CPN-27 A WCR-946 WCR-956 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #2 Motor Air Cooler CPN-27 A WCR-925 WCR-924 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #2 CPN-27 A WCR-952 WCR-942 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #2 Motor Air Cooler CPN-28 Spare Welded Closed N/A Spare 18 in sleeve N/A CPN-29 A PA-342 PCR-40 Service Air 2 10 Check Valve Auto Trip AOV CPN-29 A XCR-102 XCR-103 Instrument Air 1 10 Auto Trip AOV Auto Trip AOV CPN-30 Spare Welded Cap N/A N/A N/A N/A CPN-30 E NPX-151-V1 N/A Dead Weight Test Connection 0.5 N/A Manual CPN-31 A DCR-207 N-160 Nitrogen Supply to the Reactor Coolant Drain 1 10 Auto Trip AOV Check Valve Tank
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Number CPN-31 A DCR-201 DCR-203 Vents from the Reactor Coolant Drain Tank and 1 10 Auto Trip AOV Auto Trip AOV the Pressurizer Relief Tank CPN-31 A DCR-610 DCR-611 Drain from the Ice Condenser Vent 3 10 Auto Trip AOV Auto Trip AOV CPN-31 A DCR-620 DCR-621 Drain from the Containment Ventilation Units 1 10 Auto Trip AOV Auto Trip AOV CPN-31 A ECR-33 ECR-35 Containment Air Particulate and Radio Gas 1 10 Auto Trip AOV Auto Trip AOV Detector Sample Return CPN-32 A SI-171 or SI-172 SI-194 Safety Injection Test Line and Accumulator Test 0.75 N/A Manual Valves Manual Valve Line CPN-32 A N-102 GCR-314 Nitrogen Supply to the Accumulators 1 10 Check Valve Auto Test AOV CPN-32 A ECR-31 ECR-32 Sample Line to the Containment Air Particulate 1 10 Auto Trip AOV Auto Trip AOV and Radio Gas Detector CPN-32 A ECR-535 ECR-536 Sample Line to the Containment Air Particulate 0.5 10 Auto Trip AOV Auto Trip AOV and Radio Gas Detector -Lower Containment CPN-33 Spare N/A N/A N/A N/A N/A CPN-33 A PW-275 NCR-252 Primary Water Supply to the Pressurizer Relief 3 10 Check Valve Auto Trip AOV Tank CPN-34 A QCR-301 QCR-300 Letdown Line (CVCS) 2 10 Auto Trip AOV Auto Trip AOV CPN-35 D Closed System CS-321 Charging Line (CVCS) 3 N/A Check Valve CPN-36 A 2S-152 2SF-154 Manual Valve Refueling Water Supply to the Refueling Cavity 2.5 N/A Manual Valve
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Number CPN-36 A QCR-919 QCR-920 Demineralized Water to the Refueling Cavity 2 10 Auto Trip AOV (3) Auto Trip AOV (3)
CPN-37 A QCM-250 QCM-350 R.C. Pumps Seal Water & Excess Letdown Heat 4 15 Auto Trip MOV Auto Trip MOV Exchanger Discharges CPN-38 A CCM-458 CCM-459 R.C.Pump Motor and Thermal Barrier Cooling 8 60 Auto Trip MOV Auto Trip MOV Water Supply CPN-39 A CCM-451 CCM-452 R.C.Pump Motor and Thermal Barrier Cooling 8 60 Auto Trip MOV Auto Trip MOV Water Discharge CPN-40 A DCR-205 DCR-206 Reactor Coolant Drain Tank Pump Suction 4 10 Auto Trip AOV (3) Auto Trip AOV (3)
CPN-41 A DCR-600 DCR-601 Containment Sump Pump Discharge to Waste 3 10 Auto Trip AOV Auto Trip AOV Disposal CPN-42 A SF-159 SF-160 Refueling Cavity Drain to Purification System 3 N/A Manual Valve Manual Valve CPN-43 D Closed System ICM-265 Remote Safety Injection to the RCS Hot/Cold Legs 4 N/A Manual MOV CPN-44 D Closed System ICM-250 Boron Injection Inlet 3 N/A Remote Manual MOV or ICM - 251 Remote Manual MOV CPN-45 D Closed System ICM-305 Remote Residual Heat Removal Suction from Recirc 18 N/A Manual MOV Sump CPN-46 D Closed System ICM-306 Residual Heat Removal Suction from Recirc 18 N/A Remote Manual MOV Sump
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 20 of 27 UNIT 2 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-47 D Closed System ICM-129 Residual Heat Removal Inlet to RHR Pumps 14 N/A Remote Manual MOV CPN-47 D Closed System SV-103 Residual Heat Removal Inlet to RHR Pumps 14 N/A Relief Valve CPN-48 D Closed System ICM-321 Residual Heat Removal to R.C. Hot Legs - Low 8 N/A Remote Manual MOV Head S.I.
CPN-49 D Closed System ICM-311 Residual Heat Removal to R.C. Hot Legs - Low 8 N/A Remote Manual MOV Head S.I.
CPN-50 D Closed System RH-142 RHR to Containment Spray 8 N/A Check Valve CPN-51 D Closed System RH-141 RHR to Containment Spray 8 N/A Check Valve CPN-52 D Closed System CTS-131W Upper Containment Spray Inlet 8 N/A Check Valve CPN-53 D Closed System CTS-131E Upper Containment Spray Inlet 8 N/A Check Valve CPN-54 D Closed System CTS-127W Lower Containment Spray Inlet 6 N/A Check Valve CPN-55 D Closed System CTS-127E Lower Containment Spray Inlet 6 N/A Check Valve CPN-56 A R157 Check Valve VCR-20 Glycol to Ice Condenser Fan Coolers 3 10 or VCR-21 Auto Trip AOV Auto Trip AOV CPN-57 G Blind Flange Blind Flange Ice Loading Line 4 N/A
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Number CPN-58 A CCM-453 CCM-454 Reactor Coolant Pump Thermal Barrier Cooling 4 30 Auto Trip MOV Auto Trip MOV Water Discharge CPN-59 A VCR-105 VCR-205 Upper Containment Purge Air Inlet 30 5 Auto Trip AOV Auto Trip AOV CPN-60 A VCR-106 VCR-206 Upper Containment Purge Air Outlet 24 5 Auto Trip AOV Auto Trip AOV CPN-61 A VCR-101 VCR-201 Purge Air Inlet (Instrumentation Room) 14 5 Auto Trip AOV Auto Trip AOV CPN-62 A VCR-102 VCR-202 Purge Air Outlet (Instrumentation Room) 14 5 Auto Trip AOV Auto Trip AOV CPN-63 A VCR-104 VCR-204 Lower Containment Purge Air Outlet 30 5 Auto Trip AOV Auto Trip AOV CPN-64 A VCR-103 VCR-203 Lower Containment Purge Air Inlet 24 5 Auto Trip AOV Auto Trip AOV CPN-65 A VCR-107 VCR-207 Upper Containment Pressure Relief Line 12 5 Auto Trip AOV Auto Trip AOV CPN-66 A NCR-105 NCR-106 Sample Line from the RCS Hot Legs 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 A NCR-107 NCR-108 Sample Line from the Pressurizer Liquid Space 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 A NCR-109 NCR-110 Sample Line from the Pressurizer Steam Space 0.5 10 Auto Trip AOV Auto Trip AOV CPN-66 F N/A (2) N/A (2) Steam Generator #1 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #2 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #3 Blowdown Sample 0.5 N/A
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Number CPN-66 F N/A (2) N/A (2) Steam Generator #4 Blowdown Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #1 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #2 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #3 Steam Space Steam Sample 0.5 N/A CPN-66 F N/A (2) N/A (2) Steam Generator #4 Steam Space Steam Sample 0.5 N/A CPN-67 A ECR-416 ECR-417 Containment Sump Sample 0.5 10 Auto Trip AOV Auto Trip AOV CPN-67 A ECR-496 NS-357 Post Accident Sampling System Return 0.5 10 Auto Trip AOV Check Valve or ECR-497 Auto Trip AOV CPN-67 G Blind Flange Blind Flange For Maintenance to the Containment Annulus 2 N/A for Outage CPN-68 D Closed System ICM-260 Safety Injection to the RCS Hot/Cold Legs 4 N/A Remote Manual MOV CPN-69 Spare Welded Closed N/A Spare 18 in sleeve N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 Spare Welded Closed N/A Spare 1 N/A CPN-70 A SM-1 ECR-36 Radiation Monitor ERS-2400 Isolation Valve 1 10 Check Valve Auto Trip AOV CPN-71 G Blind Flange Blind Flange Containment Service Penetration 18 N/A
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Number CPN-72 D Closed System CCM-433 Component Cooling Water from the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-72 D Closed System CCR-441 Component Cooling Water from the Main Steam 1.5 N/A Remote Manual MOV Penetrations.
CPN-72 D Closed System CCW-244-72 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations CPN-72 D Closed System CCW-243-72 Component Cooling Water to the Main Steam 1 N/A Check Valve Penetrations CPN-72 D Closed System CCM-432 Component Cooling Water to the Pressure 1.5 N/A Remote Manual MOV Equalizing Fans CPN-73 A WCR-961 WCR-960 Non-Essential Service Water to the Instrument 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Room Ventilation Unit E CPN-73 A WCR-963 WCR-962 Non-Essential Service Water from the 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Instrument Room Ventilation Unit E CPN-73 A WCR-965 WCR-964 Non-Essential Service Water to the Instrument 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Room Ventilation Unit W CPN-73 A WCR-967 WCR-966 Non-Essential Service Water from the 2.5 10 Auto Trip AOV (3) Auto Trip AOV (3) Instrument Room Ventilation Unit W CPN-74 A XCR-100 XCR-101 Instrument Air 1 10 Auto Trip AOV Auto Trip AOV CPN-74 A N-159 GCR-301 Nitrogen Supply to the Pressurizer Relief Tank 0.75 10 Check Valve Auto Trip AOV CPN-75 C Closed System CCR-460 Excess Letdown Heat Exchanger Component 4 10 Auto Trip AOV Cooling Water Outlet
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Number CPN-75 C Closed System CCR-462 Excess Letdown Heat Exchanger Component 4 10 Auto Trip AOV Cooling Water Inlet CPN-76 G Blind Flange Blind Flange Incore Flux Detection System 8 N/A CPN-76 A SM-4 SM-6 Instrument Room Air Sample Piping 0.5 N/A Needle Valve Needle Valve CPN-77 F N/A (2 N/A (2) Steam Generator No.2 Blowdown Outlet 2 N/A CPN-78 F N/A (2) N/A (2) Steam Generator No.3 Blowdown Outlet 2 N/A CPN-79 F N/A (2) N/A (2) Steam Generator No.4 Blowdown Outlet 2 N/A CPN-80 G Blind Flange Blind Flange Ice Loading Return 5 N/A CPN-81 A RCR-100 RCR-101 Sample Line from the Pressurizer Relief Tank to 0.5 10 Auto Trip AOV Auto Trip AOV the Gas Analyzer CPN-81 A DCR 202 DCR-204 Sample Line from the Reactor Coolant Drain 0.5 10 Auto Trip AOV Auto Trip AOV Tank to the Gas Analyzer CPN-81 A ICR-5 ICR-6 Sample Line from the Accumulators 0.5 10 Auto Trip AOV Auto Trip AOV CPN-82 A CCR-456 CCR-457 Reactor Support Cooling Water Outlet 2.5 10 Auto Trip AOV Auto Trip AOV CPN-82 A CCW-135 CCR-455 Reactor Support Cooling Water Inlet 2.5 10 Check Valve Auto Trip AOV CPN-83 Spare Capped per N/A Containment Weld Channel Pressurization Air 0.5 N/A RFC-2895 Supply CPN-83 Spare Capped per N/A Containment Weld Channel Pressurization Air 0.5 N/A RFC-2895 Supply CPN-84 A WCR-954 WCR-944 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #4 Motor Air Cooler
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Number CPN-84 A WCR-948 WCR-958 Non-Essential Service Water from the Reactor 3 10 Auto Trip AO Auto Trip AOV Coolant Pump #4 Motor Air Cooler CPN-84 A WCR-933 WCR-932 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #4 CPN-84 A WCR-934 WCR-935 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #4 CPN-85 A WCR-953 WCR-943 Non-Essential Service Water to the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #3 Motor Air Cooler CPN-85 A WCR-947 WCR-957 Non-Essential Service Water from the Reactor 3 10 Auto Trip AOV Auto Trip AOV Coolant Pump #3 Motor Air Cooler CPN-85 A WCR-929 WCR-928 Non-Essential Service Water to the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #3 CPN-85 A WCR-930 WCR-931 Non-Essential Service Water from the Upper 3 10 Auto Trip AOV Auto Trip AOV Containment Ventilation Unit #3 CPN-86 A VCR-11 VCR-10 Glycol Supply from Ice Condenser Fan Coolers 3 10 Auto Trip AOV Auto Trip AOV or R-156 Check Valve CPN-87 Spare Welded Closed N/A Spare 6 in sleeve N/A CPN-88 Spare Welded Closed N/A Spare 6 in sleeve N/A CPN-89 A SM-8 SM-10 Upper Containment Radiation Sampling System 0.5 N/A Manual Valve Manual Valve CPN-90 Spare Welded Closed N/A Spare 6 in sleeve N/A CPN-91 E Membrane HI (4) Reactor Vessel Level Instrumentation System 0.5 N/A (Sensor Bellows)
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 26 of 27 UNIT 2 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-91 E Membrane HI (4) Reactor Vessel Level Instrumentation System 0.5 N/A (Sensor Bellows)
CPN-91 E PPP-302-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-92 E PPP-301-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-93 A ECR-14 ECR-24 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 4 CPN-93 A ECR-16 ECR-26 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 6 CPN-93 A ECR-17 ECR-27 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 7 CPN-93 A ECR-18 ECR-28 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 8 CPN-93 A ECR-19 ECR-29 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 9 CPN-94 E PPP-300-V1 N/A Containment Pressure Transmitters 0.5 N/A Manual Valve CPN-94 E Membrane HI (4) Reactor Vessel Level Instrumentation System 0.5 N/A (Sensor Bellows)
CPN-95 A ECR-11 ECR-21 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 1 CPN-95 A ECR-12 ECR-22 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 2
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 23 D. C. COOK NUCLEAR PLANT Table: 5.4-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 27 of 27 UNIT 2 CONTAINMENT PENETRATION ISOLATION BARRIERS Containment Class Barrier Number Barrier Number Line Isolated (Service) Line Size Closure Penetration 1 2 (in) Time (Sec.)
Number CPN-95 A ECR-13 ECR-23 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 3 CPN-95 A ECR-15 ECR-25 Containment Hydrogen Monitoring System - 0.5 10 Auto Trip AOV Auto Trip AOV From Sample Point ESR - 5 CPN-95 A NS-283 ECR-10 Containment Hydrogen Monitoring System - 0.5 10 Check Valve Auto Trip AOV Hydrogen Sample Return or ECR-20 Auto Trip AOV CPN-96 E PPP-303-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-96 E PPA-312-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-97 E PPA-310-V1 N/A Containment Pressure Transmitter 0.5 N/A Manual Valve CPN-97 E Membrane HI (4) RVLIS (NLS-130) 0.5 N/A (Sensor Bellows)
CPN-98 E Membrane HI (4) RVLIS (NLS-110, NLS-120) 0.5 N/A (Sensor Bellows)
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 5.8- 1 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT CONTAINM ENT REG IONAL D ESIG NATION / IG NITER ASSEM B LY LOCATIONS U NIT 1 TRAIN ' A' TRAIN ' B '
Reg ion Comp artment/ Area No. Reg ion Comp artment/ Area-Elevation No.
1 Upper V olume Dome Area - 7 60 ' A-13 1 Upper V olume Dome Area - 7 60 ' B -13 1 Upper V olume Dome Area - 7 60 ' A-14 1 Upper V olume Dome Area - 7 60 ' B -14 1 Upper V olume Dome Area - 7 60 ' A-15 1 Upper V olume Dome Area - 7 60 ' B -15 2 Upper V olume Dome Area - 7 4 8 ' A-16 2 Upper V olume Dome Area - 7 4 8 ' B -16 2 Upper V olume Dome Area - 7 4 8 ' A-17 2 Upper V olume Dome Area - 7 4 8 ' B -17 2 Upper V olume Dome Area - 7 4 8 ' A-18 2 Upper V olume Dome Area - 7 4 8 ' B -18 3 Ice Cond. Upper Plenum 7 0 9 ' A-1 3 Ice Cond. Upper Plenum 7 0 9 ' B -1 3 Ice Cond. Upper Plenum 7 0 9 ' A-2 3 Ice Cond. Upper Plenum 7 0 9 ' B -2 4 Ice Cond. Upper Plenum 7 0 9 ' A-3 4 Ice Cond. Upper Plenum 7 0 9 ' B -3 4 Ice Cond. Upper Plenum 7 0 9 ' A-4 4 Ice Cond. Upper Plenum 7 0 9 ' B -4 4 Ice Cond. Upper Plenum 7 0 9 ' A-5 4 Ice Cond. Upper Plenum 7 0 9 ' B -5 5 Ice Cond. Upper Plenum 7 0 9 ' A-6 5 Ice Cond. Upper Plenum 7 0 9 ' B -6 5 Ice Cond. Upper Plenum 7 0 9 ' A-7 5 Ice Cond. Upper Plenum 7 0 9 ' B -7 6 Outside # 2 SG Enclosure 662' A-12 6 Outside # 2 SG Enclosure 659 ' B -12 6 Outside # 3 SG Enclosure 662' A-11 6 Outside # 3 SG Enclosure 659 ' B -11 7 Outside # 1 SG Enclosure 662' A-8 7 Outside # 1 SG Enclosure 659 ' B -8 7 Outside # 4 SG Enclosure 662' A-9 7 Outside # 4 SG Enclosure 659 ' B -9 7 Outside PRZ Enclosure 662' A-10 7 Outside PRZ Enclosure 659 ' B -10 8 East Fan/ Accumulator Room 635' A-25 8 East Fan/ Accumulator Room 630 ' B -25 8 East Fan/ Accumulator Room 632' A-26 8 East Fan/ Accumulator Room 634 ' B -26 9 West Fan/ Accumulator Room 632' A-27 9 West Fan/ Accumulator Room 634 ' B -27 9 West Fan/ Accumulator Room 634 ' A-28 9 West Fan/ Accumulator Room 634 ' B -28 10 Instrument Room 623' A-35 10 Instrument Room 630 ' B -35 11 Primary Shield Wall 64 3' A-19 11 Primary Shield Wall 64 6' B -19 11 Primary Shield Wall 64 0 ' A-20 11 Primary Shield Wall 64 6' B -20 11 Primary Shield Wall 64 4 ' A-21 11 Primary Shield Wall 64 8 ' B -21 11 Primary Shield Wall 64 1' A-22 11 Primary Shield Wall 64 8 ' B -22 11 Primary Shield Wall 64 2' A-23 11 Primary Shield Wall 64 6' B -23
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 5.8- 1 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT CONTAINM ENT REG IONAL D ESIG NATION / IG NITER ASSEM B LY LOCATIONS U NIT 1 TRAIN ' A' TRAIN ' B '
Reg ion Comp artment/ Area No. Reg ion Comp artment/ Area-Elevation No.
11 Primary Shield Wall 64 2' A-24 11 Primary Shield Wall 64 6' B -24 12 Inside # 1 SG Enclosure 68 9 ' A-30 12 Inside # 1 SG Enclosure 68 9 ' B -30 13 Inside # 2 SG Enclosure 68 9 ' A-34 13 Inside # 2 SG Enclosure 68 9 ' B -34 14 Inside # 3 SG Enclosure 68 9 ' A-33 14 Inside # 3 SG Enclosure 68 9 ' B -33 15 Inside # 4 SG Enclosure 68 9 ' A-31 15 Inside # 4 SG Enclosure 68 9 ' B -31 16 Inside PRZ Enclosure 68 9 ' A-32 16 Inside PRZ Enclosure 68 7 ' B -32 17 V icinity PRT-618 ' A-29 17 V icinity of PRT-618 ' B -29 KEY SG - Steam Generator PZ R - Pressuriz er PRT - Pressuriz er Relief tank Note: The locations given are for Cook Nuclear Plant Unit 1. For similar locations, in some cases the igniter assembly identification numbers are different, between Unit 1 and Unit 2.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 5.8- 2 UPDATED FINAL SAFETY ANALYSIS Page: 1 of 2 REPORT IG NITER ASSEM B LY LOCATIONS 1 U NIT 2 TRAIN ' A' TRAIN ' B '
No. Comp artment/ Area Elevation No. Comp artment/ Area Elevation A-1 Ice Cond. Upper Plenum 7 0 8 ' B -1 Ice Cond. Upper Plenum 7 0 9 '
A-2 Ice Cond. Upper Plenum 7 0 9 ' B -2 Ice Cond. Upper Plenum 7 0 9 '
A-3 Ice Cond. Upper Plenum 7 0 9 ' B -3 Ice Cond. Upper Plenum 7 0 9 '
A-4 Ice Cond. Upper Plenum 7 0 9 ' B -4 Ice Cond. Upper Plenum 7 0 9 '
A-5 Ice Cond. Upper Plenum 7 0 9 ' B -5 Ice Cond. Upper Plenum 7 0 9 '
A-6 Ice Cond. Upper Plenum 7 10 ' B -6 Ice Cond. Upper Plenum 7 0 9 '
A-7 Ice Cond. Upper Plenum 7 0 9 ' B -7 Ice Cond. Upper Plenum 7 0 9 '
A-8 Inside # 1 SG Enclosure 68 6' B -8 Inside # 1 SG Enclosure 68 6' A-9 Inside # 2 SG Enclosure 68 6' B -9 Inside # 2 SG Enclosure 68 6' A-10 Inside # 3 SG Enclosure 68 6' B -10 Inside # 3 SG Enclosure 68 6' A-11 Inside # 4 SG Enclosure 68 6' B -11 Inside # 4 SG Enclosure 68 5' A-12 Inside PZ R Enclosure 68 2' B -12 Inside PZ R Enclosure 68 6' A-13 Outside # 1 SG Enclosure 659 ' B -13 Outside # 1 SG Enclosure 662' A-14 Outside # 2 SG Enclosure 662' B -14 Outside # 2 SG Enclosure 659 '
A-15 Outside # 3 SG Enclosure 662' B -15 Outside # 3 SG Enclosure 659 '
A-16 Outside # 4 SG Enclosure 662' B -16 Outside # 4 SG Enclosure 659 '
A-17 Outside PZ R Enclosure 662' B -17 Outside PZ R Enclosure 659 '
A-18 Primary Shield Wall 64 7 ' B -18 Primary Shield Wall 64 2' A-19 Primary Shield Wall 64 8 ' B -19 Primary Shield Wall 637 '
A-20 Primary Shield Wall 64 8 ' B -20 Primary Shield Wall 636' A-21 Primary Shield Wall 64 8 ' B -21 Primary Shield Wall 636' A-22 Primary Shield Wall 64 1' B -22 Primary Shield Wall 637 '
1 The locations given are for Cook Nuclear Plant Unit 2 and are typical for Unit 1.
UFSAR Revision 31.0 INDIANA MICHIGAN POWER Revision: 24.0 D. C. COOK NUCLEAR PLANT Table: 5.8- 2 UPDATED FINAL SAFETY ANALYSIS Page: 2 of 2 REPORT IG NITER ASSEM B LY LOCATIONS 1 U NIT 2 TRAIN ' A' TRAIN ' B '
No. Comp artment/ Area Elevation No. Comp artment/ Area Elevation A-23 Primary Shield Wall 64 8 ' B -23 Primary Shield Wall 64 5' A-24 East Fan/ Accumulator Room 631' B -24 East Fan/ Accumulator Room 630 '
A-25 East Fan/ Accumulator Room 629 ' B -25 East Fan/ Accumulator Room 629 '
A-26 West Fan/ Accumulator Room 629 ' B -26 West Fan/ Accumulator Room 623' A-27 West Fan/ Accumulator Room 634 ' B -27 West Fan/ Accumulator Room 634 '
A-28 V icinity of PRT 618 ' B -28 V icinity of PRT 618 '
A-29 Upper V olume Dome Area 7 60 ' B -29 Upper V olume Dome Area 7 60 '
A-30 Upper V olume Dome Area 7 60 ' B -30 Upper V olume Dome Area 7 60 '
A-31 Upper V olume Dome Area 7 60 ' B -31 Upper V olume Dome Area 7 60 '
A-32 Upper V olume Dome Area 7 4 8 ' B -32 Upper V olume Dome Area 7 4 8 '
A-33 Upper V olume Dome Area 7 4 8 ' B -33 Upper V olume Dome Area 7 4 8 '
A-34 Upper V olume Dome Area 7 4 8 ' B -34 Upper V olume Dome Area 7 4 8 '
A-35 Instrument Room 620 ' B -35 Instrument Room 620 '
KEY: SG - Steam Generator PZ R - Pressuriz er PRT - Pressuriz er Relief Tank