ML22340A186

1 to Updated Final Safety Analysis Report, Chapter 6, Tables

ML22340A186
Person / Time
Site:	Cook
Issue date:	11/30/2022
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML22340A137	List: AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1) ML22340A128 ML22340A129 ML22340A131 ML22340A132 ML22340A133 ML22340A134 ML22340A135 ML22340A136 ML22340A138 ML22340A139 ML22340A141 ML22340A142 ML22340A143 ML22340A144 ML22340A145 ML22340A146 ML22340A147 ML22340A148 ML22340A149 ML22340A150 ML22340A151 ML22340A152 ML22340A153 ML22340A154 ML22340A155 ML22340A156 ML22340A157 ML22340A158 ML22340A159 ML22340A160 ML22340A161 ML22340A162 ML22340A163 ML22340A164 ML22340A165 ML22340A166 ML22340A167 ML22340A168 ML22340A169 ML22340A170 ML22340A171 ML22340A172 ML22340A173 ML22340A174 ML22340A175 ML22340A176 ML22340A177 ML22340A178 ML22340A179 ... further results
References
AEP-NRC-2022-62
Download: ML22340A186 (19)

Text

INDIANA MICHIGAN POWER Revised: 27.0 D. C. COOK NUCLEAR PLANT Table: 6.1-1 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 1

Net Positive Suction Heads for Post-DBA Operational Pumps

Flow and Condition NPSHa NPSHr Water Pu mp (per pump) Suction Source (available (required) Te mp mi ni mum) gpm 1 ftabs ftabs °F

1. Safety Injection 678 max. flow Refueling Water 45.4 31.8 105 max.

Storage Tank

2. Centrifugal Charging 530 max. flow Refueling Water 39.8 17.6 105 max.

Storage Tank

3. Residual Heat Removal 4,175 max. flow Recirculation Sump 26.3 17.1 190

4. Containment Spray 3,406 max. flow Recirculation Sump 27.8 14.9 190

5. Component Cooling 11,200 max. flow Closed Loop 37.1 25.5 160

Screenhouse

6. Essential Service Water 12,200 max. flow (forebay at 37.5 34.1 88.8 Elevation 562 ft.)

1 NPSH values represent bounding conditions lowest NPSH margin for the most conservative operating conditions and component alignments analyzed of either unit.

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SAFETY INJECTIONSYSTEM CODE REQUIREMENTS 1

Component Code

Refueling Water Storage Tank Not applicable Residual Heat Exchanger

Tube Side ASME B&PV Code S ect i o n III C l as s C

Shell Side ASME B&PV Code S ect i o n V III

Accumulators ASME B&PV Code Section III Class C

Valves ANSI B16.5, MSS-SP-66, and ASME B&PV Code Section III, 1968 Edition 1 Piping USAS B31.1, 1967 Edition 1 ASME III Appendix F 2

Boron Injection Tank ASME B&PV Code S ect i o n III C l as s C

Recirculation Sump Strainers Edition (Main and Remote) A IS C-69, 7th Debris Interceptors (CEQ Fan Room, Flood-Up Overflow Wall, and A IS C-69, 7th Edition Entrance to Containment Wide Range Sump Level Instrument)

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 evaluation criteria of ASME III Appendix F (faulted conditions) is applicable to accumulator fill line piping from outside containment isolation valve to the normally closed inlet valv es at each accumulator and the normally closed valves in the flow path to the low head SI hot leg loops (CPN 32).

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ACCUMULATORDESIGN PARAMETERS

Number 4 per unit

T ype Stainless steel clad / carbon steel

Design pressure, psig 700

Design temperature, ºF 300

Operating temperature, ºF 120

Normal pressure, psig 621.5

Minimum pressure, psig 585.0

Total volume, ft3 1350 Maximum water volume at operating conditions, ft3 971

Minimum water volume at operating conditions, ft3 921

Boron concentration (as boric acid), ppm 2400 to 2600

Code ASME B&PV Code Section III Class C

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BORON INJECTIONTANK DESIGN PARAMETERS

Number 1 per unit

Total Volume, gal (also useable volume) 900

Boron concentration, (ppm) 0 to 2600

Design pressure, psig 2735

Design temperature, ºF 300

Operating pressure, psig (Injection Mode) 2340

Operating pressure, psig (Standby) atmospheric

Operating temperature, ºF ambient

Material SS Clad Carbon Steel

Code ASME B&PV Code Section III Class C

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REFUELING WATER STORAGE TANK DESIGN PARAMETERS

Number 1 per unit

Tank Capacity, gal. 420,000

Required Capacity, gal. 375,500

Design pressure, psig Static head and sloshing

Design temperature, ºF -30 to 100

Normal pressure, psig Atmospheric

Liquid temperature,º F 70 - 100

Inside diameter, ft (approx.) 48

Straight side height, ft 31

Material Stainless Steel

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DESIGN PARAMETERS - ECCS PUMPS

Centrifugal Charging Safety Injection Residual Heat Pumps Pumps Removal Pumps Number per unit 2 2 2

Design pressure, psig 2800 1700 600

Design temperature, oF 300 300 400

Design flow rate, gpm 150 400 3000

Design head, ft. 5800 2500 350

Max. flow rate, gpm 550 7001 4500

Head at max. flow rate, ft. 1400 1500 300

Motor horsepower 600 400 400

Pump Speed, rpm 48102 3570 1780 Horizontal Horizontal Vertical, in-line T yp e Multistage Multistage Single stage Centrifugal Centrifugal Centrifugal Stainless Steel or Material Stainless Stainless Stainless Steel clad Steel Steel Carbon steel

The motor starting times from electrical activation to full speed (steady - state -voltage) as obtained by a computer simulation are as follows:

Centrifugal Charging Pump 1.14 seconds

Safety Injection Pump 1.13 seconds

Residual Heat Removal Pump 0.704 seconds

1 Maximum flow rate is limited to 675 gpm for pumps that have not been qualified to a higher flow rate, up to a maximum of 700 gpm.

2 Equipped with speed increaser gear.

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SINGLE ACTIVE FAILURE ANALYSIS EMERGENCYCORE COOLING SYSTEM RECIRCULATIONPHASE

Component Malfunction Comments Totally passive system with one accumulator per loop.

A. Accumulator Deliver to broken loop Evaluation based on three accumulators delivering to the core and one spilling from ruptured loop.

B. Pump:

1) Centrifugal Charging Fails to start Two provided. Evaluation based on operation of one.

2) Safety Injection Fails to start Two provided. Evaluation based on operation of one.

3) Residual H eat R emoval Fails to start Two provided. Evaluation based on operation of one.

C. Automatically Operated Valves:

1) Boron injection tank isolation a) inlet valve Fails to open Two parallel lines; one valve in either line is required to open.

b) outlet valve Fails to open Two parallel lines; one valve in either line is required to open.

2) Centrifugal Charging pumps a) suction line from RWST isolation valve Fails to open Two parallel lines; only one valve in either line is required to open.

b) discharge line to the normal charging path Fails to close Two valves in series; only one valve required to close.

isolation valve1 c) minimum flow line isolation valve Fails to close Two trains in parallel; only one train required.

d) suction from volume control tank isolation Fails to close Two valves in series; only one valve required to close.

valve

1 The reactor coolant pump seal water path is left open.

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SINGLE ACTIVE FAILURE ANALYSIS EMERGENCYCORE COOLING SYSTEM RECIRCULATIONPHASE

Component Malfunction Comments Recirculation Phase A. Valves operated From Control Room for Recirculation:

1) Containment sump recirculation isolation Fails to open Two lines parallel; only one valve in either line is required to open.

2) Residual heat removal pumps suction line from Fails to close Check valve in series with two gate valves; operation of RWST isolation only one valve required.

3) Safety injection pumps suction line from RWST Fails to close Check valve in series with gate valve; operation of only one valve required.

Check valve in series with two parallel gate valves.

4) Centrifugal Charging pumps suction line from RWST isolation valve Fails to close Operating of either the check valve or the gate valves required.

Separate and independent high head injection path via the centrifugal charging pumps taking suction from discharge of

5) Safety injection pump suction line isolation valve at discharge of the west residual heat exchanger Fails to open the East residual heat residual head exchanger. A cross over line allows the flow from one heat exchanger to reach both safety injection and charging pumps if necessary.

6) Residual Heat Removal discharge bypass line Fails to close The second isolation valve for RWST backflow is still available.

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SINGLE ACTIVE FAILURE ANALYSIS EMERGENCYCORE COOLING SYSTEM RECIRCULATIONPHASE

Component Malfunction Comments B. Pumps:

Two provided. Evaluation based on operation of one. One

1) Component Cooling Water Pump Fails to start pump is running during normal operation. An additional shared pump is available.

2) Essential Service Water Pump Fails to start Four provided for both units. Two pumps are required for normal operation.

3) Residual Heat Removal Pump Fails to start Two provided. Evaluation based on operation of one.

4) Charging Pump Fails to operate Same as injection phase.

5) Safety Injection Pumps Fails to operate Same as injection phase.

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SINGLE PASSIVE FAILURE ANALYSIS - EMERGENCY CORE COOLING SYSTEM

RECIRCULATION PHASE

Flow Path Indication of Loss of Flow Path Alternate Flow Path

COLD LEG From containment recirculation sump to low head Reduced flow in the discharge line, from cold leg injection header via the residual heat one of the residual heat exchangers (one Via the independent identical low head flow path utilizing removal pumps and the residual heat exchangers. flow monitor in each discharge line) and/or the pumps second residual heat exchanger leakage sump level alarm HOT LEG From containment recirculation sump to hot leg Same as above Same as above lo w - head injection header via RHR pumps and RHR heat exchangers.

COLD LEG From containment recirculation sump to the high Reduced flow in the discharge lines from From containment recirculation sump to the high head cold head cold leg injection header via the west the safety injection pumps (one flow leg injection headers via east residual heat removal pump, residual heat removal pump, west residual heat monitor in each discharge line) and/or east residual heat exchanger and the centrifugal charging exchanger and the safety injection pumps. leakage sump level alarm. pumps cross - tie to SI pump suction.

HOT LEG Fro m containment recirculation sump to the high Reduced flow in the discharge lines from From containment spray to the high head hot leg injection head hot leg injection headers via west residual the safety injection pumps (one flow points via East residual heat removal heat removal pump, removal pump, west residual heat exchanger and monitor in each discharge line) and/or East residual heat exchanger and the centrifugal charging the safety injection pumps. leakage sump level alarm. pumps cross tie to SI Pump suction

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ACCUMULATOR INLEAKAGE

TIME PERIOD BETWEEN LEVEL ADJUSTMENTS (OBSERVED LEAK OBSERVED LEAK (BETWEEN LEVEL ALARM) 1, 2 RATE) DIVIDED BY RATE CC/HR (MAX ALLOWED MAXIMUM ANTICIPATED DESIGN) 3

1538 1 mo nth 16 days 77

513 3 months 7 weeks 25.7

256 6 mo nths 13 weeks 12.8

171 9 months 20 weeks 8.6

128 1 year 27 weeks 6.4

1 25.0 cu. ft. between level alarms.

2 Accumulator initially at "Lo" level and pressure conditions.

3 Maximum allowed leak rate for manufacturers acceptance test is 20 cc/hr (Back L eakage through check valves).

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Page: 1 of 1

RECIRCULATION LOOP LEAKAGE

No. of Type of Leakage Control and Unit Leakage Leakage to Leakage to It e ms Units Rate Used in the Original Analysis1 Atmosphere Drain Tank cc/hr cc/hr

1. Residual Heat Removal Pumps (Low Head Safety Injection) 2 Mechanical seal with leakoff - 1 drop/min 0 6

2. Centrifugal Charging Pump 2 Same as residual heat removal pump 0 6

3. Safety Injection Pump 2 Same as residual heat removal pump 0 6

4. Flanges: Gasket adjusted to zero leakage following any test 10 drops/min/flange used in analysis

a. P ump 8 240 0

b. Valves Bonnet Body (larger than 2") 40 1200 0

c. Control Valves 6 180 0

5. Valves Stem Leakoffs 40 Back-seated, double packing with leakoff 0 40 1 cc/hr/in. stem diameter

6. Misc. Small Valves 50 Flanged body packed stems - 1 drop/min used 150 0 TOTALS 1770 58

1 License amendments 49 (Unit 1) and 34 (Unit 2) require implementation of a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This table is retained as part of the original FSAR and is not intended to be updated. The original FSAR assumed approximately 1770 cc/hr ECCS leakage and 2806 cc/hr CTS leakage for a total of approximately 4576 cc/hr total ESF leakage. See Section 14.3.5.19 and Section 14.3.5.20.4 for current information.

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RECIRCULATION SUMP COMPONENT DESIGN LOADCOMBINATIONS 1

Load Combination Description Load Combination Case No.

Full Recirculation Flow with 0 Clean Main and Remote DW2 + TAL 3 + DBE 4 + FRHL 5 + DL 6 +

Strainers; Applicable to Main NL(t)7 and Remote Strainers Loads Immediately after the 1 Pipe Rupture; Applicable to DW(2) + TBL 8 + DBE(4) + NL(t) (7)

Main and Remote Strainers Containment Fill; Forward 2 Flow through Main Strainer DW(2) + TFL 9 + DBE (4) + NL(t) (7) +

with Reverse Flow through PFHL10 Waterway to Remote Strainer Plugged Main Strainer with DW(2) + TAL (3) + DBE (4) + FRHL (5) + DL (6) 3 Recirculation Flow from + NL(t)(7)

Remote Strainer Pressure Pulse at Instant of 4 Pipe Rupture; Applicable to DW(2) + TOL 11 + PP 12 + NL(t) (7)

Main and Remote Strainers

1 The load combinations are used for the design and qualification of the main and remote strainers and waterway, unless otherwise indicated in the Description column.

2 DW - Dead Weight.

3 T AL - Thermal effects at accident temperature of 160°F when recirculation is initiated for a large break LOCA consistent with the time of maximum hydrodynamic load.

4 DBE - Design Basis Earthquake.

5 FRHL - Full Recirculation Hydraulic Loads at 14,400 gpm, the bounding value for ECCS flow 6 DL - Debris Load. For s tructural analysis of main and remote strainers, bounding debris mass values of 1986 lbs and 1530 lbs, respectively, were used.

7 NL(t) - Nozzle Loads. Loads applicable only to the remote strainer and local conditions at the time of the load case.

8 TBL - Thermal Break Load. Thermal effects at post -break containment environment temperature of 236°F.

9 TFL - Thermal Fill Loads During Pool Fill (200°F).

10 PFHL - Pool Fill Hydraulic Loads - reverse flow and waterway loads.

11 TOL - Thermal effects at normal (maximum) operating temperature of 160°F for the main strainer and 120°F for the remote strainer.

12 PP - Pressure Pulse. Short term pressure pulse of 5.0 psid acting outward from within the main strainer and waterway and 2.5 psid acting outward from within the interface between the waterway and the remote strainer.

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CONTAINMENT SPRAY PUMPDESIGN PARAMETERS

Quantity 2 (per unit)

T ype Vertical, centrifugal

Design Pressure 600 psig

Design Temperature 400oF

Design flow rate 3200 gpm

Design head 490 ft.

Motor horsepower 600 hp.

Motor speed 1780 rpm

INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 6.3-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2

Containment Spray Heat Exchanger Design Parameters

Heat Exchanger Heat Exchanger

Quantity, Unit 1 / Unit 2 2 (1-HE-18E / W) / 2 (2 -HE-18E / W)

T ype Vertical / Shell and U Tube

Heat Transfer per unit (Btu / hr) 114.2 x 106

Flow, tube side, gpm 2942

Flow, shell side, gpm 2400

Shell side inlet temperature, ºF 90

Tube side inlet temperature, ºF 164

Shell side outlet temperature, ºF 137.87

Tube side outlet temperature, ºF 124.20

Material Shell / Tube Carbon Steel / SS

Design P ressure, Shell / Tube psig 150 / 300

Design Temperature, Shell / Tube, ºF 200 / 200

INDIANA MICHIGAN POWER Revised: 28.0 D. C. COOK NUCLEAR PLANT Table: 6.3-2 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2

Containment Spray Heat Exchanger Code Requirements

Shell Side ASME 1968 B&PV Code Section VIII Div. 1

Tube Side ASME 1968 B&PV Code Section III Class C

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SPRAYADDITIVE TANK DESIGN PARAMETERS

Quantity 1 (per unit)

Volume, gal 5218

Design temperature, ° F 200

Design pressure, psig 10

Material stainless steel

SPRAY ADDITIVE TANK CODE REQUIREMENTS

ASME 1968 B&PV Section VIII Div. 1

INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 6.3-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 1 of 2

Containment Spray System Malfunction Analysis

Component Malfunction Comments and Consequences

1. Containment Spray Pump Rupture of Pump Isolate train.

casing Redundant train continues to operate requirement is one train.

2. Containment Spray Pump Pump fails to start. One of two pumps operating will supply 100 percent of required flow

This is prevented by pre startup checks. During power operation, each pump is tested on a periodic basis. During these tests checks will be

3. Containment Spray Pump Pump suction line made to confirm that a motor operated valve (from the refueling water closed storage tank) is open. The manual valve from the recirculation sump is locked or sealed open. Motor operated valve positions (open or closed) are indicated in the control room Pump discharge motor Motor operated valves are redundant and only one of the two need

4. Containment Spray Pump operated valve fails to operate. Valve positions (open or closed) are indicated in the control open. room.

5. Containment Spray Pump Discharge Check The check valves were checked in preoperational tests and are checked Valve fails to open during periodic tests.

This is prevented by pre-startup checks.

6. Containment Spray Heat Drain Valve left open / Leak detection sumps in the spray s ystem compartments are provided Exchanger Manways left open with level alarms which are initiated if a drain valve is open and discharging into the compartment INDIANA MICHIGAN POWER Revised: 26.0 D. C. COOK NUCLEAR PLANT Table: 6.3-4 UPDATED FINAL SAFETY ANALYSIS REPORT Page: 2 of 2

Containment Spray System Malfunction Analysis

Component Malfunction Comments and Consequences

7. Containment Spray Heat Isolate train.

Exchangers Tube or shell rupture Redundant train continues to operate.

One train will provide 100% flow.

Motor Operated The motive water suppl y valve is normally open and is checked by

8. Containment Spray Eductors Supply Valve fails to periodic test.

open The suction supply valves (from the spray additive tank) are redundant and only one of the two need be open.

Valve position is indicated in the Control Room.