EW, NC (Essential Cooling Water, Nuclear Cooling Water) Flashcards

1
Q

UV65/145 (EW to NC)

A

Auto Close on SIAS to maximize flow to the SDCHX Auto Close on Low surge tank Level - 17” (can’t be overridden) REMEMBER ‘B’ Train is Manual

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2
Q

What happens to EW pumps on LOP

A

Sheds Pumps and Restarts on the Sequencer (20 Sec)

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3
Q

EW Pump Starts

A

SIAS/CSAS/CREFAS/CRVIAS/ AFAS 1 and 2 and LOP

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4
Q

Which of the following is an EMERGENCY make up source to EW?

A. DW Demineralized Water Header
B. CT Condensate Transfer Pump
C. FP Fire Protection Header
D. CM Cooling Water Hold Up Tank

A

C. Fire Protection Header

Demin. Water - Primary M/U
Cond. Storage and Transfer - Class Powered B/U
Chemical Waste - Non Safety Related B/U
Fire Protection - Emergency B/U
Surge tank lo lo (14”) - closes normal makeup solenoid

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5
Q

Which is lower PSI EW or SP (Spray Pond)

A

EW system < SP psi - Prevents EW to SP to Environmental Flow-path EW System on the shell side.

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6
Q

The RHPCV Refrigerant Head Pressure Control Valve senses pressure in the ____ section of the Essential Chiller package and decreases EW flow under low load conditions to prevent ____.

A

D. Condenser, Stacking

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7
Q

EW Train A and Train B Difference

A

Train A can be controlled remotely Train B is manual

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8
Q

Nuclear Cooling water has been lost due to a pipe rupture.
Train ‘A’ EW has been cross-connected to NC.
Which one of the following identifies a plant condition that will isolate essential cooling water to the RCPs?

A. ‘B’ EW Surge Tank level drops to 10 inches.
B. Manual CIAS actuation from B05.
C. Pressurizer pressure drops to 1800 psia.
D. Instrument air header pressure drops to 60 psig.

A

C. Pressurizer pressure drops to 1800 psia (SIAS >1837 psia variable)

Some common distractors ‘B’ EW Surge tank level drops to 10 inches (Question says ‘A’)

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9
Q

The control room is implementing Standard Appendix 63 (Cross-connect Train A EW to NC) and they have directed you to perform Attachment 63-A.
Which one of the following will cause EWA-UV-145 and EWA-UV-65 to close automatically?

A. Containment Isolation Actuation Signal (CIAS)
B. Essential Cooling Water surge tank high high level.
C. Nuclear Cooling Water surge tank high high level.
D. Essential Cooling Water surge tank A low level.

A

D. Essential Cooling Water surge tank A low level.

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10
Q

Action statement for 3.7.7 (Condition A) states “with one EW train inoperable, restore the EW train to OPERABLE status within 72 hours.”
3.7.7 provides NO guidance for two inoperable EW trains.
Given these conditions with the unit operating in Mode 1:
0800 4/15/04: EWA-P01 becomes INOPERABLE.
2000 4/17/04: EWB-P01 becomes INOPERABLE.
2030 4/17/04: EWB-P01 becomes OPERABLE.
Assuming extensions are applied if appropriate, which of the following identifies when EWA-P01 must be returned to service before further action is required?

A. 2030 on 4/18/04
B. 0800 on 4/18/04
C. 0800 on 4/19/04
D. 2030 on 4/19/04

A

B. 0800 on 4/18/04

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11
Q

The following plant conditions exist:
Nuclear Cooling water has been lost due to a pipe rupture.
Train ‘B’ EW has been cross-connected to NC.
Which one of the following identifies a plant condition that will isolate essential cooling water to the RCPs?

A. Instrument air header pressure drops to 60 psig.
B. Pressurizer pressure drops to 1800 psia.
C. B’ EW Surge Tank level drops to LO LEVEL setpoint.
D. Containment pressure rises to 9.0 psig.

A

D. Containment pressure rises to 9.0 psig.

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12
Q

Nuclear cooling water has been lost due to a pipe rupture in the yard.
Essential Cooling Water Train “A” has been cross-connected to supply priority loads.
No other equipment is out of service or in an abnormal lineup.
WHICH ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps?

A. High level in the “A” EW surge tank
B. RCS pressure of 1800 psia
C. High EW “A” pump discharge pressure
D. Containment pressure of 2.0 psig

A

B. RCS pressure of 1800 psia

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13
Q

Nuclear Cooling water has been lost due to a pipe rupture.
Train ‘A’ EW has been cross-connected to NC.
Which one of the following identifies a plant condition that will isolate Essential Cooling Water to the RCP’s?

A. Containment pressure rises to 4.0 psig.
B. Pressurizer pressure drops to 1900 psia.
C. Instrument Air header pressure drops to 60 psig.
D. Loss of power to the EW to NC cross connect valves

A

A. Containment pressure rises to 4.0 psig.

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14
Q

Nuclear cooling water has been lost due to a pipe rupture in the yard.
Essential Cooling Water Train “B” has been cross-connected to supply priority loads.
No other equipment is out of service or in an abnormal lineup.
WHICH ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps?

A. Containment pressure 9.0 psig.
B. Pressurizer pressure 1800 psia.
C. Instrument air header pressure 60 psig.
D. Low level in the B train essential cooling water tank.

A

A. Containment pressure 9.0 psig.

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15
Q

100% power.
Loss of Nuclear Cooling Water.
EW train “A” cross-connected to Nuclear Cooling Water.
Which one of the following describes how the Essential Cooling Water system would respond to a Safety Injection Actuation Signal under these conditions?
EW train ‘B’ pump would start and the EW Train “A”…

A. to NC cross-connect valves would remain open and Train ‘A’ EW pump would stop due to load shedding and then restart according to the sequencer.
B. would stop due to load shedding then restart according to the sequencer.
C. to NC cross-connect valves would remain open and the Train ‘A’ EW pump would remain running.
D. to NC cross-connect valves would close and the Train ‘A’ EW pump would remain running.

A

D. to NC cross-connect valves would close and the Train ‘A’ EW pump would remain running.

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16
Q

Unit 1 is operating at rated power.
EW Train A is in the process of being aligned to NC due to a problem with both NCW pumps.
Each RCP has about 375 gpm of cooling water flow indicated on B04.
An Operator is standing by in the Train A SDC Heat Exchanger room to throttle the EW outlet of the SDC Heat Exchanger using EWA-HCV-53.
Based on the above conditions, you should direct the Operator to throttle EWA-HCV-53:

A. open to increase the EW pump’s flowrate.
B. closed to divert more flow to the NCW system.
C. closed to reduce the heat load on the EW Heat Exchangers.
D. open to overcome the increased head loss that the NCW places on the EW system.

A

B. closed to divert more flow to the NCW system.

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17
Q

Of the following list of signals, select the answer that includes the signals that provide an automatic start of the Essential Cooling Water System.

A. SIAS, RAS, MSIS, AFAS
B. LOP, SIAS, MSIS, AFAS
C. LOP, RAS, CREVIAS, CREFAS
D. LOP, CSAS, CREFAS, AFAS

A

D. LOP, CSAS, CREFAS, AFAS

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18
Q

Essential Cooling Water (EW) will supply which of the following Nuclear Cooling Water (NC) loads when cross-tied to NC?

A. Normal Chillers
B. Letdown heat exchanger
C. Containment Normal AHUs
D. Waste Gas Compressors

A

A. Normal Chillers

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19
Q

Unit 1 has entered 40AO-9ZZ03, Loss of Cooling Water.
Essential Cooling Water train ‘A’ has been cross-tied to the Nuclear Cooling Water system.
An RCS leak into the Nuclear Cooling Water system now occurs.
The process Radiation Monitoring system will respond by…

A. No monitors going into alarm
B. Alarming RU-6 Nuclear Cooling Water only
C. Alarming RU-2, ‘A’ Essential Cooling Water only
D. Alarming RU-2, ‘A’ Essential Cooling Water and RU-6 Nuclear Cooling Water

A

C. Alarming RU-2, ‘A’ Essential Cooling Water only

20
Q

Unit 1 has tripped from 100% power due to a Loss of Offsite Power (LOOP) event.
The crew has cross connected Essential Cooling Water (EW) system ‘A’ to Nuclear Cooling Water per Standard Appendix 63.
Which ONE of the following describes the reason for throttling closed EWA-HCV-53 (SDCHX ‘A’ Outlet Isolation) to a minimum EW system flow of 8500 gpm or until the RCP LO NC FLOW alarms are clear?

A. Maintain operability of the EW ‘A’ system
B. Provide the NCW priority loads with adequate flow
C. Ensure adequate flow to the Fuel Pool Heat Exchangers
D. Prevent EW pump damage due to operating in a runout condition

A

B. Provide the NCW priority loads with adequate flow

21
Q

Unit 1 has entered 40AO-9ZZ03, Loss of Cooling Water Essential Cooling Water train ‘A’ has been cross-tied to the Nuclear Cooling Water system.
An RCS leak into the Nuclear Cooling Water system now occurs.
The Process Radiation Monitoring system will respond by alarming…

A. RU-6, Nuclear Cooling Water, ONLY
B. RU-2, ‘A’ Essential Cooling Water, ONLY
C. RU-2, ‘A’ Cooling Water, AND RU-6, Nuclear Cooling Water
D. RU-2, ‘A’ Essential Cooling Water, ONLY and closing the EW-NC cross-tie valves

A

B. RU-2, ‘A’ Essential Cooling Water, ONLY

22
Q

With regards to the (EW), Essential Cooling Water system in mode 1, which of the following is the correct application of Tech Specs?

(1) When cross connected to the Nuclear Cooling Water (NCW) system, EW is INOPERABLE…
(2) When cross connected to the Fuel Pool Cooling, EW is INOPERABLE…

A. (1) and remains inoperable while cross connected
(2) and remains inoperable while cross connected
B. (1) and remains inoperable while cross connected
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
C. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger
(2) and remains inoperable while cross connected
D. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and SFP heat exchanger

A

B. (1) and remains inoperable while cross connected
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger

23
Q

Unit 1 is at 100% power Nuclear Cooling Water (NC) is lost and the crew has cross-connected ‘B’ train Essential Cooling Water (EW) to NC per 40AO-9ZZ03, Loss of Cooling Water.
The crew then receives a low level alarm on EW Surge Tank ‘B’.
Which of the following describes
(1) a possible location of the leak and
(2) the action that mitigates the event?

A. (1) Inlet to the EW heat exchanger
(2) Must manually close EW to NC cross-connect valves
B. (1) Inlet to the EW heat exchanger
(2) Automatic closure of the EW to NC cross-connect valves
C. (1) Inlet to the Letdown Heat Exchanger
(2) Must manually close EW to NC cross-connect valves
D. (1) Inlet to the Letdown Heat Exchanger
(2) Automatic closure of the EW to NC cross-connect valves

A

A. (1) Inlet to the EW heat exchanger

(2) Must manually close EW to NC cross-connect valves

24
Q

Unit 1 is operating at 100% power RCP 2B has developed a leak in the high pressure seal cooler.
40AO-9ZZ03, Loss of Cooling Water, has been implemented.
Essential Cooling Water train ‘A’ has been cross-tied to the Nuclear Cooling Water system.
Which of the following alarms and/or actions will the crew observe from the control room?

A. RU-6, Nuclear Cooling Water, ONLY
B. RU-2, ‘A’ Essential Cooling Water, ONLY
C. RU-2, ‘A’ Essential Cooling Water, AND RU-6, Nuclear Cooling Water
D. RU-2, ‘A’ Essential Cooling Water, ONLY and auto closing of the EW-NC cross-tie valves

A

B. RU-2, ‘A’ Essential Cooling Water, ONLY

25
Q

Which one of the following is the correct bus power supply for the Essential Cooling Water-Nuclear Cooling Water Cross Tie valves, EWA-UV-65 and EWA-UV-165?

A. PK, 125 VDC Bus
B. PN, 125 VAC Panel
C. PG, 480 VAC Load Centers
D. PH, 480 VAC Motor Control Centers

A

D. PH, 480 VAC Motor Control Centers

26
Q

Unit 2 is operating at 100% power Both Nuclear Cooling Water Pumps have tripped on 86 lockout.
40AO-9ZZ03, Loss of Cooling Water, Appendix A, Cross-Connect EW to NC, is in progress.
The RO will direct the AO to throttle EWA-HCV-53, SDCHX A Outlet Isolation, until cooling flow to each RCP has been restored to a Minimum of ____ or EW system flow lowers to _____, whichever happens first.

A. 1. 163 gpm 2. 8500 gpm
B. 1. 163 gpm 2. 13,800 gpm
C. 1. 491 gpm 2. 8500 gpm
D. 1. 491 gpm 2. 13,800 gpm

A

C. 1. 491 gpm 2. 8500 gpm

27
Q
  1. With the Essential Cooling Water System and the Spray Pond Cooling Water System in service, a tube leak in the Essential Cooling Water Heat Exchanger will send water from the…
  2. In the event of a loss of both EW Pumps while operating on Shutdown Cooling, the Shutdown Cooling Heat Exchanger can be cooled directly from the…

A. 1. Essential Cooling Water System to the Spray Pond Cooling Water System
2. Nuclear Cooling Water System
B. 1. Essential Cooling Water System to the Spray Pond Cooling Water System
2. Spray Pond Cooling Water System
C. 1. Spray Pond Cooling Water System to the Essential Cooling Water System
2. Nuclear Cooling Water System
D. 1. Spray Pond Cooling Water System to the Essential Cooling Water System
2. Spray Pond Cooling Water System

A

C. 1. Spray Pond Cooling Water System to the Essential Cooling Water System
2. Nuclear Cooling Water System

28
Q

Priority Loads

A

(R)CP - Seal coolers, High pressure coolers, Thrust bearing, and Lube oil cooler
(C)EDM ACUs
(N)ormal Chillers
(N)uclear Sample Coolers

29
Q

NC Auto Start

A

Low Discharge Pressure (79 psig) - Amber Light B07

30
Q

NC Rad Monitor

A

RU-6 Leak Detection (Yard Area)

31
Q

UV-401, 402, 403 (NC CTMT Isolations) Auto Close

A

CSAS

32
Q

Unit is in Mode 1
‘A’ NCW Pump is under Permit
‘B’ NCW Pump trips and is locked out The Operating Crew directed to restore Nuclear Cooling Water flow within…

A. 3 minutes or commence a controlled shutdown.
B. 3 minutes or trip the reactor, stop all RCPs, and ensure controlled bleed off isolated.
C. 10 minutes or commence a controlled shutdown.
D. 10 minutes or trip the reactor, stop all RCPs, and ensure controlled bleed off isolated.

A

D. 10 minutes or trip the reactor, stop all RCPs, and ensure controlled bleed off isolated.

Most X-connect work to EW can be done Remotely, AO support required in A SDCHX room to unlock and throttle closed the SDCHX EW outlet vlv to clear low flow alarms to RCPs.

If A Train is not available - time will likely >10 min. - RX Trip will likely be required

33
Q

Proper Sequence for opening NC valves in CTMT Supply Valve (NCB-UV-401) Return Valves (NCA-UV-402 and NCB-UV-403)

A

Open return valves (NCA-UV-402 and NCB-UV-403) Then Open Supply Valve (NCB-UV-401)

34
Q

Unit is 100% Power.
An RCS leak to the NC system is in progress.
Which of the following would be indicative of an RCS leak into the letdown heat exchanger?

A. Back pressure control valve opening.
B. Back pressure control valve closing.
C. Indicated letdown flow increasing.
D. NC flow from the heat exchanger decreases.

A

B. Back pressure control valve closing.

35
Q

NC has been lost due to a pipe rupture in the yard.
EW Train ‘B’ has been cross-connected to supply priority loads.
No other equipment is out of service or in an abnormal lineup.
WHICH ONE of the following identifies the plant conditions that will isolate essential cooling water to the reactor coolant pumps?

A. Pressurizer pressure 1800 psia.
B. Instrument air header pressure 60 psig.
C. Low level in the B train essential cooling water tank.
D. Containment pressure 9.0 psig.

A

D. Containment Pressure 9.0 CSAS (>8.5 psig) will isolate the UV-401,402,403 (NC CTMT Isolations)

36
Q

Essential Cooling Water (EW) will supply which of the following Nuclear Cooling Water (NC) loads when cross-tied to NC?

A. Normal Chillers.
B. Letdown heat exchanger.
C. Containment Normal AHUs
D. Waste Gas Compressors.

A

A. Normal Chillers

R-CPs
C-EDMs
N-ormal Chillers
N-uclear Sample Coolers

37
Q

Unit 1 is operating at rated power.
An inadvertent CSAS occurs.
The Secondary Operator has been directed to restore NCW to containment, overriding valves as necessary.
Which one of the following describes the steps (in correct sequence) that must be taken to restore NCW to the containment?

A. Override and open the instrument air to containment isolation valve (IAA-UV-2) to permit operation of the NCW isolation valves.
B. Close NCN-UV-99, to cross connect the Train of ECW to supply the NCW priority loads.
C. Override and open the return valves (NCA-UV-402 and NCB-UV-403), then override and open the supply valve (NCB-UV-401)
D. Override and open the supply valve (NCB-UV-401) to pressurize the header, then override and open the return valves (NCA-UV-402 and NCB-UV-403)

A

C. Override and open the return valves (NCA-UV-402 and NCB-UV-403), then override and open the supply valve (NVB-UV-401)

(Note: NCW valves are MOVs)

38
Q

Unit 1 is at 100% power.
Charging pump ‘A’, CHA-P01 is out of service.
Pressurizer level is 52% and stable.
ERFDADS indicates a 20 gpm RCS leakrate.
The CRS enters the Excessive RCS Leakrate AOP, 40AO-0ZZ02 Reading on RU-6, Nuclear Cooling Water, Is trending up.
Letdown Heat Exchanger Outlet Temperature Controller, CHN-TIC-223, output has stabilized at a new lower value.
RCP 1A NCW temperature, NCN-TI-471 is slowly increasing.
The Area Operator informs the Control Room that Nuclear Cooling Water Surge Tank Level is slowly rising.
Which one of the following actions should be taken to mitigate these conditions?

A. Cross connect Essential Cooling water to Nuclear Cooling Water
B. Trip the reactor and initiate a Containment Isolation Actuation Signal (CIAS)
C. Trip the reactor, stop the 1A RCP, secure bleedoff and isolate the high pressure seal coolers for the 1A RCP
D. Close CHB-UV-515 (Letdown to Regen HX Isolation Valve) and take actions per appendix C (Extended Operations without Letdown) of 40AO-9ZZ05

A

C. Trip the reactor, stop the 1A RCP, secure bleedoff and isolate the high pressure seal coolers for the 1A RCP

39
Q

The following changes are observed in Nuclear Cooling Water (NCW) temperatures while opening at full power.
NCW temperatures from the Reactor Coolant Pumps are increasing.
Control Element Drive Mechanisms ACUs outlet temperature are increasing.
NCW temperature from Letdown heat exchanger is stable.
The ‘in-Service’ Fuel Pool heat exchanger NCW return temperature is stable.
Which one of the following events could have occurred?

A. Loss of Plant Cooling Water (PW)
B. Inadvertent Containment Spray Actuation (CSAS)
C. Loss of Motor Control Center PHB-M34 (de-energized)
D. Outside containment Instrument Air isolation valve IAA-UV-2 has failed closed

A

B. Inadvertent Containment Spray Actuation (CSAS)

40
Q

Unit 1 is operating at rated power.
Pressurizer level is 52.5%.
Letdown flow is 78 gpm Charging flow is 88 gpm.
Alarm window 7AO7A (Nuc Clg Sys TRBL) is in alarm.
Nuclear Cooling Water Surge Tank Press Hi-Lo is alarming.
Nuclear Cooling Water Surge Tank Level Hi-Lo is alarming.
Containment sump levels and humidity are increasing.
Containment Temperature is stable.
Nuclear Cooling Water flow to all 4 RCPs is lowering.
These events are due to…

A. A half leg CIAS initiation, implement 40AL-9RK5B, panel B05B alarm response
B. A full CSAS actuation, implement 40AO-9ZZ17, In-advertant PPS-ESFAS actuations
C. RCS leak to the Nuclear Cooling System, Implement 40AO-9ZZ02, Excessive RCS Leakrate
D. The Nuclear Cooling Water relief inside containment lifting, Implement 40AO-9ZZ03, Loss of Cooling Water

A

D. The Nuclear Cooling Water relief inside containment lifting, Implement 40AO-9ZZ03, Loss of Cooling Water

41
Q

Unit 1 is operating at 100% power NCN-P01A (NCW Pump A) is in operation with NCN-P01B 9NCW Pump B) in standby.
The A Emergency Diesel Generator is under permit for maintenance.
NBN-X03 ESF Service Transformer fails.
This loss does NOT result in a Reactor Trip Based on these conditions, the Nuclear Cooling Water system will…

A. Have no pumps running
B. Be unaffected (no change in pump operation)
C. Remain in operation, NCN-P01B running and NCN-P01A off
D. Remain in operation, with both NCN-P01A and NCN-P01B running

A

B. Be unaffected (no change in pump operation)

42
Q

Unit 1 had been operating at 100% power.
A manual reactor trip was initiated due to lowering pressurizer level and pressure.
Standard Post Trip Actions are being performed.
No manual operator actions have been taken.
All 8 RCP ‘LO NCW FLOW’ alarm windows on B04 have actuated.
Which ONE of the following conditions would have caused these alarms?

A. 8.5 psig in containment
B. 1837 psia in the pressurizer
C. Refueling Water Tank level has lowered to 9.4%
D. High alarm on RU-6 (Nuclear Cooling Water Radiation Monitor)

A

A. 8.5 psig in containment

43
Q

Which ONE of the following identifies

(1) the normal and
(2) the backup makeup source to the Nuclear Cooling Water Surge Tank?

A. (1) Condensate Storage Tank 
    (2) Cooling Water Holdup Tank
B. (1) Condensate Storage Tank 
    (2) Reactor Makeup Water Tank
C. (1) Demineralized Water System 
    (2) Cooling Water Holdup Tank
D. (1) Demineralized Water System 
    (2) Reactor Makeup Water Tank
A

C. (1) Demineralized Water System

(2) Reactor Makeup Water Tank

44
Q

Unit 1 has entered 40AO-9ZZ03, Loss of Cooling Water.
Essential Cooling Water train ‘A’ has been cross-tied to the Nuclear Cooling Water system.
An RCS leak into the Nuclear Cooling Water system now occurs.
The Process Radiation Monitoring system will respond by alarming…

A. RU-6, Nuclear Cooling Water, ONLY
B. RU-2, ‘A’ Essential Cooling Water, ONLY
C. RU-2, ‘A’ Cooling Water, AND RU-6, Nuclear Cooling Water
D. RU-2, ‘A’ Essential Cooling Water, ONLY and closing the EW-NC cross-tie valves

A

B. RU-2, ‘A’ Essential Cooling Water, ONLY

45
Q

Unit 1 is at 100% power Nuclear Cooling Water (NC) is lost and the crew has cross-connected ‘B’ train Essential Cooling Water (EW) to NC per 40AO-9ZZ03, Loss of Cooling Water.
The crew then receives a low level alarm on EW Surge Tank ‘B’.
Which of the following describes
(1) a possible location of the leak and
(2) the action that mitigates the event?

A. (1) Inlet to the EW heat exchanger
(2) Must manually close EW to NC cross-connect valves
B. (1) Inlet to the EW heat exchanger
(2) Automatic closure of the EW to NC cross-connect valves
C. (1) Inlet to the Letdown Heat Exchanger
(2) Must manually close EW to NC cross-connect valves

D. (1) Inlet to the Letdown Heat Exchanger (2) Automatic closure of the EW to NC cross-connect valves

A

A. (1) Inlet to the EW heat exchanger

(2) Must manually close EW to NC cross-connect valves

46
Q

Which of the following will automatically start the standby Nuclear Cooling Water pump when its set point is reached?

A. CEDM Normal ACU High Temperature
B. Low flow to the Letdown Heat Exchanger
C. Low NC pump discharge header pressure
D. Low discharge flow on the running NC pump

A

C. Low NC pump discharge header pressure