Sim 3

Question 1

Who energizes start up transformers?

Answer 1

• LOOP/LOFC start up xfmrs ready, coordinate w SRP and ECC

Question 2

What is the minimum required Containment Spray flow for LOCA

Answer 2

• LOCA minimum CS flow 4350 GPM, elevated iodine in CTMT indicates a loss of fuel cladding

Question 3

List the Safety Function Status Checks for LOOP/LOFC:

Answer 3

Question 4

What are the entry conditions for LOOP/LOFC:

Answer 4

Entry Conditions: (SPTAs completed OR direct entry in Modes 3-4 with LTOP not in-service)
* Loss of off-site power (loss of NAN-S01 and NAN-S02)
o Partial loss of power should be addressed with AOPs.
* Loss of forced circulation has occurred (loss of RCPs)
* SBO has occurred and at least one vital 4.16 kV bus has been restored (from affected or other Unit EDG or Offsite Power)
o Blackout EOP restored power (not from SBOG) and transitioned to the LOOP EOP
* Subcooled natural circulation and at least one non-vital 13.8 kV AC bus is energized.

NOTE: The other ORPs (LOCA, ESD, SGTR, LOAF) assume a LOOP/LOFC and will address the same required actions.

Question 5

What actuation should occur if Circulating Water is lost to the main condenser?

Answer 5

MSIS - pull ahead step
(* Prevent over-pressurizing the Main Condenser
* SGBD isolates to minimize C/D and condenser damage)

Question 6

What is the preferred order of feed during a LOOP

Answer 6

• Maintains RCS heat sink.
• LOOP: use AFN last due to water hammer concerns

EOP Expectations p. 39

Question 7

What criteria are used to determine if natural circulation is achieved

Answer 7

• Check natural circulation in at least one loop:
• Loop ΔT < 65°F
• Tc and Th ↔ or ↓
• ≥ 24°F [44°F] subcooled using CET
• < 30°F ΔT between Thot and max quadrant CET
  If unable to verify, ensure proper feed flow / steam flow.

Question 8

How long does it take for natural circulation to develop?

Answer 8

• Natural circ flow should develop within 5 - 15 minutes (longer if the plant tripped from a low power)
• Changes take ~5-15 minutes to see in the RCS.
• Initially loop ΔT ↑ as Thot ↑, then ΔT↓ as flow is established
• 65°F is full power ΔT.
• Abnormal ΔT between Th and CETs indicates possible blockage in the loop or uncoupling of the core and loops.

Question 9

What are the entry criteria for 40AO-9ZZ22 Fuel Damage?

Answer 9

New Fuel Damage entry:
* Notified by Fuel Handling Supervisor that the fuel cladding of new fuel assemblies, whether wet or dry, located in the CTMT or Fuel Building has been penetrated.
* **Notified by Fuel Handling group **that an event has occurred where fuel damage may be suspected.

Irradiated Fuel Damage entry:
* High RU alarms
* FBEVAS or CPIAS actuation
* Unanticipated contact of an irradiated F/A with any solid structure
* Bubbles emerging from a spent fuel assembly.

Question 10

What is the concern with placing a Fuel Assembly in an unanalyzed intermediate position?

Answer 10

o Placing F/As in unanalyzed intermediate positions within the core could challenge the required shutdown margin.

Question 11

What actions are required per 40AO-9ZZ22 Fuel Damage for a Breached Fuel Cladding?

Answer 11

* Breached Fuel Cladding:
o **Evacuate non-essential personnel **from Fuel Bldg and CTMT
o In CTMT:
 actuate CPIAS/CREFAS
 close airlocks
 close equipment hatch
o In Fuel Bldg:
 actuate FBEVAS/CREFAS
 ensure equal number of Aux Bldg Supply and Exhaust Fans running

Question 12

Who initiates the Fuel Handling Event Recovery Checklist?

Answer 12

Fuel Handling Event Recovery Checklist (Conduct of Ops appendix)
* Initiated by RSRO or FHS for fuel handling problems.

Safe intermediate storage locations (placement will be at the RSRO’s discretion)

Question 13

What are the entry critiera for 40AO-9ZZ01 Emergency Boration?

Answer 13

Entry Criteria:
* Loss of Shutdown Margin or RCS Boron concentration is less than required for current plant conditions.

Question 14

What are the Reactor Trip Criteria in 40AO-9ZZ01 Emergency Boration?

Answer 14

Reactor Trip Criteria:
* Adequate Shutdown Margin does NOT exist and letdown is NOT in service

Question 15

Per Tech Specs, how long do you have to initiate an emergency boration?

Answer 15

• Boration required to be initiated within 15 minutes per Tech Specs
  o 15 minute TCA to start boration
  o 30 minute TCA to start boration if CHN-UV-164 path is used

Question 16

During emergency boration, if a charging pump is available, should you use a HPSI pump?

Answer 16

If an emergency boration path using a charging pump is available, it will be used. This means that HPSI pumps should ONLY be used if Charging pumps are NOT available

Question 17

What is the order of preference for emergency boration (per 40AO-9ZZ01)?

Answer 17

If an emergency boration path using a charging pump is available, it will be used. If not,
HPSI or LPSI injection will be selected.

If RWT level is greater than 73% and the RWT is available, the RWT will be used as the
source of borated water through CHE-HV-532. If not, the alternate suction from the
RWT will be aligned or the SFP will be used.

If CHE-HV-532 is used, the preferred path will be through CHE-HV-536 to the charging pump suction. If CHE-HV-536 is unavailable, CHN-UV-514 will be used with BAMPs running or through CHN-V-164 the Boric Acid filter bypass if the BAMPs are unavailable. The normal charging pump discharge flowpath is preferred but guidance to align to the alternate path to the coldlegs or hotlegs is given in this procedure.

Question 18

If Pool Cooling and Cleanup (PC) is recirculating the Refueling Water Tank (RWT), what are the level requirements for charging pumps? What is the condition of the 3rd charging pump?

Answer 18

• If PC Cleanup is recirculating the RWT:
  o 1 Charging Pump requires > 83%
  o 2 Charging Pumps require > 92%
  o 3rd Charging Pump placed in Pull-to-Lock (cannot run all 3 pumps if PC aligned)

Question 19

What volume of the Spent Fuel Pool (SFP) is credited for Emergency Boration? What levels correlate to this volume?

Answer 19

The Spent Fuel Pool volume credited for emergency
boration (33,500 gallons) is from **137´ 4˝ down to 133´ 6˝ ** where a siphon breakwill cause loss of pump suction.

Question 20

What emergency boration flow paths require tracking the thermal fatigue cycles? (this card still needs work)

Answer 20

HPSI boration flow path:
* Used if Charging pump is not available
* One cold leg injection valve is opened to achieve flow indication of ≥ 75 gpm.
o Minimum flow that can be read on the FI (square root extractor)
* May need to de-pressurize the RCS below HPSI pump shutoff head (~1880 psia, AOP has steps to reduce pressure)
* If borating > 1 hour, ↑ flow to ≥ 225 gpm.

Question 21

What is the least preferred emergency boration flow path per 40AO-9ZZ01?

Answer 21

The charging path through the HPSI B hot leg injection path should be used as the last resort due to the thermal transient on the SDC hot leg nozzle. These thermal transients shall be tracked as part of the thermal fatigue cycle monitoring program.

Question 22

What is the primary concern with using LPSI for emergency boration?

Answer 22

LPSI boration flow path:
* Used if HPSI pump is not available
* Requires RCS pressure to be < 220 psia prior to selecting LPSI flow path (AOP does NOT have steps for de-pressurizing < 220 psia)
* LPSI suction from RWT must be opened (aligns to borated source)
* One LPSI injection valve is opened to commence flow.

Question 23

How long does an operator have to respond to an inadvertent dilution alarm (BDAS)?

Answer 23

Possible inadvertent dilution actions
* TCA to stop an inadvertent dilution. Time starts when BDAS alarm actuates.
o 15 minutes Modes 3-5
o 30 minutes Mode 6

Question 24

How does temperature affect letdown purification ion exchanger boron affinity?

Answer 24

* IX isolated for an extended period of time (> 72 hours) will cool down the IX.
o Resin at a **cooler temperature has a greater affinity to absorb boron. **
o Placing an IX in service that has cooled down and RCS boron has been reduced, can result in an unwanted RCS temperature rise unless the effluent is flushed to the CVCS HUT when initially placing the IX in service.
* IX flushing usually performed if > 20 ppm boron difference between IX and RCS (if not being used for deborating)

** ↓ letdown temperature: IX resin absorbs more boron (higher affinity), ↓ RCS boron (dilution) **

** ↑ letdown temperature: IX resin releases boron (lower affinity), ↑ RCS boron (boration) **

Question 25

What is the definition of a Condenser Tube Rupture, per 40AO-9ZZ10?

Answer 25

• Condenser tube rupture defined as a CW leak through the condenser tubes > 1.0 gpm.

Question 26

What are the Reactor Trip Criteria for Condenser Tube Rupture?

Answer 26

Reactor Trip Criteria:
* Only one train of CW is operating AND the tube rupture is in that train
* SG trip values exceeded or trending to a trip value prior to completing down power:
o SG Sodium, Sulfates, or Chlorides ≥ 1.0 ppm (1000 ppb) with ↑ Cation Conductivity
o SG Cation Conductivity ≥ 15 μmho/cm with ↑ Sodium, Sulfates or Chlorides
** Hotwell sodium > 35 ppm **(35,000 ppb)
** Sufficient Cond Demins are NOT available to accept full condensate flow **AND the CRS directs

Question 27

What post trip actions are directed per 40AO-9ZZ10 Condenser Tube Rupture?

Answer 27

When the reactor is tripped, the following actions are taken by the crew:
● Ensure Auxiliary Feedwater is supplying SG feed.
● Ensure SG Blowdown to the BFT is isolated.
● Ensure both Main Feedwater Pumps are tripped.
● If two trains of CW are in service then isolate the ruptured train.
● If one train of CW is in service shutdown the CW system.

Question 28

How many demineralizer beds are required to receive full flow?

Answer 28

• Place required demins in service with CDN-PDV-195 (Bypass Valve) closed. (based on power level and running MFPs)
  o 100 – 70%: 5 demins
  o 70 – 50% or both MFPs running: 4 demins
  o 50 – 30% with one MFP running: 3 demins
  o < 30%: 2 demins

Question 29

What is the purpose of close CDN-LV75, hotwell drawoff, during a Condenser Tube Rupture?

Answer 29

• Close and locally isolate hotwell drawoff (CDN-LV-75) (minimizes CST contamination)

Question 30

What determines how fast a down power is required during a Condenser Tube Rupture? At what percent power is the first CW pump stopped? Ruptured CW train isolated?

Answer 30

The ingress rate of contaminants will determine how fast the unit is down powered.
Full Flow Demins = Normal/Rapid Downpower
No Full Flow Demins = Rx Trip or RPCB

• Unless CW leak is very small, SG contaminants will likely reach trip criteria without full flow demin capability.
• Reduce power to 40% (allows CW train to be isolated)
  o Reduce power with LOFP RPCB or normal down power section. (decision based on chemistry and time until trip criteria is met)
  o Full flow demins should allow a normal down power.
  o LOIT: use LOFP RPCB unless otherwise directed (mentor guidance)
• 60%: Stop 1 CW pump in affected train if all 4 were running.
• 40%: Isolate the Ruptured CW Train (App. K)

Question 31

During a Condenser Tube Rupture, after isolating the affected CW train, how is hotwell alignment changed?

Answer 31

Once the affected Circ Water train has been isolated at 40% power, the condensate system is aligned to stop taking suction on the affected hotwell. Appendix F, Hotwell Level Control provides the direction:

● Hotwell activity is verified to be within release limits
● Hotwell level in the good hotwell is verified to be greater than 41 inches (Keeping level greater than 40 inches will prevent tripping all the condensatepumps at 30 inches.)
● The affected side Condensate Pump discharge valve is closed.
● The ‘B’ Condensate suction valve (CDN-HV-1 or 2) is closed for the affected hotwell and the recirc line to the affected half is verified closed.
o Full suction will now be from good hotwell; level may drop ~ 10”.
● The affected hotwell is overboarded as necessary to maintain desired level of about 41 inches.

Question 32

List the important Spent Fuel Pool levels:

Answer 32

SFP Levels
* 138’ 2” – damage new fuel elevator
* 138’ 1” – normal level
* 137’ 6” – Lo level Alarm
* 137’ 4” – LCO 3.7.14: 23’ above F/As
* 137’ – Lo-Lo level Alarm / AOP entry
* 131’ 10” – loss of PC pump suction
* 130’ 2” – lowest level due to pipe break / valve misalignment

Question 33

Given design basis conditions, how long would it take to boil the Spent Fuel Pool?

Answer 33

Design bases time to boil
* 16.7 hours (worst case M1-4)
* 3.46 hours (full core off-load and 13 previous refueling partial 1/3 cores modes 5-6/defueled)

Question 34

What are the exit conditions for 40AO-9ZZ23 Loss of SFP Level or Cooling?

Answer 34

Exit Conditions:
* Temperature controlled < 145°F (PC cooling restored) (loss of cooling)
* Leakage stopped and level stabilized at desired level. (loss of level)

Question 35

What are the safe intermediate storage locations for fuel assemblies?

Answer 35

Safe intermediate storage locations (placement will be at the RSRO’s discretion)

Question 36

During a loss of Spent Fuel Pool Cooling, if PC cooling is augmented with SDC, is SDC non-functional? How is Refueling Pool level affected?

Answer 36

• Align SDC to SFP if needed (use AOP appendices to align)
  o Aligning SDC to SFP does NOT make SDC non-functional
  o Augment SDC results in a higher level in the Refueling Pool (~ 1”) than in the SFP due to the lineup required to allow Refueling Pool water to flow into the SFP.

Question 37

What are the required Plant Protection System actions for a loss of PBA-S03/PBB-S04?

Answer 37

PPS Actions
 Loss of PBA-S03 (PBB-S04) for 90 minutes: bypass all parameters on Channel A or C (B or D) that are NOT bypassed on Channels B or D (A or C)
o Loss of PB results in loss of battery charger. Battery rated for 2 hours.
o Once battery is depleted, PK/PN on associated channel are lost
o Results in all associated PPS Bistable Trip Units going to the trip position
o Bypassing parameters minimizes chance of spurious actuations.

Question 38

Summarize Appendix M, DG A Running With Output Breaker Open, actions in 40AO-9ZZ12 Degraded Electrical:

Answer 38

LOP (PB) and DG breaker fails to automatically close
 Ensure DG running at proper frequency and voltage (override [DG start HS to start] and adjust if needed)
o 59.9 - 60.5 Hz and 4180 - 4300V
Ensure normal and alternate PB supply breakers are OPEN with NO lockouts
o No Bright green lights and green lockout alarm
o If MCR breaker lights are dark, could indicate loss of control power OR breaker is stuck closed (AOs should investigate)
 Check DG lockout relay is not actuated
 Manually close DG breaker if needed
o MCR (use Sync Switch)
o Locally. Cycle breaker control power if anti-pumped
If unable to re-energize the bus, emergency stop the DG
 SPTAs: Use the hard card
 AOP only: Use AOP guidance

Question 39

How does a Foxboro controller fail on a loss of power? What mode does it go to when power is restored?

Answer 39

Foxboro Controllers
 Loss of power: controller fails with no output
 Power restored: controller comes back in MANUAL with zero output

Question 40

What is the Rule of 58?

Answer 40

Annunciator Logic Cabinets (2) power supplies
* Cabinet 1 (RKN-C01) power (Rule of 58)
o Normal NKN-D43
o Back-up NNN-D15
* Cabinet 2 (RKN-C02) power (Rule of 58)
o Normal NKN-D42
o Back-up NNN-D16

Question 41

What annunciators have power during a loss of NKN-M45 coincident with a SIAS?

Answer 41

Loss of NKN-M45 with a SIAS:
* U1/U2: Loss of all annunciators (NNN-D15/D16 lost)
* U3: Loss of half of the annunciators

Question 42

What are the main steps of 40AO-9ZZ15 Loss of Annunciators?

Answer 42

Actions:
Perform an annunciator check.

• If PC is reliable:
  o Monitor PC alarm screen (ensure PC audible alarms are turned ON)
• If PC is NOT reliable:
  o Stabilize the plant and stop unnecessary plant evolutions

Question 43

What action is required if annunciators are lost on 4 boards?

Answer 43

• Notify Unit Ops Manager (UOM) if ≥ 4 annunciator panels are non-functional.

Question 44

What are the entry conditions for 40AO-9ZZ18 Shutdown Outside the Control Room?

Answer 44

Entry / Exit Criteria:
* Entered when CRS has determined that the MCR is uninhabitable for any reason other than fire.
* May be exited when control of the plant has been re-established from the MCR.

Purpose:
* Brings plant to Cold Shutdown if MCR is determined uninhabitable by the CRS for any reason other than fire.

Question 45

What components can be operated from the Remote Shutdown Panel?

Answer 45

In the RSP area, two panels contain the various equipment control devices used to control the
plant. The controls associated with Train ‘B’ equipment also have disconnect switches, used to
isolate these components from the Control Room in the event of a fire.
The following provides a list of those components that can be operated from the RSPs:
● Backup Heaters
● Auxiliary Spray Valves
● CHB-515 and CHA-516
(Letdown Isolations)
● CHB-505, CHA-506 (Bleedoff
to VCT Isol.) and CHA-507
● Sit Vent Valve Power Supply (‘A’ & ‘B’)
● Sit Vent Valves (‘A’ & ‘B’)
● SIB-659 & SIA-660 (SI Pump Combine Recirc to RWT Isol.)
● Control Building Normal AHU Isolation Dampers (M01/M55)
● Control Room Essential AFUs Outside Air Isolations
(M02/M03)
● ADV Controllers
● ADV Permissives
● AFW Flow Control Valves
● AFA-P01 Turbine Controls

In addition, several PPS controls for each channel are also provided:
● Low PZR Press Setpoint RESET
● Low SG Press Setpoint RESET
● Low PZR Press BYPASS
● MSIS Actuation

Question 46

State the initial actions (taken prior to leaving the Control Room) in 40AO-9ZZ18:

Answer 46

Initial Actions prior to evacuating the MCR
* Trip the Reactor
o Check power lowering and all FSCEAs inserted
o Boration performed from RSP if required
o SPTAs are NOT performed
* Stop ONE RCP in each loop. (Trip from SWGR if required)
* Ensure Main Turbine is tripped.
o Manually trip from MCR or locally if needed
* If time permits, place PLCS in Local-Auto with setpoint at 50%.
*If time permits, place Letdown Control Valve and Back Pressure Control Valve selector switches in BOTH
* Exit the MCR and continue AOP from the RSP

Question 47

How is emergency boration achieved from the Remote Shutdown Panel (during 40AO-9ZZ18)?

Answer 47

• Emergency borate if power not lowering OR any FSCEA(s) not inserted.
  o Align Charging Pump suction to the RWT (per AOP appendix)
  o Open CHE-UV-536 and Close CHN-UV-501 from NHN-M72

Question 48

During a shutdown from outside the Control Room (40AO-9ZZ18), what parameters should you stabilize the plant at (SPTA value or different?)?

Answer 48

• Stabilize the plant (similar to SPTAs)
• Control LPZR 10-65% (trending to 33-53%)
• Control PPZR 1837-2285 psia (trending to 2225-2275 psia) and within P/T Limits.
  o Manually control Aux Spray and heaters if needed.
• Monitor Core Heat removal:
  o Control within P/T limits and maintain subcooling
  o Loop ΔT < 10°F if RCPs running (should be 1 pump per loop)
  o If Natural Circulation:
   Loop ΔT < 65°F and Thot/Tcold constant or lowering.
   LPZR not rising at a rate greater than can be explained by charging flow. (Voiding in RCS)
• RCS Heat Removal
  o** Tcold 560-570°F**
  o* S/G levels 35-80% WR*
  o S/G Press 1140-1200 psia
  o If SBCS or FWCS NOT controlling in automatic:
   Actuate MSIS
   Control ADVs from RSP
   Feed the S/G with AFB or AFA
• AFB must be started locally at PBB-S04

Question 49

How is the plant cooled down in 40AO-9ZZ18 Shutdown outside the Control Room?

Answer 49

Plant Cooldown Actions
* Align charging pump suction to the RWT (boration)
* Feed SGs with AFA or AFB
* Trip MFPs locally (if running)
* Establish control with ADVs
* Initiate a MSIS
* Perform Secondary Plant Shutdown (App. F)
* Monitor subcooling (P/T limits with App. C)
* Addresses Tech Specs for P/T limits, CDRs, boron sampling, and SDM (App. H)
* These actions are performed due to lack of control systems and instrumentation available for the steam plant at the RSP

Question 50

What steps must be taken for re-entry into the Control Room following shutdown per 40AO-9ZZ18?

Answer 50

Coordination of MCR re-entry
* One RO will remain at RSP until control has been transferred back to MCR
* Perform SPTAs from the MCR
* Transfer control of ADVs to MCR(if being used)
* Transfer control of AFA to MCR (if being used)

Question 51

What temperature should the normal chillwater be maintained during a Loss of Chillers? What action is required if this temperature is exceeded?

Answer 51

Loss of Normal Chillers
* Attempt to re-start chillers
* Maintain WC temperature < 50°F
o Start additional chillers
o If chillers cannot maintain < 50°F, close WCN-70 (Radwaste and Control Bldg Header Isolation).

Question 52

What is the temperature limit for the CEDMCS room? What action is taken if this temperature is exceeded?

Answer 52

Loss of CEDMCS Room cooling (Mode 1 or 2)
* > 104°F may cause SCR breakdown and dropped CEAs
* Shutdown reactor (ZZ05) if unable to maintain < 104°F
* Limit CEA motion to that needed for ASI control
* Establish temporary ventilation

Question 53

What is the primary concern with losing a CEDMCS cabinent fan?

Answer 53

Loss of CEDMCS Cabinet Fans (RTBs Closed)
* May result in spurious CEA malfunctions.
* Limit CEA motion to that needed for ASI Control
* CEDMCS NOT in Auto Sequential
* Open CEDMCS Cabinet Doors
* Set-up temporary ventilation (I&C assistance required)

Question 54

How long do you have to take action if Containment CEDM cooling is lost?

Answer 54

Loss of CTMT CEDM Cooling
* If RCS ≥ 300°F, CEDM coils may be damaged within 40 minutes (from initial loss). (CEA drop)
* Restore in 10 minutes or start a rapid shutdown (ZZ05) (Secure from shutdown if restored in 40 minutes).
o There are no restrictions on CEA motion for the first 40 minutes following loss of cooling air flow.
o Boron and CEA insertion may be used for power reduction.
* Trip the reactor within 40 minutes (from initial loss)
* Cooldown the RCS to < 300°F in the next 4 hours if not restored (use 40OP-9ZZ24, SNOW Outage)

Question 55

In SBO, what would drive you to load shed NKN-M46?

Answer 55

Question 56

What procedure provides guidance for required actions if valid Continuous Gripper High Voltage alarms are in for CEA subgroups 4 and 5?

Answer 56

Trip the reactor PER 40AL-9SF01 (local alarm response)

Question 57

What is the E-plan definition of a SGTR?
If a SGTL (<44 gpm) is occurring, are you releasing?

Answer 57

Classifiable per SU, but not a “release”

Question 58

When can a maintenance test configuration be considered M-Rule available?

Answer 58

When the test configuration can be overriden automatically by a valid start signal

• If tagged out, UNAVAILABLE
• If INOP due to admin, AVAILABLE
  *

Question 59

What dose equivalent I-131 coolant activity would be an E-plan “LOSS” of fuel cladding?

Answer 59

greater than> 300 uCi

Question 60

If “D” Reactor Trip Circuit Breaker fails to trip, what response is required within 1 hour? What LCO is used for retest?

Answer 60

LCO 3.3.4 RTCB open the affected or redundant (B&D) within 1 hour.
LCO 3.0.5

Question 61

What acutation does CPIAS back up in modes 1-4?

Answer 61

CIAS - Tech Spec bases
The CPIAS is a backup to the CIAS Systems in MODES 1, 2, 3, and 4 and will close the containment purge valves in the event of high radiation levels resulting from a primary leak in the containment.

Question 62

What is the basis for LCO 3.4.17 RCS Activities?

Answer 62

The maximum dose that an individual at the exclusion area boundary can receive for 2 hours following an accident (SGTR), or at the low population zone outer boundary for the radiological release duration, is specified in 10 CFR 100.11 (Ref. 1). Doses to control room operators must be limited per GDC 19. The limits on specific activity ensure that the offsite and control room doses are appropriately limited during analyzed transients and accidents.

Question 63

What is the LCO completion time for HPSI B INOP?

Answer 63

72 hours

Question 64

Can you go from Mode 5 to Mode 4 with Containment Temp. above 117 (average)?

Answer 64

No - The LCO 3.6.5 TS actiontime is 8 hours, which does not allow unlimited operation.

Question 65

What equipment is required per LCO 3.8.9 Distribution Systems?

Answer 65

For one train, 3 Class 480 V Load Centers and 4 Class 480 V Motor Control Centers

Question 66

If the Shift Manager is not in the Control Room, no transient is in progress, and an event occurs requiring classification, who is the Emergency Coordinator (classifies event)?

Answer 66

The Unit Control Room Supervisor

Question 67

What is the maximum time to notify the NRC for “immediate notifications.” ?

Answer 67

60 minutes per 10 CFR 20