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.JS Sim Phase USE THIS > Tech Spec (Drey) > Flashcards

Tech Spec (Drey) Flashcards

1
Q

Per LCO 3.5.5, Refueling Water Tank, during a cooldown from 500°F to 300°F, the MINIMUM required RWT volume will ____(1)____ and the MINIMUM required boron concentration in the RWT will ____(2)____ .

A. (1) increase
(2) increase

B. (1) increase
(2) remain constant

C. (1) decrease
(2) increase

D. (1) decrease
(2) remain constant

A

D. (1) decrease

(2) remain constant

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2
Q

The bases for requiring all four SITs to be operable in MODE 1 is to ensure which of the following?

A. 100% of 2 SITs will reach the core during a LOCA.

B. 100% of 3 SITs will reach the core during a LOCA.

C. 100% of all 4 SITs will reach the core during a LOCA.

D. 50% of 1 SIT and 100% of 2 SITs will reach the core during a LOCA.

A

B. 100% of 3 SITs will reach the core during a LOCA.

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3
Q

The Bases of Tech Spec 3.5.5, RWT, states: The RWT ensures that an adequate supply of borated water is available to…

Which of the following is NOT part of the bases for this LCO?

A. to support the ECCS during the injection phase

B. maintain the reactor subcritical following a LOCA.

C. ensure that the SI pumps can deliver at least 30 minutes of full flow (plus a 10% margin).

D. ensure that an adequate level exists in the containment sump to support ESF operation in the recirculation mode.

A

C. ensure that the SI pumps can deliver at least 30 minutes of full flow (plus a 10% margin).

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4
Q

Technical Specification - LCO 3.5.5 Refueling Water Tank (RWT)

The basis for the minimum required volume of the RWT ensures that at the time of RAS initiation the water level in the containment sump will be enough to provide NPSH for the ESF pumps and the ESF pump suction will not be aligned to the containment sump until the the decay heat boil-off rate is less than …

A. the minimum design flow of two HPSI pumps.

B. 75% of the minimum design flow of one HPSI pump.

C. the minimum design flow of two HPSI pumps and two LPSI pumps.

D. 75% of the minimum design flow of one HPSI pump and one LPSI pump.

A

B. 75% of the minimum design flow of one HPSI pump.

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5
Q

Which one of the following is a basis for the LCO concerning the RWT (LCO 3.5.5)?

Ensure that…

A. boron precipitation will NOT occur in the core following a LOCA.

B. the SI pumps can deliver at least 40 minutes of full flow (plus a 10% margin).

C. the RCS boron concentration is maintained above 4000 ppm following a DBA.

D. sufficient volume exists in the containment sump to support operation of the ESF pumps at the time of transfer to the recirculation mode.

A

D. sufficient volume exists in the containment sump to support operation of the ESF pumps at the time of transfer to the recirculation mode.

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6
Q

With an initial containment average air temperature less than or equal to the LCO temperature limit (3.6.5, Containment Air Temperature), we are assured that…

A. all instrumentation within containment is guaranteed to function properly.

B. during a Design Basis Accident, the resultant peak accident temperature is maintained below the containment design temperature.

C. during a LOCA Design Basis Accident (but NOT all Main Steam Line Breaks), the resultant peak accident temperature is maintained below the containment design temperature.

D. during a Main Steam Line Break Design Basis Accident (but NOT all LOCAs), the resultant peak accident temperature is maintained below the containment design temperature.

A

B. during a Design Basis Accident, the resultant peak accident temperature is maintained below the containment design temperature.

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7
Q

One of the bases for maintaining containment pressure in its LCO stipulated band is to ensure:

A. H2 concentration post LOCA is minimized.

B. that outside air is not drawn in to the containment.

C. that instrumentation functions properly post LOCA.

D. containment pressure does not exceed 60 psig post LOCA.

A

D. containment pressure does not exceed 60 psig post LOCA.

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8
Q

LCO 3.6.4, Containment Pressure, prevents exceeding the ____(1)____ during a Design Basis Accident and minimum pressure design limit during ____(2)____.

A. (1) assumed time to Containment Spray flow
(2) an inadvertent CSAS

B. (1) assumed time to Containment Spray flow
(2) Containment venting operations

C. (1) Containment maximum pressure design limit
(2) an inadvertent CSAS

D. (1) Containment maximum pressure design limit
(2) Containment venting operations

A

C. (1) Containment maximum pressure design limit

(2) an inadvertent CSAS

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9
Q

Given the following conditions:

  • Unit 2 is operating at 100% power.
  • Unit 2 is staffed to minimum manning as defined by 40DP-9OP02, Conduct of Operations.
  • Outside Containment Isolation Valve, IAA-UV-2, has closed and cannot be reopened.
  • 40AO-9ZZ06, Loss of Instrument Air, Appendix K, Placing the Instrument Air / Service Air Cross-Tie In Service, has been performed.
  • To comply with LCO 3.6.3, Containment Isolation Valves, the Auxiliary Building Operator has been assigned to close Service Air Containment Isolation Valve, IAE-V072, if a valid CIAS signal is received.

Based on the listed conditions, the Auxiliary Building Operator must be able to close IAE-V072 within (1) minute(s), and the crew (2) minimum crew manning requirements per 40DP-9OP02, Conduct of Shift Operations.

A. (1) 1
(2) still meets

B. (1) 1
(2) no longer meets

C. (1) 30
(2) still meets

D. (1) 30
(2) no longer meets

A

A. (1) 1

(2) still meets

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10
Q

The bases for meeting the LCO on DNBR is …

A. LPD will be < 21kw/ft.

B. it ensures that the licensed power operating limit will not be exceeded.

C. it ensures that COLSS Calculated Power will not exceed the COLSS POL based on linear heat rate.

D. an acceptable minimum DNBR will be maintained in the event of a loss of flow transient, CEA misoperation, or asymmetric SG transient.

A

D. an acceptable minimum DNBR will be maintained in the event of a loss of flow transient, CEA misoperation, or asymmetric SG transient.

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11
Q

The bases for meeting the LCO on Linear Heat Rate (13.1 kw/ft) is, …

A. on loss of flow the calculated DNBR will be < actual DNBR.

B. in the event of a LOCA, fuel clad temperature will not exceed 2200°F.

C. it ensures that the POL based on linear heat rate will not be exceeded.

D. the measured radial peaking factors (RPF) will always be < calculated RPF.

A

B. in the event of a LOCA, fuel clad temperature will not exceed 2200°F.

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12
Q

Why does LCO 3.3.8, Containment Purge Isolation Actuation Signal (CPIAS), require one channel to be OPERABLE?

A. To reduce the amount of radioactive iodine released to the Aux building during refueling operations.

B. To close containment purge valves because they are not qualified for automatic closure from their open position under DBA Conditions in MODES 1, 2, 3, and 4.

C. To act as a backup for the CIAS systems signal to ensure closing of the purge valves in the event of high radiation levels resulting from a primary leak in containment.

D. To maintain the ability to monitor containment atmospheric conditions to ensure there is sufficient information available to assess conditions in the containment during a DBA.

A

C. To act as a backup for the CIAS systems signal to ensure closing of the purge valves in the event of high radiation levels resulting from a primary leak in containment.

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13
Q

The Reactor Coolant Flow Low RPS trip monitors (1) and provides protection in the event of a(an) (2) condition.

A. (1) SG ∆P
(2) under frequency

B. (1) RCP speed
(2) under frequency

C. (1) SG ∆P
(2) RCP sheared shaft

D. (1) RCP speed
(2) RCP sheared shaft

A

C. (1) SG ∆P

(2) RCP sheared shaft

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14
Q

Given the following conditions:

  • Unit 1 is at 99% power.
  • RCA-PT-199A (SPS Channel A) has failed HIGH.
  • NO RTCBs are open.

Based on this, Tech Specs require …

A. opening RTCB #1 OR #3 immediately.

B. opening RTCB #1 OR #3 within 1 hour.

C. opening RTCB #1 AND #3 immediately.

D. no specific action related to this failure.

A

B. opening RTCB #1 OR #3 within 1 hour.

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15
Q

Unit 1 is Refueling, with fuel movement in progress, when it is discovered that no CPIAS actuation logic is operable. Which of the following is required?

A. Suspend Core Alterations within 15 minutes. No other action required.

B. Close Containment Purge and Exhaust valves within 15 minutes. No other action required.

C. Immediately close the Containment Purge and Exhaust valves OR suspend Core Alterations and movement of irradiated assemblies in Containment.

D. Immediately close the Containment Purge and Exhaust valves AND suspend Core Alterations and movement of irradiated fuel in Containment.

A

C. Immediately close the Containment Purge and Exhaust valves OR suspend Core Alterations and movement of irradiated assemblies in Containment.

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16
Q

Which of the following describes LCO 3.3.3 Control Element Assembly Calculators (CEACs)?

____(1)____ CEAC(s) shall be OPERABLE in each CPC channel because ____(2)____ prevent a required trip from occurring.

A. (1) One
(2) a single RSPT is used to provide input to one CEAC in all four CPC channels, hence no single sensor failure will

B. (1) One
(2) both CEA Position Processors provide input to each CPC channel independent of the CEACs hence no single sensor CEAC failure can

C. (1) Two
(2) a single RSPT is used to provide input to one CEAC in all four CPC channels, hence no single sensor failure will

D. (1) Two
(2) both CEA Position Processors provide input to each CPC channel independent of the CEACs hence no single sensor CEAC failure can

A

C. (1) Two

(2) a single RSPT is used to provide input to one CEAC in all four CPC channels, hence no single sensor failure will

17
Q

Given the following conditions:

  • Unit 1 is at 3% reactor power and stable.
  • T-cold is 565° F.
  • Pressurizer Pressure is 2300 psia.
  • Pressurizer level is 29%.

Tech Spec Limiting Conditions for Operation (LCO) (1) is NOT MET and
(2) will restore compliance.

A. (1) 3.4.1, RCS, DNB parameters
(2) lowering RCS Tcold

B. (1) 3.4.1, RCS, DNB parameters
(2) lowering RCS pressure

C. (1) 3.4.9, Pressurizer
(2) raising Pressurizer level

D. (1) 3.4.9, Pressurizer
(2) lowering RCS pressure

A

B. (1) 3.4.1, RCS, DNB parameters

(2) lowering RCS pressure

18
Q 
Given the following conditions:
•	Unit 1 is in Mode 3
•	RCS heatup is in progress
•	RCPs are in operation
•	RCS T-cold indication over the last 60 minutes is as follows:
•	T= (-) 60 minutes
•	Loop 1A T-cold		385°F
•	Loop 1B T-cold		385°F
•	Loop 2A T-cold		388°F
•	Loop 2B T-cold		387°F
  • T= 0 minutes (current time)
  • Loop 1A T-cold 461°F
  • Loop 1B T-cold 461°F
  • Loop 2A T-cold 464°F
  • Loop 2B T-cold 463°F

RCS heatup rate ____(1)____ technical specification limits. The MAXIMUM number of RCPs running is ____(2)____.

A. (1) is within
(2) 3

B. (1) is within
(2) 4

C. (1) exceeds
(2) 3

D. (1) exceeds
(2) 4

A

C. (1) exceeds

(2) 3

19
Q

Given the following conditions:
• Unit 1 is operating at 55% following a Large Load Reject event
• RU-155D, RCS Letdown is in high alarm
• Chemistry analysis confirms that DOSE EQUIVALENT I-131 is 70uCi/gm

At this activity level what accident is public exposure not below 10CFR100 limits?

A. Loss of All Feedwater

B. Loss of Coolant Accident

C. Excessive Steam Demand

D. Steam Generator Tube Rupture

A

D. Steam Generator Tube Rupture

20
Q

Which of the following identifies an accident that the RCS Specific Activity Technical Specification limits are based on, AND what is the bases for the limit as it is relates to the accident?

A. Loss Of Coolant Accident, ensures that dose rates in Aux building are < 1R/hr to permit aligning SFP injection into the RCS.

B. Steam Generator Tube Rupture, ensures the resulting 2 hour dose at the site boundary will not exceed a small fraction of the 10 CFR 100 dose guideline limits following a SGTR accident.

C. Excessive Steam Demand, ensures that the dose rate in the low population zone is maintained less than or equal to the 10 CFR 100 limits for the duration of the event.

D. Steam Generator Tube Rupture and ESD outside of containment, ensures members of the general public do not exceed a dose of 300R to the thyroid during the first 6 hours of the event.

A

B. Steam Generator Tube Rupture, ensures the resulting 2 hour dose at the site boundary will not exceed a small fraction of the 10 CFR 100 dose guideline limits following a SGTR accident.

21
Q

Which LCO’s bases states the failure consequences could be a Loss Of Coolant Accident (LOCA) outside of containment AND the violation of this LCO could result in continued degradation and lead to the loss of the integrity of a fission product barrier?

A. LCO 3.6.1, Containment

B. LCO 3.4.18, Steam Generator (SG) Tube Integrity

C. LCO 3.4.3, RCS Pressure and Temperature (P/T) Limits

D. LCO 3.4.15, RCS Pressure Isolation Valve (PIV) Leakage

A

D. LCO 3.4.15, RCS Pressure Isolation Valve (PIV) Leakage

22
Q

In reference to Tech Spec 3.7.14 (Fuel Storage Pool Water Level), the minimum level in the Fuel Pool is based on…

A. providing adequate NPSH for the Fuel Pool Cooling Pumps.

B. absorbing the iodine released during a fuel handling accident.

C. satisfying the requirements to be considered a borated water source.

D. ensuring that decay heat generated in the Fuel Pool is adequately removed.

A

B. absorbing the iodine released during a fuel handling accident.

23
Q

According to the Applicable Safety Analysis section of Technical Specifications, which of the listed LCOs DIRECTLY mitigates the adverse consequences of a Main Steam Line Break in Containment?

A. LCO 3.5.1, Four SITs shall be OPERABLE.

B. LCO 3.7.3, Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE.

C. LCO 3.7.1, The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2.

D. LCO 3.3.1, Four RPS trip and bypass removal channels for each Function in Table 3.3.1-1 shall be OPERABLE (Function 4, Pressurizer Pressure - Low).

A

B. LCO 3.7.3, Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE.

24
Q

According to Technical Specifications Applicable Safety Analysis for the Auxiliary Feedwater System (AFW), what are the limiting design basis accidents (DBAs) and transients for the AFW system?

A. Large Break LOCA and Station Blackout

B. Main Steam Line Break and Feedwater Line Break

C. Failed Open Pressurizer Safety Valve and Loss Of All Feed

D. Rod Ejection and Failed Open Steam Generator Safety Valve

A

B. Main Steam Line Break and Feedwater Line Break

25
Q

Per the bases for LCO 3.7.17, Spent Fuel Assembly Storage, the Spent Fuel Storage Pool can provide storage for a maximum of (1) fuel assemblies and the limiting criteria for this number is the (2) .

A. 1) 1205
2) design basis of the spent fuel cooling system

B. 1) 1205
2) minimum spent fuel storage cell spacing requirements

C. 1) 1329
2) design basis of the spent fuel cooling system

D. 1) 1329
2) minimum spent fuel storage cell spacing requirements

A

A. 1) 1205

2) design basis of the spent fuel cooling system

26
Q

Given the following:

  • The Unit is in Mode 5.
  • ONE train of CREFS is declared INOPERABLE.
  • The required action for this condition has NOT been accomplished.
  • The associated completion time has been exceeded.

Which of the following is the appropriate action per Tech Spec 3.7.11, Control Room Essential Filtration System (CREFS)?

A. Place the OPERABLE CREFS train in operation immediately.

B. Place the OPERABLE CREFS train in service within 30 minutes.

C. Take immediate action to restore the INOPERABLE CREFS train.

D. Take action to restore the INOPERABLE CREFS within 30 minutes.

A

A. Place the OPERABLE CREFS train in operation immediately.

27
Q

Which of the following describes the bases for the required level in the Diesel Fuel Oil storage tank?

To provide…

A. 7 days of full load operations.

B. 4 days of required loads following a LOCA.

C. at least 26 days of required loads following a LOCA.

D. 4 days of full load operation followed by 10 days of one train of Shutdown Cooling loads.

A

A. 7 days of full load operations.

28
Q

Given the following conditions:

  • Unit 1 is operating at 100% rated power.
  • Diesel Generator ‘A’ Starting Air Receiver DGA-X01A has been removed from service for maintenance: tagged out and depressurized.
  • Diesel Generator ‘A’ air compressor for Starting Air Receiver DGA-X01B tripped on electrical fault. (Acrid odor reported from AO)
  • A short time after the air compressor failed SEIS alarm Air System Start was received in the Control Room.
  • The dispatched AO reports that air is leaking from the cap downstream of Air Receiver DGA-X01B blowdown valve DGA-V395.
  • When the cap was tightened the air leak stopped and air pressure in DGA-X01B stabilized at 190 psig.

Per LCO 3.8.1, AC Sources - Operating, and the TS Bases, what is the OPERABILITY status of Diesel Generator ‘A’?

A. OPERABLE for 48 hours with current air receiver status.

B. NOT OPERABLE until BOTH air receiver pressures are > 230 psig.

C. NOT OPERABLE until an air receiver pressure is raised to > 230 psig.

D. OPERABLE for an indefinite period of time as long as air receiver pressure remains > 185 psig.

A

A. OPERABLE for 48 hours with current air receiver status.

29
Q

To meet operability requirements for Train ‘A’ per LCO 3.8.9, Distribution Systems – Operating, a MINIMUM of ___(1)___ Class 480V Load Centers must be OPERABLE, and a MINIMUM of ___(2)___ Class 480V Motor Control Centers must be OPERABLE.

A. (1) 2
(2) 3

B. (1) 2
(2) 4

C. (1) 3
(2) 3

D. (1) 3
(2) 4

A

D. (1) 3

(2) 4

.JS Sim Phase USE THIS (19 decks)

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