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LOIT Questions > Tech Specs > Flashcards

Tech Specs Flashcards

1
Q

State the Modes 1-6

A

Mode 1 >= 0.99 keff > 5% Thermal Power
Mode 2 >= 0.99 keff < 5% Thermal Power
Mode 3 < 0.99 keff >= 350 degrees TCOLD
Mode 4 < 0.99 keff > 210 and < 350 degrees TCOLD
Mode 5 < 0.99 keff <= 210 degrees TCOLD
Mode 6 1 or more reactor vessel head bolts not fully tensioned

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2
Q

Describe LCO 3.0.3.

A

LCO 3.0.3 is applicable when an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS.

  • Action shall be initiated within 1 hour to shutdown the unit
  • Mode 3 in 7 hours
  • Mode 5 in 37 hours
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3
Q

Describe LCO 3.0.4.

A

When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;
b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specifications, or;
c. When an allowance is stated in the individual value, parameter, or other Specification

NOTE: This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

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4
Q

Describe LCO 3.0.6.

A

When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. In this event, an evaluation shall be performed in accordance with Specification 5.5.15 “Safety Function Determination Program (SFDP)” If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

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5
Q

State Reactor Core Safety Limits when in Modes 1 & 2.

A

1) Departure from Nucleate Boiling Ratio (DNBR) shall be maintained >= 1.34.
2) Peak fuel centerline temp. shall be maintained <5080 F (decreasing by 58 F for every 10,000 MWD/MTU for burnup and adjusting for burnable poisons).

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6
Q

State the Reactor Coolant System pressure Safety Limit.

A

In Modes 1, 2, 3, 4, and 5 the RCS pressure shall be maintained <= 2750 psia.

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7
Q

Who must be notified upon the violation of a Safety Limit? What is the time limit associated with this notification?

A

The NRC must be notified of the Safety Limit Violation within one hour of the violation.

(operation of the Unit shall not be resumed until authorized by the NRC).

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8
Q

What are the actions associated with violating the RCS pressure Safety Limit?

A

In MODE 1 or 2: restore compliance and be in MODE 3 within one hour.
In MODE 3, 4, or 5: restore compliance within five minutes.

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9
Q

On 9/1/2013 at 0600, ‘A’ HPSI was tagged out for maintenance. LCO 3.5.3 condition B (72 hour completion time) was entered.
On 9/3/2013 at 0800, ‘B’ HPSI is declared inoperable following an engineering evaluation. LCO 3.0.3 entered.
On 9/3/2013 at 0830, ‘A’ HPSI is declared operable. LCO 3.0.3 exited.
When must the ‘B’ HPSI pump be declared operable to avoid exceeding the completion time of LCO 3.5.3 condition B?

A

9/5/13 at 0600

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10
Q

Unit 1 ESF service transformer NBN-X03 trips on sudden pressure at 0800. LCO 3.8.1 condition A is entered for one inoperable offsite power circuit.

a) What is the latest time allowable for acceptance review of 41ST-1ZZ02 to meet SR 3.8.1.1?
b) Assuming 41ST-1ZZ02 is acceptance reviewed at 0845, what is the latest time allowable for the next performance of 41ST-1ZZ02?

A

a) 0900. No extension allowed for a one time performance frequency.
b) 1845. 1.25x frequency is allowed for subsequent performances.

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11
Q

What is the significance of a word or phrase written completely in capital letters in Tech Specs?

A

The word or phrase is defined in Tech Specs section 1.1 Definitions.

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12
Q

A surveillance test was missed on the ‘A’ HPSI pump, and the required frequency has since expired. How does SR 3.0.3 apply in this situation?

A

The ‘A’ HPSI pump may be declared inoperable. However, an immediate operability determination (IOD) may be performed, and as long as the results from the IOD indicate performance of the surveillance test would show the pump complies with the LCO, the pump may remain operable pending performance of the surveillance. The surveillance must be performed within the greater of 24 hours or the full surveillance frequency. If delayed greater than 24 hours, a risk evaluation must be performed.

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13
Q

All three units are in Mode 1 at 100% power with all systems in a normal alignment.
East and west bus voltage in the SRP switchyard is 517 kV.
Which of the following actions in accordance with LCO 3.8.1 would allow indefinite operation of Unit 1?
A. Raise switchyard voltage to 520 kV
B. Reduce Unit 1 MVAR to less than 0 MVAR boost
C. Transfer PBA-S03 and PBB-S04 from offsite power to their DGs
D. Verify bus tie breakers are open and block fast bus transfer on NAN-S01 and NAN-S02

A

D

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14
Q

All three units are in Mode 1 at 100% power with all systems in a normal alignment.
East and west bus voltage in the SRP switchyard is 517 kV.
Which of the following actions in accordance with LCO 3.8.1 would allow indefinite operation of Unit 2?
A. Raise switchyard voltage to 520 kV
B. Reduce Unit 1 MVAR to less than 0 MVAR boost
C. Transfer PBA-S03 and PBB-S04 from offsite power to their DGs
D. Verify bus tie breakers are open and block fast bus transfer on NBN-S01 and NBN-S02

A

A

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15
Q

Unit 1 was at 100% power with all systems in their normal alignment.
NAN-X03 and NBN-X03 trip on sudden pressure.
DG ‘A’ trips on low lube oil pressure.
Which of the following required actions MUST be completed within one hour for these plant conditions?
A. Enter LCO 3.0.3
B. Perform SR 3.8.1.1 for the OPERABLE required offsite circuit.
C. Restore required DG to OPERABLE status
D. Restore AC electrical power distribution subsystem to OPERABLE status

A

B

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16
Q

Unit 2 was at 100% power with all systems in their normal alignment.
NAN-X03 and NBN-X03 trip on sudden pressure.
DG ‘A’ trips on low lube oil pressure.
Which of the following required actions MUST be performed immediately for these plant conditions?
A. Enter LCO 3.0.3
B. Restore required offsite circuit to OPERABLE status.
C. Restore required DG to OPERABLE status
D. Restore AC electrical power distribution subsystem to OPERABLE status

A

A

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17
Q

Unit 3 is in Mode 1. There is no fuel movement in progress.
Which of the following would result in an LCO entry with an action required within one hour or less?
A. PKC placed on equalizing charge with ‘C’ battery charger
B. PNA inverter INOPERABLE
C. ‘A’ DG Fuel Oil Storage Tank at 70%
D. ‘A’ BOP-ESFAS sequencer INOPERABLE

A

C

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18
Q

What is in section 1.0 of the TS

A

Use and application

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19
Q

What is in section 2.0 of TS

A

Safety Limits

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20
Q

What is in section 3.0 of TS

A

LCOs and SRs

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21
Q

What is in section 3.1 of TS

A

Reactivity Control Systems

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22
Q

What is in section 3.2 of TS

A

Power distribution limits

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23
Q

What is in section 3.3 of TS

A

Instrumentation

24
Q

What is in section 3.4 of TS

A

RCS

25
Q

What is in section 3.5 of TS

A

ECCS

26
Q

What is in section 3.6 of TS

A

Containment

27
Q

What is in section 3.7 of TS

A

Plant systems

28
Q

What is in section 3.8 of TS

A

Electrical Power Systems

29
Q

What is in section 3.9 of TS

A

Refueling operations

30
Q

What is in section 4.0 of TS

A

Design Features

31
Q

What is in section 5.0 of TS

A

Administrative Controls

32
Q

Unit 1 is at 100% power with all systems in a normal lineup.
RCC-PT-101C, Narrow Range Pressurizer Pressure, fails low.
LCO 3.3.1 requires which of the following parameters on PPS channel ‘C’ to be placed in bypass?
A. Pressurizer Pressure Low
B. Local Power Density High
C. Reactor Coolant Flow Low
D. Variable Overpower High

A

B

33
Q

Unit 2 is at 100% power with all systems in a normal lineup.
SGA-PT-1013A, #1 Steam Generator Pressure, fails low.
LCO 3.3.5 requires which of the following parameters on PPS channel ‘A’ to be placed in bypass?
A. Steam Generator #2 Pressure High
B. Steam Generator #2 Pressure Low
C. Steam Generator #2 Level Low (RPS)
D. Steam Generator #2 Level Low (ESF)

A

D

34
Q 
Which of the following RPS trips is designed to protect the RCS from a single RCP rotor seizure in accordance with the bases for LCO 3.3.1?
A.	Steam Generator Level Low
B.	Local Power Density High
C.	Pressurizer Pressure High
D.	Variable Overpower High
A

A

35
Q

Unit 2 is in Mode 5.
‘A’ CREFAS is operable. ‘B’ CREFAS has been declared inoperable.
‘A’ and ‘B’ trains of CREFS are both operable, but neither is in operation.
How is compliance with LCO 3.3.9, Control Room Essential Filtration Actuation Signal (CREFAS), being met?
A. LCO 3.3.9 is not met. Two trains of CREFAS are required to be operable in MODE 5. Immediately place either train of CREFS in essential filtration mode.
B. LCO 3.3.9 is not met. Two trains of CREFAS are required to be operable in MODE 5. Immediately place the ‘A’ train of CREFS in essential filtration mode.
C. Currently in compliance with LCO 3.3.9. Only one train of CREFAS is required to be operable in MODE 5.
D. Compliance with LCO 3.3.9 is not required, as it does not apply in MODE 5.

A

C

36
Q

Unit 3 is in MODE 6.
CORE ALTERATIONS are not in progress.
Refueling Pool water level is 134 feet.
‘A’ train of Shutdown Cooling is OPERABLE and in operation.
Which of the following statements accurately describes the required condition of ‘B’ train of Shutdown Cooling?
A. ‘B’ train of SDC is not required to be operable.
B. ‘B’ train of SDC is required to be operable. If it becomes inoperable, all open containment penetrations must be closed immediately.
C. ‘B’ train of SDC is required to be operable. If it becomes inoperable, all actions that would reduce RCS boron concentration must be suspended immediately.
D. ‘B’ train of SDC is required to be operable. It may be rendered inoperable for up to two hours for surveillance testing without entering the applicable LCO.

A

D

37
Q

Unit 3 is in MODE 6.
CORE ALTERATIONS are in progress.
Refueling Pool water level is 138 feet.
‘A’ train of Shutdown Cooling is OPERABLE and in operation.
Which of the following statements accurately describes the required condition of ‘B’ train of Shutdown Cooling?
A. ‘B’ train of SDC is not required to be operable.
B. ‘B’ train of SDC is required to be operable. If it becomes inoperable, CORE ALTERATIONS must be suspended immediately.
C. ‘B’ train of SDC is required to be operable. If it becomes inoperable, all actions that would reduce RCS boron concentration must be suspended immediately.
D. ‘B’ train of SDC is required to be operable. It may be rendered inoperable for up to two hours for surveillance testing without entering the applicable LCO.

A

A

38
Q

Unit 1 is in MODE 6.
Core offload is in progress.
Refueling Pool water level is 138 feet.
‘A’ train of Shutdown Cooling is OPERABLE and in operation with ‘A’ LPSI pump.
‘B’ train of Shutdown Cooling is OPERABLE.
If ‘A’ LPSI pump trips, which of the following actions is required by Technical Specifications?
A. Suspend core offload immediately
B. Suspend actions that would reduce RCS boron concentration immediately
C. Close all open containment penetrations immediately
D. Start the ‘A’ CS pump immediately

A

B

39
Q

Unit 1 is at 15% power.
CEDMCS is in Manual Sequential, controlling with Regulating Group 5 at 60” withdrawn.
CEA 14, a Regulating Group 5 CEA, drops to the bottom of the core and brings in the rod bottom light.
Which of the following LCOs are not met?
1) LCO 3.1.5 CEA alignment
2) LCO 3.1.7 Regulating CEA insertion limits

A. Only LCO 3.1.5 is not met
B. Only LCO 3.1.7 is not met
C. Both LCO 3.1.5 and LCO 3.1.7 are not met
D. Both LCO 3.1.5 and LCO 3.1.7 are met

A

A

40
Q

Unit 1 is at 15% power.
CEDMCS is in Manual Sequential, controlling with Regulating Group 5 at 60” withdrawn.
CEA 14, a Regulating Group 5 CEA, slips to 30” withdrawn.
CPC ASI is -0.2
Which of the following LCOs are not met?
1) LCO 3.2.4 DNBR
2) LCO 3.1.7 Regulating CEA insertion limits

A. Only LCO 3.2.4 is not met
B. Only LCO 3.1.7 is not met
C. Both LCO 3.2.4 and LCO 3.1.7 are not met
D. Both LCO 3.2.4 and LCO 3.1.7 are met

A

B

41
Q

Unit 1 is at 100% power with all systems in a normal lineup.
‘A’ Main Feed Pump trips on high vibration.
All systems actuate as designed.
The CRS enters 40AO-9ZZ09, Reactor Power Cutback (Loss of Feed Pump).
At what point will entry into LCO 3.1.7, Regulating CEA Insertion Limits, be required?
A. Entry into the LCO, conditions, and required actions are required as soon as the RPCB occurs.
B. Entry into the LCO is required as soon as the RPCB occurs. The Conditions are not required to be entered, nor the required actions be performed, for two hours after the RPCB occurs.
C. Entry into the LCO is not required until two hours after the RPCB occurs.
D. Entry into the LCO is not required, as CEAs are above the insertion limits.

A

C

42
Q 
Which of the following systems is credited by Technical Specifications and the UFSAR for performing the primary depressurization in the event of a Steam Generator Tube Rupture concurrent with a loss of offsite power and a stuck open ADV?
A.	Main Spray Valves
B.	Auxiliary Spray Valves
C.	Reactor Head Vents (RCGVS)
D.	Pressurizer Vents (RCGVS)
A

D

43
Q

Unit 3 is in Mode 4, performing a plant cooldown to Mode 5 to comply with TS 3.8.1.
‘A’ DG was out of service due to a governor failure.
Both trains of Shutdown Cooling are aligned for operation but are not in service.
RCPs 1B and 2B are running, RCPs 1A and 2A are secured but available to be started.
AFN-P01 is feeding both SGs at 50 gpm.
Steam Generator levels are 45% NR and stable.
NAN-X02 locks out on a sudden pressure relay trip.
What is the status of compliance with TS 3.4.6, RCS Loops – MODE 4?
A. In compliance.
B. Not in compliance, because steam generators are not being fed.
C. Not in compliance, because a required SDC train is inoperable.
D. Not in compliance, because a required loop is not in operation.

A

A

44
Q 
Which channels of RU-1, containment atmosphere radioactivity monitor, are required to be operable in order to comply with TS 3.4.16, RCS Leakage Detection Instrumentation?
A.	Particulate and Iodine ONLY
B.	Iodine and Gaseous ONLY
C.	Particulate and Gaseous ONLY
D.	Particulate, Iodine, and Gaseous
A

C

45
Q

As the core ages, moderator temperature coefficient at 100% power becomes…
A. More negative because equilibrium xenon concentration at 100% power is higher.
B. More negative because RCS boron concentration at 100% power is lower.
C. Less negative because equilibrium xenon concentration at 100% power is higher.
D. Less negative because RCS boron concentration at 100% power is lower.

A

B

46
Q

Concerning shutdown margin requirements, the most limiting main steam line break, with respect to potential fuel damage before a reactor trip occurs, is a guillotine break of a main steam line…
A. Outside containment at the beginning of core life.
B. Inside containment at the beginning of core life.
C. Outside containment at the end of core life.
D. Inside containment at the end of core life.

A

D

47
Q

By maintaining Linear Heat Rate within the limits of LCO 3.2.1, then in the event of a LOCA…
A. Peak fuel cladding temperature will not exceed 2200 degrees.
B. Peak fuel centerline temperature will not exceed 2200 degrees.
C. Peak fuel cladding temperature will not exceed 5080 degrees.
D. Peak fuel centerline temperature will not exceed 5080 degrees.

A

A

48
Q 
The assumed boration flow rate for re-establishing shutdown margin is \_\_\_(1)\_\_\_.  When using a source of 4000 ppm, this will raise RCS boron concentration by \_\_\_(2)\_\_\_ in less than four hours.
A.	(1) 26 gpm; (2) 500 ppm
B.	(1) 40 gpm; (2) 500 ppm
C.	(1) 26 gpm; (2) 100 ppm
D.	(1) 40 gpm; (2) 100 ppm
A

C

49
Q

LCO 3.2.4, Departure from Nucleate Boiling Ratio (DNBR), is not applicable when less than 20% power because…
A. CPCs assume a minimum reactor power of 20% when generating trip signals, making the trips highly conservative.
B. DNBR will not be less than 1.34 under any anticipated operational occurrence with reactor power less than 20%.
C. Peak fuel centerline temperature will not exceed 5080 degrees under any accident condition with initial reactor power less than 20%.
D. Transmitters which provide COLSS with parameters for calculating plant power are highly inaccurate when reactor power is less than 20%.

A

A

50
Q 
The design basis for the Main Steam Safety Valves is to limit secondary system pressure to less than \_\_\_(1)\_\_\_ of design pressure when passing \_\_\_(2)\_\_\_ of design steam flow.
A.	(1) 100%; (2) 100%
B.	(1) 110%; (2) 100%
C.	(1) 100%; (2) 110%
D.	(1) 110%; (2) 110%
A

B

51
Q 
What is the minimum number of Main Steam Safety Valves required to be OPERABLE in Mode 3?
A.	1 per steam generator
B.	2 per steam generator
C.	Any two of the twenty valves
D.	Any four of the twenty valves
A

B

52
Q

Unit 1 is at 100% power with all systems in a normal lineup. It is September 21.
SG ISOL VLV TRBL alarm is in fast flash due to a bad high rod end pressure switch on FWIV 137.
Unseasonably warm daytime temperatures followed by an evening storm cause a large temperature drop in the MSSS.
Regulator settings for the MSIV air pumps were not readjusted after the pump was stalled when the MSIV pressures were last adjusted.
At 2000, the RO notes the ‘A’ train accumulators on all 4 MSIVs are now reading 4900 psig.
The CRS enters the appropriate actions per LCO 3.7.2, MSIVs.
With no operator action to readjust accumulator pressures, the unit would be required to be shutdown in mode 3 by:
A. 0300 on September 22
B. 0600 on September 22
C. 2000 on September 23
D. 2000 on September 24

A

A

53
Q

Unit 2 is in Mode 4, cooling down to SDC entry conditions.
Tc is currently 340 degrees and lowering.
Which trains of Auxiliary Feed Water are required to be operable?
A. AFA, AFB, and AFN
B. AFA, AFB, or AFN
C. AFA and AFB
D. AFB or AFN

A

D

54
Q 
The TS volume of the CST is based on holding the unit in Mode 3 for \_\_\_(1)\_\_\_ followed by a cooldown to SDC entry conditions at \_\_\_(2)\_\_\_.
A.	(1) 4 hours; (2) 75 degrees per hour
B.	(1) 4 hours; (2) 100 degrees per hour
C.	(1) 8 hours; (2) 75 degrees per hour
D.	(1) 8 hours; (2) 100 degrees per hour
A

C

55
Q

Unit 3 is at 100% power with all systems in a normal lineup.
The spray pond pumps are being started for thrice weekly spray pond chemical additions.
The ‘A’ spray pond pump fails to start. The CRS declares in inoperable and enters LCO 3.7.8, Essential Spray Pond System.
The applicable conditions and required actions for which of the following supported systems are required to be performed?
A. LCO 3.4.6, RCS Loops – MODE 4
B. LCO 3.6.6, Containment Spray System
C. LCO 3.7.7, Essential Cooling Water System
D. LCO 3.8.1, AC sources – Operating

A

D

56
Q

The maximum post-accident head load for the Ultimate Heat Sink occurs…
A. One minute following a design basis LOCA due to RCS decay heat removal
B. Twenty minutes following a design basis LOCA due to RCS decay heat removal
C. One minute following a design basis LOCA due to starting load on the DGs
D. Twenty minutes following a design basis LOCA due to SI pumps operating at runout conditions

A

B

57
Q
A

LOIT Questions (86 decks)

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