Tech. Specs. Flashcards by Mike Jones

Unit has been at 100% power for the last 200 days. Chemistry Supervisor has just informed Shift Manager that SR 3.5.5.3 has not performed for the last 18 days. Assuming a risk evaluation has been performed, LCO 3.5.5 is…

A. NOT met, boron concentration must be verified within 8 hours.
B. NOT met, boron concentration must be verified within 1 hour.
C. met, the missed SR must be performed within 7 days.
D. met, the missed SR must be performed within 24 hours.

Answer: C

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Tech Spec 3.7.7 states …with one EW train inoperable, restore the EW train to OPERABLE status within 72 hours. Tech Spec 3.6.6 states …with one Containment Spray train inoperable, restore the Containment Spray train to OPERABLE status within 72 hours. Given the following conditions:
1200 10/05/99EW ‘A’ is declared inoperable due to a breaker problem.
1200 10/07/99CS ‘A’ is declared inoperable due to failed room cooler.
1100 10/08/99EW ‘A’ is restored to service.
Assuming 3.0.6 was implemented, when does CS ‘A’ have to be restored to service?

A. 1200 10/08/99
B. 1200 10/10/99
C. 1100 10/11/99
D. 1200 10/11/99

Answer: B

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Unit is operating at rated power. One Diesel Generator becomes inoperable. Which one of the following Tech Spec actions must be completed within one hour?

A. Verify correct breaker alignment and indicated power availability for two offsite power sources.
B. Restore DG to operable status.
C. Determine that DG “B” is not inoperable due to a common cause failure.
D. Declare required feature(s) supported by DG inoperable when its redundant required feature(s) is inoperable.

Answer: A

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The plant is at 100% power. A shutdown CEA drops into the core. In accordance with Tech Specs the operator should ….

A. enter LCO 3.1.6 immediately and immediately restore shutdown CEAs to within limits.
B. not enter LCO 3.1.6, entry is not required for 2 hours.
C. enter LCO 3.1.6 immediately and restore shutdown CEAs to within limits in the next 2 hours.
D. enter LOC 3.1.6 immediately and restore shutdown CEAs to within limits in the next 4 hours.

Answer: C

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The Unit is exiting an outage with the plant at 345°F Tcold. During the outage, AFA-P01 was torn down for maintenance. A new governor assembly was installed due to older one having excessive tolerances. AFA-P01 is aligned and ready. All maintenance activities have been completed as have all applicable Surveillance Requirements, with the exception of SRs 3.7.5.2, 3.7.5.3, and 3.7.5.4. These have not been completed due to the fact that testing can only be accomplished once temperature reaches 532°F. Based on this, AFA-P01 is…

A. not operable, but functional.
B. operable until Mode 3 entry.
C. operable.
D. functional only, until tested at NOP/NOT.

Answer: C

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Unit 1 is exiting an outage with the plant at 345°F Tcold. During the outage, AFA-P01 was torn down for maintenance. A new governor assembly was installed due to older one having excessive tolerances. AFA-P01 is aligned and ready. All maintenance activities have been completed, as have all applicable Surveillance Requirements, with the exception of SRs 3.7.5.2, 3.7.5.3, and 3.7.5.4. AFA-P01 is considered…

A. operable, however SR 3.0.4 will prevent the mode change until these surveillance requirements are complete.
B. operable, SR 3.0.1 allows the unit to complete required surveillances when plant conditions can support.
C. inoperable, however the mode change can be completed and the required surveillances must be completed within 24 hours.
D. inoperable, however the mode change can be completed and the required surveillances must be completed within 72 hours.

Answer: B

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What is shutdown margin?

A. The amount of positive reactivity by which the reactor can or will be shutdown
B. The amount of positive reactivity associated with boron and temperature
C. The amount of negative reactivity associated with Xenon and temperature
D. The amount of negative reactivity by which the reactor can or will be shutdown

Answer: D

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Which of the following statements correctly identifies when a HPSI pump is to be used for Emergency Boration per 40AO-9ZZ01, “Emergency Boration”?

A. Anytime RCS pressure is less than HPSI shutoff head.
B. Anytime a SIAS/CIAS occurs.
C. Only if Charging pumps are unavailable.
D. Only if Reactor Coolant System Tcold is less than 350 degrees F.

Answer: C

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Which of the following sets of parameters are within allowable safety limits?

A. DNBR >1.25 - peak fuel centerline temperature 1.3 - peak fuel centerline temperature 1.34 - peak fuel centerline temperature 1.4 - peak fuel centerline temperature

Answer: C

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The Plant is at 100% power. Tc - 565°F. Pressurizer Pressure - 2250 psia. CEA #14 deviates from group 5 by 15 inches and is being troubleshot by I&C. The operator should …

A. be in Mode 3 within 6 hours.
B. reduce thermal power in accordance with the COLR within 1 hour.
C. open the RTCBs immediately
D. open the RTCBs within 2 hours.

Answer: B

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

A. at least 26 days of required loads following a LOCA.
B. 4 days of required loads following a LOCA.
C. 7 days of full load operations.
D. 4 days of full load operation followed by 10 days of one train of Shutdown Cooling loads.

Answer: C

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Which of the following is true regarding Tech Specs and their bases?
A. Neither Tech Specs or their bases are required to submit the application but both are required before a license to operate is issued.
B. Tech Specs are required to be submitted with the license application per 10CFR, bases are not required by 10CFR but by NUREGs.
C. Both are required to be submitted with the license application by 10CFR.
D. Only the bases of Tech Specs must be submitted with the license application, Tech Specs must be subsequently created and approved before power operations is allowed.

Answer: C

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

A. The measured radial peaking factors (RPF) will always be

Answer: D

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Unit is operating at 90% power. COLSS is declared inoperable on the CMC and PC due to computer hardware failures. The operating crew performs 72ST-9RX03, DNBR/LHR/AZTILT/ASI With COLSS Out Of Service. The value for DNBR is not within the acceptable region of the curve. Based on these conditions, the operating crew is required to…

A. determine the trend in LHR once per 15 minutes.
B. within 10 minutes, reduce power per the graph in the COLR.
C. within 15 minutes, take action to reduce thermal power to less than or equal to 20% RTP.
D. immediately take action to reduce thermal power to a value that restores LHR to within its LCO.

Answer: A

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Unit is operating at rated power. CREFAS Train “A” is in BYPASS. RU-31 (Fuel Pool Area Monitor) fails HIGH. Which of the following describes the expected plant response?

A. Both Trains of FBEVAS and both Trains of CREFAS actuate.
B. Train A FBEVAS actuates ONLY.
C. No actions should occur due to this signal failure.
D. Both Trains of FBEVAS and Train “B” of CREFAS actuate.

Answer: A

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Unit is operating at rated power. COLSS is declared inoperable. The operating crew performs 72ST-9RX03, DNBR/LHR/AZTILT/ASI With COLSS Out of Service. The value for LHR does NOT meet the LCO. Based on these conditions, the operating crew is required to…

A. reduce thermal power to less than or equal to 20% RTP in 1 hour.
B. restore LHR to a value within the LCO in 1 hour.
C. reduce thermal power by at least 20% RTP in 1 hour.
D. determine the trend in LHR once per 15 minutes.

Answer: D

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Which of the following is required for Administrative Controls to open a locked closed containment isolation valve such as DWN V-061/62. The operator must:

A. remain in the same building level, and in communication with the control room, unless the valve is in the RCA.
B. remain in the same building, and be in constant communication with the control room.
C. be able to close the valve within 5 minutes, after ordered by the control room.
D. be in constant communication with the control room, and at the valve controls.

Answer: D

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With COLSS out of service and linear heat rate (LHR) not within the acceptable operation region of the COLR, which of the following must be done?

A. restore linear heat rate to within limits within 15 minutes.
B. determine trend in LHR within 30 minutes.
C. restore linear heat rate to within limit within 30 minutes.
D. determine trend in LHR within 15 minutes.

Answer: D

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The plant is at 100% power when CRS discovers that the surveillance requirement (SR) to verify operable CEA position indicator channels indicate within 5.2 inches of each other was not performed within the last 17 hours (SR 3.1.5.2). The required frequency of SR 3.1.5.2 is 12 hours. The operator should:

A. declare entry into LCO 3.1.5 immediately & perform the SR within 1 hour.
B. declare entry into LCO 3.1.5 immediately & perform the SR.
C. invoke SR 3.0.3 and declare entry into LCO 3.1.5 immediately and reduce thermal power in accordance with the limits in the COLR.
D. invoke SR 3.0.3 but not enter into LCO 3.1.5, because the SR may be delayed for 12 hours from the time of discovery, by invoking SR3.0.3

Answer: D

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Action statement for 3.7.5 (Condition A) states, …with one steam supply to turbine driven AFW pump inoperable, restore the steam supply to OPERABLE status within 7 days AND 10 days from the discovery of the failure to meet the LCO. Action statement for 3.7.5 (Condition B) states, …with one train of AFW inoperable, restore the AFW train to OPERABLE status within 72 hours AND 10 days from the discovery of the failure to meet the LCO. Given the following conditions:
1200 11/10: Steam supply SGA-UV-134 becomes inoperable.
1200 11/15: AFB-P01 becomes inoperable.
1300 11/16: Steam supply SGA-UV-134 becomes OPERABLE.
1200 11/17: Steam supply SGA-UV-138 becomes inoperable.
1400 11/17: AFB-P01 becomes OPERABLE Assuming that extensions are applied (if applicable), which of the following identifies the time and date for restoration of SGB-UV-138 before further action is required.

A. 1200 on 11/20
B. 1200 on 11/19
C. 1200 on 11/25
D. 1200 on 11/24

Answer: A

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Tech. Spec. Surveillance Requirement 3.5.5 requires the RWT boron concentration to be verified every 7 days in modes 1 through 4. Assume it has been 8 days since the RWT boron concentration has been verified while the plant is in mode 1. What is the status of the RWT?

A. Inoperable because the surveillance interval of Tech. Spec. 3.0.3 was exceeded.
B. Operable because a 25% extension of the surveillance interval is allowed by SR 3.0.2.
C. Inoperable because the 24 hour delay period of SR 3.0.3 has been exceeded.
D. Operable because the surveillance requirement only needs to be done once within 7 days of entering mode 1.

Answer: B

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Unit 1 is operating at rated power. One Atmospheric Dump Valve (ADV) becomes inoperable. The other valves are operable. Based on these conditions, the Operating Crew is required to… (Consider the TS requirement ONLY)

A. perform no actions since the LCO is met.
B. restore the inoperable ADV within 1 hour.
C. restore the inoperable ADV within 30 minutes.
D. immediately take action to place the plant in Mode 3.

Answer: A

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Technical Specification 3.1.4 places limits on both the positive and negative values of the core’s Moderator Temperature Coefficient (MTC) of Reactivity. These limits ensures that in the event of the limiting accident occuring, a violation of the accident analysis assumption(s) will NOT occur. Of the choices below, which is the limiting accident for the NEGATIVE value of MTC?

A. Loss of all feedwater.
B. CEA ejection.
C. Main steam line break.
D. Continuous rod withdrawal.

Answer: C

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The Unit is exiting a refueling outage, with the plant at 345°F Tcold. During the outage, AFA-P01 was torn down for maintenance. A new governor assembly was installed, due to older one having excessive tolerances. AFA-P01 is aligned and ready. All maintenance activities have been completed, as have all applicable Surveillance Requirements, with the exception of SRs 3.7.5.2, 3.7.5.3, and 3.7.5.4, due to the fact that testing can only be accomplished once temperature reaches 532°F. AFA-P01 is considered operable because:

A. SR 3.0.4 allows this condition until steam pressure is >800 psi.
B. SR 3.0.4 allows this condition.
C. SR 3.0.1 allows this condition until steam pressure is >500 psi.
D. SR 3.0.1 allows this condition.

Answer: D

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The Unit has been at rated power for 6 months. The crew discovers that 40ST-9AF07, AFA-P01 Monthly Valve Alignment, was not performed this month. This ST satisfies SR 3.7.5.1. AFN-P01 and AFB-P01 are operable. In accordance with SR 3.0.3 AND assuming a risk evaluation is performed, the crew should... A. perform the required ST within 31 days. B. perform the required ST within 24 hours. C. perform the required ST within 7 days. D. declare AFA inoperable and perform the required ST.

Answer: A

The Unit is at 100% power The crew discovers that SR 3.7.5.1 required for AFA-P01 was missed. The crew must... A. declare AFA inoperable and perform the ST within 7 days in accordance with SR 3.0.1. B. maintain AFA operable and perform the ST within 31 days in accordance with SR 3.0.3. C. declare AFA inoperable and perform the required ST as required by SR 3.0.3. D. maintain AFA operable and perform the ST within 72 hours in accordance with SR 3.0.1.

Answer: B

Unit is in Mode 3. 'B" Diesel Generator has been tagged out for an on-line maintenance. The air start system is also tagged out and has been depressurized (both receivers have been depressurized to

Answer: D

RCA-PT-101A (pressurizer Pressure) fails high tripping it's RPS Channel. This instrument is bypassed. Subsequently, RCC-PT-101C fails low. Based on these indications, the Operating Crew is required to... A. remove channel A pressurizer pressure high from bypass within 1 hour. B. take no action. C. bypass channel C pressurizer pressure high within 1 hour. D. have Instrument Maintenance trip channel C pressurizer pressure high within 1 hour.

Answer: D

A plant cooldown is in progress. RCS temperature is currently 362°F. The secondary operator reports RCS cooldown rate for the last hour has been 120°F. The operator is required to restore the cooldown rate to within limits in: A. 30 minutes. B. immediately. C. 15 minutes. D. 60 minutes.

Answer: A

WHICH ONE of the following requires that boration be established per 40AO-9ZZ01, "EMERGENCY BORATION"? A. Entry into the Lower Mode Functional Recovery Procedure. B. A plant cooldown has been directed by the CRS. C. Entry into any Emergency Operating Procedure. D. Shutdown Margin has been lost.

Answer: D

What is the basis of the Technical Specification requirement to open the Reactor Trip Breakers in the event that two CEAs are misaligned by greater than 9.9 inches? A. Minimizes the potential for fuel damage B. Minimizes the possibility of operating wihout required SDM C. Minimizes the effect of a possible ejected CEA D. Prevents challenge to ASI trip

Answer: A

In accordance with Technical Specifications, the MTC maximum positive value (limit) is based on a: A. CEA withdrawal from a subcritical condition. B. steam line break at 0% power. C. steam line break at 15% power. D. CEA withdrawal at the point of adding heat.

Answer: A

``` The plant is in Mode 3 with Reactor trip breakers open. It is discovered that adequate SDM does not exist. Based on these conditions, the crew is required to initiate boration to restore SDM... A. immediately. B. within 15 minutes. C. within 30 minutes. D. within 60 minutes. ```

Answer: B

The unit is at rated power. A Regulating Group CEA slips 10 inches into the core. Based on these conditions, the crew is required to... A. reduce thermal power to within COLR limits within 30 minutes. B. trip the reactor and implement SPTAs. C. reduce thermal power to within COLR limits within 15 minutes. D. reduce thermal power to the COLR limits within 1 hour.

Answer: D

The bases for meeting the LCO on DNBR is: A. An acceptable minimum DNBR will be maintained in the event of a loss of flow transient, CEA misoperation, or assymetric SG transient. B. It ensures that COLSS Calculated Power will not exceed the COLSS POL based on linear heat rate. C. LPD will be

Answer: A

According to the ECCS design criteria found in 10CFR "The calculated total oxidation of the cladding shall nowhere exceed _____ % of the total cladding thickness before oxidation." A. 17 B. 1 C. 27 D. 35

Answer: A

Unit 1 is operating in Mode 1. A Pressurizer Safety valve becomes inoperable. All other safety valves are operable. What actions (if any) are required per Technical Specifications? A. No actions since the LCO is met. B. Restore the safety valve to OPERABLE status in 15 minutes. C. Restore the safety valve to OPERABLE status in 30 minutes. D. Restore the safety valve to OPERABLE status in 1 hour.

Answer: B

"________________ are the lowest functional capability or performance levels of equipment required for safe operation of the facility." A. Safety Limits B. LCOs C. Safety Functions D. Single trains of class equipment

Answer: B

The plant is in Mode 4 performing a heatup to Mode 3. The output from all 8 sensors on the Channel B RVLMS probe have failed. I&C suspects the cabling from the probe assembly. Based on these conditions, apply Technical Specifications LCO 3.3.10 and assess the operability impact regarding entrance into Mode 3. A. Mode 3 entry is not permitted. because two Trains of RVLMS are required to be Operable in Mode 3. B. Mode 3 entry is permitted. Enter LCO 3.3.10, Conditions A, Actions A.1. C. Mode 3 entry is not permitted. because entry into LCO 3.3.10, Conditions A, Actions A.1 is required. D. Mode 3 entry is permitted. Enter LCO 3.3.10, Conditions A and G, Actions A.1 and G.1.

Answer: B

Unit 1 is operating in Mode 1. A failure of one required Class 1E Battery Charger occurs. Technical Specifications require the operating crew to: A. take no action as long as the DC electrical power subsystem is operable. B. align the Battery Charger within 2 hour. C. immediately declare the battery inoperable. D. verify that the battery meets category A limits within 1 hour.

Answer: D

Based on Technical Specifications, entry into Mode 5 from Mode 6 will occur when..... A. all reactor head closure bolts are fully tensioned. B. RCS cold leg temperature exceeds 135°F. C. RCS cold leg temperature exceeds 200°F. D. all reactor head closure bolts are fully tensioned and cold leg temperature > 210°F.

Answer: A

The plant is at 100% power. A CEA misalignment has caused Azimuthal Power Tilt to exceed the limit specified in the Core Operating Limits Report (COLR). COLSS is in service. Which one of the following states the actions required by Tech. Specs? A. Reduce thermal power to

Answer: A

Unit 1 is in mode 1, 30% power. Atmospheric Dump Valve SGE PV 179 is declared inoperable. All other ADV's are operable What action (if any) is required by Tech Specs? A. None. B. Be in mode 3 in 6 hours. C. Restore ADV 179 to operable within 24 hours. D. Restore ADV 179 to operable within 72 hours.

Answer: A

``` TC-558°F Pressurizer Level - 50% Reactor Power 70% Group 5 CEA's @ 60" The current Tech Spec Transient Insertion limit for Group 4 CEAs is: ``` A. 60" B. 150" C. 100" D. 120"

Answer: B

The plant is at 100% power. Steam Generator Level #1 (wide range) Channel "A" fails LOW. Within 1 hour, the operator must bypass or trip Channel "A": A. Steam Generator #1 Level Low (RPS)Steam Generator #1 Level Low (ESF)Steam Generator #2 Level Low (ESF) B. Steam Generator #1 Level Low (RPS)Steam Generator #1 Level Low (ESF)Steam Generator #2 Level Low (RPS) C. Steam Generator #1 Level Low (RPS)Steam Generator #1 Pressure Low (ESF)Steam Generator #2 Level Low (RPS) D. Steam Generator #1 Level Low (RPS)Steam Generator #2 Pressure Low (ESF)Steam Generator #2 Level Low (RPS)

Answer: A

The plant is at 100%. Pressurizer pressure channel "A" (narrow range) fails HIGH. Within 1 hour the operator must bypass or trip Channel "A"... A. Variable Overpower (VOPT)Local Power Density - HIGH (RPS)DNBR - LOW (RPS) B. Pressurizer Pressure - LOW (RPS)Local Power Density - HIGH (RPS)DNBR - LOW (RPS) C. Pressurizer Pressure - HIGH (RPS)Local Power Density - HIGH (RPS)DNBR - LOW (RPS) D. Variable Overpower (VOPT)Local Power Density - HIGH (RPS)RCS Flow - LOW

Answer: C

The plant is at 20% power and stable Chemistry reports RCS Chloride is 0.75 ppm. The operator should.... A. Be in Mode 3 in 6 hours and Mode 5 in 36 hours B. Restore parameter to within Steady State limit within 24 hours C. Restore parameter to within Transient limit within 24 hours D. Reduce Pressurizer pressure to 500 psia in 6 hours and perform an engineering evaluation to determine the affects of the out-of-limit condition on structural integrity of the RCS

Answer: B

The plant is in Mode 3 and stable (post Reactor Trip). RVLMS Channel A, sensors 6, 7, and 8 fail and are not functioning. Based on these conditions, ... A. the crew must perform 3.3.10, Action A.1. B. LCO 3.3.10 is met. C. the crew must perform 3.3.10, Action C.1. D. the crew must perform 3.3.10, Action G.1.

Answer: A

The plant is at 100% power. The Crew is presently in 3.8.1 condition A due to a loss of an off-site circuit. All actions in 3.8.1 condition A. have been completed. 4 Hours later the AO reports EDG lube oil indicates 0.5 inches in the siteglass Based on these conditions, the crew should declare the EDG inoperable ... A. and enter the required actions of 3.8.1 condition b and d B. 48 hours after time of discovery. C. and enter the required actions 3.8.2 D. and enter the required actions of 3.8.1 condition d and 3.8.2 actions a and b

Answer: A

The reactor is 1.7% deltaK/K shut down Current Tave is 330°F and RCS pressure is 500 psia. What Mode is the reactor in per the Tech Spec definition? A. Mode 5. B. Mode 2. C. Mode 3. D. Mode 4.

Answer: D

EC Train has been declared inoperable due to a pump failure. What is the Maximum Out of Service Time for CREATCS as determined by the SafetyFunction Determination Procedure. (Assume CREATCS is inoperable solely due to its support system EC being inoperable) A. 144 hours B. 72 hours C. 792 hours D. 720 hours

Answer: C

Given the following information... SURVEILLANCE FREQUENCY Verify offsite circuit operable -1 hour AND Once per 8 hours thereafter. 1200 on 8/1/05: A DG becomes inoperable requiring performance of the above SR. Assuming that the Operating Crew took the maximum allowed time for the initial performance of the SR, when does the next subsequent performance of the SR have to be completed? Assume extensions are used where applicable. A. 2100 on 8/1/05. B. 2300 on 8/1/05. C. 2115 on 8/1/05. D. 2315 on 8/1/05.

Answer: B

In accordance with Technical Specifications isolation of EW to the SDC heat exchanger requires: A. Declaring that SDC system Inoperable only. B. Declaring that EW system Inoperable. C. Declaring Both the affected EW system and that SDC system inoperable. D. Engineering evaluation to determine EW Operability.

Answer: C

In accordance with Technical Specifications. CEA drop time must be 552°F and at least 2 RCPs running when performed. B. Prior to reactor criticality, after each removal of the reactor head or following maintenance/modification to the CEA drive system which could affect CEA drop time. Surveillance requires RCS Tcold > 552°F and all RCPs running when performed. C. Prior to each reactor criticality. Surveillance requires RCST cold > 545°F and all RCPs running when performed. D. Prior to reactor criticality, after each removal of the reactor head or following maintenance/modification to the CEA drive system which could affect CEA drop time. Surveillance requires RCS Tcold > 545°F and all RCPs running when performed.

Answer: B

The plant is in MODE 4 following a refueling outage. Primary pressure is 650 psia. Work control has determined that both HPSI pumps had a oil change out with the wrong oil and are inoperable. What action is required by Tech Specs? A. Immediately enter 3.0.3. B. Restore one HPSI pump to operable within 1 hour. C. No action required below 1837 psia. D. Immediately suspend all operations involving reduction of RCS boron concentration and initiate action to restore one train to operable status.

Answer: B

SR 3.8.1.9 requires each DG reject a load greater than or equal to its associated single largest post-accident load. The single largest load on the Train A EDG is: A. LPSI Pump B. Normal Chiller C. HPSI Pump D. CS Pump

Answer: B

The LCO on containment pressure prevents exceeding the... A. assumed time to Containment Spray flow during Design Basis Accident and minimum pressure design limit during an inadvertent CSAS. B. containment maximum pressure design limit during a Design Basis Accident and minimum pressure during containment venting operations. C. containment maximum pressure design limit during a Design Basis Accident and minimum pressure design limit during an inadvertent CSAS. D. assumed time to Containment Spray flow during Design Basis Accident and minimum pressure design limit during containment venting operations.

Answer: C

The bases for requiring all four SITs to be operable in Mode 1 is to ensure which of the following? A. 50% of one SIT and 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 2 SITs will reach the core during a LOCA. D. 100% of all 4 SITs will reach the core during a LOCA.

Answer: B

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. ensure that the SI pumps can deliver at least 30 minutes of full flow (plus a 10% margin). B. maintain the reactor subcritical following a DBA. C. cool and depressurize the containment in the event of a DBA and to cool and cover the core in the event of a LOCA. D. ensure that an adequate level exists in the containment sump to support ESF operation in the recirculation mode.

Answer: A

Which one of the following is a basis for the LCO concerning the RWT (Tech Spec 3.5.5)? Ensure that... A. an adequate level exists in the containment sump to support ESF operation in the recirculation mode. B. the SI pumps can deliver at least 40 minutes of full flow (plus a 10% margin). C. the RCS boron concerntration is maintained above 4000 ppm following a DBA. D. boron precipitation will NOT occur within the first three hours following a LOCA.

Answer: A

The plant is at 100% power when I & C reports that the K-1 (RTCB #1, & K-4 (RTCB#4, relays is shorted and will not deenergized if necessary, the operator should:(assume only the K-1 and K-4 relays are affected). A. Open the affected RTCBs within 1 hour in the affected legs B. Open the affected RTCBs immediately C. Be in Mode 3 in 6 hours and open all RTCBs in 6 hours D. Be in Mode 3 in 6 hours and open all RTCBs in the next 6 hours

Answer: C

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. during a Design Basis Accident, the resultant peak accident temperature is maintained below the containment design temperature. B. all instrumentation within containment is guaranteed to function properly. 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.

Answer: A

The Train 'B' Essential Chiller is declared inoperable and the crew begins to perform the required actions of 3.7.10, Condition A. Assuming LCO 3.0.6 is implemented, how should the Operating Crew treat AFW? Train 'B' AFW is considered...... A. operable since EC provides minimal support for this safety function. B. inoperable and the required actions of 3.7.5 must be entered. C. inoperable, however the conditions and required actions associated with AFW are not required to be entered. D. operable as long as the required actions for EC are being implemented.

Answer: C

One of the bases for maintaining containment pressure in its LCO stipulated band is to ensure: A. that outside air is not drawn in to the containment. B. H2 concentration post LOCA is minimized. C. containment pressure does not exceed 60 psig post LOCA. D. that instrumentation functions properly post LOCA.

Answer: C

The bases for the LCO that states containment integrity shall be maintained is: A. To ensure that containment is not negatively pressurized relative to the outside atmosphere. B. To ensure that air purity in containment is maintained. C. To ensure that containment humidity is maintained

Answer: D

Which of the following Containment conditions does NOT require a Technical Specification action to be performed within 1 hour? A. One containment air lock inoperable. B. Containment temperature above LCO limit. C. Containment pressure greater than the LCO limit. D. Both CS pumps inoperable.

Answer: B

Concerning required actions for inoperable containment isolation valves, choose the correct statement. A. Normally closed drain and vent valves, within a newly established containment penetration isolation boundary, do not have to be verified or controlled by a clearance. B. All automatically actuated valves used to isolate an open containment penetration with an inoperable containment isolation valve shall be deactivated in the closed position. C. All valves within a newly established containment penetration isolation boundary, including those controlled by 40DP-9OP19 (ZZ06), are required to be controlled with a red tag clearance. D. An automatic actuated valve used to isolate an open containment penetration with an inoperable containment isolation valve, does not have to be deactivated in the closed position if the valve actuates closed on a CIAS.

Answer: B

The Train 'A Essential Chiller is declared inoperable. The crew begins to perform the required actions of 3.7.10, Condition A. Assuming 3.0.6 is implemented, LPSI "A" is considered... A. inoperable, however, the conditions and required actions of LCO 3.5.3 are not required to be entered. B. operable since EC provides minimal support for this safety function. C. operable as long as the required actions for EC are being implemented. D. inoperable and the conditions and required actions of LCO 3.5.3 must be entered.

Answer: A

The plant is at 100% power. HPSI pump "A" has been out of service for 24 hours for preventive maintenance. Maintenance anticipates returning it to service within the next 6 hours. The Area Operator reports that the oil bubbler for HPSI "B" is broken off and there is oil all over the skid. The operator should: A. Enter LCO 3.0.3 and be in Mode 3 within 7 hours, and Mode 5 within the next 37 hours (44 hours total from entry). B. Enter LCO 3.0.3 and be in Mode 3 within 7 hours, and Mode 5 within 37 hours. C. Enter LCO 3.5.3 action "B", and verify 100% flow equivalent to a single ECCS train and restore at least 1 HPSI pump within 72 hours. D. Enter LCO 3.5.3 action "C", be in Mode 3 in 6 hours, reduce RCS pressure

Answer: B

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 p umps. 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 pool is adequately removed.

Answer: B

The RCS Pressure Safety limit is less than or equal to... A. 2850 psia. B. 2550 psia. C. 2650 psia. D. 2750 psia.

Answer: D

The unit is in Mode 1. The upper two sensors in the RVLMS Train 'B' have failed and are not functioning. All other RVLMS sensors are functioning normally. Based on these conditions, Technical Specification LCO 3.3.10 is... A. not met, enter Condition C, Action C.1. B. not applicable. C. not met, enter Condition A, Action A.1. D. met.

Answer: D

TS 3.8.1 requires that an INOPERABLE DG be restored to OPERABLE status in 10 days AND 13 days from discovery of failure to meet LCO. When does the "13 day" clock reset? A. When 3.0.3 is entered. B. When the LCO is met. C. When no more than one component covered by the LCO is INOPERABLE. D. When the component that originally caused a failure to meet the LCO is restored to OPERABLE status.

Answer: B

Unit 1 is at rated power. On 9/1/04 at 0600, DG "A" has been declared inoperable to facilitate mechanical adjustments of the fuel racks. On the same day at 1200, the mechanics who are working the job discover a Jacket Water leak on this DG. Based on these conditions, DG "A" MUST be restored to an operable condition on.... A. 9/5/04 at 0600 B. 9/4/04 at 1200 C. 9/4/04 at 0600 D. 9/5/04 at 1200

Answer: C

Following the Unit 2 power uprate, what is the Technical Specification maximum acceptable Tcold value at 100% power? A. 560.0°F B. 556.7°F C. 564.0°F D. 614.4°F

Answer: C

Following the Unit 2 power uprate, what is the technical specifications minimum allowable value to initiate a MSIS on steam generator low pressure? A. 960 psia. B. 890 psia. C. 895 psia. D. 955 psia.

Answer: D

Following the Unit 2 power uprate, what is the Technical Specifications minimum allowable value to trip the Reactor on Steam Generator low pressure? A. 895 psia B. 890 psia C. 955 psia D. 960 psia

Answer: C

In accordance with Technical Specifications, isolation of EW to its Essential Chiller requires: A. Declaring Both EW and the Essential Chiller Inoperable. B. Declaring the EW system Inoperable. C. Engineering evaluation to determine EW Operability. D. Declaring that Essential Chiller Inoperable only.

Answer: D

With a unit operating in Mode 1, which of the following describes the required AC Electrical sources which satisfies the LCO of Tech Spec 3.8.1, AC Sources - Operating? A. One offsite circuit and one diesel generator each capable of supplying the onsite Class 1E Electrical Power Distribution System and one automatic load sequencer. B. Two offsite circuits and two diesel generators each capable of supplying onsite Class 1E Electrical Power Distribution System and both automatic load sequencers. C. One offsite circuit and one diesel generator each capable of supplying the onsite Class 1E Electrical Power Distribution System and both automatic load sequencers. D. Two offsite circuits and two diesel generators each capable of supplying the onsite Class 1E Electrical Power Distribution System and one automatic load sequencer.

Answer: B

Based on present plant conditions with respect to CEA(s) position the operator should: A. reduce thermal power in accordance within the limits in theCOLR within 1 hour and restore CEA alignment within 2 hours. B. reduce thermal power in accordance with the limits in the COLR within 15 minutes and restore CEA alignment within 2 hours. C. open the RTCBs immediately. D. restore regulating CEA to within limits in 2 hours OR reducethermal power to

Answer: C

The unit is at 100% power and been there for 45 days. An engineering supervisor calls the SM in the control room to inform him of a problem with surveillance requirement 3.7.7.3 for EW pump "A". This surveillance was missed during the last outage and the last time it was performed was 24 months ago. What action is required by the Tech. Specs.? A. Immediately declare LCO 3.7.7 not met due to the missed surveillance. Be in Mode 3 within 6 hours and be in Mode 5 within 36 hours. B. Complete the surveillance within 1.25 times the interval specified in the frequency for SR 3.7.7.3. C. Immediately declare LCO 3.7.7 not met. Restore the EW train to operable status within 72 hours. D. The requirements to declare LCO 3.7.7 not met may be delayed for 18 months.

Answer: D

The plant is at 100% power HPSI "A" and LPSI "B" have just been declared inoperable. The proper action to take in accordance with Technical Specification is ... A. restore both pumps to operable status within 72 hours. B. enter LCO 3.0.3 immediately. C. restore one pump to operable status within 7 days. D. perform 40ST-9ZZ02 to verify off-site power sources with 1 hour.

Answer: A

Unit 1 is at 60% power VOPT Channel A fails due to a bad input. The operator carries out actions in accordance with Technical Specifications and I & C is notified. Subsequently, 1 hour and 10 minutes later, the Shift Manager determines due to troubleshooting the channel that it was never bypassed or trip. The Crew should ... A. Invoke 25% completion time extension time and place VOPT in trip or bypass B. Enter 3.0.3 and commence a plant shutdown C. Enter LCO 3.3.1 condition E and be in Mode 3 in 6 hours. D. Invoke a completion time extension of 1 hour and place channel in trip or bypass

Answer: C

All three AFW pumps are inoperable. Tech specs applied to this condition requires operators to immediately ... A. perform MFWP ST to ensure S/Gs can be fed via main feedwater. B. act to restore at least one AFW pump to operable. C. begin actions to line up to feed S/Gs from the condensate system. D. trip the reactor and feed S/Gs via MFW and C/D to Mode 4 within six (6) hours.

Answer: B

The plant is at 100% power Main feed pump A trips causing a RPCB actuation Groups 4 & 5 have dropped into the core In accordance with Technical Specifications the operator should: A. not enter LCO 3.1.7, but regulating CEAs must be restored within 2 hours or power must be reduced as specified in the COLR. B. enter LCO 3.1.7, immediately restore regulating CEAs to within limits within 4 hours. C. enter LCO 3.1.7 immediately and restore regulating CEAs to within limits in the next 2 hours. D. not enter LCO 3.1.7, entry is not required for 2 hours.

Answer: D

Regarding Mode 6 operations, (and using Tech Specs); The operating SDC (shutdown cooling) loop may be removed from service for: A. an unlimited time period, with no fuel movement. B. testing only, not to exceed 8 hours in 24 hours. C. 4 hour periods, with water level > 23' above the vessel flange. D. 1 hour in each 8 hour period, with no reduction in RCS Boron Concentration.

Answer: D

The Unit is in MODE 6. Both Control Room Emergency Air Temperature Control Systems (CREATCS) trains become INOPERABLE. If in progress, which of the following evolutions must be stopped per the Technical Specifications? A. New Fuel movement in the Refuel Pool. B. New fuel movement to the Spent Fuel Pool. C. Core Offload. D. Any operation involving the reduction of Refueling Cavity level.

Answer: C

In accordance with Technical Specifications a "Movement of an Irradiated Fuel Assembly" is defined as a movement of any: A. Fuel Assembly for reconstitution (1-10 pins) B. Fuel Assembly (236 pins) new or irradiated fuel assembly C. Irradiated Fuel Assembly (236 pins) D. Fuel assembly for reconstitution (any number of pins)

Answer: C

The Unit is in Mode 6 with core off-load is in progress. Chemistry calls and reports that the Boron concentration is 2290 ppm in the RCS and 3010 in the refueling canal. The COLR limit is specified as 3000 ppm. What are all the action(s) if any that should be taken. A. Suspend positive reactivity additions as soon as possible. B. Initiate action to restore Boron concentration to within limits, suspend positive reactivity additions and core alternations immediately. C. No action is required, refueling boron concentration is in specification. D. Initiate action to restore Boron concentration to within limits, suspend core alternations within one hour.

Answer: B

Following a Reactor Power Cutback, how should the operating crew comply with Technical Specification 3.1.7, Regulating Control Element Assembly (CEA) Insertion Limits? A. Enter the appropriate action, but add 2 hours to the completion time. B. Do not apply the limiting condition for operation for up to 2 hours following the RPCB. C. Enter the appropriate action, but add 4 hours to the completion time. D. Do not apply the limiting condition for operation for up to 4 hours following the RPCB.

Answer: B

When does entry into Mode 5 from Mode 6 occur? A. All reactor head closure bolts are fully tensioned and cold leg temperature > 210 degrees. B. All reactor head closure bolts are fully tensioned. C. RCS cold leg temperature exceeds 200 degrees. D. RCS cold leg temperature exceeds 135 degrees.

Answer: B

RCA-PT-199A (SPS Channel A) fails HIGH. NO RTCBs open. Based on this, Tech Specs require... A. no specific action related to this failure. B. opening RTCB #1 or #3 within 1 hour. C. opening RTCB #1 or #3 immediately D. opening RTCB #1 and #3 immediately.

Answer: B

Unit 1 is operating at 80% power. Engineering informs the operating crew that there is a problem with Reactor Trip Circuit breakers (RTCB) #1 and #3. This problem will impact their ability to open. Based on these conditions, the operating crew is required to open... A. either RTCBs #1 or #3 immediately. B. RTCBs #1 and #3 within 1 hour. C. RTCBs #1 and #3 immediately. D. either RTCBs #1 or #3 within 1 hour.

Answer: C