Tech. Specs. Flashcards
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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