ML083110619
| ML083110619 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/17/2008 |
| From: | NRC Region 1 |
| To: | Ginna |
| Hansell S | |
| Shared Package | |
| ML080030004 | List: |
| References | |
| 50-244/08-301, TAC U01687 | |
| Download: ML083110619 (204) | |
Text
I 2008 Ginna NRC Exam RO Question 1 Plant conditions occurred as follows:
0 The unit was at 100%.
0 It had been operating for 100 days.
0 A loss of off-site power occurred which resulted in a Reactor trip and all control rods inserting.
0 The operators are maintaining RCS Tavg at 547°F using the S/G ARV's in automatic control.
- 1. What would be the approximate decay heat generated (1) second after the trip?
and
- 2. How will the ARVs be operated over the next (6) hours to hold Tavg at 547"F?
- a. 1. 3.5 % RTP
- 2. The ARVs auto setpoint must be lowered.
- b. l.7%RTP
- 2. The ARVs auto setpoint must be raised.
- c. 1. 3.5 % RTP
- 2. The ARVs auto setpoint must be raised.
- d. 1.7%RTP
- 2. The ARVs auto setpoint must be lowered.
I1 2008 Ginna NRC Exam RO Answer:
- b. 1.7 % RTP
- 2. The ARV's auto setpoint must be raised.
Explanation:
- 1. This is the 1 minute expected value per Reactor Theory, Chapter 2, Nuclear Physics, pages 107-109.
- 2. If S/G pressure is lowered this will also lower Tavg due to Tcold going down due to ARV oDerations and Thot lowering: due to decav heat lowering:.
Correct I b.
- 1. This is the expected value per Reactor Theory, Chapter 2, Nuclear Physics, pages 107-109.
- 2. As decay heat lowers over time Thot lowers. To keep Tavg at 547"F, S/G pressure must go up.
Incorrect 1 c. 1. This is the 1 minute expected value per Reactor Theory, Chapter 2, Nuclear Physics, pages 107-109.
- 2. As decay heat lowers over time Thot lowers. To keep Tavg at 547"F, S/G Dressure must rro UD.
- 1. This is the expected value per Reactor Theory, Chapter 2, Nuclear Physics, pages 107-109.
- 2. If S/G pressure is lowered this will also lower Tavg due to Tcold going down due to ARV operations and Thot lowering due to decay heat lowering.
Category : Tier 1 /Group 1 Question Source: Bank Cognitive level: C/A Difficulty Level: 3 000007 Reactor Trip - Stabilization - Recovery EK1.04 - Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Decrease in reactor power
2008 Ginna NRC Exam RO Question 2 Plant conditions are as follows:
The unit was at 90% power when a Loss of Coolant Accident and a Loss of Off-Site Power occurred.
0 Manual Safety Injection (SI) and Containment Isolation (CI) were performed.
0 All systems performed as designed.
0 RCS pressure is 1510 psig and slowly lowering.
Pressurizer level is 15 % and rising rapidly.
0 Subcooling margin is lowering.
Which of the following is the most likely cause for the changes in Pressurizer level?
- a. SI accumulator Injection.
- b. Pressurizer vapor space leak.
- c. SI pumps refilling the Pressurizer.
- d. Leak in the Pressurizer transmitter variable leg.
2008 Ginna NRC Exam RO Answer:
- b. Pressurizer vapor space leak.
Explanation:
Incorrect a. RCS pressure is above SI accumulator pressure of -750#. May choose this due to Pzr level raising.
space break. Due to the high Rx head temperature and the LOOP (no RCP iunning and no MFW pump) steam voids form in the Rx head and force water back into the Pzr causing its level to rise.
RCS pressure is above SI pump injection pressure of -1500#. May choose this due to Pzr level raisinp.
Incorrect d. A leak in the Pressurizer variable leg will make the d/p go up which would indicate a lower Pressurizer level.
I Examination: I RO 2008 Ginna NRC I Question#: I 2 1 Rev.4 I Level: RO I ASE IN REACTOR COOLANT INVENTORY break and other Loss of Coolant accidents.
AA2.12 - Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PZR level indicators
~ ~~~
LP RTA04C pgs. 6,7.
2008 Ginna NRC Exam RO Question 3 Plant conditions are as follows:
0 While at 100% power, the unit experiences a large break LOCA and a loss of offsite power.
0 Neither Diesel Generator (D/G) started automatically.
Following a manual start of 1A D/G, Bus 14 and 18 are energized:
o 1A EDG load 2000 kw o All ECCS pumps are running at rated flow.
Which ONE of the following is the LONGEST amount of time the diesel generator can remain at the above conditions and what is correct with regard to D/G loading over time?
- a. (.5) hours, D/G loading will lower
- b. (2) hours, D/G loading will remain the same.
- c. (.5) hours, D/G loading will remain the same.
- d. (2) hours, D/G loading will lower.
2008 Ginna NRC Exam RO Answer:
- d. (2) hours, D/G loading will slowly lower.
Explanation:
Incorrect a. 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half ( S )hours. The time limit is 2 hrs. not .5 hrs.
- 2. Due to the removal of heathteam from Cnmt by the CRCFs and CS the load on the DIG will lower by itself. This is a known and expected condition.
Incorrect b. 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two ( 2 )hours, 2300 KW for one-half ( S )hours.
- 2. FSAR section 8 tables 8.3.2.a and b show D/G loading lowering over time due to lower loading on the CRCFs.
Incorrect c. 1. D/G KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half ( S )hours. The time limit is 2 hrs. not .5 hrs.
- 2. FSAR section 8 tables 8.3.2.a and h show DIG loading lowering over time due to lower loading on the CRCFs.
Correct d. 1. EDG KW Ratings are: 1950 KW continuous, 2250 KW for two (2) hours, 2300 KW for one-half (.5) hours.
- 2. Due to the removal of heathteam from Cnmt by the CRCFs and CS the load on the D/G will lower by itself. This is a known and expected condition.
I Examination: I I R O ~ O O ~ G ~ ~ ~Question#:
~ N R C 1 3 I Rev. 6 I Level: RO 1 EA1.06 - Ability to operate and monitor the following as they apply to a Large Break LOCA: D/Gs Generator System pg. 36 FSAR section 8 tables 2004 Ginna NRC Exam
2008 Ginna NRC Exam RO Question 4 Plant conditions are as follows:
0 While at 100%power, the unit experienced a Loss of Coolant Accident (LOCA).
0 RCS pressure is 1400 psig and trending down rapidly.
Containment pressure is 8 psig and trending up.
A and C SI pumps are running.
Both Reactor Coolant Pumps are running
- 1. Per E-0, Reactor Trip or Safety Injection, which of the conditions given would FIRST require the Reactor Coolant Pumps to be secured?
and
- 2. Why are the Reactor Coolant Pumps secured?
- a. 1. When RCS pressure minus maximum S/G pressure is 200 psi.
- 2. Mass loss is less if RCPs are turned off, resulting in greater assurance of natural circulation.
- b. 1. When RCS pressure minus maximum S/G pressure is 230 psi.
- 2. Mass loss is less if RCPs are turned off, resulting in greater assurance of natural circulation.
C. 1. When RCS pressure minus maximum S/G pressure is 200 psi.
- 2. Mass loss is greater if RCPs are left running, resulting in possible deeper core uncovery
- d. 1. When RCS pressure minus maximum S/G pressure is 230 psi.
- 2. Mass loss is greater if RCPs are left running, resulting in possible deeper core uncovery.
2008 Ginna NRC Exam RO Answer:
- d. 1. When RCS pressure minus maximum S/G pressure is 230 psi.
- 2. Mass loss is greater if RCPs are left running, resulting in possible deeper core uncovery.
Explanation:
- a. Due to adverse conditions RCPs should be secured when the d/p is less than 240 psi so 230 psig is the first correct pressure of the given options. Securing of RCPs at this specific time has no bearing on assuring natural circulation.
- b. Correct given d/p to secure the RCPs. Securing of RCPs at this specific time has no bearing on assuring natural circulation.
Incorrect C. Due to adverse conditions RCPs should be secured when the d/p is less than 240
- psig so 230 psi is the first correct pressure of the given options.
Correct d. Prior to cold leg saturation water is being removed from break and no difference in mass loss for RCP running or not. 14ftercold leg saturation phase separation L
would allow steam only to be removed with no RCPs where steam and water would be removed with RCPs running RCP trip at this time would lead to deeper core uncovery and higher PCT than if pumps tripped prior to this due to higher mass loss with pump running to this time RCP trip criteria chosen to insure pump trip prior to cold leg saturation. RCS / SG d/p < 210 psi (240 psi adverse containment). Adverse containment conditions are in effect due to Cnmt pressure
- 4 psi.
Document for E-0 step 14
2008 Ginna NRC Exam RO Question 5 Plant conditions are as follows:
0 The unit is at 50% power.
0 A leak develops that completely drains the reference side of VCT level transmitter LT-112.
0 Assume the leak affects only the VCT level transmitter LT-112.
With NO operator intervention, actual VCT will trend ...
- a. up until 83%, because of continuous automatic makeup.
- b. down to 20% and then trend up due to automatic makeup.
- c. down until the VCT is empty and all running charging pumps lose suction.
- d. down to 5% at which time the Charging Pumps will take a suction from the RWST.
2008 Ginna NRC Exam RO Answer:
- c. down until the VCT is empty and all running charging pumps lose suction.
Explanation:
Incorrect Incorrect since it has failed high there will be no auto makeun Correct c. With the reference leg at a much lower pressure the indicated level indicates high therefore no makeup will occur and VCT level will drop until Charging Pumps loose suction. LT- 112 indication at 20% starts the makeup but since it has failed high there will be no auto makeup.
Incorrect d. The logic is 2 out of 2, both LT-112 and LT-139 must both see VCT level at 5%
to shift. LT-112 is failed high, logic will not be met.
3ss or malfunction of the following apply to the Loss of Reactor Coolant Makeup: VCT level Volume Control Letdown.
P-3, Chemical and Volume
2008 Ginna NRC Exam RO Question 6 Plant conditions are as follows:
e The unit is in Mode 5 to support a refueling outage.
0 It has been five days since the unit was shutdown from 100%power.
0 RCS loops are at 54 inches.
0 RCS Temperature is 120°F.
0 RHR flow has just been stopped due to cavitation to the RHR pumps.
and
- 2. Which one of the following is the preferred method to raise RCS loop level?
- a. 1. The RCS is in a reduced inventory condition.,core uncovery could occur in a short period of time.
- 2. RWST gravity feed.
- b. 1. The RCS is in a reduced inventory condition.,core uncovery could occur in a short period of time.
- 2. Charging to loop B cold leg.
- c. 1. The RCS is above the reduced inventory condition, core uncovery times are significantly longer.
- 2. RWST gravity feed.
- d. 1. The RCS is above the reduced inventory condition, core uncovery times are significantly long x.
- 2. Charging to loop B cold leg.
2008 Ginna NRC: Exam RO Answer:
- a. 1. The RCS is in a reduced inventory condition, core uncovery could occur in a short period of time.
- 2. RWST gravity feed.
Explanation:
Correct a. 1. When less than 64 the RCS is in a reduced inventory condition and due to boil off core uncovery will occur.
Incorrect b. 1. When less than 64 the RCS is in a reduced inventory condition and due to boil off core uncovery will occur.
- 2. Charging to loop B cold leg is the slecond preferred method to raise RCS loop level per step 11 of AP-RHR.2.
Incorrect c. 1. When greater than 64 the RCS is nlot in a reduced inventory condition, times to boiling and core uncovery would be significantly longer,
Incorrect d. 1. When greater than 64 the RCS is not in a reduced inventory condition, times to boiling and core uncovery would be significantly longer.
- 2. Charging to loop B cold leg is the second preferred method to raise RCS loop level per step 11 of AP-RHR.2.
2.01 Given a set of plant and equipment conditions, evaluate the I conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or I RESPONSE NOT OBTAINED instructions to implement in AP-RHR.2, Loss of RHR While Operating at RCS Reduced Inventory 000025 Loss of RHR System AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss None While Operating at RCS Reduced Inventory I
2008 Ginna NRC Exam RO Question 7 Plant conditions are as follows:
0 The unit has been at 100%power for the last year.
0 All systems are in their normal at power alignment.
0 Pressurizer Pressure Controller - 43 1K fails and its output begins and continues to slowly rise.
If NO operator action is taken, what will the plant response be?
Spray valves initially ...
- a. close, heaters will energize, one PORV will lift.
- b. close, heaters will energize, two PORVs will lift.
- c. open, Reactor will trip, RCS pressure will stabilize at approximately 1500 psig.
- d. open, Reactor will trip, RCS pressure will stabilize at approximately 150 psig.
2008 Ginna NRC Exam RO Answer:
- c. open, Reactor will trip, RCS pressure will eventually stabilize at approximately 1500 psig.
Explanation:
Incorrect a. If the output for controller 43 1K rises this will result in the Spray valves opening. The heaters would only energize if the output for 43 1K lowers. The operation of (1) PORV is correct for 1.he given failure as the logic needed to open PORV-43 1C will not be met due to 43 1K failing low (3 of 3 required logics to operate the PORV).
Incorrect b. If the output for controller 431K rises, this will result in the Spray valves opening. The heaters would only energize if the output for 43 1K lowers. If it is not known or forgotten that the output from 43 1K goes to PORV-431C, then the operation of (2) PORVs is plausible.
Correct c. A sensed low pressure demand woulcl turn off heaters and would open spray valves to drive actual pressure low to meet the setpoint. The spray valves would continue to decrease pressure. A very rapid pressure transient develops which will result in a reactor trip and safety injection with coincident low pressure setpoints. With no operator action, pressure would continue to decrease until SI is initiated, which causes CI and isolates instrument air to containment. Since the spray valves are fail closed valves they would shut, terminating the transient.
Pressure will go to approximately the shutoff head for the SI pumps.
Incorrect d. Correct operation of the Spray valves however, pressure will not lower to RHR shutoff head with the SI pumps running.
Examination: RO 2008 Ginna NRC 1 Question #: I 1 7 RCV. 3 I Level: RO Lesson Plan: R1901C I Pressurizer Pressure and Level Control Objective(s): 1.06 Predict the effect that a loss or malfunction in the Pressurizer Pressure and Level Control System, or the Reactor Vessel Overprcssure Protection S:ystem, will have on related plant systcms and/or plant operations: d. Plant operation.
Category: Tier 1 /Group 1 Question Source: Bank Cognitive level: C/A Difficulty Level: 3 WA: 000027 Pressurizer Pressure Control System Malfunction ROI: 2.6 AK2.03 - Knowlcdgc of thc intcrrelations between thc Prcssurizer Pressure Control Malfunctions and the following: Controllers and SROI: 2.8 positioners Technical P- 10. Instrument Failure References None
References:
Reference Manual provided R 1901 C- Pressurizer during Exam:
Pressure and Level Control Question History: Used on Last (2) NRC Exams - No Exam PWR Industry Used on Audit Exam - No Bank #: Common Exani Bank 10CFR 55 Content: 55.41(a)(7) I ~55.43
2008 Ginna NRC Exam RO Question 8 Per E-3, Steam Generator Tube Rupture, what is the bases for maintaining a minimum level in a ruptured, non-faulted Steam Generator?
- a. To maximize back pressure and minimize break flow
- b. To dilute RCS water with S/G water in anticipation of a release.
- c. To prevent dryout and subsequent corrosive failure of additional steam generator U-tubes.
- d. To promote thermal stratification in the rupturedl SG during the subsequent RCS cooldown and depressurization.
2008 Ginna NRC Exam RO Answer:
- d. To promote thermal stratification in the ruptured SG during the subsequent RCS cooldown and depressurization.
Explanation:
- a. Break flow is always a concern during (any LOCA /) SGTR,efforts are made to minimize the leakage into the S/G but is not the bases for the step 5 requirement.
I b. If chosen to recover via Blowdowns this would seem to be a plausible bases but r-Incorrect - is not the reason for the 7% level requirement per the Background document.
Incorrect C. Failure of additional steam generator 1J-tubes would not be wanted during a SGTR and any action that prevented this from occurring maybe the correct thing to do, but is not the bases for the step in the background document.
I Correct d. It is also important to maintain the water level in the ruptured steam generator above the top of the U-tubes. When the primary system is cooled in subsequent steps, the steam generator tubes in the ruptured steam generator will approach the temperature of the reactor coolant, particularly if reactor coolant pumps continue to run. If the steam space in the ruptured steam generator expands to contact these colder tubes, condensation will occur which would decrease the ruptured steam generator pressure. This would reduce the reactor coolant subcooling margin and/or increase prirnary-to-secondary leakage, possibly delaying SI termination or causing SI reinitiation. Consequently, the water level must be maintained above the top of the tubes to insulate the steam space.
2008 Ginna NRC Exam RO Question 9 Plant conditions are as follows:
0 A Reactor startup is in progress following a five week Refueling Outage.
e MTC is predicted to be zero at 15% Reactor Power.
0 The reactor is critical.
0 N 35 - 1x10 -8 amps and stable 0 N 36 - 1x10 -8 amps and stable 0 Plant startup is on hold to complete required testing.
Subsequently a steam line break of 5% of rated steam flow occurs, Which one of the following describes the response of the reactor, assuming no reactor trip occurs?
- a. Reactor power will rise and stabilize at -5% power.
- b. The reactor will go subcritical.
- c. & &actor power will stabilize at the Point of Adding Heat.
- d. The reactor will remain at the current power level.
I 2008 Ginna NRC Exam RO Answer:
- b. The reactor will go subcritical.
Explanation:
Incorrect a. With a positive MTC at the beginning of life, as Tavg lowers due to steam
- demand, negative reactivity will be added driving the Rx subcritcal.
Correct b. With a positive MTC at the beginning of life, as Tavg lowers due to steam demand, negative reactivity will be added driving the Rx subcritcal. [Cycle 34, MTC = (+ 0.70)]
Incorrect C. With a positive MTC at the beginning of life, as Tavg lowers due to steam demand, negative reactivity will be added driving the Rx subcritcal.
Incorrect d. With a positive MTC at the beginning of life, as Tavg lowers due to steam
- demand, negative reactivity will be added driving the Rx subcritcal.
2008 Ginna NRC Exam RO Ouestion 10 Plant conditions are as follows:
0 The unit is operating at 14% power.
0 The turbine is rolling up to 1800 rpm.
0 A Condensate Pumps is 00s.
0 B and C Condensate Pumps have just tripped.
Which one of the following combinations will occur if no operator action is taken?
MFP TRIPS: REACTOR T R P s on: TURBINE TRIPS on:
- a. Immediately Lo-Lo S/G Level Reactor Trip
- b. Immediately Turbine Trip MFW pump Trip
- c. After 60 seconds Turbine Trip MFW pump Trip
- d. After 60 seconds Lo-Lo S/G Level Reactor Trip
2008 Ginna NRC Exam RO Answer:
- d. After 60 seconds Lo-Lo S/G Level Reactor Trip Explanation:
Incorrect MFPs trip when <15 psi seal water pressure above Feedwater pump suction of the Generator output breakers (1C; or 9X) is closed.
- c. Turbine trip less than 50% will not cause the Rx to trip. MFP trips only cause a L
2008 Ginna NRC Exam RO Ouestion 11 Plant conditions occurred as follows:
1200 - The unit is operating at rated power and all systems in their normal alignment.
1205 - An RCS leak occurs and the Letdown system is secured per AP-RCS.l, Reactor Coolant Leak, in an effort to slow the downward trend of Pressurizer water level.
1215 - A Station Blackout occurs (and no Diesel Generators will start).
1320 - Battery 1B is dead due to excessive loading.
1325 - An automatic SI actuates due to low Pressurizer pressure.
1330 - Due to a fault, Instrument Bus A is deenergized.
1335 - The HCO notices the Letdown Isolation Valve-427 is OPEN.
Letdown Isolation Valve-427 FIRST OPENED due to the effects o f . . .
(Assume no operator actions have been performed.)
- a. The Station Blackout.
- b. Battery 1B being dead.
- c. The loss of Instrument Bus A.
- d. The SI actuatuation
I 2008 Ginna NRC Exam RO Answer:
- a. The Station Blackout.
Explanation:
Correct a. AOV-427 was closed during the isolkion of the Letdown system that was given in the stem, due to the loss of the SA,IIA compressors on the station blackout AOV-427 went to its failed position-open.
Incorrect b. DC MCC 1B does power AOV-427 and its fail position on loss of DC power is closed per ER-ELEC.2. AOV-427 already failed open due the Station blackout.
This answer maybe picked if it is believed to be the P/S to AOV-427 and it fails open on a loss of power to the solenoid.
Incorrect C. Instrument Bus A does not power AOV-427, but powers one of the channels that feeds into the 2/3 logic to close AOV-427 on low Pzr level. With no power to 2/3 Pzr level channels the logic to close AOV-427 would be satisfied. With the SBO AOV-427 already failed open due the Station blackout. This answer maybe picked if it is believed to be the P/S to AOV-427 and it fails open on a loss of power to the solenoid.
Incorrect d. The auto SI would generate a CI which would close AOV-427 but with no air compressors running there is no motive force to close AOV-427. The CI would also secure IA to Cnmt which would also remove IA from AOV-427.
jescribe the design features of the V-427 on decreasing PZR level of 13% or on containment Volume Control System LP R4701C, Instrument and Service Air System Pg. 22 10905-07 17 AOV-427
2008 Ginna NRC Exam RO Ouestion 12 Plant conditions are as follows:
The unit is at 50% power.
0 The Electric plant is in a Normal 50/50 lineup.
Annunciator L-5, Safeguard Bus Main Breaker Overcurrent Trip just alarmed.
- 1. What caused the alarm to come in?
and
- 2. Which sequence of actions will support restoring power to the effected bus?
- a. 1. Bus 18 time rate over 1500 amps.
- 2. Ensure the affected D/G supply breaker is in auto after open. Depress the Overcurrent RESET pushbutton for the affected Safeguards bus Normal Feed breaker.
- b. 1. Bus 17 time rate over 1500 amps.
- 2. Ensure affected D/G supply breaker is in Pull stop. Reset the affected Safeguards bus Normal Feed breaker. Depress the Overcurrent RESET pushbutton for the affected Safeguards bus Normal Feed breaker.
C. 1. Bus 14 time rate over 3500 amps.
- 2. Ensure affected D/G supply breaker is in Pull stop. Reset the affected Safeguards bus Normal Feed breaker. Depress the Overcurrent RESET pushbutton for the affected Safeguards bus Nornnal Feed breaker.
- d. 1. Bus 16 time rate over 3500 amps.
- 2. Ensure the affected D/G supply breaker is in auto after open. Depress the Overcurrent RESET pushbutton for the affected Safeguards bus Normal Feed breaker.
'I 2008 Ginna NRC Exam RO Answer:
- c. 1. Bus 14 time rate over 3500 amps.
- 2. Ensure affected D/G supply breaker is in Pull stop. Reset the affected Safeguards bus Normal Feed breaker. Depress the Overcurrent RESE,T pushbutton for the affected Safeguards bus No -mal Feed breaker.
Explanation:
Incorrect a. 1. Bus 18 time rate over 1600 amps is the correct rating, not 1500 amps.
- 2. DIG supply breaker must be in Pull stop and must also reset the affected Safeguards bus Normal Feed breaker.
I 1. Bus 17 time rate over 1600 amps is the correct rating, not 1500 amps.
c Incorrect Correct Incorrect I d.
- 2. Actions are correct per L-5, Safeguard Bus Main Breaker Overcurrent Trip.
Amps and actions required per L-5, Safeguard Bus Main Breaker Overcurrent Trip.
D/G supply breaker must be in Pull stop and must also reset the affected Safeguards bus Normal Feed breaker.
~
I Examination: I RO 2008 Ginna NRC I Question #: I 12 I Rev. 6 I Level: RO 1 2.4.50 - Ability to verify system alarm setpoints and operate controls
2008 Ginna NRC Exam RO Ouestion 13 The Control Room Team is restoring power to Instrum~entBus D while implementing ECA-0.1, Loss of All AC Power Recovery Without SI Required.
- 1. Where will Instrument Bus D be re-powered from?
and
- 2. What is the basis for restoring power to Instrument Bus D?
2 . Instrument Bus D powers some required CVCS instrumentation.
- 2. Instrument Bus D powers some required CVCS instrumentation.
2 . Instrument Bus D powers some required Pressurizer level instrumentation.
- 2. Instrument Bus D powers some required Pressurizer level instrumentation.
2008 Ginna NRC Exam RO Answer:
- 2. Instrument Bus D powers some required CVCS instrumentation.
Explanation:
I I I anv Pressurizer level instruments. I Power Recovery Without SI
I 2008 Ginna NRC Exam RO Question 14 Plant conditions are as follows:
0 The unit has experienced a Loss of All AC power.
0 All Safeguards buses are deenergized.
0 ECA-0.0, Loss of All AC Power has been entered.
0 Service Water (SW) Pump switch alignment has been completed per Step 8.
What is the reason for the required Service Water Pump switch alignment called for in this step?
- a. To prevent water hammer in the Service Water System when power is restored to the applicable buses.
- b. To ensure Containment and ECCS cooling is restored as soon as the AC emergency buses are reenergized.
- c. To allow other systems to start and come up to normal pressures and flows prior to starting the SW system and thermally shocking the systemdcomponents being cooled.
- d. To allow a Service Water Pump to automatically load on the AC emergency bus to provide Diesel Generator cooling should that associated Diesel Generator start.
2008 Ginna NRG Exam RO Answer:
- d. To allow a Service Water Pump to autoniatically load on the AC emergency bus to provide Diesel Generator cooling should that associated Diesel Generator start..
Explanation:
Incorrect a. Water Hammer is a concern but is nit referenced in the background document.
Incorrect b. Cooling to the Cnmt and ECCS systems is a concern but is not referenced in the background document.
Incorrect c. Thermal Shock is a concern but is not referenced in the background document.
Correct d. Required per ECA-0.0, step 8 and reason is per the Background document:
Defeating the large loads as automatilc start, blackout, or SI loading of as many practical is intended to avoid potential overload of the power source. This action permits the operator to evaluate the status of the restored power source and sequence loads onto the bus consistent with bus status and plant conditions. A service water pump is permitted to automatically load on the AC emergency bus to provide D/G cooling should the diesel have started.
2008 Ginna NRC Exam RO Question 15 Plant conditions occurred as follows:
0 An unisolable Instrument Air header rupture has occurred.
0 The unit was tripped and E-0, Reactor Trip or Safety Injection was entered.
0 While executing E-0, the A S/G developed a tube rupture.
0 E-3, Steam Generator Tube Rupture, is now being performed.
0 An operator controlled cooldown is in progress.
0 All other systems have function as required.
All appropriate actions have been performed.
Which one of the following is the correct method used to lower RCS pressure?
- a. PRZR PORV using normal supply.
- c. Auxiliary Spray using Charging Pumps.
- d. Normal Sprays.
1 2008 Ginna NRC Exam RO Answer:
Explanation:
Incorrect a. Due to the IA rupture that cant be isolated the normal motive force (air) is not available.
Correct b. Nitrogen is available and can be valved in and is correct per RNO step 22a of E-3.
Incorrect c. Need IA to open AOV-296 which failed closed on the IA header rupture.
Incorrect d. Need IA to open the spray valves which failed closed on the IA header rupture.
conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE NOT OBTAINED instructions to implement in E-3, 2.4.6 - Knowledge of EOP mitigation strategies.
LP R1601C, CVCS pg. 46 LP R1401C, Pzr and PRT
2008 Ginna NRC Exam RO Ouestion 16 Plant conditions occurred as follows:
0 While at rated power, there was a disturbance on the electrical power grid which required the unit to perform a load reduction.
0 The unit is now at 85% power.
RG&E Energy Control Center reported due to the grid disturbance, current is leading voltage and the condition is continuing to degrade, Generator loading is 500 MWe Using the provided Generator Capability Curve, if current conditions continue.
- 1. Which Megavar limit will be met FIRST?
and
- 2. What type of load is the Generator carrying?
- a. 1. - 159 Megavars
- 2. Inductive Load
- b. 1. 325 Megavars
- 2. Inductive Load
- c. 1. 325 Megavars
- 2. Capacitive Load
- d. 1. -159 Megavars
- 2. Capacitive Load
2008 Ginna NRC Exam RO 194 KV 3 phase 6tl Hz 1800 RPM 6D psig Hydr~gen.92 Power Factor Rated Cold Gas 16 C
2008 Ginna NRC Exam RO Answer:
- d. 1. -159 Megavars
- 2. Capacitive Load Explanation:
Incorrect a. Wrong type of load.
Incorrect b. Wrong side of the curve and wrong type of load.
Incorrect c. Wrong side of the curve.
Correct d. With current leading voltage it is a Capacitive Load and the Megavar limit can be found on the bottom side of the curve.
AA2.01 - Ability to determine and interpret the following as they apply
2008 Ginna NRC Exam RO This page intentionally blank.
2008 Ginna NRC Exam RO Question 17 Plant conditions are as follows:
A LOCA outside containment has occurred.
The crew is performing the actions in ECA-1.2, LOCA Outside Containment.
- 1. Which of the following actions will be attempted to isolate the break?
and
- 2. Which indication is used to determine if the leak has been isolated in accordance with ECA- 1.2?
- a. 1. Isolate one SI Hot Leg pipe at a time.
- b. 1. Isolate one SI Cold Leg pipe at a time.
- c. 1. Isolate one SI Cold Leg pipe at a time.
- 2. Pressurizer level is monitored, because with the break isolated, RCS inventory will rapidly rise.
- d. 1. Isolate one SI Hot Leg pipe at a time.
- 2. Pressurizer level is monitored, because with the break isolated, RCS inventory will rapidly rise.
2008 Ginna NRC Exam RO Answer :
- b. 1. Isolate one SI Cold Leg pipe at a time.
Explanation:
Incorrect a. SI Cold Leg (not Hot leg) is isolated in step 3. RCS pressure is monitored, because SI flow will repressurize the RCS with the break isolated.
Correct b. Isolate SI Cold Leg piping per step 3f of ECA- 1.2. RCS pressure is monitored, because SI flow will repressurize the RCS with the break isolated.
Incorrect c. Isolate SI Cold Leg piping per step 3f of ECA-1.2.. Reasonable to conclude this I I is a viable means of indication that the leak is isolated however not called for in ECA- 1.2.
Incorrect d. SI Cold Leg (not Hot leg) is isolated xn step 3. Reasonable to conclude this is a viable means of indication that the leak is isolated however not called for in ECA- 1.2.
procedure determine the appropriate EXPECTED ACTIONS or
2008 Ginna NRC Exam RO Question 18 Following a unit trip, the plant is in FR-H.l, Response to Loss of Secondary Heat Sink due to a loss of the TDAFW and both MDAFW pumps.
Which of the following lists the proper order for restoring cooling (by priority) as directed by FR-H. 1, Response to Loss of Secondary Heat Sink?
(Assume both S/G WR levels are 200 inches and trending down slowly.)
- a. SAFW, MFW, condensate, feed and bleed
- b. MFW, SAFW, condensate, feed and bleed
- c. SAFW, MFW, feed and bleed, condensate
- d. MFW, SAFW, feed and bleed, condensate
2008 Ginna NRC Exam RO Answer:
- a. SAFW, MFW, condensate, feed and bleed.
Explanation:
as SAFW, MFW, condensate, feed and plant operation is assured.
AFW then SAFW, this was Incorrect C. Condensate, feed and bleed are reversed, this is not allowed by plant procedures and would constitute improper operation of the plant systems if this order of
- cooling systems were used when bothL were available.
Incorrect d. Recently the correct order was MFW first after AFW then SAFW, this was changed within the last cycle or two. (Condensate,feed and bleed are reversed, this is not allowed by plant procedures and would constitute improper operation of the plant systems if this order of cooling systems were used when both were
- available.
EK2.2 - Knowledge of thc intcrrelations betwem the (Loss of Secondary Heat Sink) and the following: Facility's heat removal
2008 Ginna NRC Exam RO Question 19 Plant conditions occurred as follows:
0 The plant was operating at rated power.
0 A control rod dropped partially into the core.
0 The Control Room staff have entered AP-RCC.3, Dropped Rod Recovery.
0 Axial Flux Difference (AFD) is no longer within the requirements of the COLR.
In accordance with Technical Specifications, (1) what are the required actions and (2) why?
- a. 1. Restore AFD to within limits or be less than 50% Rated Thermal Power in 30 minutes.
- 2. To ensure adequate shutdown margin is maintained during recovery of the dropped rod.
- b. 1. Restore AFD to within limits or be less than 50% Rated Thermal Power in 60 minutes.
- 2. To ensure adequate shutdown margin is maintained during recovery of the dropped rod.
C. 1. Restore AFD to within limits or be less than 50% Rated Thermal Power in 30 minutes.
- 2. By limiting the amount of power distribution skewing, core peaking factors are consistent with the assumptions used in the safety analyses.
- d. 1. Restore AFD to within limits or be less than 50% Rated Thermal Power in 60 minutes.
- 2. By limiting the amount of power distribution skewing, core peaking factors are consistent with tt2e assumptions used in the safety analyses.
2008 Ginna NRC Exam RO Answer:
C. 1. Restore AFD to within limits or be less than .!TO% Rated Thermal Power in 30 minutes.
- 2. By limiting the amount of power distribution skewing, core peaking factors are consistent with the assumptions used in the safety analyses.
Explanation:
Incorrect a. 1. Per ITS 3.2.3 action A.1: Restore AFD to within limits or be less than 50%
Rated Thermal Power in 30 minutes.
- 2. Concerns associated with SDM are always valid and should be addressed however, this is not the bases for the LCO.
Incorrect 1 b. 1. Correct action however the time is limited to 30 minutes.
- 2. Concerns associated with SDM are always valid and should be addressed however. this is not the bases for the LCO.
Correct C. 1. Per ITS 3.2.3 action A.1: Restore AFD to within limits or be less than 50%
Rated Thermal Power in 30 minutes.
- 2. Per ITS 3.2.3 action A.1 and associated Bases: The allowed range of the AFD is used in the nuclear design process to confirm that operation within these limits produces core peaking factors and axial power distributions that meet safety analysis requirements.
Incorrect d. 1. Correct action however the time is Limited to 30 minutes.
- 2. Per ITS 3.2.3 action A.1 and associated Bases: The allowed range of the AFD is used in the nuclear design process to confirm that operation within these limits produces core peaking factors and axial power distributions that meet safety analysis requirements.
- a. Identify action statemenls of less than one hour.
associated Bases
2008 Ginna NRC Exam RO Question 20 Plant conditions occurred as follows:
0 With the reactor critical during a startup, Control Rods were stopped at 80 steps withdrawn on Control Bank D.
0 Intermediate Range channel N-35 indicates 1.1SE-5 amps and is stable.
0 Intermediate Range channel N-36 indicated 1.02:E-5 amps and then failed low.
0 All Power Range Instruments indicated 2% power.
Which ONE of the following describes the actions to be taken for this situation?
- a. Perform NO actions that would result in a positive reactivity addition.
- b. Manually trip the Reactor and remain shutdown until N-36 is repaired.
- c. Perform a normal Reactor shutdown and remain shutdown until N-36 is repaired.
- d. Position the Level Trip switch to BYPASS for N.-36and continue with the startup.
2008 Ginna NRC Exam RO Answer:
- d. Position the Level Trip switch to BYPASS for hi-36 and continue with the startup.
Explanation:
Incorrect a. Not applicable per ITS 3.3.1 RIA E.2, since greater than 5 E-1 1 amps have 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to be greater than 8% power.
Incorrect b. Manual trip not required for these given conditions, , since > 5 E-1 1 amps have 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to be greater than 8% power or only lower power to < 5 E-1 1 amps complete shutdown is not required.
Incorrect c. Not required per ITS 3.3.1 R/A E. lor 2, since > 5 E-11 amps have 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to be greater than 8% power or only lower power to < 5 E-1 1 amps complete shutdown is not required.
Correct d. Per ITS 3.3.1 R/A E.2 and ER-NIS.2. Place affected IR Level Trip switch to BYPASS and be > 8 % power in (2) hours.
2008 Ginna NRC Exam RO Question 21 Plant conditions occurred as follows:
0 The unit was at 100%reactor power.
Condenser vacuum began to degrade.
0 The crew responded using AP-TURB.4, Loss of Condenser Vacuum.
0 The crew lowered power as directed.
0 The source of Condenser air in-leakage was found and patched but is still leaking.
0 Conditions ten minutes later are as follows:
o Power is now at 75% of full electrical output.
o Condenser back pressure is 7" Hg absolute and degrading slowly.
o Annunciator H-7, "Condenser Hi Pressure" is LIT.
o Annunciator D-24, Turbine Trip Auto Stop" is NOT LIT.
'I The CRS directs the HCO to trip the reactor.
- 1. Why was the Reactor Trip directed?
and
- 2. Determine whether the annunciators functioned properly.
- a. 1. Trip was directed due to operating outside of allowable turbine operating range and vacuum was degrading.
- 2. Annunciator H-7, "Condenser Hi Pressure" should NOT have alarmed until 22" Hg Condenser vacuum.
- b. 1. Trip was directed since turbine failed to automatically trip.
- 2. Annunciator D-24 Turbine Trip Auto Stop" should have alarmed at 25" Hg Condenser vacuum I'
C. 1. Trip was directed due to operating outside of allowable turbine operating range and vacuum was degrading.
- 2. Annunciators functioned properly.
- d. 1. Trip was directed since turbine failed to automatically trip.
- 2. Annunciators functioned properly.
2008 Ginna NRC Exam RO 2008 Ginna NRCl Exam RO Answer:
- c. 1. Trip was directed due to operating outside of allowable turbine operating range and vacuum w is degrading.
- 2. Annunciators functioned properly.
Incorrect a. 1. Directed per AP-TURB.4 step 2.a kNO,
- 2. Annunciator H-7, "Condenser Hi Pressure" alarms at 25.5" Hg Condenser vacuum and should be lit.
Incorrect b. 1. Turbine will not automatically trip until <20" Vacuum.
- 2. Annunciator D-24 Turbine Trip Auto Stop" which has many causes to bring
'I in this alarm and one of them is low condenser pressure at 20" Hg, since the condenser is only at -23" Hg (-7" Hg absolute) the annunciator should not be lit.
Correct c. 1. Directed per AP-TURB.4 step 2.a RNO.
- 2. Annunciators alarmed correctly.
Incorrect d. 1. Turbine will not automatically trip until <20" Vacuum.
I 2. Annunciators alarmed correctly. 1 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or Fig-13, Figure Back Pressure LP R4101C, Main Turbine
2008 Ginna NRC Exam RO This page intentionally blank.
I 2008 Ginna NRC Exam RO Question 22 Plant conditions occurred as follows:
0 The Control Room has been abandoned due to a fire in the Main Control Board.
0 You are the HCO and you are going to the Aux Feed Pump Area to perform applicable sections of ER-FIRE. 1, Alternate Shutdown for Control (ComplexFire.
Which one of the following correctly lists all the indications at the Intermediate Building Emergency Local Indicating Panel (IBELIP)?
- a. RCS Loop A Thot A and B S/G Pressure RCS Loop A Tcold A WR S/G Level Motor Driven AFW Pump Flow B WR S/G Level
- b. RCS Loop A Thot A S/G Pressure RCS Loop A Tcold A WR S/G Level Turbine Driven AFW Pump Flow B WR SIG Level C. RCS Loop B Thot A and B S/G Pressure RCS Loop B Tcold A WR S/G Level Turbine Driven AFW Pump Flow B WR SJG Level
- d. RCS Loop B Thot B S/G Pressure RCS Loop B Tcold A WR S,% Level Motor Driven AFW Pump Flow B WR S/G Level
2008 Ginna NRC Exam RO Answer:
- b. RCS Loop A Thot A S/G Pressure RCS Loop A Tcold A WR S8/GLevel Turbine Driven AFW Pump Flow B WR S/G Level Explanation:
Incorrect a. Motor Driven AFW Pump Flow and B S/G Pressure not available at IBELIP.
Correct b. As Der ER-FIRE.l. Attachment 3 HCO. sten 7.0.
Incorrect c. RCS Loop B Thoflcold and B S/G Pressure not available at IBELIP.
Incorrect d. Motor Driven AFW Pumr, Flow and B S/G Pressure not available at IBELIP.
I 2008 Ginna NRC Exam RO Ouestion 23 Plant conditions are as follows:
0 A Steam Line Break has occurred.
0 All equipment actuated as required.
0 The Control Room staff has isolated the faulted Steam Generator.
0 Safety Injection and Containment Isolation have been reset.
0 RCS pressure is 1850 psig and slowly trending up.
0 There are no other indications of RCS leakage.
Which one of the following describes the sequence and operation of the SI and RHR pumps in accordance with ES- 1.1, SI Termination?
- a. 1. Verify or establish Charging flow.
- 3. Verify SI flow not required.
- b. 1. Stop all running SI pumps.
- 2. Check RCS pressure stable and then verify or establish Charging flow.
- c. 1. Stop 1 SIpump.
- 2. Check RCS pressure stable and then verify or eistablish Charging flow.
- d. 1.Verify or establish Charging flow.
- 3. Stop 1 RHR pump. Ensure RCS pressure remains stable, then stop any running SI pumps and the second RHR pump.
2008 Ginna NRC Exam RO Answer:
- a. 1. Verify or establish Charging flow.
3 . Verify SI flow not required.
Explanation:
Correct a. Charging verifiedestablished first, then all pumps stopped, then verification of SI not required per ES-1.1, SI Termination steps 5-8.
Incorrect b. Flow reduction sequence not correct. Charging verified/established first, then all pumps stopped, then verification of SI not required per ES- 1.1, SI Termination steps 5-8.
Incorrect c. Flow reduction sequence not correct. Charging verifieaestablished first, then all pumps stopped, then verification of SI not required per ES- 1.1, SI Termination Incorrect I I stem 5-8.
- d. Flow reduction sequence not correct. Charging verifieaestablished first, then all pumps stopped, then verification of SI not required per ES- 1.1, SI Termination 1 steps 5-8.
ermine and interpret the following as they apply to the (SI Termination): Adherence to appropriate procedures and ES- 1.1, SI Termination
2008 Ginna NRC Exam RO Ouestion 24 Plant conditions are as follows:
0 The unit has experienced a Loss of Coolant Accident (LOCA).
0 All plant equipment operated as designed.
0 E-0 and E-1 have been completed.
0 While performing ES- 1.2, Post LOCA Cooldown and Depressurization, Reactor Coolant System (RCS) conditions are determined to be a.dequate to support stopping (1) Safety Injection (SI) pump.
When the SI pump is secured, how will the RCS be affected and why?
RCS subcooling will
- b. remain the same. The flow from the other running SI pumps will rise and achieve a balance with break flow.
- c. lower due to lower SI flow. RCS pressure will stabilize at a new lower value when SI flow equals break flow.
- d. lower due to break flow remaining constant as SI flow lowers. RCS temperature will rise and stabilizes at a higher value.
2008 Ginna NRC: Exam RO Answer:
- c. lower due to lower SI flow. RCS pressure will stabilize at a new lower value when SI flow equals break flow.
Explanation:
Incorrect a. Subcooling will lower due to lower pressure. RCS temperature is Incorrect b. Subcooling will lower due to pressure.
Correct c. As SI flow lowers due to stopping of (1) SI pump RCS pressure will lower to a new eauilibrium value.
I Incorrect 1 d. I RCS temperature is controlled by dumping steam.
1on!j,Notes, and Major Action Categories of d Depressurization)i: Operating behavior Cooldown and
2008 Ginna NRC Exam RO Question 25:
Plant conditions occurred as follows:
0 The unit was manually tripped from rated power due to a small-break LOCA.
0 Due to an Orange Path on Integrity, FR-P. 1, Response to Imminent Pressurized Thermal Shock Condition was entered.
All SI pumps were stopped.
0 Adequate subcooling was verified.
A soak is required and is in progress.
The Control Room staff is currently performing ES- 1.2, Post LOCA Cooldown and Depressurization.
With the soak period still in affect, which one of the following operations can be performed?
(Assume any other requirements to perform the step are met.)
- c. Feed the S/Gs as rapidly as possible to return S/G levels to normal levels.
- d. Run SI Pumps as needed to maintain Pressurizer water level above 7%.
2008 Ginna NRC Exam RO Answer:
Explanation:
This is allowed by FR-P.l step 29 bases. The "soak" is a period of steady state operation during which any temperature decrease or pressure increase are to be avoided. This time period allows thermal gradients in the reactor vessel wall to be reduced, thus reducing corresponding stresses. Any actions that will not cause either an RCS cooldown or RCS pressure increase and are specified by any other procedure in effect are permitted during this "soak" period.
The leak will have to wait, the important issue is the PRV wall. No cooldown is permitted till the 1 hr soak time is corndete.
This would result in a cooldown and is not allowed till the 1 hr soak time is complete.
Incorrect d. This would result in a rise in RCS time is complete.
Thermal Shock) and the following: Facility's heat removal systems, Thermal Shock Condition
2008 Ginna NRC: Exam RO Ouestion 26:
Plant conditions occurred as follows:
0 The unit tripped from rated power due to the loss of both RCPs.
A plant cooldown is underway in accordance with ES-0.2, Natural Circulation Cooldown.
Current plant conditions are as follows:
o RCS Pressure - 1550 psig and trending down slowly o RCS Tcold - 450°F and trending down o F-11, Pressurizer Lo Level 13% has just cleared o Reactor Vessel Head Thermocouples - 610°F and stable o Pressurizer Level is trending up very quickly from 10%
- 1. What is the status of the Reactor Coolant System (RCS)?
and
- 2. What actions are required to be performed?
- a. 1 Reactor Head area is subcooled.
2.Continue cooldown rate in RCS cold legs less than 25°F per hour.
- b. 1. Reactor Head area is subcooled.
- 2. Raise cooldown rate in RCS cold legs to less than 50°F per hour.
C. 1. Steam voids are forming in the reactor head area.
- 2. Repressurize the RCS within allowable limits and continue cooldown.
- d. 1. Steam voids are forming in the reactor head area.
- 2. Continue with cooldown and stop depressurization.
I 2008 Ginna NRC Exam RO Answer:
- c. 1. Steam voids are forming in the reactor head area.
- 2. Repressurize the RCS within allowable limits and continue cooldown.
Explanation:
Incorrect a. For given set of conditions the Rx heail area is not subcooled. This is the correct cooldown for the given conditions.
1 Incorrect I b. 1 For given set of conditions the Rx head area is not subcooled. Max cooldown I rate is 25°F per hour for given conditions.
Correct c. Per ES-0.2, Natural Circulation Cooldown, step 17 - Check for Steam void in Rx head - Unexpected Pzr level variations are seen, then repressurize the RCS within allowable limits and continue cooldown.
Incorrect d. Repressurization is rewired due to steam voiding in the head region.
Natural Circulation Cooldo-wn.exdain the basis for the same.
concepts as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Annunciators and conditions indicating signals, and remedial actions associated with the Natural Circulation
2008 Ginna NRC Exam RO Ouestion 27 Plant conditions are as follows:
The reactor has tripped due to a Loss of Coolant Accident (LOCA).
The Control Room staff is working through the EOPs.
0 Due to indications of failed fuel, FR-Z.3, Response To High Containment Radiation Level is entered.
Which of the following are the correct indications and actions per FR-Z.3?
Verify Charcoal filter dampers green status lights are - 1 and if they are NOT, then dispatch personnel to the Relay Room to open the dampers by - 2
- a. 1. Extinguished
- 2. pushing in the trip relay plungers
- b. 1. Bright
- 2. pushing in the trip relay plungers
- c. 1. Extinguished
- 2. opening breakers that supply power to the dampers
- d. 1. Bright
- 2. opening breakers that supply power to the dampers
1 2008 Ginna NRC Exam RO Answer:
- a. 1. Extinguished
- 2. pushing in the trip relay plungers Explanation:
Correct Per FR-Z.3 step 2b and RNO 2b.
E
$ Charcoal filter dampers green status lights should be extinguished.
Dampers are opened via plunger actuation not isolation of power. Plausible distracter if candidate equates the green status light being out to no power to the damper, thus failing to its safety configuration.
Charcoal filter dampers green status lights should be extinguished. Dampers are opened via plunger actuation not isolation of power. Plausible distracter if candidate equates the green status light being out to no power to the damper, thus failing to its safety configuration.
2008 Ginna NRC Exam RO Question 28 Plant conditions are as follows:
0 The unit is at 15% power.
0 Annunciator A-15, RCP B CCW RETURN HI TEMP OR LO FLOW 165 GPM 125°F is lit.
0 MOV-759B, CCW from RCP 1B ISOL VLV indicates closed and cannot be reopened.
0 All RCP seal injection parameters indicate normal.
What is the condition of the plant ( 5 ) minutes after the Control Room staff completes all of their required actions for these given conditions?
2008 Ginna NRC Exam Answer:
Explanation:
Incorrect a. RNO step 4a/b instructs to trip the Rx ;and only the affected RCP. Want to have
- (1) runninp. RCP for decav heat removal and better control for plant cooldown.
Correct b. Ann A-15 directs the operator to AP-CCW.2 which on RNO step 4a/b instructs
- to trip the Rx and only the affected RCP.
Incorrect C. Correct answer only the RCPs are reversed therefore incorrect.
Incorrect d. If it is believed as long as seal injection is supplied to the RCP, the pump can continue to operate which would be incorrect. It is similar to a RCP can loose injection flow as long as CCW cooling is still provided.. AP-CCW.2 RNO step
- 4a/b instructs to trip the Rx and onlv th.e affected RCP.
RETURN HI TEMP OR LO FLOW 165 GPM 125°F AP-CCW.2, LOSSof CCW
1 2008 Ginna NRC Exam RO Question 29 Per S-2.1, Reactor Coolant Pump Operation, prior to starting a Reactor Coolant Pump (RCP) ensure its Oil Lift Pump has been delivering oil to the (1) -for at least two minutes .
The Oil Lift Pump WHITE indicating light will be lit - (2)
- a. 1. upper thrust shoes
- 2. by a pressure switch when proper lift pressure is attained
- b. 1. lower radial bearing
- 2. as soon as the Oil Lift Pump starts
- c. 1. upper thrust shoes
- 2. as soon as the Oil Lift Pump starts
- d. 1. lower radial bearing
- 2. by a pressure switch when proper lift pressure is attained
2008 Ginna NRC Exam RO Answer:
- a. 1. upper thrust shoes
- 2. by a pressure switch when proper lift pressure is attained Explanation:
I Correct I a. 1 Per mecaution 4.5 of S-2.1, Reactor Coolant Pumu ODeration.
Incorrect b. All answers are incorrect per precaution 4.5 of S-2.1, Reactor Coolant Pump Operation.
Incorrect c. Oil Lift Pump WHITE indicating lig!ht will be lit by a pressure switch when DroDer lift Dressure is attained.
1 Incorrect 1 d. I Supplies oil to the upper thrust shoes not the lower radial bearing.
Coolant Pumps, to include set points, interlocks, and the related room: RCP lube oil and lift pump motor controls
I 2008 Ginna NRC:Exam RO Ouestion 30 Plant conditions are as follows:
The plant has been operating for two weeks following a Refueling outage.
The reactor is currently at 100%power.
CCW Surge Tank is 50%.
VCT level is 25%.
Rod Control is in automatic.
Tref and Tavg are matched.
Tube leaks develop in the Seal Water Return Heat Exchanger.
What will the plant response be if no operator action is taken?
- a. VCT level will slowly rise to 100%.
- b. CCW Surge Tank will slowly rise to 100%.
C. Rods will step in to maintain Tavg and Tref approximately equal.
- d. Rods will step out to maintain Tavg and Tref approximately equal.
2008 Ginna NRC Exam RO Answer:
- c. Rods will step in to maintain Tavg and Tref approximately equal.
Explanation:
Incorrect a. Level control system for VCT will divert the excess water. Level won't go much higher than -30%.
Incorrect b. RCP #1 Seal Return flow is at a much lower pressure than CCW pressure. CCW Surge Tank level will lower not rise.
Correct c. RCP #1 Seal Return flow is at a much lower pressure than CCW pressure. CCW Surge Tank will lower and water will return to the VCT. Since CCW is not borated this is the same as a dilution. ,4s VCT level rises due to the extra water, the VCT divert valve will divert borated return water away from the VCT, resulting in additional dilution. As the RCS is diluted Rx power goes up and Tavg goes up. When Tavg exceeds Tref by 1S"F rods will step in to lower Tavg.
Incorrect d. This response would be correct if therle were an inadvertent boration occurring but due to the given conditions a dilution is occurring.
ents, instrumentation K3.01 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: CRDS (automatic)
System, pgs. 25-27 LP R1601C, Chemical and Volume Control System,
2008 Ginna NRC Exam RO Question 31 Plant conditions are as follows:
The unit is in MODE 5.
0 RHR is in shutdown cooling.
RCS temperature is 180°F and stable.
0 An air leak has occurred and as a result Instrument Air has been isolated to the Auxiliary Building.
Provided there is no operator response, how will the RHR return temperature to the RCS respond over the next 15 minutes?
- a. Temperature will rise because HCV-624 and HCV-625 will fail closed and HCV-626 will fail open, therefore providing no cooling.
- b. Temperature will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed, therefore providing maximum cooling.
C. Temperature will remain unchanged because HCV-624, HCV-625 are pinned locally and are unaffected by the loss of Instrument Air.
- d. Temperature will remain unchanged because CCW supply valves (MOV-738A and MOV-738B) to the RHR Heat Exchangers are manually throttled valves and are unaffected by the loss of Instrument Air.
2008 Ginna NRC Exam RO Answer:
- b. Temperature will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed, therefore providing maximum cooling.
Explanation:
I Incorrect I a. 1 This is correct if the failure uositions of HCV-624.625 and 626 were reversed. 1 Correct I HCV-624 and 625 fail open and HCV-626 will fail closed, therefore providing I maximum cooling.
HCV-624, HCV-625 and HCV-626 are not normally operated locally.
Incorrect MOV-738A and MOV-738B are unaffected by the loss of Instrument Air but RCS temperature will lower because HCV-624 and HCV-625 will fail open and HCV-626 will fail closed. therefore moviding maximum coolinn.
following will have on the RHRS: RHR heat exchanger Hot Shutdown to Cold
2008 Ginna NRC Exam RO Question 32 Plant conditions are as follows:
A unit startup is in progress in accordance with 0-1.1, Plant Heatup from Cold Shutdown to Hot Shutdown.
RCS Tcold - 120°F RCS pressure - 350 psig RCS heatup rate - 25°F per hour A and B RCS Loops are Operable, but only A RCP is running.
The RHR system is aligned for core cooling with A and B RHR pumps running.
B SI pump is Operable and its control switch is in AUTO.
B Charging Pump is Operable and providing normal charging flow.
The conditions described above are IMPROPER because . . .
- b. the heatup rate is too high for the RCS temperaturje and pressure.
- c. the number of ECCS pumps available to provide injection is inadequate.
2008 Ginna NRC Exam RO Answer:
Explanation:
Correct a. With the RCS solid this violates ITS 3.4.12, LTOP System, A . l .
Incorrect b. Heatup rate is limited to a maximum of 50°F per hour when less than 220°F RCS temperature.
Incorrect c. No ECCS uumus are reauired in Mode 5.
1 Incorrect I d. I Non-uniform cooling is not the concern for the given conditions.
concepts as they apply to ECCS: Effects of pres,sure on a solid system 0-1.1, Plant Heatup from Cold Shutdown to Hot
2008 Ginna NRC Exam RO Ouestion 33 Plant conditions occurred as follows:
0 The plant was operating at 100%power when a Reactor Trip and SI occurred.
0 Shortly after the SI actuation the following conditions were observed:
o R-7, Incore Detector Area radiation monitor high alarm actuated.
o R-2, Containment radiation monitor is trending up.
o PRT liquid temperature is 175°F and trending up.
o Containment pressure and humidity is trending up.
o A Containment Sump level is trending up.
0 NO operator action has been taken.
Which one of the following would cause these conditions?
- a. B RCP #I seal has failed.
- b. PCV-435, Pressurizer Safety valve is stuck open.
- c. SOV-592, Reactor Head Vent valve has failed open.
- d. An Jncore Thimble Tube has ruptured at the bottom of the reactor vessel.
2008 Ginna NRC Exam RO Answer:
- b. PCV-435, Pressurizer Safety valve is stuck open.
Explanation:
Incorrect a. Failure of the B RCP seal in conjunction with SI actuation is likely to result in abnormal PRT conditions as the Seal Return Line is isolated (MOV-313), and the excess letdown relief lifts at 150 psig to the PRT. However the amount of flow from a failed # 1 seal is limited and would not result in pressurization of the PRT to ruDture disc failure in such a short time.
Correct b. Pzr Safety failing open would go to the PRT, rupture the PRT rupture disk at 100 psig then produce the given containment parameters. As the Safety continued to discharge PRT temperature would rise.
Incorrect C. SOV-592 is isolated by SV-590 which is normally closed, therefore there would be no release to the containment or the PRT.
Incorrect d. Incore thimble tube failure is likely to result in the containment radiation conditions described but will not result in the abnormal PRT conditions.
IExamination: I RO2008GinnaNRC I Question#: I 33 I Rev. 3 I Level: RO irizer Relief Tank ments or associated instruments of the Pressurizer and Pressurizer Relief Tank System, state their purpose, function, and location (when denoted with L). a. Pressurizer
- c. Safety Valves (L) e. Pressurizer Relief Tank (L) i. PRT Rupture Category: Tier 2 / Group 1 Questim Source: Bank Cognitive level: C/A Difficulty Level: 3 007 Pressurizer Relief / Quench Tank K3.01 - Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment ssurizer Relief Tank
2008 Ginna NRC Exam RO Question 34 Plant conditions are as follows:
0 The unit is at 75% power.
0 The electric plant is in an ALTERNATE 50/50 lineup.
0 B CCW pump is running.
0 A CCW pump is in Standby.
0 B Diesel Generator is tagged out for maintenance.
- 1. What is providing power to the running CCW pump?
and
- 2. If all off-site power is lost, when will the A CCW pump start?
- a. 1. 7T to Bus 12B to Bus 16.
- 2. A CCW pump starts 40 seconds after the A Diesel Generator ties on to Bus 14.
- b. 1. 767 to Bus 12B to Bus 16.
- 2. A CCW pump starts immediately after the A Diesel Generator ties on to Bus 14.
- c. 1. 767 to Bus 12B to Bus 16
- 2. A CCW pump starts 40 seconds after the A Diesel Generator ties on to Bus 14.
- d. 1. 7T to Bus 12B to Bus 16
- 2. A CCW pump starts immediately after the A Diesel Generator ties on to Bus 14.
2008 Ginna NRC Exam RO Answer:
- d. 1. 7T to Bus 12B to Bus 16.
- 2. A CCW pump starts immediately after the A Diesel Generator ties on to Bus 14.
Explanation:
Incorrect a. Correct power supplies however, CCPJ pumps starts immediately, Service Water pumps are delayed 40 seconds.
Incorrect b. 7T is P/S in an Alt 50/50 h e m .
Incorrect c. 7T is P/S in an Alt 50/50 lineup and CCW pumps starts immediately, Service Water pumps are delayed 40 seconds.
Correct d. Correct power supplies. As long as there is no coincident SI signal in conjunction with low/lost voltage, the CCW pumps will immediately start after the A Diesel Generator ties on to Bus 14.
Category: Tier 2 / Group 1 Question Source: New Cognitive level: C/A Difficultv Level: 3 008 Component Cooling Water K2.02 - Knowledge of bus power supplies to the following: CCW pump, including emergency backup LP R2801C, Component Cooling Water System
2008 Ginna NRC Exam RO Ouestion 35 Concerning Pressurizer Sprays, what design feature assists in minimizing the Thermal Shock to the Pressurizer Spray Nozzle?
- a. A Thermal Sleeve is installed at the Pressurizer Spray penetration.
- b. Each Spray line has a bypass line with a manually opened valve.
- c. The control band of the Pressurizer Heaters overlaps the control band of the Pressurizer Sprays so that Sprays always has a minimum flow.
- d. The Spray valve stems have travel stops to maintain minimum flow.
I 2008 Ginna NRC Exam RO Answer:
- b. Each Spray line has a bypass line with a manually opened valve.
Explanation:
Incorrect a. Some plants have this design feature, but not at Ginna.
Correct b. A manuallv opened valve in a bvmss line Provides the flow. ~
Incorrect c. Some plants have this design feature, but not at Ginna.
Incorrect d. Some plants have this design feature. but not at Ginna.
2008 Ginna NRC Exam RO Ouestion 36 Plant conditions are as follows:
0 The unit was at 100% reactor power.
0 Rod control is in Manual and all other controls are in automatic.
0 PT-430, Pressurizer Pressure detector is slowly failing high.
- 1. How will this affect the associated Over Temperature Delta-T trip setpoint?
and
- 2. Will the associated Over Temperature Delta-T trip setpoint become MORE or LESS Conservative?
- a. 1. The trip setpoint lowers.
- 2. MORE
- b. 1. The trip setpoint lowers.
- 2. LESS
- c. 1, The trip setpoint rises.
- 2. MORE
- d. 1. The trip setpoint rises.
- 2. LESS
2008 Ginna NRC Exam RO Answer:
- d. 1. The Over Temperature Delta-T trip setpoint will rise.
- 2. LESS Conservative.
Explanation:
I Incorrect a. The setpoint does not lower, as pressure goes up so does the set point for OT delta-T. Because the failure causes the setpoint to be higher it is less conservative.
- b. The setpoint does not lower, as pressure goes up so does the set point for OT delta-T. Because the failure causes the setpoint to be higher it is less
- conservative.
C. Because the failure causes the setpoinit to be higher it is less conservative.
- d. As pressure goes up so does the set point for OT delta-T. At 100 % power the trip set point would normally be -80°F with PI-430 failing to 2360 psig the trip set point raises to -85°F. Therefore the trip associated with this channel would happen at a higher delta-T there by beiing LESS conservative and putting the I core at greater risk.
following will have on the RPS: Sensors and detectors
I 2008 Ginna NRC Exam RO Ouestion 37 Plant conditions occurred as follows:
The unit was operating at 100%power.
Normal Letdown was in service.
A Coolant Leak in the Auxiliary Building occurred.
The leak caused grounds which lead to an isolation of MCC D.
Since the leak could not be isolated a Reactor Trip, a Manual SI and a CI were subsequently performed.
How many Component Cooling Water Containment Penetration Valves (not including any check valves), are in the CLOSED POSITION after the aboveactions are complete?
- a. 1
- b. 2
- c. 3
- d. 4
2008 Ginna NRC Exam RO Answer:
- b. 2 Explanation:
Incorrect a. With the loss of MCC-D only (2) va1vi:s will be closed as described in b below. If AOV-745 is forgotten, this answer would be selected.
Correct b. MOV-813 will get a signal and have power to close. MOV-814 will get a signal but will NOT have power to close. MOV-749NB and MOV-759NB do not receive an isolation signal so they will :stay open (loss of MCC D is not an issue). V-742A is a manual valve and is unaffected. AOV-745 is normally open but gets a CI signal to close.
Incorrect c. MOV-813 will get a signal and have power to close. MOV-814 will get a signal but will NOT have power to close, if this is not understoodhown it maybe believed this valve will shut. AOV-745 is normally open but gets a CI signal to close.
If it is assumed due to the loss of MCC D half of the Cnmt valves wont shut this would be the correct choice however as outlined in b above only (2) CCW Containment Penetration Valves will be shut .
, Att Auto Action
I 2008 Ginna NRC Exam RO Question 38 Plant conditions are as follows:
0 The unit has tripped from rated power due to a large break LOCA.
0 Prior to the LOCA, only 1B and IC Containment Recirc Fans were running.
Following the LOCA, Bus 16 is deenergized.
What is the status of the Containment Recirc Fans?
- a. Only 1A Containment Recirc Fan is running.
- b. Only 1A and 1D Containment Recirc Fans are running.
- c. Only lA, 1B and 1C Containment Recirc Fans are running.
- d. All Containment Recirc Fans are running.
I 2008 Ginna NRC Exam RO Answer:
- b. Only 1A and 1D Containment Recirc Fans are running.
Explanation:
Incorrect a. 1D Containment Recirc Fan is also running.
Correct b. Due to the large break LOCA all Containment Recirc Fans get signals to start but with the loss of Bus 16, 1B and 1C Containment Recirc fans will not have power therefore only 1A and 1D Incorrect c. Due to the loss of Bus 16, 1B Dower therefore onlv 1A and 1D Containment Recirc Fans are mnnine.
Incorrect d. Due to the loss of Bus 16, 1B and 1C Containment Recirc fans will not have power therefore only 1A and 1D Containment Recirc Fans are running.
escribe the design features of the Auxiliary, and Control Building Ventilation Systems
2008 Ginna NRC: Exam RO Ouestion 39 Plant conditions are as follows:
0 The unit has tripped due to a sudden large break. Loss of Coolant Accident (LOCA) coincident with a Loss of all Off-site power.
0 All of the Service Water (SW) header isolation valves indicate open.
0 FCV-4561 and FCV-4562, CNMT RECIRC fan coolers SW outlet valve status lights are dim.
- 1. What is the MINIMUM number of Service Water header isolation valves that need to be closed to ensure SW can perform its safety function?
and
- 2. Why are FCV-4561 and FCV-4562 status lights dim?
- a. 1. (6) valves
- b. 1. (12) valves
- 2. The FCVs are not fully open, they must be failed full open locally.
- c. 1. (12) valves
- d. 1. (6) valves
- 2. The FCVs are not fully open, they must be failed full open locally.
2008 Ginna NRC Exam RO Answer:
- d. 1. (6) valves
- 2. The FCVs are not fully open, they must be failed full open locally.
Explanation:
Incorrect a. FCV-4561 and FCV-4562 status lights are bright when failed fully open.
Incorrect b. There are (2) valves in each isolation Kine that is powered from (2) separate trains. As long as any (1) valve in each line closes SW can perform its safety function. FCV-456 1 and FCV-4562 status lights are bright when failed fully open.
There are (2) valves in each isolation Kine that is powered from (2) separate I_
trains. As long as any (1) valve in each line closes SW can perform its safety function.
Correct There are ( 2 ) valves in each isolation line that is powered from (2) separate trains. As long as any (1) valve in each line closes SW can perform its safety function. If the status lights are dim the valves are not full open and the RNO from ATT-27.0 directs the operator to have an A 0 locally fail the valves full automatic actions for the following components, instrumentation ated with operating the CCS Verification, pg. 4 LP RSlOlC, Service Water
2008 Ginna NRC Exam RO Question 40 Plant conditions are as follows:
0 The unit has experienced a Design Basis Loss of Coolant Accident (DB LOCA).
0 During execution of E-0, Reactor Trip or Safety Injection, a Station Blackout occurred.
0 The Control Room Team is performing ECA-0.0, Loss of All AC Power.
Containment Pressure and Temperature are steadily rising.
- 1. What is the MINIMUM combination of Containment Cooling Systems (CCS) that must be returned to service to meet the assumptions used in the DB LOCA accident analysis?
and
- 2. Without MINIMUM CCS available, when would the Containment DESIGN Temperature limit FIRST be exceeded?
- a. 2 . (1) Containment Spray Pump and (1) Containment Recirc Fan
- 2. Containment Temperature > 286°F
- b. 1. (1) Containment Spray Pump and (1) Containment Recirc Fan
- 2. Containment Temperature > 282°F
- c. 1. (1) Containment Spray Pump and (2) Containment Recirc Fans
- 2. Containment Temperature > 286°F
- d. 1. (1) Containment Spray Pump and (2) Containment Recirc Fans
- 2. Containment Temperature > 282°F
I 2008 Ginna NRC Exam RO Answer:
C. 1. (1) Containment Spray Pump and (2) Containrinent Recirc Fans
- 2. Containment Temperature > 286°F Explanation:
Incorrect a. Need (2) Containment Recirc Fans.
Incorrect b. Need (2) Containment Recirc Fans.
282°F is the peak temperature expected following a DB LOCA.
Correct c. IAW ITS 3.6.6, CS/CRFC Bases: During- a DBA, a minimum of 2 CRFC units and one CS train are required to maintain the containment peak pressure and temperature below the design limits (Ref. 8). To ensure that these requirements are met, two CS trains, four CRFC units, and the NaOH System must be OPERABLE. Therefore, in the event of an accident, at least one CS train, the NaOH System, and two CRFC units operate, assuming the worst case single active failure occurs.
Containment Temperature Limit is 286°F. ~~
J 3
Al.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including Containment temperature
2008 Ginna NRC Exam RO Ouestion 41 Plant conditions are as follows:
0 The unit is performing a startup following a Mid-cycle maintenance outage.
0 The SHUTDOWN BANKS have been withdrawn.
0 The CONTROL BANKS are being withdrawn.
0 ARVs are in Manual.
f ,i\ou;.c.j Which of the$lant evolutions would cause the reactor to go critical PRIOR to the value obtained in the Estimated-Critical Position (ECP)? (Assume no other operator action.)
- a. Steam Generator operating level is reduced from 60% to 50%.
- b. (1) Steam Generator Automatic Relief Valve (A:RV) fails closed.
- c. (15) gallons of Boric Acid is added to the Reactor Coolant System.
- d. Steam is bypassed around the MSIVs to start the warm-up of the Main Steam Headers.
'I 2008 Ginna NRC Exam RO Answer:
- d. Steam is bypassed around the MSIVs to start the warm-up of the Main Steam Headers.
Explanation:
Incorrect a. Feedwater is reduced to achieve new 'S/G level. No change in reactivity.
Incorrect b. If an ARV fails shut, RCS temp will go up, and due to a -MTC (middle of cycle) negative reactivity is added causing the point when the Rx will go critical to be later than the ECP.
Incorrect c. Adds negative reactivity, causing the point when the Rx will go critical to be later than the ECP.
Correct d. If steam is withdrawn, RCS temp will go down, and due to a -MTC (middle of cycle) positive reactivity is added causing the point when the Rx will go critical to be sooner than the ECP.
K5.08 - Knowledge of the operational implications of the following RRTOSC, Inherent
2008 Ginna NRC Exam RO Question 42 Plant conditions are as follows:
0 The unit is operating at 90% power.
0 All plant control systems are in their normal at power alignment.
Which of the following will cause Reactor Coolant System (RCS) Tavg to INITIALLY Rise?
- a. Low Pressure Heater Bypass Valve V-3959 opens.
- b. Main Feedwater Bypass Valve to Steam Generator-A, AOV-4271, opens.
- c. Instrument Air is lost to B Main Feedwater Regulating Valve, AOV-4270.
2008 Ginna NRC Exam RO Answer:
- c. Instrument Air is lost to B Main Feedwater Re<gulatingValve, AOV-4270.
Explanation:
AOV-4270 closes on a loss of IA, F W to the B S/G will be isolated. As B S/G level drops the heat removal from the RCS drops and Tcold rises. As Tcold rises Tavg rises INITIALLY. Following the Rx trip due to B S/G level going less than 17%, Tavg will lower.
Incorrect d. If ES steam is lost to ## 5B FW Heater, FW temp to the B S/G will lower which 1 will cause Thot to lower which will result in Tavg lowering.
will have on the following: RCS Feedwater Systems,
2008 Ginna NRC Exam RO Question 43 Plant conditions are as follows:
0 The unit is operating at 50% power.
0 All plant control systems are in their normal at power alignment.
0 A leak develops on the Condensate Storage Tanks and cannot be isolated.
As CST water level drops, the FIRST volume that will require actions to be taken per Technical Specifications is when the combined volumes of the CSTs goes below (1) gallons (or with 2 tanks, a level of (2) feet, with no instrument inaccuracies).
- a. 1. 25,200
- 2. 11.9
- b. 1. 24,350
- 2. 11.5 C. 1. 23,450
- 2. 11.1
- d. 1. 22,500
- 2. 10.6
2008 Ginna NRC: Exam RO Answer:
- b. 1. 24,350
- 2. 11.5 Explanation:
1 Incorrect 1 a. I Old ITS reauirement orior to up-rate inumbers reversed).
1 Correct I b. 1 As per SR 3.7.6.1 24,350 gallons. (ROs take logs on this daily except tank levels read out in feet)
Incorrect c. Wrong water volume (numbers reversed from ITS reauirements).
I Incorrect I d. I Old ITS reauirement Prior to up-rate. I conditions for Technical Specifications
I 2008 Ginna NRC Exam RO Question 44 Plant conditions are as follows:
The unit is tripped following an accident.
0 FR-H. 1, Response to Loss of Secondary Heat Sink is being implemented.
0 Actions to supply Service Water to the Steam Generators are underway.
0 The HCO has attempted to start the C SAFW pump, but it will not start.
0 The following is the current lineup for the C SAFW pump:
o MOV-9629A, SAFW Pump C Suction Valve is closed.
o AOV-97lOA, SAFW Pump C Recirculation Valve, is closed.
o MOV-9703A, SAFW Crossover Valve, is open.
o MOV-9701A, SAFW Discharge Valve, is closed.
Why wont the C SAFW pump start?
- a. MOV-9703A, SAFW Crossover Valve must be closed, to prevent runout and damage to the C SAFW pump.
- b. MOV-9629A, SAFW Pump C Suction Valve must be open to provide a suction source to the CY SAFW pump.
- c. AOV-9710A, SAFW Pump C Recirculation Valve must be open to ensure the C SAFW pump does not run at a shut off head.
- d. MOV-9701A, SAFW Discharge Valve must be open, it does not receive any automatic signal to open and is interlocked to not allow the pump to start until MOV-9701A is open.
2008 Ginna NRC Exam RO Answer:
- b. MOV-9629A, SAFW Pump C Suction Valve must be open to provide a suction source to the C SAFW pump.
Explanation:
Incorrect a. C SAFW pump will start with MOV-9703A open, not a normal alignment but it will not prevent a pump start.
Correct b. Interlocked with pump. MOV-9629A must be open to start the C SAFW pump.
Incorrect c. AOV-9710A, SAFW Pump C Recirculation Valve, is normally closed and will automatically open as required while the C SAFW pump is running.
Incorrect d. MOV-9701A, SAFW Discharge Valve receives any automatic signal to open when the C SAFW pump switch is itaken to start.
2008 Ginna NRC Exam RO Ouestion 45 Plant conditions are as follows:
The unit is operating at rated power.
The electric plant is in a Normal 50/50 alignment.
All other systems are in their normal alignment.
Subsequently, the breaker that supplies Station Service Transformer 14 opens.
Which of the following actions will occur automatically?
(Assume other abnormal conditions are present.)
- a. The Bus 13 to Bus 14 tie breaker repositions to open.
- b. The normal feeder breaker for Bus 14 repositions to open.
- c. The A CCW Pump breaker trips and recloses after the undervoltage condition clears.
- d. The A MDAFW Pump breaker closes 30 seconds after the undervoltage condition clears.
2008 Ginna NRC Exam RO Answer:
- b. The normal feeder breaker for Bus 14 repositions to open.
Explanation:
Incorrect a. The Bus 13 to Bus 14 Tie Breaker is ii manually operated breaker. There are no automatic actions associated with the breaker and it is normally OPEN at power.
Correct b. The UV relay will pick up and cause the normal feeder breaker to trip open, Incorrect c. A CCW Pumu breaker does not trir) on a UV signal with no SI mesent.
Incorrect d. No Auto Start signal is generated for the A MDAFW Pump breaker on a UV without an SI signal. A MDAFW Pump breaker would close -30 seconds after an SI with a UV signal.
the related automatic action(s) for the following components, and/or interlock(s) which provide for the following: Circuit breaker Distribution pgs. 13-15,19
2008 Ginna NRC Exam RO Question 46 Plant conditions are as follows:
The unit is at 90% power.
The electric plant is in a 100/0 lineup.
Instrument Bus IC is being supplied by Inverter IB.
Subsequently, the 125 VDC supply from DC distribution panel 1B is lost.
How is the AC distribution system affected?
Static Transfer Switch 1B .
- a. will automatically transfer to the Constant Voltage Transformer, and will automatically transfer back to the 1B Inverter when 125 VDC is restored.
- b. must be manually transferred to the Constant Voltage Transformer, but will automatically transfer back to the 1B Inverter when 125 VDC is restored.
C. will automatically transfer to the Constant Voltage Transformer, but must be manually transferred back to the 1B Inverter when 125 VDC is restored.
- d. must be manually transferred to the Constant Voltage Transformer, and must be manually transferrc:d back to the 1B Inverter when 125 VDC is restored.
2008 Ginna NRC Exam RO Answer:
- c. will automatically transfer to the Constant Voltage Transformer, but must be manually transferred back to the IB Inverter when 125 VDC is restored.
Explanation:
I Incorrect 1 a. I Must be manuallv transferred back.
Incorrect b. Automatically transfers to alt P/S and must be manually transferred back.
Correct c. This is the proper operation of the 1B Static Transfer Switch.
Incorrect d. Automaticallv transfers to alt P/S.
I Examination: I RO2008GinnaNRC I Question#: I 46 I Rev. 3 I Level: RO 1
2008 Ginna NRC: Exam RO Ouestion 47 Plant conditions are as follows:
0 The unit is at 100% power.
0 The electric plant is in a Normal 50/50 lineup.
Subsequently, there is a complete Loss of B DC Train.
How will the Reactor Trip breakers respond?
- a. I. The A Reactor Trip Breaker will be tripped by its shunt coil.
- 2. The B Reactor Trip Breaker will be tripped by its undervoltage coil.
- b. 1, The A Reactor Trip Breaker will be tripped by its undervoltage coil.
- 2. The B Reactor Trip Breaker will be tripped by its shunt coil.
- c. 1. The A Reactor Trip Breaker will be tripped by its shunt coil.
- 2. The B Reactor Trip Breaker will be tripped by its shunt coil.
- d. 1. The A Reactor Trip Breaker will be tripped by its undervoltage coil.
- 2. The B Reactor Trip Breaker will be tripped by its undervoltage coil.
2008 Ginna NRC Exam RO Answer:
- a. 1. The A Reactor Trip Breaker will be tripped by its shunt coil.
- 2. The B Reactor Trip Breaker will be tripped by its undervoltage coil.
Explanation:
I Correct I a. 1 Per P-10 and ER-ELEC.2.
Incorrect b. Order reversed.
Incorrect c. The B Reactor Trip Breaker will be tripped by its undervoltage coil.
Incorrect d. The A Reactor Trip Breaker will be tripped by its shunt coil.
2008 Ginna NRC Exam RO Question 48 Plant conditions are as follows:
The unit is at 80% power.
Station Service Transformer - 18 (SST-18) had an internal fault which automatically isolated and deenergized Bus- 18.
The A D/G has started and loaded on to Bus-18.
0 While checking on the automatic start of the A :D/G and fault on SST-18, the A 0 reported MCC H is deenergized due to its feeder breaker being open.
0 The A 0 reports an acrid smell in the area of the feeder breaker.
Regarding the A DIG . , .
- 1. What is the impact of MCC H being deenergized?
and
- 2. What action(s) idare required to mitigate the consequences of MCC H being deenergized?
- a. 1. There is no power to the A D/G Air Start Compressor.
- 2. If a subsequent start is required for A D/G, cross connect the A and B Air Start Systems to enable the B Air Start System to start both D/Gs.
- b. 1. There is no power to the A D/G Fuel Oil Transfer Pump.
- 2. Lineup a temporary pump to fill the A D/G Fuel Oil Day Tank.
- c. 1. There is no power to the A D/G Air Start Compressor.
- 2. If a subsequent start is required for A D/G, lineup a temporary air compressor to fill the A D/G air tank.
- d. 1. There is no power to the A D/G Fuel Oil Transfer Pump.
- 2. Lineup to fill the A D/G Fuel Oil Day Tank using the B D/G Fuel Oil Transfer Pump.
2008 Ginna NRC Exam RO Answer:
- d. 1. There is no power to the A D/G Fuel Oil Transfer Pump.
- 2. Lineup to fill the A D/G Fuel Oil Day tank using the B D/G Fuel Oil Transfer Pump.
This crosstie alignment has been considered and no operability concerns exist.
Explanation:
Incorrect a. There is power to the A D/G Air Start Compressor it comes from MCC J.
Incorrect b. With MCC H deenergized there is ndpower to the A D/G Fuel Oil Transfer Pump. Temp pump not required, x-conn ops of D/G Fuel Oil Transfer Systems has been considered and no operability concerns exist.
Incorrect c. There is power to the A D/G Air St,art Compressor it comes from MCC J.
Correct d. With MCC H deenergized there is no power to the A D/G Fuel Oil Transfer Pumn. X-corm ODS are allowed Der T-27.6.
A2.13 - Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, Setpoints, Att. 1 pg. 11
2008 Ginna NRC Exam RO Question 49 Plant conditions are as follows:
0 The plant is at 2% power conducting a unit startup per 0-1.2, Plant Startup from Hot Shutdown To Full Load.
0 A and B MDAFW pumps are running to maintain S/G water levels at 52%.
0 AOV-5738, A S/G Blowdown Isolation Valve key switch is in AUX.
0 AOV-5737, B S/G Blowdown Isolation Valve key switch is in AUX.
0 S/G Blowdown Valves AOV-5737 / 5738 / 5735 / 5736 Close - Remote switch is in Remote.
0 S/G Blowdowns are in progress for both S/Gs to maintain S/G chemistry.
0 Chemistry is currently sampling both S/Gs.
Subsequently, the detector for R- 19, S/G Blowdown ProlcessRadiation Monitor fails high.
- 1. How does the detector failure affect the S/G Process Radiation Monitoring system?
and
- 2. What actions are required to permit completion of sampling?
(Assume all ITS, TRM and ODCM requirements are met.)
- a. 1. S/G Blowdown valves, AOV-5737 15738 are closed.
- 2. Place AOV-5738/5737, A/B S/G Blowdown Isolation Valve key switches to DEFEAT to reonen the S/G Blowdown valves.
- b. 1. S/G Blowdown valves, AOV-5737 15738 are open.
- 2. Immediately place S/G Blowdown Valves AOV-5737 / 5738 / 5735 / 5736 Close - Remote switch is in Close.
- c. 1. S/G Sample valves, AOV-5735 / 5736 are closed.
- 2. The only way to reopen the sample valves is to clear the close signal coming from R-19.
- d. 1. S/G Sample valves, AOV-5735 / 5736 are open.
- 2. When the chemist is done sampling and secures the lineup, the S/G Sample valves will close.
2008 Ginna NRC Exam RO Answer:
- d. 1. S/G Sample valves, AOV-5735 / 5736 are open.
- 2. When the chemist is done sampling and secures the lineup, the S/G Sample valves will close.
Explanation:
r-Incorrect a. S/G Blowdown valves, AOV-5737 / 5738 will be closed however regardless of the switch position of AOV-5738/7, A/B S/G Blowdown Isolation Valve key switches the S/G Blowdown valves, AOV-5737 / 5738. will not reopen.
Incorrect b. S/G Blowdown valves, AOV-5737 / 5738 will be closed regardless of the switch Dosition of AOV-5738/7. A/B S/G Blowdown Isolation Valve kev switches.
Incorrect C. With the chemist sampling the S/Gs the Hi Rad signal from R-19 is bypassed.
When the sample is complete the chernist will place the local Auto/close switch to close which will then close the valve. Clearing the high signal from R-19 is
- not required to open the sample valve(;.
k d. With the chemist sampling the S/Gs the Hi Rad signal from R-19 is bypassed.
When the sample is complete the chemist will place the local Auto/close switch to close which will then close the valve.
Given system conditions, describe the design features of the Steam Generator Blowdown System, to include set points, interlocks, and the related automatic action(s) for the following components, instrumentation and/or processes. a. Containment Isolation Valves AOV-5735 and 5736 b. Containment Isolation Valves AOV-5737 and 5738 f. MCB Blowdown Key Defeat Switches (2) g. MCB Blowdown Remote/Close Switch Predict the effect(s) of a loss or malfunction of the following component(s) and/or instrumentation on the Steam Generator Blowdown System:
2008 Ginna NRC Exam RO Ouestion 50 Plant conditions occurred as follows:
0 Due to a Loss of Coolant Accident (LOCA) which was followed by significant fuel failure, radiation levels throughout the plant are trending up.
0 Control Room (CR) Radiation Monitor alarms were received as follows:
(ARM = Area Radiation Monitor and PRM = Process Radiation Monitor) 0800 - R- 1, CR ARM Warning Alarm comes in.
0803 - R-45, CR PRM Warning Alarm comes in.
0806 - R-1, CR ARM High Alarm comes in.
0809 - R-46, CR PRM Warning Alarm comes in.
0812 - R-46, CR PRM High Alarm comes in.
0815 - R-45, CR PRM High Alarm comes in.
From the following choices, what is the FIRST time that BOTH Trains of CREATS system will be in the Emergency mode? (Assume no operator actions.)
- a. 0804
- b. 0807
- c. 0813
- d. 0816
2008 Ginna NRC Exam RO Answer:
C. 0813 Explanation:
I Incorrect I a. I Indication only. May choose if unclear on which PRM alarm causes CREATs to go into the Emergency mode.
Incorrect b. Indication only. CREATs goes into the Emergency mode on R-45 or 46 not on R-1.
Correct c. As per P-9 and AR-E- 11. Takes only R.45 or R-46 to be in High alarm for both trains of CREATs to go to Emergency mode.
Incorrect d. Only takes 1 out of 2 possible RM high alarms from on R-45 or 46. May choose I 1 I this if uncertain on Ionic.
annunciator or alarm.
HYVAC Isol. pg. 1 P-9, Radiation Monitor
2008 Ginna NRC Exam RO Question 51 The UFSAR defines a critical load as one that has either. a post-accident function or a function important to nuclear safety.
Which one of the following is NOT a critical Service Water load?
- a. Residual Heat Removal Pump Room Coolers
- b. Containment Recirculation Fan Motor Coolers
- c. Preferred Auxiliary Feedwater Pump Oil Coolers
- d. Safety Injection Pump Outboard Thrust Bearing Housing Oil Coolers
I 2008 Ginna NRC Exam RO Answer:
- a. Residual Heat Removal Pump Room Coolers Explanation:
Correct a. Non-critical load.
Incorrect b. Critical load.
Incorrect c. Critical load.
I Incorrect 1 d. I Critical load. I 2.1.27 - Knowledge of system purpose and/or function.
I 2008 Ginna NRC Exam RO Question 52 Plant conditions are as follows:
0 The unit is at 100% power.
0 Due to issues associated with the Service Water (SW) pumps, AP-SW.2, Loss of Service Water has been entered.
0 C SW pump is the only SW Pump running.
0 Operations personnel are monitoring plant equipment.
- 1. What is the plant response for the given plant conditions if they remain unchanged?
and
- 2. What is directed to be performed per AP-SW.2, Loss (of Service Water if conditions continue to degrade?
- a. 1. Condensate Pump motor temperatures slowly rise, while Condensate Booster Pump motor temperatures remain relatively steady.
- 2. Align Alternate DIG Cooling to the A D/G.
- b. 1. Condensate Pump and Condensate Booster Pump motor temperatures slowly rise.
- 2. Align Alternate D/G Cooling to the A D/G.
- c. 1. Condensate Pump and Condensate Booster Pump motor temperatures slowly rise.
- 2. Perform a Load Reduction.
- d. 1. Condensate Pump motor temperatures slowly rise, while Condensate Booster Pump motor temperatures remain relatively steady.
- 2. Perform a Load Reduction.
2008 Ginna NRC Exam RO Answer:
- d. 1. Condensate Pump motor temperatures slowly rise. while Condensate Booster Pump motor temperatures remain relatively steady.
- 2. Perform a Load Reduction.
Explanation:
i Incorrect Right plant response but, with C SW pump as the only SW Pump running, AP-SW.2 directs lining up Alternate D/G Cooling per ER-DG.2 to the B D/G.
Incorrect SW does not supply cooling water to the CB pumps therefore they should stay relatively the same temperature and with C SW pump as the only SW Pump running, AP-SW.2 directs lining up Alternate D/G Cooling per ER-DG.2 to the B D/G.
Incorrect SW does not supply cooling water to the CB pumps therefore they should stay Correct 5 RNO directs a power reduction to stabilize eauiument ternueratures.
or operations on the SWS; and (b) based on those predictions, use the consequences of those LP R5101C, Service Water
2008 Ginna NRC Exam RO Question 53 Plant conditions are as follows:
0 The unit is at 100%power.
0 The Service and Instrument Air headers are split.
0 Service Air compressor is supplying the Service Air header.
0 T-21, Periodic Operation of Instrument Air Compressors A and B is being performed.
0 A and B Instrument Air Compressors are running.
0 C Instrument Air Compressor is running unloaded.
0 Instrument Air header pressure is 115 psig and stable.
Subsequently, Instrument Air header pressure starts to trend down.
Which one of the following is the correct system and/or operator response per T-21, for the given conditions?
- a. C Instrument Air Compressor will automatically reload when the Instrument Air header pressure reaches 105 psig.
- b. The Control Room Operator must push the LOAIY button on the MCB (back panel) by the C Instrument Air Compressor, when the Instrument Air header pressure reaches 105 psig.
- c. Under direction from the Control Room, an Auxiliary Operator (AO) must locally push the LOAD button on the C Instrument Air Compressor, when the Instrument Air header pressure reaches 105 psig.
- d. Under direction from the Control Room, an Auxiliary Operator (AO) must locally push the LOAD and RESET-TEST buttons on the C Instrument Air Compressor, when the Instrument Air headcr pressure reaches 105 psig.
2008 Ginna NRC Exam RO Answer:
- c. Under direction from the Control Room, an Auxiliary Operator (AO) must locally push the LOAD button on the C Instrument Air Compressor, when the Instrument Air header pressure reaches 105 psig.
Explanation:
Incorrect a. No auto reload feature, plausible due i.0 A/B IA Compressors do.
Incorrect b. P/B is on local panel.
Correct c. Rewired Der T-21. Notes Drior to steD 5.3.
Incorrect d. Depressing the RESET-TEST P/B only required after an emergency shutdown but and not required by T-21, plausible if uncertain of interlocks/logics.
2008 Ginna NRC Exam RO Question 54 Plant conditions are as follows:
0 The unit is at 50% power.
0 C Instrument Air Compressor (IAC) is running.
0 A and B Instrument Air Compressors are in Auto.
0 Service and Instrument Air headers are cross-connected per T-1C, Instrument Air/Service Air Cross Connect.
Subsequently, power to Bus 15 is lost.
Proper IA system response, as indicated by PI-2086, IA header pressure gauge, shows that when IA header pressure lowers to 105 psig the . . .
- a. A IAC will automatically start and load. If IA pressure rises to 125 psig, A IAC will unload.
- b. B IAC will automatically start and load. If IA pressure rises to 125 psig, B IAC will unload.
- c. A IAC will automatically start and load. If IA pressure rises to 130 psig, A IAC will unload.
- d. B IAC will automatically start and load. If IA pressure rises to 130 psig, B IAC will unload.
2008 Ginna NRC Exam RO Answer:
- a. A IAC will automatically start and load. If IA pressure rises to 125 psig, A IAC will unload.
Explanation:
With the local switch position in Auto the A IAC starts on IA header press
<lo5 psig. Constant speed - comp runs loading/unloading to maintain IA header B IAC will not start it is owered from Bus 15, which is dead.
Incorrect c. Loads and unloads 110-125 mig.
1 Incorrect I d. I B IAC will not start it is powered from Bus 15, which is dead.
Instrument and Service Air System, to include set points, interlocks, and the related automatic action(s) for the following components, tation and/or processes a. Instrument Air Compressors A4.01 - Ability to manually operate and/or monitor in the control R4701C, Instrument and Service Air System
2008 Ginna NRC Exam RO Question 55 Plant conditions are as follows:
0 The unit is in Mode 6.
0 Shutdown Containment Purge is running to support refueling operations.
0 Core Alterations are in progress.
0 All pool levels are NORMAL.
Which one of the following would require the immediate: suspension of Core Alterations in accordance with Technical Specifications?
- a. The Containment Equipment hatch is in place with (6) equally spaced bolts.
- b. Annunciator L-4, Safeguard DC Failure CI and CVI Logic, comes in.
- c. The Containment Personnel hatch interlock mechanism is disabled, but one of the two personnel air lock doors remains closed.
- d. While the A RHR system is in operation the B RHR pump motor develops a leak that drains a11 of the oil out of the motor.
2008 Ginna NRC Exam RO Answer:
- b. Annunciator AR-L-4, Safeguard DC Failure CI arid CVI Logic, comes in.
Explanation:
Incorrect- a. Allowed per ITS Bases 3.9.3. as long as (4) equally spaced bolts are in place the LCO is met.
Correct b. With Shutdown Containment Purge running there must be (2) trains of CVI Operable to close the penetrations. With AMCB DC Distribution Panel isolated train A is inop. LCO NOT met. Must suspend Core Alterations.
This question is in reference to lessons learned at Ginna during a Refueling outage in 2006. DC power was inadvertently tagged out to the CVI isolation ckts. during Refueling operations See CR-2006-005236.
Incorrect C. Allowed per ITS Bases 3.9.3. As long as one of the two personnel air lock doors remains closed. the LCO is met.
Incorrect d. Per 0-5.1 step 6.1.3 and ITS 3.9.4 with water level >23 above the top of the
- reactor vessel flange only one RHR pump/Hx must be operable and in operation.
2008 Ginna NRC Exam RO Ouestion 56 Which of the following correctly describes where the Reactor Vessel Level Indication System (RVLIS) connects to the RCS?
- a. Upper Tap: Single tap at the Reactor Vessel head.
Lower Tap: Teeing off of the RCS Loop B Nuclear sampling penetration.
- b. Upper Tap: Teeing off of the Head Vent Valve piping.
Lower Tap: Teeing off of one of the neutron flux mapping guide tubes.
- c. Upper Tap: Single tap at the Reactor Vessel head.
Lower Tap: Teeing off of one of the neutron flux inapping guide tubes.
- d. Upper Tap: Teeing off of the Head Vent Valve piping.
Lower Tap: Teeing off of the RCS Loop B Nuclear sampling penetration.
2008 Ginna NRC Exam RO Answer:
- c. Upper Tap: Single tap at the Reactor Vessel head.
Lower Tap: Teeing off of one of the neutron flux mapping guide tubes.
Explanation:
Incorrect a. Upper Tap: Correct location.
Lower Tap: This is the tap for LI-432B, B Loop level indicator that is only used
- and aligned when the unit is S / D .
Incorrect b. Upper Tap: This is where it was originally
- connected.
Lower ~ i pCorrect
- location Correct C. Upper tap: On reactor vessel head (500;B isolation valve): 3/8 stainless steel piping. Swagelok fitting. Runs through refueling cavity wall. Tubing inside cavity removable for refueling. Piping welded to liner to maintain cavity integrity.
Lower tap: Containment Sump A below vessel. Tee off neutron flux map (incore detector before seal table) guide tube for location I - 11. 3/8 stainless steel
- pipe. Swagelok fitting Incorrect d. Upper Tap: This is where it was originally connected.
Lower Tap: This is the tap for LI-432B. B Loop level indicator that is only used and aligned when the unit is S / D .
- tions between the Reactor Vessel Level Indication System and a given interrelated system
2008 Ginna NRC Exam RO Ouestion 57 Plant conditions are as follows:
A unit Startup is in progress.
The Reactor is at 6% power.
Subsequently, N-35, Intermediate Range Detector, fails to 1.OE-3 amps.
How will the plant respond?
- a. The reactor will trip, Source Range indications will automatically become available.
- b. The reactor remains at 6% power, however N-35 must be bypassed prior to raising power greater than P-10.
C. The reactor will trip , manual action is required for Source Range indications to become available.
- d. The reactor remains at 6% power, and because N -36 remains Operable, all controls will function normally.
2008 Ginna NRC Exam RO Answer:
- c. The reactor will trip , manual action is required for Source Range indications to become available.
Explanation:
- a. The reactor has tripped due to N-35 failing to the top of the IR scale which is greater than the Trip set point of -25% Rx power and also satisfies the 1/2 logic for the Rx trip. Manual action will be required because SR detectors will not auto energize because N-35 has failed high and the logic (212 IR <5x10-11
- amps) wont be met.
- b. The reactor has tripped due to N-35 failing to the top of the IR scale.
C. The reactor has tripped due to N-35 failing to the top of the IR scale which is greater than the Trip set point of -25% Rx power and also satisfies the 1/2 logic for the Rx trip. . Manual action will be required because SR detectors will not auto energize because N-35 has failed high and the logic (2/2 IR <5x10-11 amps) wont be met.
I Incorrect -d. The reactor has tripped due to N-35 failing to the top of the IR scale.
ct that a loss or malfunction of the NIS
2008 Ginna NKG Exam KO Question 58 Plant conditions occurred as follows:
0 The unit tripped due to a Loss of Offsite power.
0 Both D/Gs started and energized the required loads.
0 All equipment responded as designed.
0 ES-0.2, Natural Circulation Cooldown is being implemented Subsequently, during the cooldown, the following conditions exist:
0 Containment pressure is 5.5 psig and slowly rising.
0 Average corc exit thermocouple (CET) temperature is 420OF and stable.
RCS pressure is 500 psiig and stable.
Pressurizer level is 20% and stable.
Given the above conditions and provided references:
1 . Per Fig- 1 ,0 Figure Min Subcooling, what is the status of the RCS'?
and
- 2. Based on the status oP the RCS, which action is required per ES-0.2, Natural Circulation Cooldown Foldout page'!
- a. I . Thc RCS is subcooled.
- 2. DO NOT initiate SI and CI.
- b. 1. The RCS is inadequately subcooled.
- 2. Initiate SI and CI.
- c. I . The RCS is inadequately subcooled.
- 2. DO NOT initiate SI and CI.
- d. 1 . The RCS is subcooled.
- 2. Initiate SI and CI.
Answer:
- b. 1 . The KCS is inadequately subcooled.
- 2. Initiate SI and CI.
Explanation:
liicorrcct Correct Incorrect Incorrect Examination:
Lesson Plan:
Objective(s):
Category:
a.
b.
c.
d.
Cognitive level:
RES02C 2.01 CIA 1
2008 Ginna NRC Exam
- 1. This would be correct if adverse containment conditions did not exist.
- 2. Correct action if adverse-___containment conditions did not exist.
I . RCS is inadequately subcooled by 40°F.
- 2. Action required per ES-0.2, Natural Circulation Cooldown Foldout age.
2.
subcooled by 40°F.
1 . This would be correct if adverse containment conditions did not exist.
- 2. Action required per ES-0.2,____. Natural Circulation Cooldown Foldout page..
RO 2008 Ginna NRC I Question #e: 1 58 Natural Circulation Cooldown ES-0.2 I Rev.3 I Lcvel:~~
Given a set of plant and equipment conditions, evaluate the conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE N O T OBTAINED instructions to implement in ES-0.2, Tier 2 I ;roup 2 Question Source:
Difficulty Level:
KS.02 - Knowledge of the operational implications of the following concepts as they apply to the ITM system: Saturation and subcooling of ES-0.2, Natural Circulation Bank 3
RO Used on Audit Exam - No I Bank #: I Common Exam Bank 10CFR 55 Content: 55.4 1(a)( IO) I 55.43
2008 Ginna NRC Exam RO Question 59:
A new fuel assembly is being transferred from the Auxiliary Building to Containment.
What automatically stops the conveyer car movement at the correct position to upend the fuel assembly?
- a. e conveyer car moves for a preset period of time and theti stops.
- b. A counter measures conveyer car movement and stops the conveyer car at a predetermined distance.
- c. A location encoder on the conveyer car determines the car is in the correct location.
- d. A travel limit switch is actuated by the conveyer car.
~
2008 Ginna NRC Exam RO Answer:
- d. A travel limit switch is actuated by the conveyer car.
Explanation:
Incorrect a. A conveyer car travel limit switch is used.
Incorrect b. Some stations use this to determine the location of a conveyer car but is not used at Ginna to stop car movement.
Incorrect c. Some stations use this to determine the location of a conveyer car but is not used at Ginna to stop car movement.
Correct d. Underwater switches stop the car at the limits of travel and indicate its position on the track.
Handling System, to include set points, interlocks, and the related automatic action(s) for the following components, instrumentation
{ LP R3701C, Fuel Handling 1
2008 Ginna NRC Exam RO Question 60 Plant conditions occurred as follows:
0 The unit was operating at 100% power.
0 Rod control is in Manual.
0 All other Control Systems are in their normal alignment.
Subsequently, one of the Turbine Control Valves failScompletelyshut.
0 During the transient Tavg spikes to 586°F.
0 NO Operator actions have been performed.
Which one of the following describes the plant response for these given conditions?
- a. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately equal to Tref.
- b. Four Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is approximately equal to Tref.
- c. Four Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is stable: at a temperature that is at least 4°F higher than Tref.
- d. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is stable at a temperature that is at least 4°F higher than Tref.
I 2008 Ginna NRC Exam RO Answer:
- d. All Steam Dumps will snap open and then the Steam Dumps will throttle close until Tavg is stablc at a temperature that is at least 4°F higher than Tref.
Explanation:
Incorrect a. This would be the correct response if Rods were in Auto, with rods in Manual there is a 4°F dead band.
Incorrect b. Due to the initial high delta T (>I 1°F) in Manual there is a 4°F dead band.
Incorrect c. Due to the initial high delta T (>11"F)
Correct d. Due to the initial high delta T (>I 1OF) in Manual there is a 4°F dead band.
2008 Ginna NRC Exam RO Question 61 Plant conditions are as follows:
0 The unit is at 55% power.
0 All control systems are in their normal at power alignment.
0 Alarm 1-27, Rotor Eccentrity or Vibration Alarm is lit.
0 Turbine Bearing Vibrations are as follows:
Bearing 1 - 1.2 mils 4 - 2.7 mils 7 - 2.5 mils 2 - 1.7 mils 5 - 2.8 mils 8 - 3.4 mils 3 - 1.0 mils 6 - 2.0 mils 9 - 11.0 mils Per AP-TURB.3, Turbine Vibration ,the correct INTIAL operator response is to:
- a. Reduce turbine load to stabilize vibration.
- b. Trip the turbine, and perform immediate operator actions for E-0.
- c. Trip the turbine, verify power above 1% and verify control rods are driving in to reduce power.
- d. Adjust generator hydrogen temp or turbine lube oil temp or exciter cooling to stabilize vibrations
2008 Ginna NRC Exam RO Answer:
- d. Adjust generator hydrogen temperature or turbine lube oil temp or exciter cooling to stabilize vibrations.
Explanation:
Incorrect a. This would be the correct response if the high vibrations (>7 mils) were on bearings 1-8.
Incorrect b. This would be the correct response per AP-TURB.3, Turbine Vibration RNO step 1 if any turbine vibration was >14 mils since power is > P-9.
Incorrect c. This would be the correct response pcr AP-TURB.3, Turbine Vibration RNO step 1 if any turbine vibration was >14 mils and power was less than 50 %
(<P-9).
Correct d. This is the correct response per AP-TURB.3, Turbine Vibration RNO step 3.
2008 Ginna NRC Exam RO Question 62 Plant conditions are as follows:
0 The unit is at 90% power.
0 All systems are in their normal alignment.
0 Auxiliary Building (AB) Ventilation IMS Switch i s in FILTER IN.
0 C Gas Decay Tank (GDT) is being released.
- 1. What is the effect if R- 13, Auxiliary Building Particulate Monitor, or R- 14, Auxiliary Building Gas Monitor, goes into high alarm?
and
- 2. What are the operator actions for that plant response?
- a. 1. If R-13, goes into high alarm, C Gas Decay Tank release is automatically secured.
- 2. Verify the GDT release AOV to the plant vent closes.
Ensure 1F AB Exhaust fan is no longer running.
Ensure lA, 1B and 1C Intermediate Building Ex.haust fans are no longer running.
- b. 1. If R-13, goes into high alarm, C Gas Decay Tank release is automatically secured.
- 2. Verify the GDT release AOV to the plant vent closes.
Ensure lA, lB, 1C and 1F AB fans are no longer running.
Ensure IA, 1B and 1C Intermediate Building Exhaust fans are no longer running.
- c. 1. If R-14, goes into high alarm, C Gas Decay Tank release is automatically secured.
- 2. Verify the GDT release AOV to the plant vent closes.
Ensure I F AB Exhaust fan is no longer running.
Ensure lA, 1B and IC Intermediate Building Exhaust fans are no longer running.
- d. 1. If R- 14, goes into high alarm, C Gas Decay Tank release is automatically secured.
- 2. Verify the GDT release AOV to the plant vent closes.
Ensure IA, IB, 1C and 1F AB fans are no longer running.
Ensure 1A, 1B and 1C Intermediate Building Exhaust fans are no longer running.
2008 Ginna NRC: Exam RO Answer:
- c. 1. If R-14, goes into high alarm, C Gas Decay Tank release is automatically secured.
- 2. Verify the GDT release AOV to the plant vent closes.
Ensure IF AB Exhaust fan is no longer running.
Ensure lA, 1B and 1C Intermediate Building Exhaust fans are no longer running.
Explanation:
Incorrect a. R- 13 will cause this realignment of the AB exhaust system but it will not stop the Gas Decay Tank release so RCV- 14 (the GDT release AOV to the plant vent) will not close.
Incorrect b, R-13 will cause a realignment of the AB exhaust system but it will not stop the Gas Decay Tank release so RCV-14 (the GDT release AOV to the plant vent) will not close. This is correct if the Auxiliary Building (AB) filters are OUT, but in the stem the Auxiliary Building (AB) filters are IN, so the additional fans are not affected.
T Correct With a high alarm on R-14 and the A13 filters are IN the automatic actions that should occur are: RCV-14 (the GDT release AOV to the plant vent) closes. 1F AB Exhaust fan receives a trip signal. 1A, 1B and 1C Intermediate Building fans receive trip signals.
I L With a high alarm on R-14, RCV-14 closes. This is correct if the Auxiliary Building (AB) filters are OUT, but in the stem the Auxiliary Building (AB) filters are IN, so the additional fans are not affected.
room: Waste gas release rad monitors Monitoring System
2008 Ginna NRC Exam RO Question 63 Plant conditions occurred as follows:
0 While operating at rated power, a major steam leak developed downstream of the MSIVs.
0 The unit tripped, an automatic Safety Injection (SI) occurred and the MSIVs automatically closed.
0 All systems operated as designed.
Subsequently, RCS pressure has recovered and ARVs are controlling Tavg.
0 The Control Room Team is performing E-0, Reactor Trip or Safety Injection.
0 A tube rupture then develops in the B Steam Generator.
As the Control Room operators monitor their equipment, which Radiation Monitor will indicate the Steam Generator tube rupture first?
- a. R Main Steam Line Radiation Monitor
- b. R Air EjectorExhaust Radiation Monitor
- c. R Condenser Air Ejector Radiation Monitor
- d. R Steam Generator Blowdown Radiation Monitor
2008 Ginna NRC Exam RO Answer:
- a. R Main Steam Line Radiation Monitor Explanation:
Correct a. Still available and with flow thru the'ARV will be the first RM to indicate the SGTR.
Incorrect b. New R M installed last R/F outage to calculate S/G tube leaks however, R-47 was isolated by the MSIVs.
Incorrect c. R-15was isolated bv the MSIVs.
I Incorrect I d. I R-19is isolated by the CI that happened when the auto SI occurred.
and function, and 1.01 - Ability to predict an nitor changes in parameters
2008 Ginna NRC Exam RO Question 64 Plant conditions are as follows:
0 The unit is at 100% power.
0 B and C Service Water pumps are running.
A and D Service Water pumps are selected.
The normal supply breaker to Bus 17 fails open.
How will the Service Water System (SWS) respond?
(Assume no operator action.)
- a. B Service Water pump will trip and only D Service Water pump will start 40 seconds after the B D/G breaker closes.
- b. B Service Water pump will trip and only D Service Water pump will start 17 seconds after the B D/G breaker closes.
C. B Service Water pump will restart immediately after the B D/G breaker closes and D Service Water pump will start 17 seconds after the B D/G breaker closes.
- d. B Service Water pump will restart immediately after the B D/G breaker closes and D Service Water pump will start 40 seconds after the B D/G breaker closes.
2008 Ginna NRC Exam RO Answer:
- a. B Service Water pump will trip and only D Service Water pump will start 40 seconds after the B D/G breaker closes.
Explanation:
~
Correct a. On an undervoltage the running SW pump will trip and only the selectedSW-pump will start for that train 40 seconds after B D/G breaker closes.
Incorrect b. 17 seconds is if there was a SI signal concurrent with an undervoltage condition.
Incorrect c. There is no immediate restart. There is for CS if it was already running and 17 seconds is if there was a SI signal concurrent with an undervoltage condition.
Incorrect d. B Service Water Dump will triD and not restart because it is not selected.
Examination: RO 2008 Ginna NRC I Question #: I I 64 Rev. 2 I Level: RO Lesson Plan: R5101C I Service Water System Objective(s): 1.07 Given system conditions, describe the design features of the Service Water System, to include sei points, interlocks, and the related automatic act ions for the Io1lowing components, instrumentation and/or processes. d. Safeguards Buses 17 and 18 undervoltage condition.
Category: Tier 2 / Group 2 Question Source: Ncw Cognitive level: C/A Difficulty Level: 3 075 Circulating Water K2.03 - Knowledge of bus power supplies to the following:
Emergency/essential SWS pumps
I 2008 Ginna NRC Exam RO Ouestion 65 The following alarms were received simultaneously on the Fire Control Panel in the Control Room:
218 - Control Bldg. 271-0 Relay Room First Alarm SO8 - Control Bldg. 271-0 Rly Rm Computer Rin Auto Halon What is the condition of the Halon system for the Relay and Mux room one minute after receiving these alarms?
- a. Halon system has not actuated.
- b. Halon system for Relay and Mux rooms has actuated.
- c. Halon system for Relay room has actuated and Mux room has not actuated.
- d. Halon system for Relay room has not actuated and Mux room has actuated.
2008 Ginna NRC Exam RO Answer:
- a. Halon system has not actuated.
Explanation:
Fire Panel (FCP) (Gamewell)
SC-3.2.7, Immediate Action
- Relay/Multiplexer Room
2008 Ginna NRC E:xam RO Question 66 In accordance with CNG-OP-1.01-2001, Communications and Briefings, which of the following is used by Ops Management to communicate short-term information and instructions to Ops personnel and how long is it kept?
- a. Standing Order, 30 days maximum.
- b. Night Order, 30 days maximum.
- c. Standing Order, Until removed by the GS-Shift Operations or conditions are no longer applicable.
- d. Night Order, Until removed by the GS-Shift Operations or conditions are no longer applicable.
2008 Ginna NRC Exam RO Answer:
- d. Night Order, Until removed by the GS-Shift Operations or conditions are no longer applicable.
Explanation:
Incorrect a. Stem states definition of Night Order, Night Orders are maintained as long as they are applicable or until they are Incorrect b. Night Orders are maintained as removed bv the GS-Shift Onerations..
Incorrect c. Stem states definition of Night Order.
Correct d. Per CNG-OP- 1.01-2001, Communications and Briefings per section 5.3 B and D.
management directives, such as standing orders, night orders, Operations memos, etc.
I 2008 Ginna NRC Exam RO Question 67 Which one of the following describe the operator actions required when a YELLOW terminus is identified in the CSFSTs and assuming no higher CSF is indicated during the implementation of an Emergency Operating Procedure (EOP).
- a. Immediately implement the yellow path terminus procedure.
- b. Transition to the yellow path can only be implemented after the current step of EOP in effect is completed.
- c. Transition to the yellow path can only be implemented after the current EOP in effect is completed
- d. Transition is at operator discretion based on evaluation of the yellow path.
2008 Ginna NRC Exam RO Answer:
- d. Transition is at operator discretion based on evaluation of the yellow path.
Explanation:
Incorrect a. This is correct for a Red or Orange path terminus but not for a Yellow path.
Incorrect b. Transition is at the discretion of the CRS.
Incorrect c. Transition is at the discretion of the CRS.
Correct d. A YELLOW path terminus (3) is an indication of an off-normal condition. These do not take priority over other procedures. The operator is allowed to decide if an FR procedure noted at a YELLOW terminus is to be implemented based on the plant status and system trends at the time the condition is noted. While performing the actions of the yellow path, continuous actions or foldout page items of the EOP in effect are still applicable and shall be monitored by the Operator and STA.
2008 Ginna NRC Exam RO Question 68 The plant is in Mode 6 preparing to offload fuel.
Per lmproved Technical Specifications (ITS), which ONE (1) of the following describes the MINIMUM Source Range Nuclear Instrumentation requirement that must be met prior to off-loading fuel from the reactor vessel?
Visual in Control Room Audible in Control Room Audible in Containment
- a. 1 1 0
- b. 1 1 1 C. 2 1 0
- d. 2 0 1
$1 2008 Ginna NRC Exam RO Answer:
C. 2 1 0 Explanation:
2/1/0 is the ITS requirements. May choose if its believed as long as any (1) SR is operable and working in the control room area the Refueling requirements are Incorrect b. 2/1/0 is the ITS requirements. May choose if its believed as long as any (1) SR is I operable and working in all the areas the Refueling requirements are met.
Correct I c. 1 This is correct per ITS 3.9.2 and 0-15.1.
I Incorrect d. 2/1/0 is the ITS requirements. May choose if its believed that (2) SR are required to be operable and working in the control room area and only 1 working in the Cnmt.
2008 Ginna NRC Exam RO Question 69 Which one of the following jobs would REQUIRE an 1:solatedWork Area (a HOLD), due to it meeting the definition of a Hazardous Energy in accordance with A-1401, Station Holding Rules?
(Assume NO instrument calibrations will be performed.)
Work on a(n) . . .
C. system which has a maximum pressure of 30 psig and a maximum temperature of 90°F.
- d. system which has a maximum pressure of 15 psig and a maximum temperature of 100°F.
I 2008 Ginna NRC Exam RO Answer:
Explanation:
Incorrect I a. I Per A-1401 a hold is required for > 50 volts (AC OR DC).
Correct I b. I Per A-1401 a hold is reauired for > 50 volts (AC OR DC).
I Incorrect I c. I Per A-1401 a hold is required for > 50 psig hydraulic pressure and/or > 120°F I temperature .
Incorrect d. Per A-1401 a hold is required for > 50 psig hydraulic pressure and/or > 120°F temDerature.
2008 Ginna NRC: Exam RO Ouestion 70 Which one of the following plant conditions would require entry into a Technical Specification Action Statement?
- a. While in Mode 5, the HCO reports the Refueling Water Storage Tank (RWST) borated water volt (me is 275,000 gallons.
- b. Chemistry reports, Spent Fuel Pool boron concentration is 2400 ppm and there are fuel assemblie in I the Spent Fuel Pool.
C. During the roll up of the Turbine Generator, the CO reports A Loop Tavg is 545F, B Loop 1avg is 525°F and both are trending up slowly.
- d. During a Reactor Startup, just after the Shutdown Bank rods are pulled to step 223, it is discovered that one of the Shutdown Rods is untrippable.
2008 Ginna NRC Exam RO Answer:
- c. During the roll up of the Turbine Generator, the CO reports A Loop Tavg is 545F, B Loop Tavg is 525°F and both are trending up slowly.
Explanation:
Incorrect a. RWST level is not applicable in Mode 5 per ITS 3.5.4. (Less than a one hour LCO.)
Incorrect b. Spent Fuel Pool boron concentration minimum limit is 2300 ppm per ITS 3.7.12.
(Less than a one hour LCO.)
Correct C. When in Mode 1, BOTH RCS Tavgs must be > 540°F per ITS 3.4.2. (Less than a one hour LCO.)
Incorrect d. Still in Mode 3 per 0-1.2, Plant Startup from Hot Shutdown to Full Load, therefore LCO 3.1.4 is not applicable. (Less than a one hour LCO.)
I 2008 Ginna NRC Exam RO Ouestion 71 To ensure release rates are within limits, the Auxilia y Building Exhaust Fan C must be in operation taking suction through the Charcoal Filter Banks d&&&%andling &fuel assemblies in the Auxiliary Building when either the fuel being handled or the fuel stored in the Spent Fuel Storage Pool has decayed less thew days since irradiation.
Ck& b
- b. 30%
- d. 98
2008 Ginna NRC Exam RO Answer:
- c. 60 Explanation:
Incorrect a. If less than 60 days AB Exhaust Fan'C must be in operation taking suction through the Charcoal Filter Banks.
Incorrect b. If less than 60 days AB Exhaust FanC must be in operation taking suction through the Charcoal Filter Banks.
Correct c. As required per T-35A, Auxiliary and Intermediate Building Ventilation System (Startup and Shutdown) precaution 4.2.
Incorrect d. If less than 60 days AB Exhaust Fan C must be in operation taking suction through the Charcoal Filter Banks.
I Building Ventilation Svstems Given a specific fundamental principle, performance test, limits andor precautions for the Containment, Auxiliary, or Control Building Ventilation Syste:ms or component, describe the reasonhasis and the effect on the operations of the system or comDonent.
I 2008 Ginna NRC Rxam RO Question 72 Plant conditions are as follows:
0 The Reactor is critical and at 2% power.
0 A containment entry is underway to look for a leak identified during the startup.
0 The mechanic and contractor RP tech who are looking for the leak, have called the Control Room and informed you they have found a Boric ,4cid leak coming from the reactor cavity area and going into the A sump.
0 They want permission to enter the reactor cavity area and A sump to determine the extent of the Boric Acid leak.
0 The contractor RP tech says that he has a portable radiation monitoring device with him that will cover the expected doses, and they are both wearing all the required dosimitry.
What is the correct personnel action in accordance with A-3, Containment Vessel Access Requirements?
- a. They may not enter either of the areas at this time.
- b. They may enter the A sump, but not the reactor cavity area.
- c. They may enter the reactor cavity area, but not the A sump.
- d. As long as the RP tech stays with the mechanic, they can enter both areas.
2008 Ginna NRC E:xam RO Answer:
- a. They may not enter either of the areas at this time.
Explanation:
Correct a. Per A-3, Containment Vessel Access Rcquirements precaution 3.5: When the reactor is critical, personnel SHALL NOT enter the reactor cavity or A Sump.
Incorrect b. Entering sump might be possible with R.P support however procedurally not allowed.
Incorrect c. Entering reactor cavity area might be possible with RP support however procedurally not allowed.
Incorrect d. With RP coverage, lends validity to the possibility of entering either area I however procedurally not allowed. 1 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, 4,
A-3, Containment Vessel Access Requirements
2008 Ginna NRC Exam RO Question 73 Plant conditions are as follows:
0 The Control Room staff is responding to an Orange path on Containment per FR-Z. 1, Response To High Containment Pressure.
0 The STA provides an update with the following information:
o Inventory - Yellow o Containment - Red o HeatSink - Red o Subcritical - Green o Integrity - Orange o Core Cooling - Red What is the correct action to be taken and why?
- a. Immediately transition to FR-C. 1, Response To Inadequate Core Cooling because efforts need to )be made to ensure the fuel cladding remains intact.
- b. Immediately transition to FR-H.l, Response To Loss of Heat Secondary Sink, because efforts nersd to be made to ensure the Reactor Coolant System remains intact.
C. Complete FR-Z. 1, Response To High Containment Pressure, because the Orange path is now a Rcd path and efforts need to be made to ensure Containment, the last barrier to the public, remains intact, then transition to FR-C. 1, Response To Inadequate Core Cooling.
- d. Complete FR-Z. 1, Response To High Containment Pressure, because the Orange path is now a R!.d path and efforts need to be made to ensure Containment, the last barrier to the public, remains int:ct, then transition to FR-H. 1, Response To Loss of Secondary Heat Sink.
2008 Ginna NRC Exam RO Answer:
- a. Immediately transition to FR-C. 1, Response To Inadequate Core Cooling because efforts need to be made to ensure the fuel cladding remains intact.
Explanation:
Correct a. Even with a Cnmt Red path, the Red path for Core Cooling is a higher priority and must be performed first.
Incorrect b. Correct to leave Cnmt Orange/ Red path, but Core Cooling is a higher priority then Loss of Secondary Heat Sink.
Incorrect c. Required to immediately exit FR-Z.l and enter FR-C.l due to it being the highest Red Dath at this time.
Incorrect d. Required to immediately exit FR-Z. 1 and enter FR-C. 1 due to it being the highest Red path at this time.
- tion Status Trees (CSFSTs) in order of
2008 Ginna NRC Exam RO Ouestion 74 Plant conditions are as follows:
0 The plant is in a Site Area Emergency.
0 Due to degrading plant conditions an entry into containment must be made in the next 15 minutes to prevent a severe radiation release I:O the public from occurring and escalating the site to a General Emergency.
0 RP has determined the volunteer will receive 3500 mrem (TEDE) for the evolution.
What is the MINIMUM authorization required to approve the expected exposure in accordance with EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure?
(Answers listed are from lowest to highest authorization required.)
- a. Radiation Protection Technician
- b. Supervisor, Radiation Protection Operations
- c. Radiation Protection Manager
- d. Emergency Coordinator
I 2008 Ginna NRC Exam RO Answer:
- c. Radiation Protection Manager Explanation:
~.
Incorrect a. Radiation Protection Manager authorization is required. Possible choice due to is required. Possible choice due to Correct Required per EPIP 2-8, Voluntary Acceptance of Emergency Radiation Exposure pg. 2. Radiation Protection Manager can authorize up to (4) rem (TEDE).
Incorrect d. Emergency Coordinator approval required for >4 rem (TEDE).
the emergency plan.
2008 Ginna NRC Exam RO Question 75 Plant conditions are as follows:
0 The plant is in a General Emergency.
0 The Ginna Station Nuclear Emergency Response Plan is being implemented.
From the list below, which one of the following correctly identifies the responsibilities of the HCO/CO during the General Emergency in accordance with EPIP 5-7, Emergency Organization?
- 1. Report all unusual observations or communicatiorls to the Shift Manager.
- 2. Sound the alarm and make announcements as necessary.
- 3. Peer check the Shift Manager in the diagnosis of unusual event conditions and above.
4.Check that the Control Room ventilation system is in re-circulation mode.
- 5. Assist as directed and inform Shift Manager of all Control Room changes.
- 6. Ensure search and rescue is initiated, if necessary, per EPIP 1-8.
- a. 1,3, 5
- b. 2,4,6
- c. 1, 3 , 6
- d. 2,4,5
2008 Ginna NRC Exam RO Answer:
- d. 2,4, 5 Explanation:
Incorrect a. # 1 is the responsibility of the C/R Communicator. # 3 is the responsibility of the STA per EPIP 5-7, Emergency Organization.
Incorrect b. # 6 is the responsibility of the Emergency Coordinator per EPIP 5-7, Emergency Organization.
Incorrect c. # 1 is the responsibility of the C/R Communicator. # 3 is the responsibility of the STA per EPIP 5-7, Emergency Organization.. # 6 is the responsibility of the Emergency Coordinator.
Correct d. Per EPIP 5-7, Emergency Organizati'on pg 33.
Organization pg. 26,29,30,33
2008 Ginna NRC Exam SRO Ouestion 76 Plant conditions occurred at the following times:
1330 - While operating at rated power, the following alarms came in:
A-6, CONT Spray Pump Cooling Water Out Lo Flow A-7( 1 3 , RCP CCW Return Hi Temp or Lo Flow A-9, RHR Pump Cooling Water Outlet Lo Flow A-14, Safety Inj Pumps Cooling Water Out Lo Flow A-17,MotorOff RCP CCWP 0 A-22, CCW Pump Discharge Lo Pressure 1331 - Standby CC,W pump trips when it auto-starts leaving no CCW pumps running.
1332 - Surge Tank level is trending up.
1333 - R-17, CCW Radiation Monitor is in alarm arid counts are trending up slowly.
Based on the information given, which of the following is the most important action(s) to be taken IMMEDIATELY after 1333?
- a. Direct entry into AP-CCW.1, Leak into Component Cooling Loop and verify that the CCW surge t a n k vent valve has automatically isolated.
- b. Direct entry into AP-CCW.2, Loss of CCW During Power Operation and trip the reactor, perform -he Immediate actions of E-0, and then trip the RCPs.
C. Direct entry into AP-CCW.2, Loss of CCW During Power Operation and if a RCP bearing temp exceeds 150 degrees F, trip the reactor and then the RCPs.
- d. Direct entry into AP-CCW. 1, Leak into Component Cooling Loop and verify seal injection flow normal, then manually close the thermal barrier return valves (AOV-754N754B).
2008 Ginna NRC Exam SRO Answer:
- b. Direct entry into AP-CCW.2, Loss of CCW during Power Operation and trip the reactor, perform the Immediate actions of E-0, and then trip the RCPs.
Explanation:
Incorrect a. Correct expected action, but with no CCW pumps running, tripping the unit and
- securing the RCPs is the priority.
Correct b. Most important item to perform per AP-CCW.2 step l a RNO, with no CCW pumps running tripping the unit and RCPs are the priority.
Incorrect C. With no CCW pumps running per the AP, are to trip the unit and securing the running RCPs, this choice is not correct because the AP directs tripping only the RCP that exceeds 200 degrees F not both RCPs. 150 degrees F is an alarm setpoint for high seal water supply temperature to the RCPs (A-8 and A-16).
Incorrect d. Correct for AP-CCW.l, but with no CCW pumps running tripping the unit and
- securing the RCPs is the priority.
g Power Operation
I 2008 Ginna NRC Exam SRO Ouestion 77 The plant is at 100% power.
The control room has just been informed by the system engineer that non-quality parts, made of substandard material, were used to rebuild both Component Cooling Water (CCW) pumps during the last outage.
The CCW system has passed all of its surveillances and has been operating satisfactorily for the past 6 months.
Which one of the following applies?
- a. No actions required, both CCW pumps are Operable. The CCW pumps have passed all surveillances and testing.
- b. Declare both CCW pumps Operable but Degraded. Immediately initiate action for Engineering to perform an Operability Determination.
C. Declare both CCW pumps Inoperable. Immediately enter LCO 3.0.3 because no other Tech Spcc applies and perform a plant shutdown when allowed by Tech Specs.
- d. Declare both CCW pumps Inoperable. Initiate action to restore one CCW train to Operable statm within (1) hour. If action not completed after (1) hour be in Mode 3 in (6) hours and Mode 4 in (1 2) hours when allowed by Tech Specs.
2008 Ginna NRC Exam SRO Answer:
- b. Declare both CCW pumps Operable but Degradeld. Immediately initiate action for Engineering to perform an Operability Determination.
Explanation:
Incorrect I a. At a minimum a safety determination should be done, not no action required.
I Even though it passed all its testing and surveillances it is still degraded due to the wrong parts being installed.
Correct Engineering would perform an Operability Determination to verify the pumps could perform their safety functions for and at the times required by ITS and per the FSAR. If it passes the Operability Determination, then additional engineering evaluations would be performed on the parts. If it does not pass the Operability Determination, it would then be declared Inop.
There is an ITS for both CCW trains inop. Entry into LCO 3.0.3 is not required.
Incorrect ITS 3.7.7 does not allow (1) hour to restore a train.
2008 Ginna NRC Exam SRO Question 78 Plant conditions occurred as follows:
The unit was operating at 20% power.
0 An RCS leak has caused Pressurizer pressure to lower to 1850 psig.
Power remains near 10% and both Reactor trip breakers still indicate closed.
0 The operators are performing Step 1 of E-0, Reactor Trip or Safety Injection.
Pressurizer level is 10% and stable.
Bus 13 Normal Feed breaker will NOT open.
0 Bus 15 Normal Feed breaker is open.
Which ONE of the following describes the correct path !.he crew will perform?
- a. Perform step 2 of E-0 and manually initiate SI.
- b. Perform step 2 of E-0 and DO NOT manually initiate SI.
- c. Transition to FR-S. 1, Response to Nuclear Power GeneratiodATWS and manually initiate SI.
- d. Transition to FR-S.l, Response to Nuclear Power GeneratiodATWS and DO NOT manually initiate SI,
I 2008 Ginna NRC Exam SRO Answer:
- d. Transition to FR-S. 1, Response to Nuclear Power GeneratiodATWS and DO NOT manually initiate SI.
Explanation:
Incorrect a. E-0 stepdactions no longer apply, a crew transition to FR-S. 1 is required to mitigate the ATWS. May chose to perform this action based on power dropping from 20% to 10 % and Pzr pressure being within 100 psig of the SI set point.
Incorrect b. The crew must immediately transition to FR-S.l to mitigate the ATWS, E-0 no longer applies while in FR-S. 1 May chose to perform this action based on power dropping from 20% to 10 % and Pzr pressure still being greater than 100 psig above the SI set point and Pzr level is stable.
Incorrect c. FR-S. 1 has no instructions/RNO for manually initiating SI. May chose to perform this action based on Pzr pressure being within 100 psig of the SI set point.
Correct d. Must transition per E-0 step Id RNO. No guidance is given in any RNO or I procedure step to initial SI: only to verify SI equipment alignment if running.
000029 ATWS 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
RestartJATWS E-0, Reactor Trip or Safety
2008 Ginna NRC Exam SRO Ouestion 79 Plant conditions occurred as follows 0 The plant was operating at rated power when the unit experienced a fire in the cable tunnel.
ER-FIRE.0, CR Response to Fire Alarms and Reports is being performed.
0 Just before the fire was reported as being extinguished there were numerous alarms received in the control room, the reactor automatically tripped and there was a complete loss of power to the "B" DC Train.
- 1. What procedure is entered to restore power to the "B" IX system?
and
- 2. How will it be accomplished?
- a. 1. ER-ELEC.2, Recovery from Loss of A or B DC Train.
- 2. The TSC Battery will be cross tied to the "B" DG Train and the TSC Diesel will supply the TSC Battery Chargers.
- b. 1. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
- 2. The "B" DC Train Battery chargers will be back fed from the TSC Diesel through Bus 15 and thc Bus 15-16 cross-tie.
- c. 1. ER-ELEC.2, Recovery from Loss of A or B DC Train.
- 2. The B DC Train Battery chargers will be back fed from the TSC Diesel through Bus 15 and the Bus 15-16 cross-tie.
- d. 1. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
- 2. The TSC Battery will be cross tied to the "B" DC Train and the TSC Diesel will supply the TSC Battery Chargers.
2008 Ginna NRC Exam SRO Answer:
- d. 1. ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire.
- 2. The TSC Battery will be cross tied to the "B" DC Train and the TSC Diesel will supply the TSi3 Battery Chargers.
Explanation:
Incorrect a. ER-ELEC.2, Recovery from Loss of ,4or B DC Train deals with the loss of the bus and how it affects the plant, with a known fire in the cable tunnel area ER-FIRE.2 should be entered. ER-ELEC.2 gives no specific procedure steps to restore power after electricians have investigated the problem. The actions are correct per ER-FIRE.2.
ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire provides guidance in Att. 8 section 2, to provide long term DC power. The actions given are plausible to restore power but not called out for per ER-FIRE.2.
ER-ELEC.2, Recovery from Loss of A or B DC Train deals with the loss of the bus and how it affects the plant, with a known fire in the cable tunnel area ER-FIRE.2 should be entered. ER-ELEC.2 gives no specific procedure steps to restore power after electricians have investigated the problem. The actions given are plausible to restore power but not called out for per ER-FIRE.2.
7 Correct ER-FIRE.2, Alternate Shutdown for Cable Tunnel Fire provides guidance
- in Att. 8 section 2, to provide long term IDC power. The actions are correct per ER-FIRE.2.
I I 4*6 I Shutdown for Cable Tunnel ER-FIRE.0, CR Response to Fire Alarms & Reports pg. 4 ER-ELEC.2, Recovery from
2008 Ginna NRC Exam SRO Ouestion 80 Plant conditions occurred as follows:
0 A Reactor Coolant Leak has been identified in the Auxiliary Building.
Efforts to enter the area to isolate the leak have been unsuccessful.
0 The Control Room team has worked their way through the EOPs and are about to leave ECA-1.2, LOCA Outside Containment.
RWST level is 55% and lowering slowly.
0 Reactor Coolant System pressure and Pressurizer water level continue to lower slowly.
Which procedure will be transitioned to and why?
- a. E- 1, Loss of Reactor or Secondary Coolant, to clontinue actions to address the LOCA.
- b. ECA-1.1, Loss of Emergency Coolant Recirculation, to identify the location of the LOCA and isolate it.
- c. E-1, Loss of Reactor or Secondary Coolant, to initiate actions to lower RCS pressure to minimize break flow to slow the loss of inventory,
- d. ECA- 1.1, Loss of Emergency Coolant Recirculation, to address the loss of inventory available for core cooling.
2008 Ginna NRC Exam SRO Answer:
- d. ECA-1.1, Loss of Emergency Coolant Recirculation, to address the loss of inventory available for core cooling.
Explanation:
Incorrect a. Per step 7 of ECA-1.2, only if the lealc is isolated you are to return to E-1. Per the background document: The opera1:or transfers to E- 1, LOSS OF REACTOR OR SECONDARY COOLANT, if the break has been isolated, for further recovery actions.
Incorrect b. Per step 7 RNO, of ECA-1.2, if the leak is NOT isolated you are to go to ECA- I. 1 but while it is prudent to continue to look for the leak, ECA-1.1 is going to address the loss of inventory.,to make the RWST last as long as possible by minimizing its depletion and makeup to the RWST.
Incorrect c. Per step 7 of ECA-1.2, only if the leak is isolated you are to return to E-1. Per the background document: The operator transfers to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, if the break has been isolated, for further recovery actions. The action to lower RCS pressure to slow the leak rate would to be prudent but not the stated reason.
Correct d. Per step 7 RNO, of ECA-1.2, if the leak is NOT isolated you are to go to ECA- 1.1 and per the background document: The operator transfers to E- 1, LOSS OF REACTOR OR SECONDARY COOLANT, if the break has been isolated, for further recovery actions. If the break has not been isolated, the operator is sent to ECA- 1.1, LOSS OF EMERGE,NCY COOLANT RECIRCULATION, for be no inventory in the sump.
RESPONSE NOT OBTAINED instructions to implement in ECA-
2008 Ginna NRC Exam SRO Ouestion 81 Plant conditions are as follows:
The unit automatically tripped from rated power and the crew is currently in E-0, Reactor Trip or Safety Injection.
RCS pressure - 1780 psig and lowering.
Pressurizer Level - 2 % and lowering.
Containment pressure - 0.1 psig and stable.
A S/G Pressure - 800 psig and lowering slowly.
B S/G Pressure - 450 psig and lowering quickly.
A S/G Water Level - 8% (NR) and slowly rising.
3 S/G Water Level - 300 inches (WR) and lowering.
R-9, Letdown Rad Monitor is in alarm.
R-32, B Main Steam Line Rad Monitor is slowly rising.
R-2, Containment Rad Monitor is rising slowly but not in alarm.
R-7, Incore Detector Area Rad Monitor is rising sllowly but not in alarm.
Which of the following procedures will the CRS transition to FIRST to mitigate the consequences of the given plant conditions?
- a. E-3, Steam Generator Tube Rupture
- b. E-2, Faulted Steam Generator Isolation
- c. ECA- 1.2, LOCA Outside Containment
- d. E-1, Loss Of Reactor or Secondary Coolant
2008 Ginna NRC Exam SRO Answer:
- b. E-2, Faulted Steam Generator Isolation Explanation:
Incorrect a. SI will be actuated on low S/G press at 514 psig and should be terminated but only after first going to E-2 to isolate the steam leak.
Correct b. With S/G level and pressure trending down E-2 is the correct procedure to mitigate the given plant conditions.
Incorrect c. Leak is outside containment but it is a Steam leak not a coolant leak, ECA- 1.2 will provide no assistance. With the R-9 alarm may think there is a leak outside Cnmt.
Incorrect d. Has all the classic signs of a LOCA and with Rad alarms in various areas it maybe mistaken for a coolant leak.
Given a set of plant and equipment conditions, evaluate the conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or RESPONSE NOT OBTAINED instructions to implement in E-2,
I 2008 Ginna NRC Exam SRO Question 82 Plant conditions occurred as follows:
0 The plant is in a Refueling outage.
0 Core Alterations were in progress.
0 Fuel movements were taking place in Containment and the Auxiliary Building.
0 The Refueling SRO reported one of the spent fuel assemblies dropped on to the core and damaged several fuel assemblies.
0 R-2, Containment Area Monitor is in alarm and reading off scale high.
0 R-29/30, Containment Radiation Monitors are reading 125 R h r and slowly trending up.
Which one of the following emergency classifications would apply for the current plant conditions?
- a. Unusual Event
- b. Alert
- c. Site Area Emergency
- d. General Emergency
2008 Ginna NRC Exam SRO Answer:
- b. Alert Explanation:
Incorrect a. Meets the requirements of 5.3.1 but conditions are given for an Alert.
Correct b. Required per EAL 2.4.2.
Incorrect c. Meets the requirements of 2.3.2 but only applicable in Modes 1-4 not in Mode 6.
Incorrect d. May select GE due to dropped fuel and rad levels. Incorrect EAL call at this 1 time. Meets rad requirements for 4.1.6, but 4.1.6 is only applies in Modes 1-4.
I Examination: I RO 2008 Ginna NRC I Question #: I 82 I Rev. 1 [ Levcl: SRO I classifications.
2008 Ginna NRC Exam SRO Question 83 Plant conditions are as follows:
The reactor is currently at 100% power.
0 The unit has been operating with a Steam Generator Tube Leak (SGTL) of 60 Gallon per Day (GPD) in the "B" S/G for the last three months.
The crew is currently doing four hour leak determinations per AP-SG. 1, S/G Tube Leak Subsequently, PPCS alarm R-47G 2 75 GPD alarms.
0 A review of recent leak rates show the following:
1300 - leak started increasing above 60 GPD 1301 - 175 GPD 1302 - 65 GPD 1310 - 135 GPD 1311 - 75 GPD 1320- 85GPD 1330- 90GPD 1345 - 95 GPD and steady (current time)
All radiation monitors operable and consistently trend with R-47G What procedure will be used and what actions are required based on the current plant conditions'?
- a. Remain in AP-SG.1, Steam Generator Tube Leak and increase monitoring the "B" S/G to one hour intervals for leakage.
- b. Remain in AP-SG.l, Steam Generator Tube Leak and check S/G leak rate remains greater than 75 GPD for greater than one hour.
- c. Commence a Load Reduction per AP-TURB.5, Rapid Load Reduction because power must be reduced to less than 50% power in the next hour.
- d. Commence a plant shutdown per 0-2.1, Normal Shutdown to Hot Shutdown because the unit is required to be in Mode 3 within the next six hours.
2008 Ginna NRC Exam SRO Answer:
- c. Commence a Load Reduction per AP-TURB.5, Rapid Load Reduction because power must be reduced to less than 50% power in the next hour.
Explanation:
Incorrect a. If misapplies step 4c and goes to RNO column and then will be sent to step 5 and at step 5b will have the operators increase monitoring of the B S/G to one hour intervals for leakage.
Incorrect b. If misapplies step 4d and goes to RNO column will come to requirement for monitoring S/G tube leakage for >75 GPD for greater than one hour prior to moving / proceeding to step 6.
Correct c. This is correct if during evaluation/execution of step 7 that the rise in S/G tube leakage is less than 30 GPD / hr and answers no and goes to RNO to lower Dower to 50% w/I (1) hour.
Incorrect d. This is correct only if during evaluationlexecution of step 7 that the rise in S/G tube leakage is less than 30 GPD / hr and answers yes to this step will proceed to c then to d where: would answer no to has remained e150 GPD since leak initiation (due to mike at 1301 - 175 GIPD).
1 1 SG.1)
I C/A I 000037 Steam Generator Tube Leak 2.1.20 - Ability to interpret and execute procedure steps.
Tube Leak pgs. 3-10 Generator Tube Leak
2008 Ginna NRC Exam SRO Ouestion 84 Plant conditions are as follows:
The unit is at rated power.
A liquid radwaste release is in progress.
R-18, Waste Liquid Radiation Monitor Warning Alarm comes in followed 15 seconds later by the High Alarm.
- 1. Which one of the following describes system status?
and
- 2. The action required.
- a. 1. RCV-018 is closed
- 2. Contact an A 0 to resample the tank; and refer to EPIP 1-16, Radioactive Liquid Release to Lake Ontario or Deer Creek.
- b. 1. The tank is recirculating.
- 2. Verify the lineup is correct, contact an A 0 to resample the tank; and refer to EPIP 1- 1, Unusual Event.
- c. 1. The tank is recirculating.
- 2. Perform a flush of R-18, and refer to EPIP1-0, Ginna Station Event Evaluation and Classificatioi .
- d. 1. RCV-018 is closed.
- 2. Declare R-18 inoperable, submit an A-52.12 for R-18. Contact an A 0 to resample the tank.
2008 Ginna NRC Exam SRO Answer:
- a. 1. RCV-0 18 is closed
- 2. Contact an A 0 to resample the tank; and refer tlo EPIP 1-16, Radioactive Liquid Release to Lakf Ontario or Deer Creek.
Explanation:
Correct a. All required per AR-RMS- 18, R- 18 Waste Liquid.
Incorrect b. Suppose to verify RCV-018 is closed, tank wont be in recirc as the high alarm also trips the pump. Not required to verify the lineup except if performing a discharge with R-18 inon Refer to EPIP 1-0 or 1-16 not 1-1.
Suppose to verify RCV-018 is closed, t,ank wont be in recirc as the high alarm also trips the pump. Referring to EPIP1-0, Ginna Station Event Evaluation and operating correctly and should entry required.
LP R3901C, Radiation
2008 Ginna NRC Exam SRO Question 85 Plant conditions are as follows:
0 A Large Break Loss of Coolant Accident is in progress E- 1, Loss of Reactor or Secondary Coolant is being implemented A CNMT Spray Pump is secured per step 13 of E-1, Loss of Reactor or Secondary Coolant CNMT Pressure is 35 psig and slowly lowering RWST Level is 50% and lowering Subsequently, the STA reports that Containment Integrity is meeting ORANGE path criteria and the crew transitions to FR-Z. 1, Response to High Containment Pressure.
- 1. Which of the following is correct concerning operation of Containment Spray?
and
- 2. why?
- a. 1 . ACNMT Spray Pump should remain off per Step 2 of FR-Z. 1.
- 2. A less restrictive criteria is allowed that permits conservation of RWST water.
- b. 1 . A CNMT Spray Pump should remain off per Step 13 of E-1.
- 2. A less restrictive criteria is allowed that permits conservation of RWST water.
- c. 1. A CNMT Spray Pump must be restarted per Step 2 of FR-Z. 1.
- 2. Maximum available heat removal capability is required to reduce CNMT pressure.
- d. 1. A CNMT Spray Pump must be restarted per Step 13 of E- 1.
- 2. Maximum available heat removal capability is required to reduce CNMT pressure.
2008 Ginna NRC Exam SRO Answer:
- b. 1. A CNMT Spray Pump should remain off per Step 13 of E-1.
- 2. A less restrictive criteria is allowed that permits conservation of RWST water.
Explanation:
Incorrect a. 1. Wrong step/procedure.
- 2. Correct reason.
Correct b. In the procedure for FR-2.1, Response To High Containment Pressure, it instructs the operators to use the guidance in E-1 if it was in effect. The background document warns the operator that the operation of the containment spray pumps indicated in E-1 takes precedence over that noted in the next step of this procedure. This procedure specifies maximum available heat removal system operability in order to reduce containment pressure. E-1 uses a less restrictive criteria, which permits reduced spray pump operation depending on containment pressure and number of emergency fan coolers operating. The less restrictive criteria for containment spray operation is used in E- 1 to conserve RWST water, if possible, by stopping containment spray pumps.
1, Wrong step/procedure.
- 2. Wrong reason.
- 1. Correct step/procedure.
Loss of CTMT Integrity I I 3.3 I I E- 1, Loss of Reactor or
2008 Ginna NRC Exam SRO Question 86 Plant conditions are as follows:
The unit has tripped automatically from rated pourer due to a Loss of Coolant Accident (LOCA).
RCS pressure - 1450 psig and stable.
RVLIS Water Level - 65% and stable.
Containment pressure - 8.5 psig and slowly rising;.
CETs - 810°F and slowly rising.
RWST level - 70% and lowering.
Containment sump 78 inches.
No RCPs are running.
Containment radiation monitors are in alarm.
All required ECCS systems are running.
E-0, Reactor Trip or Safety Injection is being performed.
- 1. What would be the impact on the SI system if a rupture were to occur on the inlet weld to MOV-87SA, SI to RCS injection valve?
and
- 2. Which procedures and procedure transitions are implemented due to the LOCA and the postulated SI rupture?
SI Line to RCS Loop B - SI flow on FI-924 would rise and SI pressure on PI-922 would lowr r.
SI Line to RCS Loop B - SI flow on FI-924 and SI pressure on PI-922 would remain stable.
- 2. FR-C.2 to E-0 to E-1 to ECA-1.1
SI Line to RCS Loop B - SI flow on FI-924 .would rise and SI pressure PI-922 would lower.
- 2. FR-C.2 to E-0 to E-1 to ECA-1.1
SI Line to RCS Loop B - SI flow on FI-924 iind SI pressure PI-922 would remain stable.
2008 Ginna NRC Exam SRO Answer:
- a. 1. SI Line to RCS Loop A - SI flow on FI-925 and SI pressure on PI-923 would remain stable SI Line to RCS Loop B - SI flow on FI-92,4 would rise and SI pressure on PI-922 would lolver.
Correct a. 1 , MOV-878A is a normally closed valve that gets SI flow from the A SI pump and delivers it to the B Hot leg. With the leak on the upstream side where MOV-878B also taps in will result in high flows and lowering pressure on the SI line to the B RCS loop.
- 2. Transition out of E-0 to E- 1 prior to start of CSFST monitoring. Once in E- 1 CSFST monitoring starts, then go to FR-C.2 then back to E-1, ES-I .2 and ES-1.3. ECA-1.1 will be entered if the leak cant be stopped. Any trimsition to ECA- 1.1 will only happen after ES- I.3 is entered.
Incorrect b. 1. This would be correct if MOV-878A was on a common line that went to the ARCS loop but it does not, it is on a common line that goes to the B RCS loop.
- 2. Not monitoring CSFST in E-0 yet, so transition would only happen when in E-1. Would come back to E-0 when FR-C.2 was completed then go to E- 1. Would make sense to go to ECA- 1.1 from E- 1 but none of the requirements are rnet to go to ECA- I . I , have SW, CCW, RHR loops all available and there is a leak in the AB but not a coolant leak.
Incorrect c. 1. MOV-878A is a normally closed valve that gets SI flow from the A SI pump and delivers it to the B Hot leg. With the leak on the upstream side where MOV-878B also taps in will result in high flows and lowering pressure on the SI line to the B RCS loop.
- 2. Not monitoring CSFST in E-0 yet, so transition would only happen when in E- 1. Would come back to E-0 when FR-C.2 was completed then go to E- 1. Would make sense to go to ECA- 1.1 from E-I but none of the requirements are met to go to ECA-I. 1, have SW, CCW, RHR loops all available and there is a leak in the AB but not a coolant leak.
Incorrect d. 1. This would be correct if MOV-878A was on a common line that went to the A RCS loop but it does not. it is on a common line that goes to the B RCS loop.
- 2. Transition out of E-0 to E-1 prior to start of CSFST monitoring. Once in E-I CSFST monitoring starts, then go to FR-C.2 then back to E- I , ES- 1.2 and ES- 1.3. ECA- 1.1 will be entered if the leak cant be stopped. Any trainsition to ECA- 1.1 will only happen after ES- 1.3 is entered.
ing components, instrumentation andlor processes. b.
ces of those malfunctions or operations:
ES-1.3, FR-C.2, ECA-I.
2008 Ginna NRC Exam SRO Question 87 The unit is at rated power when Engineering informs you that an error was made when the Pressurizer Safety Valve setpoints were adjusted.
Engineering tells you the Pressurizer Safety valves will now lift at: PCV-434 - 2540 psig PCV-435 - 2580 psig
- 1. What is the correct Technical Specification action?
and
- 2. What is the bases for the Pressurizer Safety Valve lift setpoint?
- a. 1. Restore valve to Operable status within 15 minutes.
- 2. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure for all anticipated transients except for the RCP locked rotor accident.
- b. 1. Restore valve to Operable status within 15 minutes.
- 2. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure for all anticipated transients except for the RCP sheared shaft accident.
- c. 1. Be in Mode 3 within (12) hours.
- 2. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure for all anticipated transients except for the RCP sheared shaft accident.
- d. 1. Be in Mode 3 within (12) hours.
- 2. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure for all anticipated transients except for the RCP locked rotor accident.
2008 Ginna NRC Exam SRO Answer:
- a. 1. Restore valve to Operable status within 15 minutes.
- 2. OPERABILITY of the safety valves ensures that the RCS pressure will be limited to 110% of design pressure for all anticipated transients except for the RCP locked rotor accident.
Explanation:
it protected by this Specification is the PB) SL of 110% of design pressure for all transients except locked rotor accidents which has an allowed limit of 120% of design pressure. Inoperability of one or more valves could result in exceeding the SL if a transient were 1.0 occur. The consequences of exceeding the ASME pressure limit could include damage to one or more RCS itional stress analysis being required Ten in the bases.
op and time is to Mode 4 not Mode 3.
en in the bases.
op and time is to Mode 4 not Mode 3.
protected by this Specification is the reactor coolant pressure boundary (RCPB) SL of 110% of design pressure for ts which has an allowed limit of one hour. b. Describe the 2.2.40 - Ability to apply technical specifications for a system.
2008 Ginna NRC Exam SRO Question 88 Plant conditions are as follows:
0 The unit is at 90% power.
Channel 2 of OP-delta T is inoperable and has been in the trip condition for the last 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
It has been determined that Channel 3 OP-delta T surveillance must be performed.
$The crew invokes the note in ITS 3.1.1 that says, The ino erable channel may be bypassed for 7
up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels, o support surveillance testing on Channel 3 OP-delta TI %
Two hours into the surveillance I/C reports the as-found set point for Channel 3 OP-delta T was not within the required band and cannot be adjusted into the proper band.
- 1. When must Channel 3 OP-delta T be declared inoperable?
and
- 2. What is the bases for the OP-delta T trip function?
- a. 1. I&C has (2) hours to fix and retest Channel 3OP-delta T before the train must be declared inoperable.
2 . Ensures that the design limit departure from nucleate boiling ratio (DNBR) is met.
- b. 1. Immediately declare Channel 3 OP-delta T inoperable.
- 2. Ensures that the design limit departure from nucleate boiling ratio (DNBR) is met.
- c. 1. I&C has (2) hours to fix and retest Channel 3 OP-delta T before the train must be declared inoperable.
- 2. Ensures that protection is provided to ensure the integrity of the fuel (Le., no fuel pellet melting and less than 1% cladding failure).
- d. 1. Immediately declare Channel 3 OP-delta T inoperable.
- 2. Ensures that protection is provided to ensure the integrity of the fuel (i.e., no fuel pellet melting and less than 1% cladding failure).
2008 Ginna NRC Exam SRO Answer:
- d. 1. Immediately declare Channel 3 OP-delta T inoperable.
- 2. Ensures that protection is provided to ensure the integrity of the fuel (Le., no fuel pellet melting and less than 1% cladding failure).
Explanation:
Incorrect a. 1. The surveillance testing is done and must be declared inop immediately.
Corrective maintenance and trouble shooting is now required to fix the channel. The note only allows testing to verify the channel is working correctly.
- 2. This is the ITS bases for OT-delta T trip set point.
Incorrect b. 1. The channel no longer meets the surveillance requirements and is therefore inop
- 2. This is the ITS bases for OT-delta T trip set point.
Incorrect c. 1. The surveillance testing is done and must be declared inop immediately.
Corrective maintenance and trouble shooting is now required to fix the channel. The note only allows testing to verify the channel is working correctly.
- 2. This is the ITS bases for OP-delta T trip set point.
Correct d. 1. The channel no longer meets the surveillance requirements and is therefore inop.
- 2. This is the ITS bases for OP-delta T trip set point.
perform the following in accordance with (Technical Specifications, TS Bases, TRM, COLR, PTLR, ODCM): b. Describe the basis of
L 2008 Ginna NRC Exam SRO Ouestion 89 Plant conditions are as follows:
0 The unit has experienced a large break Loss of Coolant Accident (LOCA).
0 The Control Room team has properly implemented the EOPs as required.
0 The plant is in Cold Leg Recirculation with the following conditions:
o A RHR pump is running and B RHR pump is available.
o All of the Containment Recirc Fans have failed to start and wont run.
o B CCW pump is running and A CCW pump is 00s.
o C SI pump is running with A and B SI pumps available.
o A CS pump is running and B CS pump is available.
o Total RHR flow is 1500 gpm and stable.
o Containment Pressure is 48 psig and stable.
o RHR Suction Temperature is 285°F.
Subsequently B CCW pump trips and cannot be restarted.
- 1. What will be the INITIAL indications on the RHR system?
and
- 2. What actions will the crew need to take over the next (15) minutes based on those indications?
- a. 1. A RHR pump will begin to show signs of cavitation.
- 2. Secure the running CS pump per ES-I .3, Cold Leg Recirculation due to limitations on the CS Pump.
- b. 1. RHR suction temperature will begin to rise.
- 2. Per ECA- 1.1, Loss of Emergency Coolant Recirculation, start the B RHR pump and raise RZ iR flow.
- c. 1. A RHR pump will begin to show signs of cavitation.
- 2. Per ECA- 1.1,Loss of Emergency Coolant Recirculation, start the B RHR pump and raise RI IR flow.
- d. 1. RHR suction temperature will begin to rise.
2008 Ginna NRC Exam SRO Answer:
- d. 1. RHR suction temperature will begin to rise.
Explanation:
Incorrect I a' With 48 psig in Cnmt and RHR lined up to the B sump there will be NO indications of cavitation but it is plausible with loss of CCW for the student to think RHR will cavitate. ES-1.3 calls for the running CS pump to be secured due to RHR suction temD rising.
Incorrect b. RHR suction temperature will begin to rise due to loss of CCW, with nothing else providing cooling (CRFs not running). Entry into ECA-1.lwould be correct however SI, CS and RHR pumps would be secured not started T
Correct d.
With 48 psig in Cnmt and RHR lined up to the B sump there will be NO indications of cavitation but it is plausible with loss of CCW for the student to think RHR will cavitate.
RHR suction temperature will begin to rise due to loss of CCW, with nothing else providing cooling (CRFs not running). ES-1.3 calls for the running CS pump to be secured due to RHR suction temp rising.
malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of containment Leg Recirculation pg. 13 Att 28.0, Att Cnmt Spray Fig-21 Fig Cnmt Spray Restart Criteria pg. 1
2008 Ginna NRC Exam SRO Question 90 Plant conditions are as follows:
The plant is in Mode 3.
Tavg is 547°F and stable.
RCS pressure is 2235 psig and stable.
STP-O-12.2, Emergency Diesel Generator B, monthly surveillance test is underway.
0 B DIG has been loaded per the surveillance procedure for about 30 minutes.
Subsequently, all of Off-site power is lost coincident with a large break Loss of Coolant Accident (LOCA).
- 1. What is the plant response if all equipment operates as designed?
and
- 2. What actions must the crew take in response to the loss of Off-site power coincident with the LOCA?
- a. 1. Initially, the voltage and frequency of Emergency Diesel Generator B will be high.
- 2. Per STP-0-12.2, immediately place the IJNITPARALLEL switch to UNIT.
Then adjust voltage as required to achieve 480 volts and adjust frequency to 60.0 HZ.
- b. 1. Initially, the voltage and frequency of Emergency Diesel Generator B will be high.
- 2. Per STP-0-12.2, adjust voltage as required to achieve 480 volts.
When load sequencing is completed, place the IJNITPARALLEL switch to UNIT and adjust frequency to 60.0 HZ.
- c. 1. Initially, the Emergency Diesel Generator B output breakers to Buses 16 and 17 will open.
- 2. Per AP-ELEC.14/16 and AP-ELEC.17/18, place the UNIT/PARALLEL switch to UNIT first, anal then close the D/G supply breakers to Buses 16 and 17.
Then adjust voltage as required to achieve 480 volts and adjust frequency to 60.0 HZ.
- d. 1. Initially, the Emergency Diesel Generator B output breakers to Buses 16 and 17 will open.
- 2. Per AP-ELEC.14/16 and AP-ELEC.17/18, close the D/G supply breakers to Buses 16 and 17 first, then when load sequencing is completed, place the UNITPARALLEL switch to UNIT.
Then adjust voltage as required to achieve 480 volts and adjust frequency to 60.0 HZ.
I 2008 Ginna NRC Exam SRO Answer:
- b. 1. Initially, the voltage and frequency of Emergency Diesel Generator B will be high.
- 2. Per STP-0-12.2, adjust voltage as required to achieve 480 volts.
When load sequencing is completed, place the UNIT/PARALLEL switch to UNIT and adjust frequency to 60.0 HZ.
Explanation:
Incorrect a. Per Att. 2 of STP-0-12.2, Emergency Diesel Generator B initially, the voltage and frequency of Emergency Diesel Generator B will be high and only after the loads have sequenced should the Correct b. As Der Att. 2 of STP-0-12.2.
Incorrect c. Breakers will not open, entry into AP ELECT.14/16 or 17/18 is not required.
Incorrect d. Breakers will not ooen. entrv into AP ELECT.14/16 or 17/18 is not reauired.
a1 principle, performance test, limits or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of
2008 Ginna NRC Exam SRO Question 91 Plant conditions are as follows:
The unit is at 90% power.
All control system$$ their normal alignment, and no equipment is out of service.
The following annunciators come in:
o F-28, Pressurizer High Level Channel Alert 87%
o F-4, Pressurizer Level Deviation -5 NORMAL +S o A-4, Regen Hx Outlet Hi Temp 395°F 1 . What was the common cause for these annunciators?
and
- 2. What procedure will provide the proper guidance to mitigate the current plant conditions?
- a. 1. There is a steam space leak in the Pressurizer, which has caused Pressurizer level to swell.
- 2. Enter AP-RCS. 1, Reactor Coolant Leak.
- b. 1. LT-426 Pressurizer Level Failed High causing the charging pump in auto to go to minimum speed.
- 2. Enter ER-INST. 1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure.
- c. 1. There is a leak on the charging header down stream of HCV-142, Charging Backpressure Contrcql Valve, causing HCV- 142 to throttle closed.
- 2. Enter AP-RCS. 1. Reactor Coolant Leak.
- d. 1. LT-428 Pressurizer Level Failed High causing the charging pump in auto to go to minimum specd.
- 2. Enter ER-INST. 1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure.
2008 Ginna NRC Exam SRO Answer:
- d. 1. LT-428 Pressurizer Level Failed High causing the charging~-pump in auto to go to minimum spe;d.
~
- 2. Enter ER-INST. 1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure.
Exdanation:
Steam space leaks will result in Pzr level rising but only after level has dropped and a steam void is drawn in the Rx head. No RCS leak therefore no entry into
-+
AP-RCS.l is needed but if it were a leak it would be the correct AP to enter.
The controlling channel, LT-428 is in service per the stem, LT-426 is not the controlling channel at this time. Entry into ER-INST.1, Reactor Protection Bistable Defeat after Instrumentation Loop Failure is the correct procedure to enter.
Explains why A-4, Regen Hx Outlet Hi Temp 395°F is in but not the other alarms. No other indications of a leak so entry into AP-RCS.l is not required.
Correct The controlling channel, LT-428 has failed high which caused the F-4 and F-28 alarms, A-4 came in because the auto charging pump seeing a high Pzr level slowed to minimum and reduced the cooling flow to the RHX. Entry into ER-INST.l will provide guidance to cope with the instrument failure.
IExamination: I RO 2008 Ginna NRC 1 Ouestion #: I 91 I Rev. 3 I Level: SRO Channel Instrumentation will have on related plant system(s) and/or A2.10 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use malfunctions or operations: Failure of PZR level instrument -
ER-INST. 1, Reactor Protection Bistable Defeat
2008 Ginna NRC Exam SRO Question 92 Plant conditions occurred as follows:
0 The unit is at 80% power.
0 All control systems in their normal alignment.
0 Pl-429, Pressurizer Pressure transmitter failed last shift and its required Technical Specification actions have been completed while awaiting repairs.
Subsequently, PI-449, Pressurizer Pressure instrument output signal , fails low.
- 1. What is the plant response?
and
- 2. What procedure is entered in response to plant conditions?
- a. 1. Low Pressurizer pressure Safety Injection.
- 2. Enter E-0, Reactor Trip or Safety Injection.
- b. 1. OP Delta T runback with Rod Stop channel alert.
- 2. Enter AP-TURB.2, Turbine Load Reduction.
- c. 1. Low Pressurizer pressure Reactor trip.
- 2. Enter E-0, Reactor Trip or Safety Injection.
- d. 1. OT Delta T runback with Rod Stop channel alert.
- 2. Enter AP-TURB.2, Turbine Load Reduction.
2008 Ginna NRC Exam SRO Answer:
- c. 1. Low Pressurizer pressure Reactor trip.
- 2. Enter E-0, Reactor Trip or Safety Injection.
Explanation:
Incorrect a. No SI signal, SI signals (2/3 LOGIC) come from PI-429,430,43 1. Correct procedure to enter based on SI.
Incorrect b. OP and OT delta-Ts frequently confused. Pressure has no input so OP Delta T will be unaffected.
Correct c. 2/4 logic met Reactor will trip and entry into E-0 required.
Incorrect d. Will get signals and alarms for an OT Delta T runback with rod stop channel alert however there will also be a Reactor Trip which requires entry into E-0.
2008 Ginna NRC Exam SRO Question 93 Plant conditions occurred as follows:
1300 - The unit is operating at 45% power with both CW pumps running and all conditions normal.
1400 - A release of A Monitor Tank begins.
1455 - The outside operator reports that B CW pump sounds very bad.
1500 - The crew implements actions to secure the B CW pump.
What action is now required prior to stopping the B CW pump?
- a. The release may continue provided the B CW pump is restarted by 1600.
- b. Inform Chemistry to update the release rate calculations or secure the release.
- c. The release must be immediately secured, no exceptions are allowed.
- d. The release may continue provided all non-running Service Water pumps are started.
2008 Ginna NRC Exam SRO Answer:
- b. Inform Chemistry to update the release rate calculations or secure the release.
Explanation:
Incorrect a. While there are specific time limits foir some items while preparing and releasing radioactive tanks, this is not one of them.
Correct b. Per T-8A, Startup and Shutdown Circulating Water Pumps A and B, precaution 4.6 Notify Duty RP (Chemistry) of changes in Circulating Water flow rate for Liquid Waste Release Form calculations. For liquid waste releases in progress, either notify the Duty RP (Chemistry) to update the release rate permissible, or terminate the release prior to changing the Circulating Water flow rate.
Incorrect c. This is correct if one of the CW mmDs were to trir>.
I Incorrect 1 d. 1 This will allow additional dilution, but is not the required action.
lain and apply system limits and precautions.
2008 Ginna NRC Exam SRO Ouestion 94 The following conditions exist:
0 The plant is in mode 4.
0 The shift crew composition is at minimum shift manning.
0 The CO becomes seriously ill and must be taken to the hospital.
0 There are five hours left until shift change.
it? w%!
What action is required in accordance with Technical Specifications?
- a. Immediate action must be taken to obtain a replacement reactor operator within a maximum of one hour.
- b. Immediate action must be taken to obtain a replacement reactor operator within a maximum of two hours.
- c. Immediate action must be taken to obtain a replacement reactor operator within a maximum of thrce hours.
m y '7'
- d. Shift turnover occurs beforeNction is required. A G .e
2008 Ginna NRC Exam SRO Answer:
- b. Immediate action must be taken to obtain a replacement reactor operator within a maximum of tws ) hours.
Explanation:
Incorrect a. ITS requires that immediate action be l.aken to find a replacement. The position cannot remain unmanned for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Correct b. ITS requires that immediate action be faken to find a replacement. The position cannot remain unmanned for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Incorrect c. ITS requires that immediate action be taken to find a replacement. The position cannot remain unmanned for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Incorrect d. ITS requires that immediate action be taken to find a replacement. The position cannot remain unmanned for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
uling requirements including rotation minimum crew complement, overtime limitations, etc.
ITS 5.2.2.a Plant Staff
2008 Ginna NRC Exam SRO Question 95 The following conditions exist:
0 The plant is performing PT-34.1, Initial Criticality and Low-Power Physics Testing with DRWM 0 All Technical Specification exceptions for Physics Testing are in effect.
0 Plant conditions are as follows:
o Pressurizer pressure - 2210 psig o Pressurizer water level - 20 %
o Both RCS Loop Tavg - 535°F o Thermal Power - 6%
For these given conditions, what is the required Technical Specification action?
- a. Immediately lower power to 4% Thermal Power.
- b. Restore RCS Tavg to within limits within 30 minutes.
- c. Immediately open the Reactor trip breakers.
- d. Restore Pressurizer Pressure to within limits withi-n30 minutes.
2008 Ginna NRC Exam SRO Answer:
- c. Immediately open the Reactor trip breakers.
Explanation:
ITS 3.1.8 Action B. 1 requires the Rx trip breakers to be opened immediately if thermal power is not within the limit (limit is c or = to 5% RTP). With the requirement to lower power less than the limits lends credibility.
Incorrect b. Tavg is allowed to be as low as 530°F during Physics Testing so the limit is not violated however the time allowed to restore the parameter is the same as listed in 3.4.2, RCS Minimum Temz, for Criticalitv.
Correct C. As per ITS 3.1.8 Action B.1 Rx trip thermal power is not within the limit Incorrect d. Pzr pressure is lower than normal but to restore the parameter is the same as listed in 3.4.3, RCS Press and Temp Limits. 4 with reactivity management,
2008 Ginna NRC Exam SRO Question 96 Plant conditions are as follows:
The unit is at rated power.
0 You are standing watch as the CRS and the Shift Manager (SM) is in a meeting.
0 You have just been requested to review a Condition Report (CR) that requires corrective maintenance on the A Diesel Generator which will place the unit in a (7) day shutdown LCO.
- 1. What are your actions?
and
- 2. Per CNG-MN-4.01-1002, Work Order Screening and Prioritization, when can the corrective maintenance start?
- a. 1. You can perform an initial review however the SM must approve.
- 2. Once the maintenance work package is completely written and approved the corrective maintenatice can start.
- b. 1. You can perform an initial review however the SM must approve.
- 2. The corrective maintenance can start immediately and the work package can be put together and approved while the maintenance is being done.
- c. 1. You as the CRS can complete the review.
- 2. The corrective maintenance can start immediately and the work package can be put together and approved while the maintenance is being done.
- d. 1. You as the CRS can complete the review
- 2. Once the maintenance work package is completely written and approved the corrective maintenai x e can start.
2008 Ginna NRC Exam SRO Answer:
- d. 1. You as the CRS can complete the review
- 2. Once the maintenance work package is compktely written and approved the corrective mainten mce can start.
Explanation:
SM approval is not required. CNG-MN-4.01-1002, Work Order Screening and Prioritization allows any SRO to review the CR if the SM is unavailable. The process for work package/work would be correct if it were for a priority E -
Emergency Maintenance screening however the work is Pri-2.
SM approval is not required. CNG-MN-4.01-1002, Work Order Screening and Prioritization allows any SRO to review the CR if the SM is unavailable. A I 1 I :
priority-2 work package must be completed before work begins per, CNG-MN-4.01- 1002, Work Order Screening and Prioritization.
The CRS can review the CR in the absence of the SM. The process for work package/work would be correct if it were for a priority E - Emergency Maintenance screening however the work is Pri-2.
Correct The CRS can review the CR in the absence of the SM. A priority-:! work package must be completed before work begins per, CNG-MN-4.01-1002, Work Order Screening and Prioritization.
IExamination: I RO 2008 Ginna NRC I Question#: I 96 I Rev. 5 I Level: SRO I Order Execution and Closure CNG-MN-4.01- 1002, Work
2008 Ginna NRC Exam SRO Question 97 Plant conditions occurred as follows:
The Plant was operating at 100% power with all systems in a normal configuration when a transient occurred that resulted in a Reactor Trip and Safety Injection.
E-0, Reactor Trip or Safety Injection, is in progress.
The conditions (2) minutes after the trip are as follows:
RCS Tavg - 500°F and lowering at a constant rate.
RCSPressurizer Pressure - 1850 psig and lowering.
Both S/G Pressures - 500 psig and lowering.
Both S/G Water Levels - 6% Narrow Range and slowly lowering.
Both MSIV's are closed.
Both MFP's are tripped.
Both MDAFW pumps are running and delivering -220 gpm each.
TDAFW pump is running.
Containment Pressure is 0.3 psig and stable.
- 1. What procedures will be utilized to mitigate this event'?
and
- 2. What major action will be directed to mitigate the impact on the reactor?
- a. 1. E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
- 2. Isolate the TDAFW pump and Reduce AFW Flow to 50 gpm to each Steam Generator to minimi r,e RCS cooldown.
- b. 1. E-1, Loss of Reactor or Secondary Coolant, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
- 2. Isolate the TDAFW pump and Reduce AFW Flow to 50 gpm to each Steam Generator to minirni+f,e RCS cooldown.
- c. 1. E-1, Loss of Reactor or Secondary Coolant, then ECA-2.1, Uncontrolled Depressurization of Bot'i Steam Generators.
- 2. Control AFW Flow to maintain narrow range level between 7% and 50% in both Steam Generatfirs to ensure maintenance of the secondary heat sink.
- d. 1. E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
- 2. Control AFW Flow to maintain narrow range level between 7% and 50% in both Steam Generators to ensure maintenance of the secondary heat sink.
2008 Ginna NRC Exam Answer:
- a. 1. E-2, Faulted Steam Generator Isolation, then ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
- 2. Isolate the TDAFW pump and Reduce AFW Flow to 50 gpm to each Steam Generator to minin ize RCS cooldown.
Explanation:
Correct a. The condition in the question indicates an uncontrolled depressurization of both S/Gs.
The transition to E-2 is made upon recognition that the S/G secondary side is not intact as indicated by S/G pressures lowering (Step 15 of E-0). The transition to ECA-2.1 is made at step 2 of E-2 since neither S/G pressure is stable or rising. ECA-2.1 directs the operator pull stop the TDAFF' Steam supply and close the pump flow control valves then reduce Feed Flow to 50 gpm in each S/G due to the cooldown rate being >
1OO"F/hr.
Incorrect b. Procedure routing is incorrect. The conditions for entry into E-1 could conceivably be applied due to secondary coolant is being lost and E-1 does cover the loss of secondary coolant and the resulting cooldown. The action given is correct.
Incorrect C. Procedure routing is incorrect. The conditions for entry into E-1 could conceivably be applied due to secondary coolant is being lost and E-1 does cover the loss of secondary coolant and the resulting cooldown. The action given would also result in continued cooldown.
Incorrect d. Correct procedure routing however the action is not consistent with the guidance in ECA-2.1 Controlling S/G levels would result in continuing to feed the fault and result in a continued cooldown.
conditions to determine the applicable procedure, and from the procedure determine the appropriate EXPECTED ACTIONS or
2008 Ginna NRC Exam SRO Ouestion 98 You as the Shift Manager, are authorizing a Gas Decay Tank Release per CH-RETS-GDT-REL,
&e release must be initiated within 1 -hours of the tank sample time with p no additions to the tank since the sample was &:awn and if the release is not initiated within the required time limit, (2) is required to initiate the release.
- a. 1. 12 2, Chemistry Supervisor permission
- b. 1. 12
- 2. resampling
- c. 1. 24
- 2. Chemistry Supervisor permission
- d. 1. 24
- 2. resampling
2008 Ginna NRC Exam SRO Answer:
Correct a. As required per CH-RETS-GDT-REL, Gas Decay Tank Release limitation 7.1:
A release is required to be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after sample time, unless no
.=
additions have been made to tank. (Chemistry) Supervisor's permission is required for release if initiation is not started within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. This was correct prior to the recent procedure change. The procedure does not
& require resampling. The SM or others may choose to do so but is not required.
Incorrect c. As required per CH-RETS-GDT-REL, Gas Decay Tank Release limitation 7.1 except the time allowed is not 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, it is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Incorrect d. This was correct prior to the recent procedure change except the time allowed is not 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, it is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The procedure does not require resampling.
- - The SM 1 or others may choose to do so but is not required.
.3.6 - Ability to approve release permits.
2008 Ginna NRC Exam SRO Question 99 Plant conditions occurred as follows:
The unit was operating at 100% power with a mini-purge in progress.
0 A reactor trip occurred coincident with a loss of off-site power.
0 The Control Room Team have just transitioned to E-1, Loss of Reactor or Secondary Coolant, and the following conditions exist:
o RCS pressure approximately 25 psig and lowering.
o Mini purge has failed to isolate.
o R-29 and R-30 read 125 Rhr.
o R14 on alarm.
o R14A7 is reading 2 uci/cc.
o Meteorological conditions are:
++: 33 ft temp 65 degrees F
- 250 ft temp 66 degrees F
- Wind direction 135 degrees
+:* Wind speed 4 mph As the Shift Manager acting as the Emergency Coordinator, you have declared a General Emergency and recommend . . .
- a. shelter-in-place of ERPA W-1.
- b. evacuation of ERPAs W-1,2,3.
- c. evacuation of ERPA W- 1.
- d. shelter-in-place of ERPAs W-1,2,3.
2008 Ginna NRC Exam SRO Answer:
C. evacuation of ERPA W-1.
Explanation:
Incorrect a. Correct if using att. 2 instead of att.1.
Incorrect b. Correct if wind direction used is 325 degrees (180 degrees out from 135 degrees) and using att. 1.
- c. Correct PARS per EPIP-2.1 and using att. 1. -
- d. Correct if wind direction used is 325 degrees (180 degrees out from 135 degrees) and if using att. 2 instead of att. 1.
2008 Ginna NRC Exam SRO Question 100 Plant conditions are as follows:
e The unit has experienced a Reactor Trip and Safety Injection due to a Loss of Coolant Accident (LOCA).
a RCS pressure is 800 psig.
e Containment pressure is 10 psig and slowly rising.
e No RCPs are running.
e (4)CETs are reading 1250°F and the remaining CETs are reading 680°F and stable.
e RVLIS level is 45% and stable.
e All S/G narrow range levels are off-scale low.
a Unable to start the MDAFW pumps and the TDA,FW pump.
e All SI pumps have tripped on overload.
e MOV-896B, RWST outlet to SI and CS pumps, was found closed and is now open.
a The Control Room Staff is performing E- 1, Loss of Reactor or Secondary Coolant.
Given these plant conditions, which ONE of the fol1owin.g identifies the procedure action to mitigate this event?
- a. Transition to FR-H.l, Response to Loss Of Secondary Heat Sink, attempt to start SAFW pumps.
- b. Transition to FR-C. I, Response to Inadequate Core Cooling, reset overloads and attempt to start Si pumps.
- c. Transition to FR-H. 1, Response to Loss Of Secondary Heat Sink, open PORVs and Block Valves.
- d. Transition to FR-C. 1, Response to Inadequate Core Cooling, open PORVs and Block Valves.
2008 Ginna NRC Exam SRO Answer:
- a. Transition to FR-H. 1, Response to Loss Of Secondary Heat Sink, attempt to start SAFW pumps.
Explanation:
Heat Sink is currently the highest priority red path safety function. AFW pumps are not available so the SAFW pumps would be started to restore flow to the SIGs. ~ ~~
Incorrect b. It is reasonable to believe that the SI pumpswould be restarted with the suction path restored, however core cooling is only in an orange path since a minimum of 5 CETs must be indicating > 1200 degrees for a red path condition per the background document, and the remaining CETs would only support an orange path condition, therefore FR-C. 1 is not the correct procedure to implement at this time.
Incorrect c. Heat Sink is currently the highest priority red path safety function; however, a start of the SAFW pumps would be attempted prior to resorting to feed and bleed cool ing .
Incorrect d. Cooling is only in an orange path since a minimum of 5 CETs must be indicating > 1200 degrees for a red path condition per the background document, and the remaining CETs would only support an orange path condition, therefore FR-C.l is not the correct procedure to implement at this time. The depressurization of the RCS to dump the accumulators would not be attempted until starting the SI pumps is attempted.
Of Secondary Heat Sink